View source for NL-08-081, Official Exhibit - ENT000310-00-BD01 - 2007 Annual Radiological Environmental Operating Report (NL-08-081) (May 15, 2008)

{{Adams
| number = ML12338A687
| issue date = 05/15/2008
| title = Official Exhibit - ENT000310-00-BD01 - 2007 Annual Radiological Environmental Operating Report (NL-08-081) (May 15, 2008)
| author name = Walpole R
| author affiliation = Indian Point Energy Center
| addressee name = 
| addressee affiliation = NRC/ASLBP, NRC/Document Control Desk, NRC/NRR
| docket = 05000247, 05000286
| license number = 
| contact person = SECY RAS
| case reference number = RAS 22135, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, NL-08-081
| document type = Legal-Exhibit
| page count = 151
}}

=Text=
{{#Wiki_filter:United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.
In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3)
ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000310-00-BD01                  Identified: 10/15/2012 Admitted: 10/15/2012                         Withdrawn:                                        ENT000310 Rejected:                                       Stricken:                                      Submitted: March 29, 2012 Other:                                                                                   Indian Point Energy Center 450 Broadway, GSB
                    -===- Entergy .
P.O. Box 249 Buchanan, NY. 10511-0249 Tel (914) 734-6710 Robert Walpole Manager, Licensing May 15, 2008 Re: Indian Point Units 1, 2 & 3 Docket Nos. 50-003, 50-247, 50-286 NL-08-081 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

==Subject:==
Indian Point Nuclear Power Plants Units 1, 2 and 3 Annual Radiological Environmental Operating Report for 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.
Sincerely yours,
                                                                                           ~obert  Walpo e Manager, Licensing Indian Point Energy Center Enclosure cc: wlo enclosure 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.
Lc = ka Sb (1 + TtlTsl* 5 in cpm where:
ka = 1.645 (corresponds to a 95% confidence level)
Sb = standard deviation of the background count rate = (R bITb )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:
N LXi X=~
N where:        Xi = value of each individual observation N = number of observations N
L(ERRJ PE =-,--,-i=...:....1_ __
N where:         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/m 3 and the average for the control location was 0.013 pCilm 3 . The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location.               Gamma spectroscopy analyses of the quarterly composite air 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/m 3 ) in the charcoal cartridge samples, which is consistent with historical trends.
From the data, it can be seen that no airborne radioactivity attributable to the 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 Onsite -
3                   DR8          Service Center Building                                     0       Direct Gamma 0.35 Mi (SSE) at 158 A1                                               Onsite - 0.28 Mi (SW) at        Air Particulate 4                                Algonquin Gas Line                      0 A1                                              234                              Radioiodine A4                                                                              Air Particulate Onsite - 0.88 Mi (SSW) 5                  A4           NYU Tower                                                            Radioiodine at 208 0 DR10                                                                              Direct Gamma 7                 Wb1           Camp Field Reservoir                3.4 Mi       at 51 0           Drinking Water 0
8                     **         Croton Reservoir                    6.3 Mi (SE) at 124             Drinking Water Onsite -
9                  Wa1           Plant Inlet (Hudson River Intake)*                        0           HR Water 0.16 Mi (W) at 273 Wa2                                               Onsite -                          HR Water 10                               Discharge Canal (Mixing Zone) 0.3 Mi (WSW) at 249 0       HR Bottom Sediment Onsite -
14                  DR7                r Meter House                                                 Direct Gamma 0.3 Mi (SE) at 133 0 HR Aquatic Vegetation 17                    **         Off Verplanck                       1.5 Mi (SSW) at 202.5"        HR Shoreline Soil HR Bottom Sediment Cortlandt Yacht Club 20                 DR38                                              1.5 Mi (S) at 180 0             Direct Gamma (AKA Montrose Marina)
Air Particulate 22                               Lovett Power Plant                  1.6 Mi (WSW) at 244 0
                          **                                                                              Radioiodine
                          **                                                                              Precipitation A5                                                                              Air Particulate, A5                                                                               Radioiodine 23                 DR40          Roseton*                            20.7 Mi (N) at 357"             Direct Gamma Ic3                                                                        Broad Leaf Vegetation Soil Ib2                                                                          Fish & Invertebrates 25                   Ib1         Downstream                          Downstream                  Fish & Invertebrates Air Particulate 0
27                               Croton Point                        6.36 Mi (SSE) at 156             Radioiodine DR41                                                                              Direct Gamma HR Shoreline Soil DR4                                                                       0 Direct Gamma 28                               Lent's Cove                         0.45 Mi (ENE) at 069 HR Bottom Sediment HR                    on Air Particulate 29                    **         Grassy Point                        3.37 Mi (SSW) at 196 0            Radioiodine DR39                                                                               Direct Gamma
  * = Control location
** = Locations listed do not have sample designation locations specified in the aDCM HR = Hudson River R1S = Reuter Stokes                             A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 33                 DR33           Hamilton Street (Substation)             12.88 Mi (NE) at 053 0           Direct Gamma IOnsite -
34                 DR9            South East Corner of Site                                                 Direct Gamma 10.52 Mi (S) at 1790 Onsite -
35                 DR5            Broadway & Bleakley Avenue                                                Direct Gamma 0.37 Mi (E) at 092 0 38                 DR34           Furnace Dock (Substation)                 3.43 Mi (SE) at 141 0           Direct Gamma
                         **                                                                                      Precipitation 44                   **           Peekskill Gas Holder Bldg                 1.84 Mi (NE) at 052 0           Air Particulate
                         **                                                                                      Radioiodine 50                 Wc2            Manitou Inlet*                            4.48 Mi (NNW) at 34r           HR Shoreline Soil Wc1                                                                                     HR Shoreline Soil 53                                White Beach                               0.92 Mi (SW) at 226 0 DR11                                                                                     Direct Gamma 0
56                 DR37                            - Broadway & 6th Street  1.25 Mi (SSW) at 202            Direct Gamma 0
57                  DR1           Roa Hook                                  2 Mi (N) at 005                 Direct Gamma 0
58                 DR17           Route 90 - Garrison                       5.41 Mi (N) at 358              Direct Gamma 59                 DR2            Old Pemart Avenue                         1.8 Mi (NNE) at 032 0           Direct Gamma Gallows Hill Road & Sprout Brook 60                 DR18                                                     5.02 Mi (NNE) at 029 0          Direct Gamma Road 61                 DR36           Lower South Street & Franklin Street      1.3 Mi (NE) at 052 0            Direct Gamma Westbrook Drive 62                 DR19                                                     5.03 Mi (NE) at 062 0           Direct Gamma (near the Community Center)
Lincoln Road - Cortlandt 64                 DR20                                                     4.6 Mi (ENE) at 06r             Direct Gamma (School Parking Lot) 66                 DR21           Croton Avenue - Cortlandt                 4.87 Mi (E) at 083 0            Direct Gamma 67                 DR22           Colabaugh Pond Road - Cortlandt           4.5 Mi (ESE) at 114 0           Direct Gamma 69                 DR23           Mt. Airy & Windsor Road                   4.97 Mi (SE) at 12r             Direct Gamma 71                 DR25           Warren Ave - Haverstraw                   4.83 Mi (S) at 188 0            Direct Gamma 0
72                 DR26           Railroad Avenue & 9W - Haverstraw 14.53 Mi (SSW) at 203                . Direct Gamma IVVIllOW Grove Road & Captain 73                 DR27                                                     4.97 Mi (SW) at 226 0           Direct Gamma Faldermeyer Drive 74                 DR12          IWest Shore Drive - South                  1.59 Mi (WSW) at 252 0          Direct Gamma 0
75                 DR31           Palisades Parkway                        14.65 Mi (NW) at 225             Direct Gamma 76                 DR13          IWest Shore Drive - North                  1.21 Mi (W) at 276 0            Direct Gamma 77                 DR29           Palisades Parkway                         4.15 Mi (W) at 272   0 Direct Gamma 78                 DR14           Rt. 9W across from RlS #14                1.2 Mi (WNW) at 295 0           Direct Gamma 0
79                 DR30            __ , '" 'v, '1 Wayne Park                4.57 Mi (WNW) at 296            Direct Gamma
  * = Control location
** = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River RlS = Reuter Stokes                                 A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 81                 DR28                                              4.96 Mi (WSW) at 310 0       Direct Gamma 0
82                 DR16                                              1.01 Mi (NNW) at 334         Direct Gamma 83                 DR32          Route 9W - Fort Montgomery          4.82 Mi (NNW) at 339 0       Direct Gamma HR Aquatic Vegetation 84                    **         Cold Spring
* 10.88 Mi (N) at 356 0       HR Shoreline Soil HR Bottom Sediment 88                  DR6          RlS Pole #6                         0.32 Mi (ESE) at 1180        Direct Gamma Highland Ave & Sprout Brook Road 89                 DR35                                              2.89 Mi (NNE) at 025 0       Direct Gamma (near rock cut) 90                  DR3          Charles Point                       0.88 Mi (NE) at 047"         Direct Gamma 0
92                 DR24          Warren Road - Cortlandt                   Mi (SSE) at 149        Direct Gamma A2                                                                            Air Particulate A2                                              Onsite- 0.39 Mi (S) at         Radioiodine 94                               IPEC Training Center Ic2                                              193 0                     Broad Leaf Vegetation Soil A3                                                                            Air Particulate A3                                              Onsite -                       Radioiodine 95                               Meteorological Tower Ic1                                                   Mi (SSW) at 208 0   Broad Leaf Vegetation Soil MW-40 Boundary Well, lower parking 104                    **                                             Onsite - 0.21 mi (SW)         Groundwater lot MW-51 Boundary Well, middle 105                                                                   Onsite - 0.18 mi (SSW)        Groundwater parking lot
  * = Control location
** = Locations listed do not have sample designation locations specified in the aDCM HR = Hudson River RlS = Reuter Stokes                             A-4

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point Peekskill Westchester County Rockland County Indian    .&r-pOint~A:
rn   (7)                  1 mile (3)121 Ic1     IC2 11              9
                                    @rn Buchanan Key:      I::J. - Waterborne: Surface (HR) Wa#            Ic# - Broadleaf Vegetation o -Direct Radiation Sample Location DR#          Ib1 - Fish and Invertebrates (where available downstream) o -Air Particulate & Radioiodine A#
         <> - HR Shoreline Sediment Wc#
A-5

FIGURE A-2 SAMPLING LOCATIONS Greater Than 2 Miles From Indian Point N
                                     ~ Roseton (20.7 mJ. N), 0      @    Ic3 Upstream:     Ib2 Orange County                                       Putnam County
                                                 @)
Bear Mountain Bridge
(@
             @)
5 miles Rockland County                                   Westchester County Key:  o -Direct Radiation Sample Location DR#       Ic3 - Broadleaf Vegetation o -Air Particulate & Radioiodine A#           Ib2 - Fish and Invertebrates 0- HR Shoreline Sediment Wc#                        (where available upstream) o - Waterborne: Drinking Wb#
A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N
                                  .~            Roseton (20.7 mi: N): 23 : p +
Orange C()unty                           Rutnam County Cold Spring (10.88 mi. N) : 84 :'f
                                                                              +'
Bear Mountain Bridge 10:
* 17: ...
            <>r-------f-;.                                     -104/105 :gw
* 22:. - -.......
29:. _ _ _....
Westchester County Rockland County 27: *
                                                                    &deg;8: dw
                                                     ,/
5 miles Key:   * - Air Particulate & Radioiodine    <>- HR Shoreline Sediment
       'f - Aquatic Vegetation              +-Soil
      * - HR Bottom Sediment                \g# - Ground Water Boundary Monitoring p - Precipitation                         (see detailed site map) dw - Drinking Water A-7

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

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES H-3                   20,000 (a)
Mn-54                   1,000                                   30,000 Fe-59                    400                                    10,000 Co-58                   1,000                                   30,000 Co-60                    300                                    10,000 Zn-65*                   300                                    20,000 r-Nb-95                400 1-131                    2 (b)                0.9                                    3           100 Cs-134                    30                   10                1,000              60          1,000 Cs-137                    50                  20                 2,000              70          2,000 8a-La-140                200                                                        300 Sr-90                      8                                       40 (a) For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCilL may be used.
(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.
A-9

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

==SUMMARY==

APPENDIX B B.1 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% See Table B-1a CHARCOAL FIL TER                      466              2   99.6% See Table B-1a TLD                                   164              2    99%  See Table B-1b HUDSON RIVER WATER                     32              0   100%       N/A DRINKING WATER                         24              0   100%       N/A ORELINE SOIL                        20              4    80%  See Table B-1c LEAF VEGETATI                  54              0   100%       N/A H & INVERTEBRATES                   27              0   100%       N/A UATIC VEGETATION                     3              0   100%       N/A 8              0   100%       N/A IL                                   3              0   100%       N/A PRECIPITATION                           8              0   100%       N/A GROUNDWATER SAM                        45              0   100%       N/A ALS                             1322              9   99.3%
TOTAL NUMBER OF ANALYSES REPORTED =                   1313
* Samples not collected or unable to be analyzed.
B-2

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!;&sect;<.!~i~~\r;:l:i<:  ::j:~:~!:e~fi?&sect;I!E&#xa5;JJi!'<:;1iI~~\"f;~~e~V~!;~E~.Y~R&sect;~g.~;:I;f~';r ",','J; LOVETT                           01/16/2007                              We lost about 90 hours of sample this past week. The pump had failed.
The Lovett air sample lost 48 hours of sample time last week. It was running LOVETT                           03/12/2007 when we left it last week and it was running when we changed it this week.
The Lovett air sample lost 105 hours of sample time last week. It was running LOVETT                           04/16/2007 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 LOVETT                           04/23/2007 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 hours of sample time last week. II was LOVETT                           05/21/2007                              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 hours TRAINING BLDG                    06/12/2007 of sample. We replaced the pump.
The Peekskill Gas Holder air sample was not running when we went to change PEEKSKILL GAS HOLDER             07/30/2007 it out. The pump had failed and we lost 80 hours of sample this past week, The Training Bldg air sampler lost 18 hours of sample time last week. It was TRAINING BLDG                    11/13/2007                              running when left the week berofre and it was running when changed out again.
The Grassy Point air sample lost 47 hours of sample last week, It was running GRASSY POINT                     12/26/2007 when we left it last week and it was running when we changed it this week.
TABLE B-1b 2007 TLD Deviations
        ~1~'9111*;r:,                           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 TLD 200 & 212                    10/18/2007 missin .
TABLE B-1c 2007 Other Media Deviations The dock was snow covered and ice covered and unsafe to go out and get the HUDSON RIVER INLET               02/16/2007 sample, HUDSON RIVER OUTLET              02/16/2007                              The hose was frozen and there was no sample for the week, LENT'S COVE                      06/06/2007                              Shoreline soil sample not analyzed for Sr-90 WHITE BEACH                      06/07/2007                              Shoreline soil sample not analyzed for Sr-90 MANITOU INLET                    06/06/2007                              Shoreline soil sample not analyzed for Sr-90 COLD SPRING                      06/06/2007                              Shoreline soil sample not analyzed for Sr-90 LENTS COVE                       09/06/2007                              No aquatic vegetation was found in this area VERPLANCK AREA                   09/06/2007                              No aquatic vegetation was found in this area 8-3

TABLE B-2 ODeM ANNUAL 

==SUMMARY==
 - 2007 (mR 1 standard quarter)
TLD Reads N/A 14.3 (160/160) /
West Shore Drive - North 1.21 Mi (W) at 276: . DR13 I    18.8 (4/4) /
I 0 164                              9.5 - 22.2                                         17.4-21.5 8-3                                                                              20.0 (4/4) / 18.3 - 21.6 AIR PARTICULATES AND RADIOIODINE (pCi/m3) 8-6, 8-7, 8-8 G8 (467) 0.013     (415/416) /
0.003 - 0.026
                                                                                               #22 Lovett Power Plant 1.6 Mi (WSW) at 244 0 0.014 (51/52) 1 0.003-0.023 I 0.013 (52152) /
0.003-0.023 I 0 1-131 (466)           0.07                 <Lc                         <L(
r.::C::.d {':l~\
0.05                 <Lc                         <Lc                    <Lc         0 0.06                 <Lc*                        <Lc                    <Lc         0 L.S- 1"1      I I
SURFACE HUDSON RIVER WATER (pCi/L)                H-3 (8)       I 3000 (c)   I           <Lc          I              <Lc            I       <Lc       I 0 8-9,8-10 GSA (24}
Mn-54             15                  <Lc                         <Lc                    <Lc         0 Co-58             15                  <Lc                         <Lc                    <Lc         0 Fe-59             30                  <Lc                         <Lc                    <Lc         0 Co-60             15                  <Lc                         <Lc                    <Lc         0 Zn-65             30                  <Lc                         <Lc                    <Lc         0 Zr/Nb-95              15                  <Lc*                        <Lc                    <Lc         0 1-131            15                  <Lc                         <Lc                    <Lc         0 Cs-134             15                  <Lc                         <Lc .                  <Lc         0 Cs-137              18                  <Lc                         <Lc                    <Lc         0 8a/La-140              15                  <Lc                         <Lc                    <Lc (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                   B-4
* TABLE B-2 aDeM ANNUAL 

==SUMMARY==
 - 2007 Mn-54                 15             <Lc                     <Lc                N/A           0 Co-58                15             <Lc                     <Lc                N/A           0 Fe-59               30              <Lc                     <Lc                N/A           0 Co-60                 15 c           <Lc                     <Lc                N/A           0 Zn-65                30              <Lc                     <Lc                N/A           0 Zr/Nb-95               15*            <Lc                     <Lc                N/A           0 1-131               15              <Lc                     <Lc                N/A           0 Cs-134                15             <Lc                     <Lc                N/A           0 Cs-137                18             <Lc                     <Lc                N/A           0 Ba/La-140               15             <Lc                     <Lc                N/A           0 GSA (10)
I (pCilkg -dry) B-13 Cs-134               150             <Lc                     <Lc                <Lc           0
                                                                                         #17 Off Verplanck    #50 Manitow Inlet 106 (2/6) 1 Cs-137               180 63.3 - 149 1.5 Mi (SSW) at 202.5"     357 (114) /    I 0 106 (2/2) 1 63.3 - 149    357 - 357 Sr-90 (6)            5000             <Lc                     <Lc                <Lc '         0 (a) Positive values above L"; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCilL              8-5

TABLE B-2 ODeM ANNUAL 

==SUMMARY==
 - 2007 (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           8-6

TABLE B-2 aDeM ANNUAL 

==SUMMARY==
 - 2007 BOTTOM SEDIMENT (pCi/kg - DRY)
I      GSA(8)
Co-60              NONE                <Lc                    <Lc                  <Lc             0 Cs-134              150                <Lc                    <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 Cs-137              180                                                                            0 95.0 - 373.7           291.5 (2/2) 1        254.8 (1/2) /
373.7 - 209.2        254.8 - 254.8 SOIL GSA(3)
(pCilkg - DRY)
Co-60              NONE                <Lc                    <Lc                  <Lc             0 Cs-134              150                <Lc                    <Lc                  <Lc             0
                                                                   #94 Training Center    #94 Training Center 0.45 Mi (SSW) at 208 0 0.45 Mi (SSW) at 208 0 Cs-137              180                                                            <Lc             0 136.5 (1/2) 1          136.5 (1/1) 1 136.5 - 136.5          136.5 - 136.5 PRECIPITATION                 GSA(8)
(pCi/L)
H-3             3000 (c)             <Lc                    <Lc                  <Lc             0 Co-60                15                <Lc                    <Lc                  <Lc             0 Cs-134               15                <Lc                    <Lc                  <Lc             0 Cs-137               18                <Lc                    <Lc                  <Lc             0 (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 pCiJL                 8-7

TABLE B-2 aDeM ANNUAL 

==SUMMARY==
 - 2007 GROUNDWATER GSA(45)
(pCilL)
                                                                                           #105 MW-51 194 (5/45) I         0.18 mi -ssw H-3 (45)           3000 (c)                                            N/A 0 176 - 223            203 (3/26) I 187 - 223 Co-60 (45)             15              <Lc                    <Lc       N/A 0 Cs-134 (45)             15              <Lc                    <Lc       N/A 0
                                                                                           #105 MW-51 11.5 (5/45) 1        0.18 mi - ssw Cs-137 (45)             18                                               N/A 0 5.15 - 21.6           11.5 (5/26) 1 5.15-21.6 Sr-90(41)                              <Lc                    <Lc       N/A 0 (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 pCiIL               8-8

TABLE B-3 2007 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER) 15.69     1.03 DR-02       14.00  +/- 0.55  15.4         13.24 +/- 0.7  14.54     0.69 14.3 57 DR-03    NE 11.91  +/- 0.77  12.9  +/- 0.7  10.47 +/- 0.7  11.75 +/-   0.82 11.8 47 DR-04   ENE 13.03  +/- 0.65  15.0  +/- 0.8  12.57 +/- 0.7  13.63 +/-   0.70 13.6 54 DR-05     E 13.29  +/- 0.75  15.2  +/- 0.7  13.24 +/- 0.8  14.20 +/-   0.82 14.0 56 DR-06   ESE 13.99  +/- 0.53  15.7  +/- 0.7  12.79 +/- 0.7  14.41 +/-   0.63 14.2 57 DR-07    SE 15.44  +/- 0.73  18.5  +/- 0.7  14.73 +/- 0.8  15.96 +/-   0.79 16.2 65 DR-08   SSE 11.70  +/- 0.55  1~.6  +/- 0.7  11.38 +/- 0.8  12.04 +/-   0.55 12.2 49 DR-09     S 12.81  +/- 0.71  14.3  +/- 0.8  12.46 +/- 0.9  13.43 +/-   0.82 13.3 53 DR-10   SSW 13.28  +/- 0.62  15.2  +/- 1.1  13.64 +/-.0.9. 14.53 +/-   0.78 14.2 57 DR-11    SW 10.35  +/- 0.57  12.3  +/- 0.8   9.96 +/- 0.6  10.63 +/-   0.69 10.8 43 DR-12   WSW 16.39  +/- 0.77  19.5  +/- 0.9  16.86 +/- 0.9  15.52 +/-   0.79 17.1 68 DR-13     W 18.34  +/- 0.78  21.6  +/- 1.1  19.49 +/- 1.5  20.74 +/-   1.07 20.0 80 DR-14   WNW 12.51  +/- 0.69  15.5  +/- 1.2  13.39 +/- 1.1  12.86 +/-   0.99 13.6 54 DR-15    NW 12.95  +/- 0.66  15.4  +/- 0.6  12.59 +/- 0.7  13.88 +/-   0.86 13.7 55 DR-16   NNW 13.82  +/- 0.61  16.9  +/- 0.6  14.78 +/- 0.7  15.08 +/-   0.82 15.2 61 DR-17     N 14.27  +/- 0.78  17.3  +/- 1.0  14.49 +/- O.         +/-   1.35 15.3 61 DR-18   NNE 13.53  +/- 0.66  16.2  +/- 0.9  12.85 +/- 0.7  14.50 +/-   0.93 14.3 57 DR-19    NE 14.89  +/- 1.28  16.7  +/- 0.9  13.47 +/- 1.0  15.17 +/-   0.85 15.0 60 DR-20   ENE 12.58  +/- 0.58  14.6  +/- 0.7  12.37 +/- 0.8  13.71 +/-   0.87 13.3 53 DR-21     E 13.27  +/- 0.71  15.5  +/- 0.6  12.09 +/- 0.8  13.94 +/-   0.76 13.7 55 DR-22   ESE 11.42  +/- 0.65. 13.1  +/- 0.9   9.52 +/- 0.6  11.63 +/-   0.70 11.4 46 DR-23    SE 13.28  +/- 0.47  16.3  +/- 1.0  12.q4 +/- 0.7  13.97 +/-   1.20 14.0 56 DR-24   SSE 13.87  +/- 0.85  16.4  +/- 0.8  13.68 +/- 0.7  14.93 +/-   0.73 14.7 59 DR-25     S 12.17  +/- 0.56  15.5  +/- 1.0  11.51 +/- 0.8  13.42 +/-   0.91 13.1 53 DR-26 . SSW 13.58  +/- 0.61  16.9  +/- 0.7  13.70 +/- 1.2  14.73 +/-   1.18 14.7 59 DR-27    SW 13.01  +/- 0.91  17.3  +/- 2.2  12.61 +/- 0.8  13.65 +/-   0.84 14.1 57 DR-28   WSW 18.05  +/- 0.66  22.2  +/- 0.9  18.57 +/- 0.9  20.06 +/-   1.19 19.7 79 DR-29     W 13.12  +/- 0.68  17.9  +/- 1.3  13.43 +/- 0.7  14.27 +/-   0.88 14.7 59 DR-30   WNW 13.55  +/- 0.58  18.8  +/- 1.0  14.42 +/- 0.7  14.56 +/-   0.63 15.3 61 DR-31    NW 15.57  +/- 0.67  19.8  +/- 0.9  15.46 +/- 1.1  16.59 +/-   0.89 16.9 67 DR-32   NNW 12.97  +/- 0.50  16.1  +/- 0.9  12.31 +/- 0.7  13.33 +/-   0.68 13.7 55 DR-33    NE 13.12  +/- 0.88  15.8  +/-  .7        +/- 0.7  13.50 +/-   0.68 13.7 55 DR-34    SE 12.24  +/- 0.50  15.5  +/- 0.9  11.28 +/- 0.6  12.21 +/-   0.59 12.8 51 DR-35   NNE 12.95  +/- 0.62  15.4  +/- 0.8  11.63 +/- 0.6  13.01 +/-   0.95 13.2 53 DR-36 . 14.28  +/- 0.76  17.6  +/- 2.3  13.07 +/- 0.8  14.91 +/-   1.34 15.0 60 DR-37       12.75  +/- 0.61  15.4  +/- 0.6  12.17 +/- 1.6  14.60 +/- . 0.86 13.7 55 DR-38       11.71  +/- 0.58  14.5  +/- 0.7  11.60 +/- 0.7  13.59 +/-   0.66 12.8 51 DR-39       14.46  +/- 0.70  18.1  +/- 2.2  13.79 +/- 0.7  14.94 +/-        15.3 61

TABLE B-4 DIRECT RADIATION, 1997 THROUGH 2007 DATA (mR per Standard Quarter) 64.4                   53.7 48.2                   43.8      50.4  47.0 53.9     3.7           46.8      58.6  54.3 54.5     2.6           48.3      58.0  55.9 53.8     3.1           46.2      57.6  56.9 DR-07 63.7     3.7           55.6      68.6  64.6 DR-08 52.1     2.6           47.1      56.3  48.7 DR-09 51.6     3.6           44.1      55.2  53.0 DR-10 55.3     6.0           39.2      59.8  56.7 DR-11 45.3     2.2           40.8      48.5  43.3 DR-12 67.0     3.7           62.4     .76.0  68.3 DR-13 76.2     4.0           67.8            80.2 DR-14 54.4     3.5           49.8 4.1           46.5 55.2 DR-18 57.0     2.6           52.2      60.7  57.1 DR-19 60.0     2.8           55.1      63.6  60.2 DR-20 54.8     3.7           47.4      59.2  53.3 DR-21 55.2     3.2           49.8      60.6  54.8 DR-22 46.8     3.6           40.2      51.9  45.7 DR-23 56.1     2.9           49.5      58.9  56.1 DR-24 55.7     2.9           49.2      59.8  58.9 DR-25 49.7     2.5           44.7      53.2  52.6 DR-26 55.2     2.5           50.4      58.9  58.9 DR-27 55.3     3.9           46.8      61.5  56.6 DR-28 64.8     6.5           57.2      77.1  78.9 DR-29 66.8     8.7           54.6            58.8 DR-30 63.9     6.3           52.2            61.3 5.8           62.1 3.4           45.9 DR-34 53.5     4.7           43.2      60.7  51.2 DR-35 57.4     4.1           48.6      61.2  52.9 DR-36 61.8     5.0           52.5      70.5  59.9 DR-37 55.2     3.3           48.9      60.0  54.9 DR-38 52.2     2.8           48.6      58.4  51.4 DR-39 62.8                             66.8* 61.3 6-10

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

TABLE B-6 IPEC ENVIRONMENTAL AI~BORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pCiI m3 +/- 1 Sigma SAMPLE STATION #                           ----              - - -         ----         - -     - -          -          -
Week  ';WeekEnd 1-Number ,. 'Date'-
                               ,A',*
                                       ~,
                                                            .i, I'
I?,:    95'"
1
                                                                                                  \
                                                                                                        *t;f,.;" ' W~~~;,
Numbe'i * '-~'-T:~ ~ :'-!~D;    ',....
                                                                                                                                                         ..,:.;t:~~:;,',: b,:'~J{-'
                                                                                                                                                                    -  -,:               ." ~      4:;~::'
1    01/02/2007    0.012 +/- 0.001      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         0.016 +/- 0.001    0.012 +/- 0.001 2    01/0912007    0.013 +/- 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    O.oI 5 +/- 0.002 3    01116/2007    0.011 +/- 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         0.010 +/- 0.001    0.012 +/- 0.001 4    01/23/2007    0.017 +/- 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         0.014 +/- 0.001    0.014 +/- 0.001 5    01/3012007    0.015 +/- 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         0.016 +/- 0.001    0.016 +/- 0.001 6    02/06/2007    0.020 +/- 0.002     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         0.020 +/- 0.001 '0.023 +/- 0.002          I 7    02/13/2007    0.015 +/- 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         0.011 +/- 0.001    0.014 +/- 0.001 8    0212012007    0.017 +/- 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         0.015 +/- 0.001    0.016 +/- 0.001
  *9      02127/2007    0.010 +/- 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        0.013 +/- 0.001    0.010 +/- 0.001        I 10    03/06/2007    0.011 +/- 0.001     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         0.009 +/- 0.001    0.009 +/- 0.001        I 11    03113/2007    0.018 +/- 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         0.020 +/- 0.001    0.018 +/- 0.001' 12    03/20/2007    0.015 +/- 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         0.016 +/- 0.001    0.015 +/- 0.001 13    0312712007    0.010 +/- 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         0.015 +/- 0.001    0.013 +/- 0.001 14    04/03/2007    0.011 +/- 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         0.011 +/- 0.001    0.012 +/- 0.001 15    0411012007    0.004 +/- 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         0.004 +/- 0.001    0.004 +/- 0.001 16    04/17/2007    0.004 +/- 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         0.005 +/- 0.001    0.009 +/- 0.001 17    04/2412007    0.011 +/- 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         0.012 +/- 0.001    0.006 +/- 0.001 18    05101/2007    0.008 +/- 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         0.007 +/- 0.001    0.008 +/- 0.00 I       !
19    05108/2007    0.008 +/- 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         0.008 +/- 0.001    0.008 +/- 0.001 20    05/15/2007    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         0.006 +/- 0.001    0.009 +/- 0.001 21    05122/2007    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         0.012 +/-O.OOI     0.013 +/- 0.001!
22    05129/2007    0.015 +/- 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         0.015 +/- 0.001    0.020 +/- 0.001 23    06/05/2007    0.012 +/- 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         0.015 +/- 0.001    0.013 +/- 0.001        I 24    06/12/2007    0.009 +/- 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          0.008 +/- 0.001    0.010 +/- 0.001        I 25    06/19/2007    0.009 +/- 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         0.010 +/- 0.001    0.009 +/- 0.001 L-26_   ~/26/2007       (J.013 +/- O.()()l 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         0.011 +/- 0.001    0.013 +/- 0.001        I
               ** Control sample location 8-12

TABLE B-6 ENVIRONMENTAL AIRBORNE PARTICVLATE SAMPLES - 2007 3
GROSS BETA ACTIVITY pCiI m +/- I Sigma SAMPLE STATION #
I Number.'
weeki* WeekEnd Date 07/02/2007 I
4 0,010 +/- 0,001 I      5 0,009 +/- 0,00 I I';'   94    . 'I 0,013 +/- 0,001 95
                                                                                    ... ~
0.013 +/- 0.001
                                                                                           ',; ,I****.  '23**: '
0.016 +/- 0,001 11~:~t~rff' 22,::~.
27   0,016 +/- 0.001
                                                                                                                                       'I '    27, 0,013 +/- 0,001 l'       29' 0.013 +/- 0,001 I
44 0.017 +/- 0.001 27 28     07/1012007    0,016 +/- 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    0.012 +/- 0,001   0,010 +/- 0,001 I 29     07/17/2007    0,016 +/- 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    0.015 +/- 0,001   0.016 +/- 0.001 30     07124/2007    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    0,009 +/- 0.001   0.016 +/- 0.001 31     07/3112007    0.015 +/- 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    0.012 +/- 0.001   0.010 +/- 0,002 32     08/07/2007    0,021 +/- 0.002      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    0.017 +/- 0,001   0.Dl8 +/- 0.002 33     08/14/2007    0.017 +/- 0.001      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   0.018 +/- 0.001    0,015 +/- 0.001 34     0812112007    0.013 +/- 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   0,012 +/- 0.001    0.013 +/- 0.001 35     08/28/2007    0.011 +/- 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   0,010 +/- 0.001    0.009 +/- 0.001 36     09/04/2007    0.016 +/- 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   0.018 +/- 0.001    0.015 +/- 0,001 37     0911112007    0,018 +/- 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   0.017 +/- 0.001    0,020 +/- 0.002 38     09118/2007    0.010 +/- 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   0.008 +/- 0.001    0,009 +/- 0.001 39     09/2512007    0,020 +/- 0,002      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   0,017 +/- 0.001    0.021 +/- 0.002 40     10/02/2007    0.017 +/- 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   0.021 +/- 0.001    0,018 +/- 0,002 41     10/09/2007    0,015 +/- 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    0.013 +/- 0.001   0.012 +/- 0,001 42     1011612007    0,005 +/- 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   0.007 +/- 0.001    0.004 +/- 0.001 43     10/23/2007    0,024 +/- 0,002      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   0,020 +/- 0.001    0.021 +/- 0.002 44     10/30/2007    0,011 +/- 0,001      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   0.011 +/- 0.001    0.022 +/- 0,002 45     11/06/2007    0.019 +/- 0,002      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   0.019 +/- 0.001    0,017 +/- 0,002 46     11113/2007    0,011 +/- 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    0.013 +/- 0.001 47     11119/2007    0,016 +/- 0.002      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]   0,015 +/- 0,001    0.017 +/- 0.002 48     11127/2007    0,011 +/- 0,001      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   0.014 +/- 0.001    0,013 +/- 0,001 49     12/04/2007    0,014 +/- 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    0.014 +/- 0.001 50     12/1112007    0.013 +/- 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   0.013 +/- 0,001    0.012 +/- 0.001 51     12118/2007    0,016 +/- 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   0,019 +/- 0,001    0.019 +/- 0.002 52     12/24/2007    0,018 +/- 0,002      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   0.020 +/- 0,001    0.019 +/- 0.002
                ** Control sample location 8-13

TABLE B-7 CONCENTRA TIONS OF GAMMA EMITTERS IN QVARTERL Y COMPOSITES OF SITE AIR PARTICVLATE SAMPLES - 2007 j
Results in Vnits of 10E-3 pCiI m +/- 1 Sigma SAMPLE LOCATIONS -1ST QTR 2007
                                                            , :',                ,s*  ..       ','            "
Loyett#22;~* :              Roseton#23<',                       Peekskill #44 :', '
Nuclide    Algonquin Sta #4  NYU Tower #5      Croton Point.#27 Training Bldg #94 ' Met Tower #95'
                                                                       ,    '   "":          .     !'I-,
                                                                                                                         .'                             .,,'            Grassy,Point #29 Be-7       57.5 +/-   20.2  84.2 +/-  20.5   122.4 +/-     29.3   115.3 +/-      23.7    95.7 +/-           24.3    108.5 +/-                25.5 112.2 +/-  21.2   91.4 +/-     17.8     < 26.8 C5-134         < 1.5           < 1.6             < 1.5                < L1                        < 1.9                    < 1.5                      < 1.4              < 0.9             < 1.6 C5-137         < 0.8           <  0.7            <  1.3               < 1.0                       <   0.8                  < LI                       < 1.6              <   0.5           <  1.2 Zr-95         < 2.6           <  3.0            <  3.5               < 2.8                       <   3.0                  < 5.3                      < 2.5              <   1.9           <  3.8 Nb-95         < 2.5           <  2.7            <  2.9               < 2.5                       <   2.5                  < 2.7                      < 2.4              <   2.0           <  3.1 Co-58         < 2.2           <  1.4            <  2.3               < 1.7                       <   1.6                  < 2.5                      <1.5               <   Ll            <  2.5 Mn-54          <\.2            <  1.0            <  1.5               <\.2                        <   1.2                  <\.2                       < 1.5              <   0.8           <  1.7 Zn-65         < 3.0           <  3.8            <  4.5               < 2.8                       <   3.3                  < 3.0                      < 3.2              <   3.0           <  4.9 Co-60         <\.7            <  \.2            <  2.2               < 1.6                       <   1.7                  < 1.7                      < \.7              <   1.0           <  2.6 K-40          < 18.7          <  13.4           <  24.2              < 14.1                      <   17.6                 <; 18.6                    < 17.1             <   10.3          <  24.4
**  Control Sample Location SAMPLE LOCATIONS - 2ND QTR 2007
 , Nuclide    A}gonquin Sta #4  NYU_Tower #5     ,Croton Point~~7: Tiaining,Bldg#941 'My,tTo>>,erif95.                  _, ;' I:,6ve~#22
                                                                                                                                                  **'   Roseton #23.   ;,Q~assY~~int: ;291 . Peekskill#44 Be-7      13 L5 +/-   17.0 103.3 +/-  12.7   110.1  +/-     14.6  125.5 +/-      14.6 I 136.0         +/-   14.1    107.1      +/-           15.0 137.1  +/- 17.2  131.3 +/-     12.31109.5 +/-         15.1 C5-134         < 0.7           < 0.6             <  0.4               < 0.9                       < 0.7                    <  0.9                     <  0.5             <   ~3            <  ~6 C5-137         < 0.5           < 0.3             <  0.4               < 0.6                       < 0.3                    <  0.6                     <  0.4             <   0.6           <  0.6 Zr-95         < 1.6           < 1.8             <  1.6               < 1.4                       < 0.9                    <  2.4                     <  2.0             <   \.2           <  1.2 Nb-95         < 1.5           < 0.6             <  LI                < 0.8                       < 1.5                    <  0.9                     <  1.4             <   1.0           <  1.4 Co-58         < 0.7           < 0.7             < 0.7                < 0.7                       < 0.7                    <  0.6                     <  0.9             <   0.4           <  0.7 Mn-54          < 0.8           < 0.6             < 0.9                < 0.8                       < 0.5                    <  0.6                     <  0.5             <   0.6           <  0.7 Zn-65         < 2.9           < 1.6             <\.2                 < 1.4                       <1.3                     <  2.0                     <  2.2             <   1.2           <  1.5 Co-60        < 1.0            < 0.5             < 0.8                < 0.8                      < 0.5                     <  0.6                     <  0.9             <   0.8           < 0.8 K-40         < 8.5            < 5.7             < 7.2                < 7.5                       < 6.8                    <  7.1                     <  9.4             <   4.1           <  7.5
**  Control Sample Location 8-14

TABLEB-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2007 3
Results in Units of 10E-3 pCi/ m +/- 1 Sigma
                                                                      ..... a.* .. &~&.J ........... -....~ ..................  ~.~_
                                                                                                                                        --- --~.
Nuclide   Algonquin Sta #4  NYU Tower #5 *. Croton p,oint #27  T~airiingBl?g #94                           ';'MetOTower #95                    Lovett #2i.~*  '.'  R6seton#23'.';
Grassy;. Point..: #29   Peekskill #44 .
Be-7    132.7  +/-  13.6 130.1  +/- 13.2  116.9  +/-  13.6    104.3     +/-         15.0                  112.5           +/-     13.9     143.8  +/-  14.9   130.6   +/-     13.2   136.5 +/-      15.1   112.5  +/-   13.5 Cs-134      <  0.6           <  0.8           <  0.5              <     0.8                                        <      0.3                  <  0.9              <  0.6                < 0.5                 <  0.8 Cs-137      <  0.5           <  0.3           <  0.5              <     0.5                                        <      0.3                  <  0.6              <  0.4                < 0.4                 <  0.3 Zr-95       <  1.4           <  0.9           <  1.9              <     1.6                                        <      1.9                  <  1.4              <  1.7                < 1.2                 <  1.5 Nb-95       <  1.1           <  1.6           <  0.9              <     1.6                                        <      1.6                  <  1.4              <  1.7                < 1.0                 <  0.7 Co-58      .<  0.4           <  0.5           <  0.7              <     1.0                                        <      0.7                  <  0.5              <  1.1                < 0.8                 <  1.0 Mn-54       < 0.3            <  0.7           <  0.5              <     0.7                                        <      0.3                  <  0.4              <  0.3                < 0.5                 <  0.6 Zn-65       < 1.3            <  1.0           <  1.5              <     1.2                                        <      1.6                  <  0.9              <  1.6                <1.3                  <  2.2 Co-60       < 0.5            <  0.5           <  0.5              <     0.8                                        <      0.8                  <  0.5              <  0.5                < 0.6                 <  1.1 K-40       < 6.5            <  5.1           <  9.6              <     7.2                                        <      5.9                  <  5.0            39.4  +/-     8.9       < 7.5                 <  10.5
** Control Sample Location SAMPLE LOCA nONS - 4TH QTR 2007 I
Nuclide I Algonquin Sta#4INYU Tower #5 I Croton Point #27 Training Bldg #941 Met 'rower #95                                                    L~v~ri#22**:"1      Ro~eton ~~3 :;d Grassy POint #29            Peekskill #44 Be-7    109.9 +/-   11.9 105.0 +/-  15.2   89.4 +/-   12.1    119.6     +/-         14.9                  102.8           +/-     13.4      99.4  +/-  13.0   109.2 +/-       12.4    96.1 +/-      13.5   102.2 +/-    12.9 Cs-134      < 0.7            < 0.7            < 0.3               <     0.4                                        <      0.4                  <  0.6              < 0.5                 < 0.6                 < 1.0 Cs-137      < 0.4            < 0.7            < 0.2               <     0.5                                        <      0.6                  <  0.6              < 0.5                 < 0.4                 < 0.4 Zr-95       < 1.4            < 1.6            < 0.8               <     1.8                                        <      1.2                  <  1.7              <1.7                  < 1.0                 < 1.5 Nb-95       < l.l            < 1.0            <1.3                <     2.0                                        <      1.4                  <  1.6              < 0.9                 < 1.6                 < 1.7 Co-58       < 0.5            <1.3             < 0.8               <     1.0                                        <      1.0                  <  1.0              < 0.9                 < l.l                 < 1.0 Mn-54       < 0.7            < 0.9            < 0.5               <     0.5                                        <      0.7                  <  0.8              < 0.4                 < 0.4                 < 0.7 Zn-65       < 1.9            < 2.3            < 0.8               <     2.5                                        <      2.1                  <  1.7              < 1.5                 < 1.3                 < 1.8 Co-60       < 0.8            < 0.9            < 0.8               <    0.8                                         <     0.6                   < 0.6               < 0.7                 < 0.7                 < 0.5 K-40     45.2 +/-   8.9     < 8.2            < 5.2               <     10.2                                       <      6.0                  < 6.9             27.8 +/-      7.6       < 7.6                 < 5.5
** Control Sample Location 8-15

TABLE B-8
                                                                  }PEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCiI m 3 +/- 1 Sigma SAMPLE STATION #
Week     WeekEnd       I                                      I,' --"--, ','       : ..
                                                                                          ",'< "                       i':  I>,':,      ",";"
Number Date' 4 ,         5     "
94'
                                                                '(:>-;
                                                                              -23**           ,22
                                                                                                ,; ",~,
                                                                                                          -'27-
                                                                                                          ':'j,      :39,:'   '-t,':';,   _.
I      01102/07         <  0.025     <  0.023       < 0.022    <   0.018   < 0.028       <   0.022      < 0.022 <  0.020      <  0.021 2      01109107         <  0.029     <  0.019       < 0.024    <   0.031   < 0.036       <   0.067      < 0.020 <  0.020      <   0.034 3      01116/07         <  0.033     <  0.032       < 0.035    <   0.039   < 0.023       <   0.041      < 0.023 <  0.022      <  0.025 4      01/23/07         <  0.022     <  0.020       < 0.023    <   0.029   < 0.034       <   0.046      < 0.022 <  0.013      <  0.007 5      01130107         <  0.014     <  0.025       < 0.027    <   0.033   < 0.030       <   0.031      < 0.019 <  0.019      <  0.033 6      02/06/07         <  0.026     <  0.017       < 0.022    <  0.023    < 0.026       <   0.034      < 0.014 <  0.026      <  0.023 7      02/13/07         <  0.056     <  0.024       < 0.027    <   0.047   < 0.039       <   0.058      < 0.035 <  0.030      <  0.045 8      02/20107         <  0.023     <  0.025       < 0.032    <   0.040   < 0.017       <   0.027      < 0.019 <  0.020      <  0.029 9      02/27/07         <  0.051     <  0.036       < 0.030    <  0.042    < 0.029       <   0.046      < 0.035 <  0.033      <  0.011 10      03/06107         <  0.023     <  0.016       < 0.024    <   0.023   < 0.039       <   0.032      < 0.027 <  0.013      <  0.019 II      03113/07         <  0.022     <  0.036       < 0.024    <   0.015   < 0.032       <   0.038      < 0.026 <  0.018      <  0.023 12      03120107         <  0.033     <  0.028       < 0.031    <  0.021    < 0.036       <   0.044      < 0.027 <  0.017      <  0.025 13      03/27/07         <  0.017     <  0.021       < 0.024    <  0.030    < 0.028       <   0.020      < 0.022 <  0.022      <  0.027 14      04/03/07         <  0.044     <  0.023       < 0.035    <   0.031   < 0.Q28       <   0.028      < 0.030 <  0.022      <  0.017 15      04110107         <  0.029     <  0.031       < 0.024    <   0.019   < 0.022       <   0.027      < 0.013 <  0.021      <  0.032 16      04117/07         <  0.038     <  0.027       < 0.032    <   0.026   < 0.036       <   0.068      < 0.025 <  0.017      <   0.029 17      04/24/0?-        <  0.021     <  0.030       < 0.026    <  0.023    < 0.026    Deviation Report  < 0.026 <  0.013      <  0.017 18      05101/07         <  0.023     <  0.016       < 0.023    <   0.038   < 0.023       <   0.028      < 0.026 <  0.023      <  0.032 19      05/08/07         <  0.030     <  0.038       < 0.030    <   0.031   < 0.034       <   0.041      < 0.029 <  0.017      <   0.020 20      05/15/07         <  0.042     <  0.041       < 0.014    <  0.031    < 0.039       <   0.033      < 0.027 <  0.032      <  0.019 21      05122107         <  0.028     <  0.009       < 0.027    <   0.030   <0.031        <   0.049      < 0.017 <  0.028      <  0.020 22      05129107         <  0.036     <  0.024       < 0.031    <   0.039   < 0.016       <   0.018      < 0.022 <  0.031      <  0.039 23      06/05/07         <  0.024     <  0.021       < 0.019    <  0.022    < 0.036       <   0.035      < 0.017 <  0.031      <  0.023 24      06112107         <  0.030     <  0.024       < 0.044    <  0.035    < 0.037       <   0.033      < 0.026 <  0.027      <  0.028 25      06/19107         <  0.035     <  0.021       < 0.026    <   0.030   < 0.033       <   0.029      < 0.022 <  0.029      <  0.032 26      06126107         <  0.024     < 0.024        < 0.055    <  0.025    < 0.027       <   0.052      < 0.022 <  0.017      <  0.024
             ** Control sample location B-16

TABLEB-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 3
1-131 ACTIVITY pCiI m +/- 1 Sigma SAMPLE STATION #
        . Week End                                     94    **.                 .'. 23**  ....
* C".
iT "
Week
.Number       Date 4           5
                                                                 ***. **C*95 :        ..   . . .*.
                                                                                                   ... 22 I
: 29.          .' 44 27      07/02/07          <  0.030     < 0.031    < 0.024           <.0.028      <    0.030        < 0.036    < 0.025          <    0.016     <   0.024 28      07110107          <  0.027     < 0.030    < 0.029           < 0.022      <    0.024        < 0.037    < 0.018          <    0.018     <   0.022 29      0711 7/07         <  0.032     < 0.005    < 0.020           < 0.032      <    0.025        < 0.035    < 0.009          <    0.023     <   0.010 30      07124/07          <  0.022     < 0.023    < 0.020           < 0.037      <    0.024        < 0.021    < 0.021          <    O.oJ8     <   0.016 31      07/31/07          <  0.021     < 0.023    < 0.028           < 0.020     <     0.006        <0.031     < 0.016         <    0.036      <   0.011 32      08/07/07          <  0.034     < 0.029    < 0.030           < 0.033     <     0.027        < 0.030    < 0.036         <    0.024      <   0.018 33      08/14/07          <  0.035     < 0.025    < 0.028           < 0.022      <    0.027        < 0.053    < 0.021          <    0.025     <   0.009 34      08/2I107          <  0.029     < 0.016    < .0.020          < 0.028     <     0.028        < 0.042    < 0.031          <   0.022      <   0.034 35      08/28/07          <  0.027     < 0.032    < 0.021           < 0.034     <     0.010        < 0.037    < 0.022         <    0.021      <   0.029 36      09104/07          <  0.032     < 0.006    < 0.032           < 0.021      <    0.029        < 0.028    < 0.026         <     0.025     <   0.021 37      09/11/07          <  0.035     < 0.028    < 0.021           < 0.033     <     0.033        < 0.022    < 0.027        .<    0.016      <   0.031 38      09118107          <  0.022     < 0.033    < 0.027           < 0.029      <    0.033        < 0.031    < 0.019         <     0.037     <   0.023 39      09125107          <  0.034     < 0.021    < 0.028           < 0.021      <    0.029        < 0.027    < 0.031         <     0.027     <   0.027 40      10102/07          <  0.028     < 0.016    < 0.030           < 0.036      <    0.035        < 0.031    < 0.025         <     0.028     <   0.027 41      10109107          <  0.029     < 0.029    < .0.037          < 0.007      <    0.036        < 0.034    < 0.027         <     0.014     <   0.027 42      10/16/07          <  0.029     < 0.033    <0.030            < 0.032      <    0.045        < 0.036    < 0.031         <     0.023     <   0.039 43      10/23107          <  0.027     < 0.034    < 0.027           < 0.036     <     0.030        < 0.031    < 0.019         <    0.D21      <   0.022 44      10/30107          <  0.028 .   < 0.029    < 0.031           < 0.028      <    0.025        < 0.029    < 0.020          <    0.024     <   0.038 45      1 II06/07         <  0.037     < 0.025    < 0.030           < 0.022      <    0.033        < 0.025    < 0.024          <    0.022     <   0.028 46      11/13107          <  0.026     < 0.029    < 0.040           < 0.030      <    0.024        < 0.026    < 0.033          <    0.031     <   0.023 47      11/19107          <  0.010     < 0.028    < 0.025           < 0.040      <    0.046        < 0.029    < 0.040          <    0.020     <   0.030 48      11127107          <  0.008     < 0.030    < 0.023           < 0.023      <    0.038        < 0.036    < 0.021          <    0.022     <   0.035 49      12104/07          <  0.030     < 0.024    < 0.007           < 0.022      <    0.023        < 0.044    < 0.032          <    0.026     <   0.028 50      12111107          <  0.007     < 0.033    < 0.028           < 0.028      <    0.032        < 0.031    < 0.034          <    0.023     <   0.044
                                                                       < 0.025      <    0.026        < 0.025    < 0.020          <    0.022     <   0.030 51 52
          -12/18/07 12/24/07 0.032 0.039 0.028 0.042
                                                     < 0.024
                                                     < 0.037           < 0.046     <     0.028        < 0.037    < 0.024          <    0.027     <   0.035 53      12/31/07          <  0.035     < 0.022    < 0.031           < 0.048     <     0.026        < 0.034    < 0.033        Deviation Report <   0.034
               ** Control sample location B-17

TABLE B-9 CONCENTRAnONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCilliter +/- 1 Sigma
                                         #9 PLANT INLET (HUDSON RIVER INTAKE)
Date       01126/2007 .< ;' .02/23/2007 "             "~03/3012007             0412712007 ..,.          .. 0512512007           0612912007
.. NUCLIDE                   .... '.  '.                 '.:\ .>" ',.' "               .:'
1-131           <  6.03                  < 4.09                   < 5.78                < 7.03                  < 6.91                     <     5.70 Cs-134           <  0.75                  <  1.01                  < 0.75                < 1.78                  < 1.27                     <     1.10 Cs-137           <  0.94                  < 0.79                  <  1.00                < 1.35                  < 1.22                     <     0.63 Zr-95           <  2.09                  < 1.84                  <  1.94                < 3A3                   < 2.64                     <     2.19 Nb-95           <  IA2                   <  1.29                 <  1.51                < 2.16                  < 1.72                     <      1.08 Co-58           <  1.07                  < 1.00                  <  1.30                < 1.59                  < 1.24                     <     1.29 Mn-54            <  0.90                  < 0.89                  <  1.12                < 1.71                  < 1.14                     <     1.10 Fe-59           <  2.97                  < 2.99                  <  3.36                < 5.19                  < 4.03                     <     3A7 2n-65           <  2.12                  < 1.06                  <  2.55                < 2.01                  < 2.95                     <     1.38 Co-60           <  0.76                  < 0.90                  <  1.01                < 1.47                  < 1.25                    <     0.99 K-40     106.5 +/- 9.51         321.7 +/-  12A3        157.9 +/-    11.24   349.6 +/-     21.96         127.3 +/- 12.77      326.4 +/-           13.70 BalLa-140         <  3.13                  < 2A8                   <  3.11                < 3.82                  < 4.20                     <     3.65 Date:      07/2712007.              08/3112007 .    '. .09/28/2007         *"10126/2007' .                 1113012007 .'.       12/31/2007 .
NUCLIDE                 Y      ..... ,\ ...........             .':',
I*/~:       .      ....... :.                .. ...."  ..
                                                                                                                                         ~
1-131           <  5.34                  < 7.00                  <  6.87                < 6.72                  < 6.89                    <     6.75 Cs-134           <  1.41                  < 1.37                  <  IA5                 < 1.09                  < 1.14                    <      1.98 Cs-137           <  1.18                  < 1.14                  <  1.84                < 1.54                  < 1.05                    <      1.88 2r-95           <  2.65                  < 2.70                  <  4.08                < 2.94                  < 2.23                    <      3.06 Nb-95           <  1.70                  < 2.12                  <  2.65                < lAO                   < 1.47                    <     2.30 Co-58           <  lAO                   < 1.56                  <  1.95                < 1.77                  < 1.14                    <     2.19 Mn-54            <  1.34                  < 1.25                  <  2.05                < lAI                   < 0.96                    <      1.63 Fe-59           <  4.27                  < 4A9                   <  5.08                < 4.31                  < 3.94                    <     5.69 Zn-65           <  1.69                  < 1.57                  <  4.72                < 1.91                  < 1.41                    <     4.72 Co-60           <  1.44                  < 1.24                  <  2.11                < 1.33                  < 1.12                    <      1.96 K-40     361.6 +/- 18.82        348.3 +/-  17.84      365.1 +/-     27.71   190.2 +/-     14.55         337.6 +/- 14.56      163.9 +/-          20.54 BalLa-1 40        <  4.15                  < 4.10                  <  5.35                < 3.73                  < 3.89                    <     4.09 8-18

TABLE B-9 CONCENTRA nONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units ofpCiIliter +/- 1 Sigma
                                            #10 DISCHARGE CANAL (MIXING ZONE) 02123/2007                                                               0512512007 ' .
Date NUCLIDE ...
01l26!2007
                                     ....;, ...               . 03/30/2007 04/27/2007.
                                                                                                                                '0612912007 1-131              < 6,91                    < 4,02                      < 6.75                < 6.57             < 6.42              <    6.95 Cs-134              < 1.22                    < 0.68                      < 0.87                < 0.81             < 1.32              <    1.50 Cs-137              < 1.45                    < 1.09                      < 1.30                < 1.24             < 1.29              <    1.36 Zr-95              < 3.33                    < 2.02                      < 2.81                < 2.44             < 2.30              <    3.21 Nb-95              < 2.04                    < 1.40                      < 2.07                < 1.94             < 1.90              <    2.17 Co-58              < 1.86                    < 1.23                     <  1.61                < 1.41             < 1.49             <     1.87 Mn-54               < 1.75                    < 1.06                     <  1.21                < 1.43             < 1.29              <    1.55 Fe-59              < 4.00                    < 3.51                      < 5.05                < 4.47             < 4.21              <    4.85 Zn-65              < 3.89                    < 2.56                      < 3.44                < 1.79             < 3.04              <    1.80 Co-60              < 1.40                    < 1.27                     <  1.58                < 1.24             < 1.23             <     1.34 K-40        128 +/- 14.77        271.2 +/- 14.85           162.4 +/-       15.84          122 +/- 13.66  293.2 +/-  17.84    277.1 +/-     19.80 BalLa-140            < 3.55                    < 4.01                     <  5.30                < 3.96             < 3.82             <     4.13 Date        07/27/2007 .*.*. .***. 08/3112007              . .09/2812007                  10/26/2007 '., .. 11130/2007'        12/3112007 ..
. NUCLIDE          .....    -*:.i 1/>           '.::..,::    ,;:.~f'_              .. ' ..: .. ..
                                                                                              ~
                                                                                                                .:      --.            .* .. F-::::~
1-131              < 5.19                    <                          <  5.74                <  6.41            < 6.59             <     5.42 Cs-134              < 0.72                    <     0.79                 <  1.70                <  1.84            < 1.45             <     1.03 Cs-137              < 1.08                    <     0.69                 <  1.56                <  1.81            < 1.33             <     1.21 Zr-95              < 2.09                    <     1.65                 <  2.99                <  4.03            < 2.43             <     2.75 Nb-95               < 1.56                    <     1.20                 <  2.24                <  2.73            < 1.75             <     1.86 Co-58              < 1.14                    <     0.93                 <  1.81                <  1.89            < 1.77             <     1.55 Mn-54               < 1.07                    <     0.75                 <  1.58                <  1.58            < 1.36             <     1.48 Fe-59              < 3.05                    <     2.70                 <  4.17                <  4.95            < 4.53             <     4.58 Zn-65              < 1.35                    <     0.95                 <  3.49                <  3.31            < 3.06             <     3.34 Co-60              < 0.94                    <     0.72                 <  1.47                <  1.63            < 1.26             <     1.41 K-40      171.5 +/-  11.44       322.5 +/-         10.33  203.9 +/-        20.17    385.3 +/-     24.76  163.2 +/-  15.73    136.5 +/-     15.47 BalLa-140            < 3.15                    <     3.26                 <  4.16                <  5.77            < 4.53             <     4.37 8-19

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

TABLE B-ll CONCENTRA nONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2007 Results in Units of pCilliter +/- 1 Sigma CAMP FIELD RESERVOiR Date NUCLIDE 1-131          <  0.25           <  0.26             <  0.37            <  0.35         < 0.27        <  0.41 Cs-134          <  2.23           <  3.52             <  3.96            <  4.42         < 3.57        <  2.52 Cs-137          <  2.73           <  3.68             <  2.95            <  2.50         < 3.18        <  2.45 Zr-95          <  3.24           <  5.06             <  6.19            <  5.39         < 5.92        <  4.18 Nb-95           <  2.78           <  3.97             <  4.24            <  4.49         < 3.37        <  2.83 Co-58           <  2.13           <  3.51             <  3.98            <  4.44         < 3.60        <  2.31 Mn-54           <  2.16           <  2.97             <  2.97            <  4.11         < 4.00        <  2.24 Fe-59          <  5.15           <  9.96             <  10.92           <  8.47         < 12.62       <  5.16 Zn-65           <  5.21  -        <  6.54             <  8.03            <  9.12         < 7.78        <  4.50 Co-60           <  1.74           <  5.52             <  5.04            <  2.30         < 4.42        <  2.21 K-40    321.2 +/- 35.25   231.5 +/- 45.77            < 42.91     275.6 +/- 48.57 89.5 +/- 31.21 99.1 +/- 26.92 Date.
1-131          <  0.33           <  0.31             <  0.38            <  0.32 Cs-134          <  2.59           <  2.84             <  1.94            <  2.51         < 1.63        <  1.93 Cs-137          <  2.62           <  2.12             <  3.58            <  3.15         < 2.38        <  2.77 Zr-95          <  4.35           <  4.60             <  5.99            <  4.86         < 3.65        <  3.94 Nb-95           <  2.91           <  2.71             < 4.46             <  3.16         < 2.16        <  2.32 Co-58           <  2.23           <  2.49             < 4.50             <  3.36         < 2.16        <  2.88
 'Mn-54           <  2.80           <  1.90             < 4.28             <  3.49         < 1.94        <  2.41 Fe-59           <  6.52           <  7.41             <  9.80            <  8.79         < 3.99        <  8.78 Zn-65           <  6.36           <  6.05             <  13.23           <  6.39         < 6.45        <  9.14 Co-60           <  2.42           <  2.84             < 3.90             <  3.97         < 2.25        <  2.58 K-40    197.3 +/- 31.68   133.6 +/- 30.08    326.8 +/- 47.02     85.98 +/- 32.57  131 +/- 22.62 215 +/-  32.21 8a/La-140         <  3.49           <  3.06             < 2.35             <  3.13       . < 3.23        <  3.44 8-21

TABLE B-11 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma NEW CROTON RESERVOIR Date                                       ' .. >,                                       ,
                                                                                                                  ,"'''., :'/"",'.,"            .:.,,">,                  /'
NUCLIDE
                                                                                .",:"           , ' ......   ': 'J';"            '::            ,. ~~.:'.
                                                                                                                                                                  ,,:c'\'<
f-131              <  0,26            <   0.23                     <   0.34                 < 0.32         c                 <    0.34                     <  0.30 Cs-134              <  3.65             <  3.50                     <   2.84                 <    3.64                        <    2.81                     <  3.26 Cs-137       -     ,<  3.17             <  3.53                     <   2.90                 <    3.89                        <    2.88                      < 2.52 Zr-95              <  5.16            <   6.50                     <   6.03                 <    5.77                        <    5.99                      < 4.92 Nb-95               <  3.60            <   4.16                     <   2.68                 <    3.53                        <    3.65                     <  3.05 Co-58              <  2.62            <   3.71                     <   2.24                 <    3.49                        <    3.90                     <  2.88 Mn-54               <  2.70             <  3.22                     <   2.49                 <    3.19                        <    4.28                      < 2.97 Fe-59              <  7.57            <   6.41                     <   5.37                 <    12.84                       <    9.82                     <  9.08 Zn-65              <  9.\3            <   3.31                     <   6.83                 <    8.86                        <    11.53                    <  7.41 Co-60              <  3.08            <   3.60                     <   2.31                 <    4.21                        <    4.21                     <  2.66 K-40        221.9 +/- 38.95           <   40.52              177 +/-   32.14  243.1 +/-          47.97          347.2 +/-         53.88     137.6 +/-         27.55 Ba/La-140            <  4.62            <   4,21                     <   2.23                 <    6.23                        <    5.28                     <  3.96 Date,         07/10/2007    '08/07/2007                      09111/2007           10/09/2007 .. '                   11119/2001"                  12/18/2007
,NUCLIDE   ~.                                                     .,,"C.            "c',:        ,>-                   ':', "::".,,,    .;, I: ,"':.      ',:":      ,;\.,.
f-\31              <  0.29            <   0.25                     <   0,31                 < 0.30 Cs-134              <  2.35            <   2.38                     <   3.40                 < 2.51                           <    1.78                     <  2.89 Cs-137              <  2.45            <   2.19                     <   3.29                 < 2.29                           <    1.96                     <  2.39 Zr-95              <  4.43            <   3.78                     <   3.75                 < 5.18                           <    4.34                     <  5.13 Nb-95               <  2.62            <   2.89                     <   3.69                 < 2.78                           <    3.00                     <  3.19 Co-58               <  2.59            <   2.61                     <   2.49                 < 3.11                           <    2.52                     <  3.00 Mn-54               <  2.88            <   2.85                     <   3.62                 < 3.42                           <    2.30                     <  2.54 Fe-59              <  8.76            <   6.30                     <   7.84                 < 7.54                           <    6.24                     <  7.14 Zn-65               <  5.36            <   5.36                     <   7.96                 < 5.91                           <    3.12                     <  7.29 Co-60               <  3.02            <   2.47                     <   2.38                 < 2.76                           <    2.32                     <  2.06 K-40        139.6 +/- 29.84  315.7 +/-    35.43              201 +/-  42.41   277.3 +/- 41.09                   146.9 +/-         27.10     142.8 +/-         29.31 Ba/La-140            <  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

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma 1- ,
Sample,                 COLDSpRING             ,LENTS COVE                MANITOU                 VERPLANCK,.           :::WRITE'BEACH location                 'SHORELINE              SHORELINE                SHORELINE            ISH~~ELl~.~:            ; : 'SHORELINE Date                      06/06/2007            '06/,06/2007 '        ','06/06/2007                06;07l200~i',     '''06/0712007 Client ID                      ISS842307              ISS282307                ISS502307                ISSI72307                 ISS532307 Radionuclide 1 Req. CL Be-7                    <    234.9              <   319.8                <    448.6               <    165.3                <    176.4 1-131                    <     44.2              <    80.7                <    118.3               <     39.9                <    30.3 Cs-134        75          <     31.4              <   46.2                 <     36.2               <     11.3                <    11.2 Cs-137        90          <     26.0              <    54.7           357.0       +/-  33.4       63.3     +/-  18.1          <    19.6 Zr-95                    <     46.6              <   82.9                 <     62.3               <     41.3                <    35.7 Nb-95                    <     34.6              <   68.6                 <     55.3               <     30.0                <    26.3 Co-58                    <     30.3              <    39.5                <     47.8               <     22.2                <    18.6 Mn-54                     <     28.7              <   49.1                 <    46.4                <    '15.1                <    20.0 Zn-65                    <     92.4              <   52.5                 <    115.3               <     54.8                <    61.3 Fe-59                    <     95.9              < 143.4                  <    125.4               <     53.6                <    60.2 Co-60                    <     37.9              <   41.0                 <     49.4               <     22.1                <    15.5 BalLa-140                   <     40.3*             <    96.6                <     59.0               <     45.4                <    30.9 Ru-103                    <     20.6              <   44.6                 <     51.2               <     20.4                <    22.2 Ru-106                    <    298.9              < 381.1                  <    555.5               <   264.8                 <   202.5 Ce-141                    <     45.9              <   63.6                 <     86.0               <     39.8                <    30.7 Ce-l44                    <    164.1              < 259.6                  <    341.1               <    150.2                <    104.7 AcTh-228                 468.4     +/-  98.0   1052.0 +/- 187.2         806.3       +/-  154.1     194.3     +/-  64.0          <    61.5 Ra-226                    <    593.0         2250.0 +/- 702.7        2006.0       +/-  737.3    1194.0     +/-  388.5      979.4    +/-   314.7 K-40               36000.0 +/- 1070.0    115770.0 +/- 1077.0 124470.0           +/-  1177.0 I 5423.0     +/-  411.2     9411.0    +/-   598.1 Sr-90       5000                                                                                   <     140 8-24

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2007 Results in Units of pCilkg +/- I Sigma Sample Location
                        .I   ,COLD SPRING             LENT"SCOVE               MANITOU;            "'VERPLANcK. 'I:"                WHITE BEACH S H 9 RELIN.Ji:        SH()RELINE              SHORELINE-'            'SHOREqN~               . .'. <';SHORE~INE         ,'.
Date                        09/06/2007             09/06/2007              09/06/2007            ;'. 09/07/2007:;'              . ,09/07/2007 Client ID                       ISS843607              ISS283607               ISS503607               ISS I 73607R 1                  ISS533607 Radionuclide   Req. CL Be-7                       <    312.9             <    332.2               <     615.1               <    175.9                    <    167.6 1-131                      <     46.4             <     57.6               <      86.9               <     30.9                    <    26.5 Cs-134        75            <     24.2             <     39.9               <      58.2               <     23.4                    <     18.5 Cs-137        90            <     38.3             <     37.3               <      67.0         149.0        +/-   22.6             <    19.2 Zr-95                      <     70.0             <     59.9               <     107.1               <     36.7                    <    30.8 Nb-95                       <     38.2             <     52.4               <      78.1               <     20.1                    <    27.2 Co-58                       <     37.7             <    43.3                <      32.7               <     18.6                    <    20.7 Mn-54                       <     33.6             <     37.3               <     48.7                <     24.7                    <    20.3 Zn-65                       <     68.5             <     46.1               <     198.1               <     58.9                    <    66.3 Fe-59                      <    147.0             <    107.0               <      98.2               <     57.7                    <    51.6 Co-60
                                    --50.9             <     39.5               <      39.9               <     21.2                    <    28.4 BalLa-140                     <     57.0             <     55.1               <     114.6               <     22.2                    <    24.2 Ru-103                      <     32.3             <     39.7               <      52.4               <     24.4                    <    18.8 Ru-106 268.8             <    309.3               <     383.3               <    163.2                    <    191.8 Ce-141
                                <     51.7             <     58.8               <      80.1               <     31.8                    <    23.7 Ce-144                      <    167.4             <    235.8               <     324.0               <    123.3                    <    112.0 AcTh-228                   691.6     +/-  138.8   992.0     +/-   151.6   1380.0      +/- 284.0   141.9        +/-    71.2            <    77.8 Ra-226                  1508.0     +/-  492.5  3924.0     +/-   683.2  2561.0       +/- 1041.0  748.8        +/-   371.0            <   397.7 K-40                  31600.0     +/-  1200.0 4540.0     +/-   894.9 10230.0       +/- 1239.0 8613.0        +/-   624.5       8537.0     +/-   586.
Sr-90       5000            <    300               <    350                 <     370                 <     270                     <   1200 8-25

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma
                                                                   #95 Meteorological Tower
;,  'SamJ)le    1\' ,:,"    'MET TOWER*;'
MEri:T()WE~<: }','*METTOWER "
                                                                                                   'MJi1l'TOWER I' 'ijE)'.JOWE~          . i;'tlMln TOWER Location '"   .-
Date                    05/2412007 0$124/2007 '.' ,             ';" 05;25;2~07 "         ,;06126/2007 .           :'0612612007: .        ~*'<:ri6/2612~07 .
Client ID                   IBV952107S3        IBV952107S2                     IBV952107S1            IBV952607S I             IBV952607S2               IBY952607S3 MULLEN            RAGWEED                      MOTHERS WORT           GRAPE LEA YES               RAGWEED                     MULLEN Radionuclide   Req. CL Be-7                   <    73.05      441,1      +/- 812               357,1     +/- 73.5    394.1    +/-   53.9       681.3    +/- 84.9         422.9    +/-   82.2 1-131          50       <    18.99          <    16.52                       <   27.21             <   727                   <  10.59                 <    13.44 Cs-134          50       <    11.49          <     13.43                      <   11.74             <   8.34                  < 13.63                  <    14.78 Cs-137          50       <    9.71           <     9.92                       <    8.97             <   6.35                  < 10.15                  <    11.96 Zr-95                   <    14.46          <    14.50                       <   15.75             < 11.71                   < 19.55                  <    19.25 Nb-95                   <    9.44           <    11.31                       <   13.31             <   7.76                  < 12.38                  < 10.99 Co-58                   <    11.60          <     9.71                       <   13.34             <   7.53                  < 13.16                  < 11.02 Mn-54                   <   10.51           <    11.30                       <   10.59             <   7.54                  < 11.54                  <    11.06 Zn-65                   <   29.73           <    28.85                       <   31.51             < 19.45                   < 29.27                  < 29.20 Fe-59                   <   30.05           <    46.86                       <  48.51              < 19.06                   < 42.10                  < 32.25 Co-60                   <    8.62           <    12.01                       <    8.51             <   6.92                  < 16.93                  <    16.49 Ba/La-140                  <    13.10          <     18.44                      <   28.56             <   6.74                  < 13.62                  <    11.06 Ru-103                   <    9.16           <     9.82                       <   12.63             <   6.23                  < 10.93                  <    10.39 Ru-106                   <   91.08           <    93.88                       <  120.90             < 74.87                   < 94.36                  < 120.80 Ce-141                   <    12.72          <    12.38                       <   16.66             <   9.80                  < 11.93                  < 14.98 Ce-144                   <   48.86           <   42.50                        <   58.89             < 41.41                   < 47.90                  < 58.53 AcTh-228                   <   34.94           <    37.75                       <  46.54              < 25.89                   < 48.41                  < 53.57 Ra-226                   <   146.30          <   150.70                   312.4     +/- 131.1   218.8    +/-   121.9      280.2    +/-   138.6         < 210.50 K-40              .- ~.O~           2~ 6498.0      +/-_300.7 .... '--- 4962.0      +/- 320.2  4307.0    +/-   203.4    10580.0    +/-   386.5     7602.0    +/-   395.4 8-26

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma
                                                              #95 Meteorological Tower Sample.
 . Location
                     . I\1ET TOWER*          METTOWER *.... ' METTOWER                    :< MET 'TOWER .." .          }i Mirf'TOWER           ' ; MET TO""ER Date' ,              07/24/2007           07/24/2007 .> , 07/24/2007" ~" ~.. 08/14)2~0;                     .**.* '~\08/l4~2007 .'              08/14/2007
* Client ID                lBV953007S I         IBV953007S2              IBV953007S3            IBV953307S I                  lBV953307S2             IBV953307S3 GRAPE LEAVES           RAGWEED                    MULLEN             GRAPE LEAVE                     RAGWEED                  CATALPA Radionuclide Req. CL Be-7            491.8    +/-    77.3 1007.0    +/-   99.2      1258.0    +/-  131.6   746.5    +/-    73.1        2332.0     +/-   121.1   1047.0   +/-    95.8 1-131     50         <  12.16             <   17.77                 <   18.01             <   16.82                      <  16.43               <   18.17 Cs-134     50         <   9.64             <    8.67                 <    7.73             <    8.73                      <  11.80               <   12.56 Cs-137     50         <   9.37             <    9.48                 <   12.30             <    6.74                      <   9.00               <   10.80 Zr-95                <  20.83             <   22.03                 <   17.45             <   13.15                      <  16.85               <   19.57 Nb-95                 <  10.04             <   13.02                 <   13.63             <    9.27                     <   12.70               <   12.71 Co-58                 <   9.49             <   11.87                 <   12.23             <    7.84                     <    9.80               <   11.56 Mn-54                 <  10.05             <   13.38                 <   11.92             <    7.96                     <    9.31               <   12.17 Zn-65                 <  32.62             <   31.94                 <   36.43             <   18.90                     <   30.37               <   36.59 Fe-59                 <  33.42             <   35.49                 <   41.73             <   25.76                     <   32.09               <   37.74 Co-60                 <   9.03             <   11.71                 <   13.49             <    9.40                     <    9.52               <   16.51 BalLa-140                <  18.70             <   16.44                 <   11.31             <   11.85                     <   17.74               <   23.26 Ru-103                <  11.85             <   10.24                 <   11.49             <    7.43                     <    9.68               <   10.86 Ru-106                <  96.38             <  109.60                 <  111.90             <   89.75                     <   93.88               <   95.17 Ce-141                <  11.69             <   17.94                 <   13.90             <   11.84                      <  12.37               <   15.04 Ce-144                <  43.14             <   69.45                 <   55.13             <   44.93                      <  42.83               <   46.99 AcTh-228                 <  40.90             <  40.06                 .<   44.84             <   25.64                     <   34.75               <  _43.88 Ra-226                <  175.60            <  225.80                 <  212.60             <  139.50                  340.6    +/-   97.3     366.8   +/-    133.1 K-40           3716.0    +/-   264.0 8313.0    +/-   343.1    6807.0     +/-  380.4 4246.0     +/-    205.8       7933.0     +/-   300.7  6510.0    +/-    288.6 8-27

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma
                                                                  #95 Meteorological Tower Sample MET TOWER              METT()WER              . MET-TOWER             . i'lVI EtTOWER-1';            <~MET-TOWER';;""
                                                                                                                                    ..., .. .. ; ' ; . / .... ;' .~ETTOWER .
:Location                                                                 "0,:     '":,'            .                .
                                                                                                                               ~f,f \ 10/1~i2.j()7 .......... , .
                                                                                                           '",             .~
  , Date                  09/1812007             0911812007' .              0911'8/2007              .. 10/16/2007         .                                         "10/16/2007.:;
Client ID                 IBV953807S1           IBV953807S2                IBV953807S3                  IBV954207S I                 IBV954207S2                      IBV954207S3 GRAPE LEAVES             RAGWEED                     MULLEIN                  GRAPE LEAVES                    RAGWEED                          MULLEIN Radionuclide Req. CL Be-7             929.3     +/-   94.6  1715.0     +/-   118.3      362.2      +/-    85.9    1214.0      +/-    96.9       2203.0       +/-     157.3        755.2      +/-   94.1 1-131      50        <     9.79             <    12.14                 <     13.83                  <    12.85                    <    14.82                     <    11.32 Cs-134      50        <    13.59             <    13.33                 <      9.17                  <    8.50                     <    18.55                     <    12.13 Cs-137      50        <     7.73             <     9.84                 <     14.32 .                <    6.62                     <    13.55                     <     9.82 Zr-95                <    14.96             <    18.34                 <     23.08                  <    14.97                    <    23.41                     <    16.86 Nb-95                <    10.44             <    10.14                 <     16.12                  <    10.20                    <    13.46                     <    12.26 Co-58                <    11.80             <    12.51                 <     15.19                  <    8.45                     <    17.00                     <     8.66 Mn-54                <    10.44             <    11.69                 <     15.53                  <    8.22                     <    13.48                     <    10.57 Zn-65                <    23.10             <    27.20                 <     44.00                  <   21.80                     <    32.83                     <    26.33 Fe-59                <    23.00             <   28.69                  <    48.12                   <   20.26                     <   40.10                      <    35.01 Co-60 .              <    12.11             <    9.10                  <     21.25                  <   12.40                     <   20.87                      <    12.86 Ba/La-140               <    11.41             <     9.33                 <     16.40                  <    6.78                     <    17.40                     <    12.12 Ru-103                <     8.41            ,<    8.92                  <     10.75                  <    8.10                     <    12.76                     <     8.35 Ru-106                <   103.00             <   99.95                  <    117.90                  <   75.51                     <   133.60                     <   108.80 Ce-141                <    13.27             <    13.78                 <     15.38                  <    12.01                    <    17.88                     <    11.26 Ce-144                <    56.27             <   64.28                  <     57.44                  <   53.08                     <    82.95                     <    49.55 AcTh-228                <    34.20             <    46.23                 <     56.26                  <   31.59                     <    54.58                     <    35.01 Ra-226             299.2     +/-   179.2     <   200.70                 <    250.10                  <   174.80                510.8     +/-     216.9            <   190.40 K-40             3719.0     +/-   249.0 7667.0     +/-  347.4     7117.0       +/-   373.7    4006.0      +/-    228.4      8246.0      +/-     454.5        6177.0    . +/- . 309.9 8-28

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma
                                                                            #23 Roseton     **
Sample                                                                                                                                                                    ..
ROSETON              ROSETON                  RDSETON,                   ROSETON:            ,       ; RPSETON"            : ROSETON
   . Location Date I
05/24/2007*           05/24/2007              .0512412007
:,>,: 06/25J201)7.* . <. I.'     06125/2007            06/251io07 Client ID                     lBV232107S1          IBV232107S2              lBV232107S3                lBV232607S I                 IBV232607S2           IBV232607S3 RAGWEED              BURDOCK                   MULLEN                    RAGWEED                      BURDOCK                 MULLEN Radionuclide     Req. CL 6e-7                  406.5     +/- 95.8    389.9    +/-  59.2       165.9     +/-   64.9   1084.0       +/- . 105.7       1352.0    +/-   83.5  1130.0    +/-   135.4 1-131         50          <    27.19            <   16.65                 <   23.51                 <    12.27                   <    8.19             <    17.41 Cs-134         50          <    12.10            <    9.90                 <   12.94                 <    13.35                   <   10.85             <    17.92 Cs-137         50          <    10.85            <    6.89                 <    9.67                 <    11.65                   <    8.25             <    15.90 Zr-95                     <    21.42            <   17.45                 <   16.28                 <    18.80                   <   14.73             <   24.09 Nb-95                      <    14.49            <    9.31                 <   11.56                 <    12.70                   <    7.45             <    15.30 Co-58                      <    12.42            <    7.19                 <   11.21                 <    12.95                   <    8.47             <    9.28 Mn-54                      <    13.49            <    9.65                 <    9.25                 <    10.63                   <   8.71              <    19.39 Zn-65                      <    31.73            <   30.83                 <   22.32                 <   29.58                    <   23.68             <   46.40 Fe-59                     <    57.99            <   24.10                 <   33.86                 <   41.95                    <   26.95             <   44.85 Co-60                      <    13.58*           <    9.40                 <    9.70                 <    15.35                   <    8.44             <    16.27 6a/La-140                    <     9.90            <   15.22                 <   19.09                 <    11.92                   <   12.88             <    16.78 Ru-103                     <    10.99            <    6.78                 <   12.63                 <    10.31                   <    7.76             <    11.72 Ru-106                     <    99.86            <   62.41                 <   110.00                <   126.00                   <   82.92             <   138.00 Ce-141                     <    17.01            <    9.87                 <   12.25                 <    12,39                   <    9.39             <    17.78 Ce-144                     <   66.45             <   33.14                 <   46.19                 <   59.93                    <   32.27             <    74.82 AcTh-228                     <    37.64            <   29.74                 <   34.95                 <   47.51                    <   28.42             <    53.33 Ra-226                     <   208.30            <  115.40                 <   155.70                <   208.70                   <  130.50          385.0    +/-   213.4 K-40                  8773.0     +/-  406.3 5144.0    +/-  249.1     3757.0     +/-   252.3 10020.0       +/-    412.2       6088.0    +/-   248.3 5830.0    +/-   402.7
.. Control Sample Location 8-29

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units ofpCilkg +/- 1 Sigma
                                                                          #23 Roseton    **
    , ....III"..'....
I nr.:dinn ROSETON             ROSETON ...              ROSETON';.*
                                                                                                 .' ':ROS12!ON ,::~\
ROSETON'               ROSETON,
   .;. Date                       07/23/2007           07123/2007,           *.07/23/2007 ,.'       :.:08/13/2007.',         08/1312007           ,08/13/2007 Client ID                     IBV233007S 1         IBV233007S2             IBV233007S3             IBV233307S1           IBV233307S2           IBV233307S3 Req. CL CATALPA             BURDOCK                  MULLEN               GRAPE LEA YES           RAGWEED                MULLEN Radionuclide         (pC i)
Be-7                  141.5    +/-  71.0  1411.0   +/-   107.5     504.4    +/-   82.2    541.5    +/-    88.5  1990.0    +/-   144.4 2027.0    +/-   139.7
        /-131           50        <   13.77            <   14.60                <   18.33              <   23.19             <   26.68             <   25.24 Cs-134           50        <   11.49            <   9.97                 <   11.34              <   13.95             <    17.31            <   13.58 Cs-137           50        <    9.32            <   6.86                 <   11.06              <   12.91             <    11.74            <   10.15 Zr-95                     <   11.35            <  11.77                 <   18.85              <   19.02             <   24.50             <   11.85 Nb-95                      <   8.55             <   6.61                 <   8.87               <   12.49             <    15.12            <   17.40 Co-58                      <   11.24            <   7.95                 <   11.34              <   12.11             <    16.73            <    8.45 Mn-54                      <   8.06             <   9.92                 <   9.94               <   8.51              <   14.63             <   9.53 Zn-65                      <   17.59            <  23.96                 <  29.01               <   33.00             <   46.81             <   15.40 Fe-59                     <   32.87            <  23.90                 <  33.82               <   22.92             <   52.13             <   37.44 Co-60                      <    9.29            <  11.90                 <   15.87              <   15.42             <   21.23             <   10.64 Ba/La-140                     <   6.85             <   10.46                <   8.64               <   17.60             <   24.23             <   24.24 Ru-103                     <   11.55            <   8.32                 <   9.01               <   11.06             <    13.27            <   12.54 Ru-106                      <   66.64            <  85.69                 <  96.44               <   85.24             <   124.30            <  110.80 Ce-141                     <   10.71            <   12.36                <   13.70              <   12.54             <:   17.30            <   16.31 Ce-144                     <   39.73            <  42.25                 <  61.21               <   42.12             <    53.71            <   59.70 AcTh-228                      <   22.66            <  30.64                 <  42.01               <   40.03             <   48.92             <   36.33 Ra-226                     <  157.10            <  155.70                <  192.40              <  181.20             <  220.00             <  183.90 K-40                 2478.0    +/-  211.3 6527.0   +/-  298.3     4840.0    +/-   277.8 3640.0     +/-    246.0 7920.0    +/-   358.9 3590.0    +/-   243.8
-- Control Sample Location 8-30

                                                  /
TABLE B-14 CON CENTRA TIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2007 Results in Units ofpCilkg +/- 1 Sigma
                                                                                #23 Roseton **
   ,.Sample
                                                                                \icROSETON
                                                                                                     ,: . ROSETON           ,>:,                  ,"   , ,., '"
L.ocation ROSETON                 'ROSETON         . "
ROSETON              If:'I~OSETON:,
Date                      09117/2007               09/17/2007                0911712007        . '.:  i 0/15/~oki;:    "
I***::*'
Hi/15/2007                10115/2007 Client ID                   IBV233807S1              IBV233807S2                IBV233807S3              IBV234207S1                     IBV234207S2                IBV234207S3 MULLEIN                 RAGWEED                     CATALPA                  MULLEN                         RAGWEED                     CATALPA Radionuclide Req. CL 8e-7                1589.0     +/-   142.8   994.1     +/-    114.0      693.1      +/- 87.2  1679.0      +/-     185.7          1961.0     +/-     140.4  1771.0      +/-   94.1 1-131        50          <    17.12               <    11.84                  <    10.81             <    21.35                       <    15.31                 <    11.14 Cs-134        50          <    16.78               <    12.18                  <    12.76             <    21.33                       <    1220                  <     823 Cs-137        50          <    14.27               <    12.29                  <     8.32             <    17.33                       <    12.82                 <     7.78 Zr-95                    <    23.44               <    22.37                 <     18.96             <    19.63                       <    23.40                 <    12.55 Nb-95                    <    16.53               <    11.41                 <      7.72             <    21.11                       <    13.88                 <     7.76 CO-58                    <    14.47               <    11.52                 <     11.48             <    16.56                       <    12.36                 <     5.86 Mn-54                     <    15.07               <    11.84                 <     8.76              <    18.93                       <    12.90                 <     7,08 Zn-65                    <   44.37                <    26.80                 <     27.74             <    56.50                       <    16.03                 <    17.21 Fe-59                    <   49.21                <    39.91                 <     26.74             <    54.21                       <    36.91                 <    21.02 Co-60                    <    17.12               <    11.39                 <     12.00             <    25.33                       <    14.26                 <     6.57 8a/La-140                   <    21.48               <    13.69                 <      5.36             <    20.04                       <    14.25                 <     9.19 Ru-103                    <     9.53               <    10.93                 <      9.59             <    12.89                       <    10.09                 <     6.94 Ru-106                    <   145.10               <   111.30                 <     88.46             < 175.50                         <   106.50                 <    88.35 Ce-141                    <    20.31               <    13.53                 <     14.15             <    22.65                       <    15.18                 <    11.39 Ce-144                    <   68.00                <    56.57                 <     51.31             < 100.40                         <   47.94                  <    48.36 AcTh-228                    <    58.61               <    44.71                 <     30:05         126.5     +/-    59.9                <   42.54                  <    30.34 Ra-226                    <   226.20               <   226.70                 <    151.90             < 334.90                         <   241.70                 <   146.90 K-40                4950.0     +/-   363.5 6742.0      +/-   380.3     3412.0       +/- 245.5 8119.0      +/-    494.8          7434.0      +/-     366.0  3715.0      +/-   188.1
.. Control Sample Location 8-31

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 I
Client ID             IBV942I07S1          IBV942I07S2              IBV942I07S3           IBV942607S1            IBV942607S2             IBV942607S3 BURDOCK               MULLEN                 RAGWEED                GRAPE LE               MULLEN                  RAGWEED         I Radionuclide Req. CL 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

TABLE B-14 CONCENTRAnONS OF GAMMA EMITTERS IN BROADLEAF VEGET AnON SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma
                                                                    #94 IPEC Training Center
  ~am"le Location                                    I TRAINING BLDG TRAINING BLDG                       I TRAINiNG BL))G            TRAINING      BLDd,I,JRAIN~GBLPG              TRAINING Bu~G '
Date*                '07/2412007.        .,' . . *,'07/2~/2007*"    .';~; '07;;4;2007 .              08114/2007           .. 08/14/2007 .          08/i4/2007 :'
Client ID                  IBV943007S 1               IBV943007S2               IBV943007S3             IBV943307S 1            IBV943307S2           IBV943307S3 GRAPE LEAVES                  MULLEN                   RAGWEED                  GRAPELE                BURDOCK                RAGWEED Radionuclide I Req. CL Be-7                831.5    +/-   118.61     1097.0    +/-   104.5       916.9     +/-  125.3 1 1585.0    +/-    105.1  346.4    +/-    92.5  1492.0    +/-   134.5 1-131        50         <   14.37                  <   16.38                  <   19.93               <  18.16               <   20.72             <    26.73 Cs-134        50         <   12.89                  <   10.47                  <   19.76               <   9.82               < 15.78               <    13.85 Cs-137        50         <   9.26                   <  10.50                   <   16.32              <    8.77               <   12.85             <    12.31 Zr-95                   <   15.66                  <  21.68                   <   23.25              <   16.52               < 25.16               <    23.18 Nb-95                    <   14.83                  <   15.56                  <   14.67              <   10.05               < 15.95               <    14.79 Co-58                    <   10.96                  <   9.88                   <   12.37              <   10.39               <   10.47             <    15.48 Mn-54                    <   14.32                  <  13.09                   <   17.46              <   10.83               <   10.73             <    14.65 Zn-65                    <  25.76                   <  16.40                   <   43.55'             <   25.86               < 27.85               < ' 25.77 Fe-59                   <   33.86                  <  33.51                   <   57.00              <   31.31               < 52.61               <    55.43 Co-60                    <   14.54                  <   10.25                  < .13.80               <   10.48               <   10.08             <    14.28 BalLa-140                  <  20.05                   <   13.78                  <   30.32              <   18.13               < 26.26               <    18.79 Ru-103                   <   9.86                   <   10.29                  <   13.65              <    8.90               <   12.52             <    13.34 Ru-106                   <   92.23                  <  90.79                   <  150.10              <   85.99               < 149.40              <   108.50 Ce-141                   <   12.52                  <  16.13                   <   18.07              <   14.03               <   16.79             <    17.93 Ce-144                   <  58.37                   <  65.13                   <   55.64              <   49.71               < 52.33               <    69.60 AcTh-228                   <   31.12                  <  45.20                   <   46.22              <   30.53'              <   58.82             <    50.57 Ra-226                   <  166.60              362.0    +/-   175.2           <  230.70           256.0    +/-   129.6   253.5    +/-    145.7     <   234.60 K-40               4100.0    +/-   293.0      7202.0    +/-  328.7      9241.0     +/-   482.9   4136.0    +/-   231.0  5268.0    +/-    396.7 8102.0    +/-   404.9 8-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units ofpCilkg +/- 1 Sigma
                                                                          #94 IPEC Training Center TRAINI~GBLDG I*** TRA~iN!~(;BLD(;:1 :TRAI~~~G;BiDG*1 Sample Location *..         .. TRAINING BLQG           . TRt\,iNING BLDG                                                                                  TRAINU;.JG BLDG
   . Date'                    09/18/2007 .               09/18/2007                09/18/2007 .      . ..>10/16/2007>* . .         .10~16/2007***         10/16/2007 Client ID                     IBV943807S I              IBV943807S2               IBV943807S3               IBV944207S 1            IBV944207S2          IBV944207S3 GRAPE.LEA YES                 MULLEIN                   RAGWEED                   GRAPELE                 MULLEN              RAGWEED Radionuclide I Req. CL Be-7                1345.0     +/-     105.7    539.2     +/-   83.5     1440.0     +/-   146.5    2445.0    +/-     164.7  314.8    +/-  54.4  2255.0    +/-    147.3 1-131        50          <     12.91                <    26.90                <    14.73                <    12.31              <    7.31            <    12.15 Cs-134        50          <     11.06                <    12.41                <    10.65                <    12.05              <    8.90            <    14.17 Cs-137        50          <     9.24                 <     8.45                <    13.38                <    13.34              <    6.91            <    11.70 Zr-95                   <     17.68                <    19.26                <    30.52                <    22.31              <   13.52            <   23.37 Nb-95                    <     11.46                <    12.49                <    20.10                <    13.74              <    8.15            <    13.93 Co-58                    <     9.74                 <    10.82                <    16.24                <    12.24              <    6.64            <   13.63 Mn-54                    <     10.97                <    10.12                <    18.94                <    13.22              <    8.48            <   12.65 Zn-65 .                  <    29.70                 <    30.89                <    58.15                <    30.11              <   21.11            <   30.71 Fe-59                    <    25.02                 <    35.04                <    56.13                <    34.50              <   28.90            <   42.12 Co-60                    <    12.39                 <    10.57                <    21.37                <    9.60               <    7.22            <   18.43 Ba/La-140                   <     15.63                <    18.94                <    25.72                <    8.65               <    8.32            <   10.32 Ru-103                    <     9.51                 <    10.06                <    15.31                <    13.29              <    8.36            <   12.73 Ru-106                    <    115.00                <    92.89                < .161.70                 <   145.50              <   91.07            < 136.70 Ce-141                    <     14.60                <    15.71                <    18.53                <    15.71              <    8.63            <    15.01 Ce-144                    <    63.04                 <    57.79                <    70.35                <    58.49              <   40.61            <   56.59 AcTh-228                    <    32.22               52.2     +/-   27.3         <    59.71                <    36.52              <   24.55            <   54.05 Ra-226                    <   203.30                 < 180.00                  < 269.20                  <   204.60           213.7    +/-  106.8     < 223.10 K-40                6580.0     +/-     309.2   7892.0     +/-   291.2    7873.0     +/-   455.9    3811.0    +/-    327.3  4757.0    +/-  228.5 6010.0    +/-    337.7 B-34

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma
                                                               #25 Downstream (Hudson River)
  -Sample
                          'VOP FISH'               VOP FISH:               Vo,PFISH.?           \,OPFISH.                 VOPFlSH                   VOPFISH' Location .-                                                                                     'c!':",'"  "':
Date       !.,
06/06/2007            . 06/06/2007 ."          06/07/2007",         ' 06/08/2007 ....     .'"
06(08/2007 .             06/11/2007 Client ID                  IFH252407S6            IFH252407S4             IFH252407S2            IFH252407S5             IFH252407S3               IFH252507S7 CRABS               WHITE PERCH             STRIPED BASS                 CARP                 CATFISH                   SUNFISH Radionuclide  Reg. CL Be-7                  <   289.1             <    322.6              <    214.0              <     255.9             <   269.8               <     373.3 1-131                  <  1042.0             <   1360.0              <    972.2              <     971.1             <   857.3               <     1023.0 Cs-134        65        <    23.1             <     23.5              <     20.5              <      17.9             <    17.8               <      24.6 Cs-137       75         <    18.9             <     17.6              <     15.7              <      15.7             <    17.5               <      22.6 Zr-95                  <    59.6             <     54.7              <     41.9              <      44.7             <   48.1                <      73.4 Nb-95                  <    50.1             <     50.4              <     39.9              <      38.5             <    39.6               <      56.8 Co-58        65         <    38.1             <     26.5              <    26.0               <      29.5             <   26.0                <      29.9          I Mn-54        65         <    20.4             <     25.0              <     16.6              <      19.5             <    19.2               <      28.8 Zn-G5       130        <    50.3             <     59.7              <     41.1              <      46.4             <   49.7                <      64.7 Fe-59       130        <    90.9             <     99.1              <     83.5              <      95.5             <    69.9               <     107.5 Co-GO        65        <    23.9             <     29.7              <     17.8              <      23.5             <    17.9               <      22.9 Ba/La-140                 <   442.3             <    254.7              <    268.1              <     252.2             <   193.5               <     360.2 Ru-103                  <    49.2             <     49.8              <     35.1              <      32.1             <    37.6               <      54.5 Ru-106                  <   217.1             <    250.7              <    186.4              <     212.9             <   173.1               <     274.8 Ce-141                  <    75.9             <     77.0              <     46.5              <      56.0             <    50.9               <      73.5 Ce-144                  <   115.8             <    135.6              <    102.1              <     103.8             <    88.6               <     134.4 AcTh-228                  <   62.9              <     74.8              <    66.3               <      50.5             <    52.7               <      97.6          I Ra-226                  <   361.6             <    429.1              <    295.3          723.7       +1-   245.7     <   286.8           1001.0      +/-    376.6 K-40             3784.0     +/-  373.4  4656.0     +/-  484.3 3680.0       +/-   333.1 4399.0       +/-   331.8 3913.0    +/-  343.2    7191.0      +/- . 468.2 Sr-90         5_  _~_Jl - - - -         ~         ~-- -              <       6               <      6.8              <     7.7               <       14 8-35

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units ofpCilkg +/- I Sigma
                                                                   #25 Downstream (Hudson River)
                                                                                                                                ;VO~FISH
  *Sample VOP FISH;;~"
VOPFISH                  VOPFISH                    **NOPFISH"                                                         , . , },"";VOP,FISH; .
Location                                                                                ',.
                                                                                                                             ... 08/24/200,7 ...'~: '08/29/2007*
   *'Date'                 06/13/2007              08/16/2007                    08/16/2007              08/20/2007   j".
Client ID                  IFH252507S I             IFH254407S I                IFH254407S5             IFH254407S4             IFH254407S3                  IFH254407S2 AMERICAN EEL               BLUE CRAB                  WHITE PERCH            AMERICAN EEL                CATFISH                     SUN FISH Radionuclide I Req. CL Be-7                  <   306.7               <      203.3                <    309.0               <   223.4               <    213.8                   <    267.5 1-131                  <   658.1               <      5898.0               <   10980.0              <   5610,0              <   4142,0                   <   3583.0 Cs-134        65        <    22,8               <        8,9                <     10,6               <    10,9               <      7,1                   <     10,0 Cs-137        75        <    25.8               <        9.6                <     14.0               <    12.3               <     10.9                   <     152 Zr-95                  <    67.6               <       28,7                <     53,1               <    38.8               <     342                    <    44.4 Nb-95                  <    42.7               <       35.5                <     56.7               <    52.9               <     45.4                   <    50.8 Co-58         65        <    21.6               <       17.4                <     29,3               <    23,9               <     20,7                   <    26,2 Mn-54         65        <    22.6               <        9.9                <     17.4               <    13.6               <     13.5                   <    18.0 Zn-65        130       <    60.1               <       25.2                <     24.3               <    18.3               <     20.2                   <    23.0 Fe-59        130       <    86.5               <       80.7                <    114.6               <    90.4               <     88.3                   <    90,7 Co-60         65        <    28.8               <        9,8                <     14,7               <    12.6               <     12.4                   <    15.7 Ba/La-140                 <   267,7               <      583,5                <    774.0               < 645.4                 <    479.7                   <   395,1 Ru-103                  <    39,7               <       34.9                <     53,9               <    38,8               <     38,5                   <    41.2 Ru-106                  <   232.3               <      104.3                <    160.5               < 132.0                 <    143.1                   <   172.6 Ce-141                  <    66.4               <       58.1                <     98.2               <    70.2               <     62.5                   <    75,8 Ce-144                  <   103.0               <       57.8                <    100,6               <    71.4               <     73.3                   <    98.9 AcTh-228                  <    93,5             95.8       +/-   292      219.5      +/-     41.4    99.4    +/-   33.0    48,6       +/-   29.9            <    55.0 Ra-226                  <   401.0            707.8       +/-   155.2     580.8     +/-     209.5  521.0    +/-   187.4  456.1       +/-   158.1       968.4      +/-   215.9 K-40              3629.0    +/-   422.8   4690.0       +/-   183.9   4539.0      +/-     206.2 5245.0    +/-   222.3 4154,0       +/-   219.7      4196.0      +/-   196.3 Sr-90         5        <     6.6               <        7.1                <     6.5                <    6.3                <     6,8                    <     52 9-36

TABLE B-15 CONCENTRA nONS OF RADJONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma
                                                                      #23 Roseton (Control)
                                              "':;l{qSETO~"FlS!l',
Sample Location:,           ROSETON FISH'                                     "ROSET()N FISH *.'      ROSET()N)ISH:: tROSETONFisH' ><.ROSETO~FISH .
Date                  06/07/2007
                                                   '06/07/2007                0610712007           :06/07/2007'         . 06/13/2007 .      '::Gt~ OS/14/2'()07 .
Client ID                 IFH232407S I              IFH232407S3               IFH232407S4           IFH232407S5           IFH232507S2              IFH234407S4 AMERICAN EEL                    CARP                     CATFISH           WHITE PERCH               SUNFISH               WHITE PERCH Radionuclide Req. CL Be-7                <    194.6               <     210.0                <    190.2            <    238.9            <    169.6              <     359.8 1-131                <    744.3               <     896.0                <    855.9            <    999.5            <    476.2              <    14910.0 Cs-134      65        <     16.2               <     20.0                 <     14.0            <     15.5            <     16.5              <      17.6 Cs-137      75        <    .17.2               <      18.0                <     12.5            <     15.0            <     15.2              <      15.9 Zr-95                <     43.1               <     46.9                 <     33.4            <    41.6             <     38.5              <      63.5 Nb-95                 <     36.6               <     41.9                 <     35.0            <     43.8            <     29.0              <      79.6 Co-58       65        <     21.7               <     25.1                 <    23.0             <    22.0             <     21.3              <      39.0 Mn-54       65        <:    15.3               <:    22.3                 <:    15.0            <:    11.9            <     16.6              <      17.3 Zn-65       130       <     35.8               <:    48.9                 <    32.5             <:   41.5             <     34.2              <      28.5 Fe-59       130       <     86.7               <:    106.4                <:   68.7             <:    71.9            <     53.3              <     107.8 Co-60       65        <:    18.2               <     21.3                 <:    14.6            <:    16.3            <     20.8              <      19.8 Ba/La-140               <    197.4               <     329.7                <:   158.8            <:   235.4            <    140.9              <:    1306.0 Ru-103                 <     33.1               <     42.3                 <:   27.1             <:   26.7             <     23.0              <      63.8 Ru-106                 <    156.4               <:    162.9                <    132.6            <    151.1            <:   173.2              <     200.2 Ce-141                <     43.0               <     47.0                 <    44.2             <    41.1             <     23.1              <      98.6 Ce-144                <     77.4               <     12.8                 <    79.0             <     78.0            <     73.0              <      92.3 AcTh-228                <     52.4               <     66.3                 <:   41.2             <    59.0             <:    44.6              <      66.5 Ra-226                <    251.6            833.9      +/-   240.7        <:   232.9            <:   267.7         667.5     +/-  178.4   617.1       +/-   268.4 K-40             3849.0     +/-  276.6    4407.0      +/-   342.6    5490.0     +/-  266.8 3751.0     +/-  280.4 3405.0     +/-  303.4 5439.0        +/-   308.5 Sr-90       5        <      7.2               <:     9.5                 <:    5.2             <:    8.3             <:     7.2              <:      6.8 8-37

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma
                                                #23 Roseton (Control)
R~:8jf~;:;jSH'*: R?:::~2::;SH ?IM;';:::i~:':SH' Sample ."            ROSI;TON FISH
 , Location' Date                 , 08/15/2007 Client ID                  IFH234407S3               IFH234407S2            IFH234407S5            IFH234407S 1 BLUE CRAB               AMERICAN EEL               SUNFISH                CATFISH Radionuclide I Reg. CL 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

TABLE B-15 CONCENTRAnONS 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 Sample, Location Date Client lD           IFHCA T2407SS         IFHCA T2407S2           IFHCAT2407S3          IFHCAT2407S4         IFHCA T2607S I CARP             AMERICAN EEL             WHITE PERCH              CATFISH              SUNFISH Radionuclide Be-7             <   199.4            <    254.2               <   182.8             <   207.1            <   201.6 1-131            <   849.4            <    971.4                <  999.4             <   999.6            <   421.5 Cs-134     65     <    16.4            <     13.8                <   14.3             <     9.4            <    18.7 Cs-137    75      <    15.0            <     18.1               <    13.1             <    15.0            <    14.9 Zr-95            <   36.6             <    46.7                <    37.8             <   44.0             <    37.0 Nb-95            <   33.1             <    47.2                <    32.1             <    37.1            <    31.2 Co-58      65     <    24.5            <    26.1                <    19.6             <    19.3            <    22.3 Mn-54     65      <    18.0            <     19.9               <    13.4             <    15.0            <    18.6 Zn-65     130     <   45.1             <    48.1                <    37.5             <   20.2             <   40.6 Fe-59    130     <   98.9             <    83.9                <   80.4              <    74.5            <    61.3 Co-60     65      <    16.7            <     16.3               <    16.1             <    13.7            <    16.5 Ba/La-140           <  249.5             <    340.8               <   224.0             <   203.0            <   129.5 Ru-103            <   30.4             <    37.3                <   27.8              <    32.1            <    31.2 Ru-106            <   170.2            <    157.9               <   139.2       -     <   164.2            <   177.9 Ce-141            <   44.0             <    60.2                <   46.1              <    54.6            <   44.8 Ce-144            <   62.5             <    91.1                <   77.1              <   82.8             <   107.1 AcTh-228            <   46.9             <    54.1                <   47.8*             <   48.7          133.0 +/-     42.9 Ra-226         504.3    +/-  180.1  702.6     +/-  266.5     427.1    +/- 167.9    831.8    +/-  254.8  580.1    +/-  250.4 K-40         4487.0    +/-  293.7 3331.0     +/-  320.6   5681.0     +/- 273.5   4671.0    +/-  234.7 3946.0 . +/-   258.2 Sr-90     5      <    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<,," ",":'     ,'<" ;':'..      :                        ':  '"",-;"
                                                                                                                                  '~ERPLANCK SalllP'eLcication              (;::;\,,:';' ,':
* COLDSPRING                               '    'COLD SPRING'"
 /:2";"D~te':> i '
                                                                    >;.:*i                   .
                                                                "',                ",,):',',
                                                               '06/()6ti()07< "                    "
09/06j2()07     :' , I       06/07/2007,., '
Client ID                                                      IAV842307                             IAV843607                     IAVI72307 Aquatic                     W ATERMILFOIL                      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

TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma Sample COLD SPRING:*           'COLD SPRING               LENTS COVE                . LENTSCOV]i;*'.VERPLANCK                       1.;t'&#xa5;,ERPLANCK Location Date                  06/06/2007                09106/2007 ;;. 1';.06i06/2007                  ";01)(06/20(jj", ;          06/07/2007             '>:09/07/2007.' .
Client lD                  IBS842307        I        IBS843607        I        IBS282307        I          IBS283607       I       IBSI72307        I         IBSI73607
                       ~
Radionuclide Req. CL Be-7                 <    423.0                <   234.0                <    399.4                   <    339.4              <   417.3                  <    309.8 1-131                 <     108.6               <    48.9                <    112.3                   <     54.1              <    86.0                   <    55.5 Cs-134      75         <      31.3               <     38.3               <     32.9                   <     54.1              <    48.5                   <    39.4 Cs-137      90      254.8      +/- 44.1          <    34.9             373.7     +/-   58.4        209.2      +/-  41.1     252.7    +/-   49.6        217.1     +/-  41.0 Zr-95                 <     68.5                <     56.1               <    121.4                   <    77.0               <   100.1                  <     70.3 Nb-95                  <     64.8                <    25.4                <     83.2                   <    47.0               <    44.8                  <     51.5 Co-58                  <     43.6                <    36.4                <     54.1                   <    45.0               <    56.7                  <     27.2 Mn-54                  <     50.9                <    40.7                <     62.4                   <    42.1               <    45.1                  <    42.8 Zn-65                  <    133.6                <    93.9                <    167.7                   <    149.8              <   131.5                  <    100.4 Fe-59                  <    133.0                <    114.8               <    171.8                   <    143.4              <   175.8                  <    130.9 Co-60                  <     47.3                <    26.1                <     56.1                   <    77.3               <    46.6                  <    40.6 Ba/La-140                <    101.9                <    57.5                <    151.2                   <    101.2              <    36.0                  <    47.6 Ru-103                  <     47.5                <    35.0                <     54.3                   <    36.7               <    43.8                  <    42.9 Ru-106                 <    393.5                <    399.4               <    599.5                   <    379.5              <   463.1                  <    392.2 Ce-141                 <   . 84.9                <    45.3                <     79.7                   <    58.0               <    72.1                  <     56.5 Ce-144                 <    322.1                <    183.0               <    268.5                   <   231.0               <   260.2                  <    211.0 AcTh-228             1045.0      +/- 170.7      960.5     +/-  141.8    1214.0     +/-   237.0      658.1       +/-  152.0   1143.0    +/-   176.9       728.1     +/-  134.6 Ra-226             3153.0      +/- 869.8     2009.0     +/-  581.3    2263.0     +/-   908.4     1630.0       +/-  603.7   2008.0    +/-   792.1      1796.0     +/-  668.7 K-40             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
                                                                               ., I***'.....
Sample             '"
l,6cation      I.
DISCHARGE CANAL DISCHARGECANAL l'*,.*,         !'-,                                            .,
     ;'ii'.*;,i,Datc.                                                                                            ' ..
                                                                            'j                      '.
t .       , ..* :                 0'6107/2007     ; '
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!"                                                                                                              .. ,J{()~Et()~,*,
                    ':"::'i,':',      ".       ~OSETbN,            ,;"::,,,iROSETON!            ii!i~ROSEl'ON      '.'
RAINWATER                    ',i{AINWATEJ{         "
                                                                                                 .*~iNWATER.(1;           RAINWATER"":!"
                                                     ';,"',,"Y:                                                                                     ;'
1"\ '" Da:te .,.*. h');'!;':i;ii, .'."'.
                                              . 03/26/2007          :*:':i' ."()6/28/20oi'          .10/011200,7 I     ""12/3112007' 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 I" .;   Date"               "\'"
                                      ,.03/26/2007          .. ,
                                                                     .' 06/28/2007 ..     .'.' 10/01/2007          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~',               ..
I', , Location      .
                                     . ;,'        ROSETON                     MET JOWER                   .TRAINING
                                                                                                         ':     ... ,       .BLDG
                                             .,.r                      < ..    "   "," .* i".'"" i
 **:*" *.*Dafel       .'. ":,. :'
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

TABLE B-20 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCilliter +/- 1 Sigma ALGONQUIN OUTFALL Date     '0\/23/2007     "0211312007       I'.        03120/2001:         0411612007     051\5/2007 .         . '.()6(l9/2007 .' .
: Nl,JCLlI)E
                                                                          ' . .' .                :,' :': :.>            ':>>"E,:
1-/31          <   3.73         <  5.28                    < 2.82              < 3.31           <   4.09                    <  3.67 Cs-134          <   4.28         <  3.22                    < 2.58              < 1.57           <    3.70                   <  2.66 Cs-137          <   3.79         <  3.05                    < 2.32              < 2.77           <    3.78                   <  3.08 Zr-95          <   6.07         <  6.10                    < 4.02              < 3.78           <    5.08                   <  4.19 Nb-95           <   2.66         <  3.47                    < 2.48              < 1.81           <   4.44                    <  3.23 Co-58           <   3.63         <  3.15                    < 2.52              < 2.61           <    2.85                   <  3.16 Mn-54           <   2.76         <  3.33                    < 2.39              < 2.50           <    3.54                   <  3.22 Fe-59          <   7.14         <  6.88                    < 6.20              < 5.73           <    7.99                   <  4.62 Zn-65           <   4.68         <  4.26                    < 4.81              < 2.75           <   3.87                    <  4.02 Co-60           <   3.06         <  2.73                    < 2.66              < 2.35           <   3.42                    <  2.97 K-40    389.6 +/-  45.28 259.7 +/- 38.73         183.9 +/-   26.41     109.4 +/- 22.55 253.6 +/-    39.58       170.5 +/-      30.22 Ba/La-140         <   4.81         <  5.81                    < 2.85              < 2.66           <    3.54                   <  2.15 Date'     07/\7/2007       08/2112007                 09125/2007                                        :
  ~UCLIDE                                                     ,"":j:: ..'                                      '. . :::."  .
1-131          <   3.60         <  3.27                    < 3.82 Cs-134           <   3.21         <  3.05                    < 3.15 Cs-137           <   2.93         <  3.15                    < 4.10 Zr-95           <   5.07         <  4.47                    < 6.16 Nb-95           <  '3.96         <  3.23                    < 2.20 Co-58           <   3.14         <  2.67                    < 3.73 Mn-54           <   3.14         <  2.60                    < 2.74 Fe-59           <   6.63         <  7.10                    < 8.63 Zn-65           <   3.84         <  8.31                    < 2.92 Co-60           <   3.48         <  2.27                    < 3.28 K-40    126.2 +/-  30.28 191.2 +/- 33.92             115 +/- 30.54 Ba/La-140         <   3.97         <  2.54                    < 3.03                                                                    I B-46

TABLE B-20 CON CENTRA nONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma GYPSUM PLANT Date        01/2312007.**.**.         02/1312007 ...         03120/2007                04/16/2007             (j5/15/200T .           06/19/2007
                                ..:                                    ..:: .. :;        . .:                     '.                    i.,
NUCLIDE     ':                   ......     .':                                               '.::'.'.               ;::i: * ** :":                     .:'.>.:'
1-131            <  5.06                     < 5.75                   < 4.01                 <   3.29               < 3.11            \    <     2.91 Cs-134            <  3.90                     < 3.93                   < 3.44                 <   2.86               < 2.92                 <     2.57 Cs-137            <  2.38                     < 4.38                   < 1.54                 <   2.61               < 3.50                 <     2.94 Zr-95            <  6.75                     < 6.64                   < 6.22                 <   4.11               < 5.91                 <     4.76 Nb-95             <  2.75                     < 2.63                   < 2.73                 <   2.60               < 3.07                 <     3.15 Co-58            <  4.81                     < 3.78                   < 4.21                 <   2.48               < 2.64                 <     2.81 Mn-54             <  3.78                     < 3.29                   < 3.97                 <   2.77               < 3.46                 <     2.99 Fe-59            <  9.55                     < 11.75                  < 7.81                 <   6.81               < 6.51                 <     9.63 Zn-65            <  5.26                     < 4.39                   < 4.86                 <   3.76               < 6.35                 <     9.20 Co-60             <  4.99                     < 3.65                   < 3.63                 <   1.94               < 2.42                 <     3.44 K-40    244.5 +/-   46.13           130.7 +/- 35.72      149.7 +/- 31.47               300 +/-   35.31     129.6 +/- 37.81          266.3 +/-    42.45 Ba/La-140           < 4.75                      < 5.39                   < 4.44                 <   3.20               < 3.01                 <    4.17
     . Date        07117/2007 /              08/21/2007:\*       ! .09/2512007
.. :NUCLIDE 1- I31
                        <  2.49                     < 3.43
                                                                             ~t2.81 ....         i!';:*       I';
Cs-134            <  2.12                     < 3.39                   < 2.35 Cs-137            <  2.24                     < 1.70                   < 2.67 Zr-95            < 4.03                      < 5.22                   < 5.07 Nb-95             <  2.16                     < 2.65                   < 3.43 Co-58             <  2.06                     < 1.88                   < 2.04 Mn-54             <  2.42                     < 3.14                   <2.69 Fe-59            <  6.56                     < 7.04                   < 8.12 Zn-65            <  6.06                     < 4.02                   < 6.05 Co-60             <  3.02                     < 3.73                   < 2.84 K-40    402.3 +/-   38.66           169.5 +/-  27.58     197.4 +/- 32.26 Ba/La-I 40          <  2.89                     < 3.02                   < 4.35 8-47

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 Date NUCLIDE
[-131         <   3.12         <  4.34             < 2.56             <  3.64         <  3.95         <  3.87 Cs-134          <   1.78         <  3.27             <  1.91            <  2.24         <  3.30         <  4.33 Cs-137          <   2.67         <  2.90             < 2.28             <  2.35         <  3.97         <  3.63 Zr-95         <   4.02         <  5.16             < 3.90             <  4.58         <  5.03         <  4.59 Nb-95          <   1.98         <  3.00             < 2.04             <  3.37         <  4.16         <  3.13 Co-58          <   2.72         <  3.15             < 2.20             <  1.81         <  2.94         <  4.60 Mn-54           <   2.50         <  3.04             < 2.06             <  3.59         <  3.22         <  2.74 Fe-59         <   5.85         <  9.25             < 5.05             <  7.48         <  4.53         <  4.91 Zn-65          <   5.31         <  8.64             < 4.96             <  6.74         <  9.37         <  7.21 Co-60          <   1.51         <  4.38             < 1.95             <  2.74         <  2.38         <  4.24 K-40   122.5 +/-  26.20 267.9 +/- 38.23    277.1 +/- 29.28     103.8 +/- 30.27 134.9 +/- 37.84 127.7 +/- 36.36 BalLa-140                                                                <  3.29         <  4.53         <  4.53
  , Date
'NUCLIDE 1-131         <   3.12 Cs-134          <   3.89         <  2.07 Cs-137          <   2.65         <  3.07             < 3.65 Zr-95          <   5.28         <  5.03             < 4.89 Nb-95          <   3.15         <  2.79             < 3.01 Co-58          <   2.90         <  3.63             < 3.08 Mn-54           <   3.25         <  2.81             < 2.72 Fe-59          <   8.01         <  9.26             < 6.54 Zn-65          <   7.91         <  4.08             < 11.33 Co-60          <   3.24         <  3.03             < 3.97 K-40   234.6 +/-  39.31 218.6 +/- 43.43    241.2 +/- 45.51 Ba/La-140        <  '5.37         <  6.14             < 4.80 8-48

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCilL +/- 1 Sigma Monitoring We',,:
                               ..... MW::51'                   MW:40.         ....      MW-51
                                                                                                           'I'      MW-40      .. ,    .
Sample Name:'                      " MW"51-012.*.*             MWAO-01t*                MW-51~012 .            ....
MW"40-011 ..',"':,':"
Sarnple Date:             ....  . 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 C'c'c MonitoringWell:                          ",   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           10112/2007L .
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 v
K-40                                                          < 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

TABLE C-1 DIRECT RADIATION ANNUAL 

==SUMMARY==

1997 - 2007 1997        15.0      15.0      18.0 1998        14.0      15.0      16.0 1999        15.0      15.0      16.0 2000        14.0       15.0     16.0 200.1       15.0       15.0     17.0 2002        15.0       15.0     14.0 2003        14.3       13.9     14.7 2004        13.0       13.0     14.0 2005        14.1       14.1     15.9 2006        13.9       14.3     17.5 2007        14.4       14.6     18.8 14.3       14.5     16.2 C-2

FIGURE C-1 DIRECT RADIATION 40.0                         1997._ --_.
                                                      ~Inner   Ring 35.0                                             DOuter Ring
                                                      - Control Location 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  2003 2004  2005    2006   2007 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1997 to 2007 1997                     0.01           0.01       < Lc < Lc 1998                     0.02           0.01       < Lc < Lc 1999                     0.02           0.01       < Lc < Lc 2000                     0.01         . 0.01       < Lc < Lc 2001                     0.02           0.02       < Lc < Lc 2002                     0.02           0.02       < Lc < Lc 2003                     0.01           0.01       < Lc < Lc 2004                     0.01           0.01       < Lc < Lc 2005                     0.02           0.02       < Lc < Lc 2006                     0.01           0.01       < Lc < Lc 2007                     0.01           0.01       < Lc < Lc 0.01           0.01       < Lc < Lc Critical Level (Lc) is less than the aDCM required LLD.
<Lc indicates no positive values above sample critical level.
C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1997 to 2007 0.051------;----------.:~~==-----------------.
t?AJ All aDeM Indicator Locations
                                                                          -    Control Location 0.04 0.03
       ~
(3 c.
0.02 0.01 0.00 1997        1998          1999  2000    2001       2002       2003  2004   2005  2006  2007
* Includes aDCM and non-aDCM indicator locations.
Gross Beta aDCM required LLD = 0.01 pCi/m 3
c-s

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1997 to 2007 (pCi/L) 1997                      < Lc             430     < Lc .< Lc 1998                      < Lc             220     < Lc  < Lc 1999                       191             318     < Lc  < Lc 2000                       190             267     < Lc  < Lc 2001                      < Lc             323     < Lc  < Lc 2002                       432             562     < Lc  < Lc 2003                      < Lc             < Lc    < Lc < Lc 2004                      < Lc             553     < Lc  < Lc 2005                       < Lc            618     < Lc  < Lc 2006                      < Lc             386     < Lc < Lc 2007                      < Lc             < Lc    < Lc < Lc 271              409     < Lc < Lc Critical Level (Lc) is less than the aDCM required LLD.
<Lc indicates no positive values above sample critical level.
C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1997 to 2007 2000 e1J Inlet (H-3) 1800
                                                                                  ~   Discharge (H-3) 1600 1400 1200
      ...J
      ~ 1000 a.
800 600 400 200 0
1997        1998       1999 2000     2001        2002   2003 2004      2005   2006 2007 Tritium ODCM required LLD = 3000 pCilL C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1997 to 2007 (pC ilL) 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
                                            < Lc              < Lc Critical Level (Lc) is less than the ODCM required LLD.
<Lc indicates no positive values above sample critical level.
C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1997 to 2007 2000 1800 1600 1400 1200
      ...J i3 Q,
1000 NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR 800 600 400 200 0
1997      1998       1999       2000      2001        2002    2003   2004 2005 2006 2007 Tritium ODCM required LLD =2000 pCi/L e-g

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1997 to 2007 (pCi/Kg, dry) 1997                      < Lc   "-       < Lc     203   340 1998                      < Lc .          < Lc     143   < Lc 1999                       46             < Lc     200   238 2000                       58             < Lc     179   231 2001                       45             < Lc     230  .427 2002                      < Lc            < Lc     221   238 2003                      < Lc            < Lc     124    73 2004                      < Lc            < Lc     104   138 2005                      < Lc            < Lc     < Lc  174 2006                      <Lc             < Lc     120   < Lc 2007                      < Lc            < Lc     156   < Lc 50            < Lc      ,168  232 Critical Level (Lc) is less than the RETS required LLD.
<Lc indicates no positive values above sample critical level.
C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 750                                             1997 to 2007
                                                                                   ~    Indicator (Cs-134) 650                                                                      EB Control (Cs-134)
IiIIlndicator (Cs-137) 550
                                                                                  -     Control (Cs-137) 450
      ~
     ~
en
     ~
(3 c..
350 250 150 50 1997      1998       1999   2000     2001       2002    2003   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

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1997 to 2007 100~--------------------------------------------------------------------------------------.
IS) Indicator (Cs-137) 121 Control (Cs-137) 80
  -Q) 60 C)
  ~
(3 Co 40 20 01                           [::di~     j I&sect;l     i
                                                             ~<>J    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
                                          < Lc                < Lc Critical Level (Lc) is less than the ODeM required LLD.
<Lc indicates no positive values above sample critical level.
C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1997 to 2007 200
                                                                                            ~   Indicator (Cs-137) 180 EJ Control (Cs-137) 160 140 120 Q;
    ~
c; 100
    ~
U Q.
80 NO IDENTIFIED Cs-137IN PREVIOUS TEN YEAR HISTORY 60 40 20 0
1997       1998        1999        2000         2001        2002       2003  2004     2005    2006  2007 Cs-137 ODCM required LLD = 150 pCilKg, wet                            C-15

                  ,.: - ~. ~;
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                      1 Air                Gross Beta                     3 Air                   1-131                       4 Air              Mixed Gamma                      2                      1 Milk                   1-131                       3 Milk              Mixed Gamma                      3 Soil             Mixed Gamma                       1 Vegetation           Mixed Gamma                      2 TOTAL SAMPLE INVENTORY                              30                     2 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 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 ANALYTICS 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*     RATIO DATE        10 NO.      MEDIUM    ANALYSIS          pCi +/-1 sigma             pCi +/-2 sigma      (1) 06/14/2007    E5352-05       Filter                      78.3    +/-    2.2 GROSS              79.6    +/-    2.3 72.8   +/-    2.43 1.07   A BETA              76.6    +/-    2.2 Mean =    78.2    +/-    1.3 06/14/2007    E5346-09       Filter                      78.0    +/-    2.2 GROSS              82.0    +/-    2.3 75~0   +/-      3  1.07   A BETA              80.0    +/-    2.3 Mean =    80.0    +/-    1.3 12/06/2007    E5767-05       Filter                      76.6    +/-    2.2 GROSS              82.2    +/-    2.3 73.8   +/-    2.46 1.06   A BETA              76.8    +/-    2.2 Mean =    78.5    +/-    1.3 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D-5

TABLE 0*3 (Continued)
Tritium Analysis of Water SAMPLE                               JAF ELAB RESULTS         REFERENCE LAB*        RATIO DATE        IDNO.       MEDIUM   ANALYSIS         pCi/liter +/-1 sigma     . pCi/liter +/-2 sigma    (1 )
3/22/2007    E5331-05      Water     H-3              5510             177 5584             179 5010     +/-    167  1.10    A 5490             178 Mean =   5528        +/-    103 12/6/2007    E5542-09      Water     H-3              9671        +/-    208 9901        +/-    210   9000     +/-    300  1.09    A Mean =   9786        +/-    148 12/6/2007    E5543-09      Water     H-3              9684        +/-    209 9843        +/-    210   9000     +/-    300  1.08    A Mean =   9764        +/-    148 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D-6

TABLE 0-3 (Continued)
Gross Beta Analysis of Water SAMPLE                              JAF ELAB RESULTS       REFERENCE LAB* RATIO DATE        10 NO.      MEDIUM   ANALYSIS        pCilliter +/-1 sigma    pCi/liter +/-2 sigma    (1 )
11109/2007 A21998-0S         Water                   9.11E+OS +/- 1.S0E+04 GROSS           8.9SE+OS +/- 1.49E+04    9.30E+05 +/-
0.97 A BETA           8.91E+OS +/- 1.48E+04      S.S8E+04 Mean = 8.99E+OS +/- 8.60E+03 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D-7

TABLE 0-3 (Continued) 1-131 Gamma Analysis of Ai~ Charcoal SAMPLE.                                 JAF ELAB RESULTS      REFERENCE LAB*     RATIO DATE         10 NO. MEDIUM      ANALYSIS          pCi +/-1 sigma          pCi +/-2 sigma      (1 )
E5315-09     3/22/2007        Air                        66.8     +/-  4.46 69.8     +/-  4.55.
1-131            61.7    .+/-  3.99    70.0  +/-     2.3 0.97    A 72.7     +/-   5.2 Mean =    67.8     +/-  2.29 E5355-05    6/14/2007         Air                        72.7     +/-  4.22 79.7     +/-  5.09 1-131                               .79.0  +/-    2.63 0.99    A 83.0     +/-  4.16 Mean =    78.5     +/-  2.60 E5466-05     9/13/2007        Air                         74.4    +/-  3.46 65.7     +/-  3.92 1-131                                69.6  +/-    2.32 0.98    A 64.5     +/-  3.13 Mean =    68.2     +/-  2.03 E5446-09     9/13/2007        Air                        67.8     +/-  3.34 61.8     +/-  3.27 1-131                                70.0  +/-      2  0.93    A 66.3     +/-  3.18 Mean =    65.3     +/-  1.88 (1) Ratio = Reported/Analytics.
,
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D-8

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma A nalysis I       0 fW at er SAMPLE                                     JAF ELAB RESULTS           REFERENCE LAB*       RATIO DATE        IDNO.       MEDIUM     ANALYSIS              pCilliter +/-1 sigma       pCi/liter +/-2 sigma    (1 )
4/18/2007     E5332-05      Water                               153       +/-    7.98 151       +/-     2.4 Ce-141                                        140     +/-    4.65 1.08    A 148       +/-    3.63 Mean    =      151       +/-     3.0 115       +/-    12.1 Cr-51                  139       +/-    15.4   104          3.47 1.22    A Mean    =      127       +/-     9.8 83.0       +/-    6.11 94.3       +/-    2.03 Cs-134                                       91.2     +/-    3.04 1.02    A 102       +/-    2.43 Mean    =     93.1       +/-     2.3 201       +/-    7.53 195       +/-    2.41 Cs-137                                        196     +/-    6.53 1.01    A 197       +/-    3.08 Mean    =      198       +/-     2.8 65.6       +/-    6.04 67.0       +/-    1.71 Co-58                                       63.5     +/-    2.12 1.01    A 59.8       +/-    2.27 Mean    =     64.1       +/-     2.2 168       +/-    7.48 146       +/-    2.36 Mn-54                                        144     +/-    4.79 1.08    A 154       +/-    2.89 Mean    =      156       +/-     2.8 63.1       +/-     6.4 58.1       +/-    2.26 Fe-59                                       58.0     +/-    1.93 1.03    A 58.6       +/-     2.5 Mean    ==    59.9       +/-     2.4 830       +/-     23 817       +/-    7.46 Zn-65                                        776     +/-    25.9 1.06    A 825       +/-    9.26 Mean    ==     824       +/-     8.6 123       +/-    4.79 128       +/-     1.6 Co-60                                        126     +/-     4.2 1.01    A 129       +/-    1.95 Mean    =      127       +/-     1.8 100       +/-    4.75 99.4       +/-     4.9 1-131 **                                     89.8     +/-    2.99 1.10    A 90.9       +/-    4.32 104       +/-    4.32 Mean ==       98.6       +/-     2.3 (1) Ratio = Reported/Analytlcs.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A==Acceptable U==Unacceptable 0-9

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma Analysis 0 fW ater SAMPLE                                    JAF ELAB RESULTS          REFERENCE LAB* RATIO DATE        IDNO.       MEDIUM     ANALYSIS            pCilliter +/-1 sigma       pCilliter +/-2 sigma    (1 )
6/14/2007     E5345-09       Water                             158      +/-    3.78 181      +/-    3.47 Ce-141                                      160     +/-      5  1.06    A 169      +/-    9.27 Mean =        169      +/-     3.5
                                                             , 428       +/-    20.1 420       +/-    16.3 Cr-51                                      411     +/-     14  1.06    A 461       +/-    52.3 Mean =       436       +/-    19.5 208      +/-     3.6 204      +/-    2.73 Cs-134                                      194     +/-      6  1.05 A 202       +/-    10.3 Mean =       205       +/-     3.7
                                                               '132      +/-    2.99 141      +/-    2.34 Cs-137                                      135     +/-      5  1.01    A 140      +/-    8.12 Mean =        138      +/-     3.0 164      +/-     3.3 166      +/-    2.49 Co-58                                      159     +/-      5  1.05    A 170      +/-    8.93 Mean =        167      +/-     3.3 147      +/-    3.32 154      +/-    2.41 Mn-54                                      133     +/-      4  1.15    A 159      +/-    8.67 Mean =        153      +/-     3.2 141      +/-    4.05 145      +/-    2.81 Fe-59                                      134     +/-      4  1.03    A 130      +/-    10.4 Mean =        139      +/-     3.8 277       +/-   7.04 293      +/-    5.05 Zn-65                                      268     +/-      9  1.08    A 300      +/-    18.7 Mean =        290       +/-    6.9 192       +/-   2.79 195      +/-      2 Co-60                                      191     +/-      6  1.01    A 189      +/-    7.36 Mean =        192       +/-    2.7 108      +/-    B.97 102       +/-   2.13 1-131**                                     102     +/-      3  1.02    A 103       +/-   2.37 Mean =        104       +/-    3.2 (1) Ratio = Reported/Analytlcs.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable D-10

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma A nalysis I      0 fWater SAMPLE                                     JAF ELAB RESUL TS         REFERENCE LAB*       RATIO DATE        IDNO.       MEDIUM     ANALYSIS             pCilliter+/-1 sigma        pCi/liter +/-2 sigma    (1 )
9/13/2007     E5463-05      Water                              198      +/-    9.06 179      +/-    9.53 Ce-141                                       182     +/-    6.05 1.03    A 188      +/-    10.8 Mean =        188      +/-     5.7 253       +/-    37.5.
245       +/-    41.3 Cr-51                                       249     +/-    8.29 0.93    A 200       +/-    42.5 Mean =       233       +/-    23.4 134      +/-     8.9 134      +/-    9.08 Cs-134                                       127     +/-    4.22 1.10    A 150      +/-    8.93 Mean =        139      +/-     5.2 105      +/-    6.75 107      +/-    7.68 Cs-137                                       112     +/-    3.74 0.96    A 109      +/-    7.87 Mean =        107      +/-     4.3 103      +/-    6.62 103      +/-    7.11 Co-58                                      98.1     +/-    3.27 0.99    A 86.5      +/-    7.35 Mean =       97.5      +/-     4.1 173      +/-    8.22 161      +/-    8.73 Mn-54                                       144     +/-     4.8 1.14    A 158      +/-    8.93 Mean =        164      +/-     5.0 105      +/-    7,93 106      +/-    8,51 Fe-59                                      95.1     +/-    3,17 1.15    A 117      +/-    9,07 Mean =        109      +/-     4.9 204      +/-    13,8 212      +/-    15.9 Zn-65                                       174     +/-     5,8 1.20 A 208      +/-    16,3 Mean =        208      +/-     8.9 121       +/-    5,3 128      +/-    6.28 Co-60                                       127     +/-    4.24 1.03    A 144       +/-   6.72 Mean =        131      +/-     3.5 83.5      +/-    1.77 80.3       +/-   2.51 1-131**                                     80.1     +/-    2.67 1.04    A 86,1      +/-    2.38 Mean =       83.3       +/-    1,3 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 0-11

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gam rna A nalysis I      0 fW at er SAMPLE                                     JAF ELAB RESULTS           REFERENCE LAB*       RATIO DATE        IDNO.       MEDIUM     ANALYSIS             pCilliter +/-1 sigma        pCi/liter +/-2 sigma    (1 )
12/6/2007    E5544-09       Water                             156       +/-    10.7 155       +/-    8.47 Ce-141                                        157     +/-      5  0.99    A 153       +/-    11.5 Mean =        155       +/-     5.9 657        +/-      52 557       +/-    40.6 Cr-51                                        572     +/-     19  1.06    A 611       +/-    58.7 Mean =        608       +/-    29.4 168       +/-    8.91 155       +/-    7.61 Cs-134                                        153     +/-      5  1.05    A 161       +/-    9.97 Mean =        161       +/-     5.1 191       +/-    8.36 177       +/-    7.05 Cs-137                                        185     +/-      6  0.97    A 172       +/-    9.27 Mean =        180       +/-     4.8 214       +/-    8.97 223       +/-    7.81 Co-58                                        194     +/-      6  1.10    A 202       +/-    10.1 Mean =        213       +/-     5.2 240       +/-    9.27 228       +/-    7.81 Mn-54                                         212     +/-      7  1.10    A 231       +/-    10.9 Mean =        233       +/-     5.4 177       +/-    9.99 182       +/-    8.84 Fe-59                                        166     +/-      6  1.06    A 169       +/-    .11.6 Mean =        176        +/-    5.9 296        +/-    16.6 287        +/-    14.3 Zn-65                                        261     +/-      9  1.10    A 278        +/-    19.3 Mean =        287        +/-    9.7 229        +/-   6.95 228        +/-   6.05 Co-60                                        236     +/-      8  0.98    A 237        +/-    8.36 Mean =        231        +/-    4.1 73.7        +/-    3.53 74.5        +/-    1.97 1-131**                                      72.0     +/-      2  1.04    A 76.3        +/-    3.37 Mean =       74.8        +/-     1.8 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 0-12

TABLE 0*3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma A nalysis 0 fM"lk     I SAMPLE                                    JAF ELAB RESULTS            REFERENCE LAB*        RATIO DATE        10 NO.      MEDIUM     ANALYSIS            pCilliter +/-1 sigma        . pCi/liter +/-2 sigma    (1 )
3/22/2007    E5316-09       MILK                            304         +/-     4.2 304         +/-     5.4 Ce-141                                        297      +/-     9.9 1.01    A 293         +/-     5.5 Mean =      300         +/-     2.9 227         +/-    16.6 204         +/-    22.1 Cr-51                                         245     +/-     8.2 0.90    A 227         +/-    22.9 Mean =      219         +/-    12.0 110        +/-     2.8 111        +/-     3.2 Cs-134                                         112     +/-     3.7 0.98    A 107        +/-     3.5 Mean =       109        +/-     1.8 227         +/-     3.5 232        +/-     4.1 Cs-137                                        234      +/-     7.8 0.98    A 232         +/-   . 4.7 Mean =      230         +/-     2.4 95.6        +/-     3.1 101        +/-     3.3 Co-58                                        99.0     +/-     3.3 0.99    A 98.0        +/-     3.8 Mean =      98.2        +/-     2.0 189        +/-     3.6 189       .+/-     3.9 Mn-54                                         182     +/-     6.1 1.04    A 189        +/-     4.5 Mean =       189        +/-     2.3 114        +/-     3.8 127        +/-     4.1 Fe-59                                         106     +/-     3.5 1.12    A 114        +/-     4.6 Mean =       118        +/-     2.4 1040        +/-     11.6 1090        +/-     12.9 Zn-65                                        1000     +/-    33.3 1.06    A 1050        +/-     14.7 Mean =      1060        +/-     7.6 144        +/-     2.4 146        +/-     2.6 Co-60                                         152     +/-     5.1 0.95    A 144        +/-     3.0 Mean =       145        +/-      1.5 97        +/-     3.9 91.2        +/-     4.1 1-131**                                       85.0     +/-     2.8 1.11    A 95.5        +/-     5.3 Mean =      94.6        +/-     2.6 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable D-13

TABLE D-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma A nalysls 0 fM"lk    I SAMPLE                                    JAF ELAB RESULTS          REFERENCE LAB* RATIO DATE        IDNO.       MEDIUM     ANALYSIS            pCilliter +/-1 sigma       pCilliter +/-2 sigma    (1 )
6/14/2007     E5353-05       MILK                            209        +/-    4.33 205        +/-    5.94 Ce-141                                     200,     +/-    6.66 1.01    A 192       +/-    4.16 Mean =      202        +/-    2.82 519       +/-    22.1 575       +/-    26.9 Cr-51                                      512     +/-    17.1 1.07    A 543        +/-    19.2 Mean =      546        +/-    13.3 249        +/-    4.19 257       +/-    4.55 Cs-134                                      242     +/-    8.06 1.06    A 260       +/-    3.47 Mean =      255        +/-    2.36 162       +/-    3.45 169       +/-    3.86 Cs-137                                      169     +/-    5.63 0.99    A 170       +/-    3.06 Mean =       167       +/-    2.00 198       +/-    3.81 211       +/-    4.14 Co-58                                      198     +/-    6.61 1.04    A 208       +/-    3.30 Mean =       206       +/-    2.17 177       +/-    3.55 185       +/-    3.94 Mn-54                                      166     +/-    5.53 1.10    A 185       +/-    3.19 Mean =       182       +/-    2.06 184       +/-    4.42 182       +/-    4.75 Fe-59                                      167     +/-    5.56 1.09    A 181       +/-    3.78 Mean =       182       +/-    2.50 352       +/-    7.63 379       +/-    10.6 Zn-65                                      334     +/-    11.1 1.08    A 354       +/-    6.73 Mean =       362       +/-    4.90 237        +/-   3.02 242       +/-    3.27 Co-60                                      238     +/-    7.93 1.01    A 240       +/-    2.62 Mean =       240        +/-   1.72 65.4        +/-   2.07 65.9        +/-   2.29 1~131**                                   70.1     +/-    2.34 0.94    A 65.9       +/-    1.87 Mean =      65.7        +/-   1.20 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable D-14

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM G amma A nalysis 0 fM"lk    I SAMPLE                                   JAF ELAB RESULTS            REFERENCE LAB*       RATIO DATE         10 NO.      MEDIUM    ANALYSIS            pCi/iiter +/-1 sigma         pCi/liter +/-2 sigma    (1) 9/13/2007     E5465-05        MILK                            188       +/-    10.8 239        +/-    10.5 Ce-141                                        211     +/-    7.04 0.99   A 198       +/-    9.94 Mean :::    208        +/-    6.02 200        +/-    42.5 250        +/-    41.4 Cr-51                                        289     +/-    9.65 0.89   A 320       +/-    42.1 Mean :::    257        +/-    24.3 150       +/-    8.93 156       +/-    8.74 Cs-134                                        147     +/-    4.91 1.03   A 149       +/-    8.69 Mean :::     152       +/-    5.07 109       +/-    7.87 144       +/-    8.32 Cs-137                                        131     +/-    4.35 0.96   A 126       +/-    7.38 Mean :::     126       +/-    4.54 86.5       +/-    7.35 127       +/-    8.17 Co-58                                        114     +/-    3.80 0.95   A 111       +/-    7.19 .
Mean :::     108       +/-    4.38 158       +/-    8.93 176       +/-    9.18 Mn-54                                        168     +/-    5.59 1.03   A 184       +/-    8.60 Mean :::     173       +/-    5.14 117       +/-    9.07 113       +/-    9.94 Fe-59                                        111     +/-    3.69 1.04   A 117       +/-    8.44 Mean :::     116       +/-    5.29 208       +/-    16.3 226       +/-    17.5 Zn-65                                        202     +/-    6.74 1.10   A 232       +/-    15.7 Mean :::     222       +/-    9.54 144       +/-    6.72 151       +/-    6.83 Co-60                                        148     +/-    4.94 0.98   A 139       +/-    5.89 Mean :::     145       +/-    3.75 77.6       +/-    2.52 76.4       +/-    2.34 1-131**                                      85.2     +/-    2.84 0.89   A 72.7        +/-   3.10 Mean :::    75.6       +/-    1.54 (1) Ratio::: Reported/Analytics.
* Sample provided by Analytics, Inc.
** Result determined by Resin Extraction/Gamma Spectral Analysis.
A:::Acceptable U:::Unacceptable 0-15

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma Analysis I   0 fA*Ir Pa rfleu Iate F"IIter SAMPLE                               JAF ELAB RESULTS           REFERENCE LAB* RATIO DATE        IDNO.       MEDIUM   ANALYSIS            pCi +/-1 sigma             pCi +/-2 sigma      (1 )
3/22/2007    E5333-05*     FILTER                       234      +/-     3.01 230      +/-     2.54 Ce-141                                    233    +/-    7.78 1.02    A 246      +/-     8.32 Mean =     237      +/-     3.07 206      +/-     15.8 197      +/-      15.6 Cr-51                                    192    +/-    6.41 1.10    A 230      +/-     40.0 Mean =     211      +/-     15.3 95.8     +/-     1.99 76.8     +/-     3.02 Cs-134                                    87.9   +/-    2.93 1.02    A 95.6     +/-     5.43 Mean =     89.4     +/-     2.17 188      +/-     2.43 179      +/-     2.04 Cs-137                                    185    +/-    6.15 1.00    A 186      +/-     6.48 Mean =     184      +/-     2.41 76.9     +/-     2.18 77      +/-. 2.09 Co-58                                    77.7   +/-    2.59 0.99    A 76.4     +/-     6.07 Mean =     76.8     +/-     2.26 160      +/-     2.62 150      +/-     2.17 Mn-54                                    144    +/-    4.78 1.08    A 157      +/-     6.71 Mean =     156      +/-     2.51 93.1     +/-     3.46 84.2     +/-     2.94 Fe-59                                    83.1   +/-    2.77 1.08    A 93.1     +/-     8.98 Mean =     90.1     +/-     3.35 870      +/-     8.82 852      +/-     7.55 Zn-65                                    787    +/-    26.2 1.09    A 856      +/-     23.5 Mean =     859      +/-     8.74 114      +/-      1.69 118      +/-      1.46 Co-60                                    120    +/-    3.99 0.95    A 111      +/-     4.42 Mean =     114      +/-      1.65 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 0-16

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM G amma A nalysis 0 fA"Ir Pa rfleu Iate Fit I er SAMPLE                                  JAF ELAB RESUL TS        REFERENCE LAB*    RATIO DATE         10 NO.      MEDIUM   ANALYSIS             pCi +/-1 sigma           pCi +/-2 sigma      (1 )
9/13/2007    E5464-05        FILTER                        195      +/-     5.84 194      +/-     5.05 Ce-141                                    207   +/-    6.90 0.96    A 209      +/-    6.01 Mean =      199      +/-      3.3 238      +/-    27.9 256      +/-      23 Cr-51                                    284   +/-    9.46 0.94    A 307      +/-     33.5 Mean =      267      +/-     16.4 163      +/-     8.66 151      +/-    6.52 Cs-134                                    145   +/-    4.82 1.13    A 177      +/-     10.2 Mean =      164      +/-      5.0 117      +/-     6.54 123      +/-     5.42 Cs-137                                    128   +/-    4.27 0.94    A 120      +/-     7.64 Mean =      120      +/-      3.8 109      +/-       7 112      +/-     5.44 Co-58                                    112   +/-    3.73 0.99    A 113      +/-     7.41 Mean =      111      +/-      3.9 179      +/-     8.69 166      +/-     6.59 Mn-54                                    164   +/-    5.48 1.04    A 168      +/-     9.02 Mean =      171      +/-      4.7 117      +/-     8.96 130      +/-     7.02 Fe-59                                    108   +/-    3.61 1.10    A 110      +/-      9.8 Mean =      119      +/-      5.0 211      +/-     15.1 239      +/-     12.6 Zn-65                                    198   +/-    6.61 1.16    A 237      +/-     18.5 Mean =     229      +/-      9.0 141      +/-     6.38 140      +/-     4.88 Co-60                                    145   +/-    4.84 0.96    A
                -                                            135      +/-       7 Mean =     139      +/-      3.6 (1 ) RatiO = Reportedl Analytlcs.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D-17

TABLE D-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gam rna A nalYSIS 0 fS 01"I SAMPLE                               JAF ELAB RESUL TS          REFERENCE LAB*      RATIO DATE        10 NO.      MEDIUM   ANALYSIS           pCi/g +/-1 sigma           pCi/g +/-2 sigma      (1 )
6/14/2005    E5354-05        SOIL                       0.164      +/-  0.007 0.144      +/-  0.014 Ce-141                                    0.178  +/-    0.006 0.93    A 0.190      +/-  0.012 Mean =    0.166      +/-  0.007 0.413      +/- *0.041 0.401      +/-  0.071 Cr-51                                    0.456  +/-    0.015 0.88    A 0.387      +/-   0.057*
Mean =    0.400      +/-   0.033 0.218      +/-   0.007 0.218      +/-   0.013 Cs-134                                    0.215   +/-   0.007 1.02    A 0.220      +/-   0.009 Mean =    0.219      +/-   0.006 0.242      +/-   0.007 0.249      +/-   0.013 Cs-137                                    0.248   +/-   0.008 1.00    A 0.251      +/-   0.008 Mean =    0.247      +/-   0.006 0.166      +/-   0.006 0.154      +/-   0.012 Co-58                                    0.176   +/-   0.006 0.93    A 0.169      +/-   0.007 Mean =    0.163      +/-   0.005 0.137      +/-   0.006 0.161      +/-   0.011 Mn-54                                    0.148   +/-   0.005 1.01    A 0.152      +/-   0.007 Mean =    0.150      +/-   0.005 0.141      +/-   0.009 0.147      +/-   0.016 Fe-59                                    0.148   +/-   0.005 0.97    A 0.144      +/-   0.009 Mean =    0.144      +/-   0.007 0.315      +/-   0.013 0.305      +/-   0.023 Zn-65                                    0.297   +/-   0.010 1.04    A 0.306      +/-   0.014 Mean =    0.309      +/-   0.010 0.201      +/-   0.005 0.192      +/-   0.010 Co-60                                    0.212   +/-   0.007 0.93    A 0.196      +/-   0.005 Mean =    0.196      +/-   0.004 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D:-18

TABLE D-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma Analysis 0 tvegetafIon SAMPLE                              JAF ELAB RESULTS        REFERENCE LAB* RATIO DATE        IDNO.       MEDIUM   ANALYSIS         pCi/g +/-1 sigma          pCi/g +/-2 sigma      (1 )
6/14/2007    E5356-05        VEG                      0.158      +/-  0.010 0.145      +/-  0.005 Ce-141                                0.161   +/-    0.005 0.95    A 0.154      +/-  0.007 Mean =   0.152      +/-  0.004 0.404      +/-  0.050 0.349      +/-  0.028 Cr-51                                0.413    +/-   0.014 0.92    A 0.388      +/-  0.043 Mean =   0.380      +/-  0.024 0.210      +/-  0.010 0.215      +/-  0.006 Cs-134                                0.195    +/-   0.007 1.11    A 0.222      +/-  0.009 Mean =   0.216      +/-  0.005 0.132      +/-  0.008 0.134      +/-  0.005 Cs-137                                0.136    +/-   0.005 0.96    A 0.126      +/-  0.008 Mean =   0.131      +/-  0.004 0.145      +/-  0.010 0.151      +/-  0.005 Co-58                                0.160    +/-   0.005 0.98    A 0.173      +/-  0.008 Mean =    0.156     +/-  0.005 0.144     +/-  0.009 0.137     +/-  0.005 Mn-54                                0.133    +/-   0.004 1.05    A 0.138      +/-  0.008 Mean =    0.140     +/-  0.004 0.122     +/-  0.013 0.141     +/-  0.007 Fe-59                                0.135    +/-   0.005 1.00    A 0.143     +/-  0.011 Mean =    0.135     +/-  0.006 0.241     +/-  0.021 0.275     +/-  0.011 Zn-65                                0.270    +/-   0.009 0.98    A 0.279     +/-  0.018 Mean =    0.265     +/-  0.010 0.188     +/-  0.008 0.182     +/-  0.004 Co-60                                0.192    +/-   0.006 0.98    A 0.193     +/-  0.007 Mean =    0.188     +/-  0.004 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable .
D-19 ..

TABLE 0*3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma A nalysis 0 tVeget afIon SAMPLE                              JAF ELAB RESULTS        REFERENCE LAB* RATIO DATE        10 NO.      MEDIUM   ANALYSIS         pCi/g +/-1 sigma         pCi/g +/-2 sigma      (1 )
9/13/2007    E5447-09        VEG                       0.342     +/-. 0.016 0.298     +/-  0.015 Ce-141                                0.333 .+/-    0.011 0.95    A 0.312     +/-  0.014 Mean =    0.317     +/-  0.009 0.409     +/-  0.070 0.392     +/-  0.068 Cr-51                                0.457  +/-    0.015 0.90    A 0.433     +/-  0.063 Mean =    0.411     +/-  0.039 0.269     +/-  0.026 0.221     +/-  0.018 Cs-134                                0.233  +/-    0.008 1.05    A 0.243 .+/-     0.016 Mean =    0.244     +/-  0.012 0.224     +/-  0.015 0.206     +/-  0.014 Cs-137                                0.206  +/-    0.007 1.05    A 0.220     +/-  0.014 Mean =    0.217     +/-  0.008 0.161     +/-  0.013 0.166     +/-  0.014 Co-58                                0.180  +/-    0.006 0.94    A 0.179     +/-  0.013 Mean =    0.169     +/-  0.008 0.282     +/-  0.016 0.275     +/-  0.016 Mn-54                                0.265   +/-   0.009 1.00    A 0.240     +/-  0.014 Mean =    0.266     +/-  0.009 0.178     +/-  0.017 0.169     +/-  0.019 Fe-59                                0.175   +/-   0.006 1.01    A 0.185     +/-  0.017 Mean =    0.177     +/-  0.010 0.346     +/-  0.032 0.392     +/-  0.031 Zn-65                                0.319   +/-   0.001 1.17    A 0.379     +/-  0.029 Mean =    0.372     +/-  0.018 0.244     +/-  0.012 0.235     +/-  0.012 Co-60                                0.234   +/-   0.008 1.02    A 0.235     +/-  0.012 Mean =    0.238     +/-  0.005 (1) Ratio = Reported/Analytics.
* Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D-20

TABLE 0-3 (Continued)
INTERLABORATORY COMPARISON PROGRAM G amma A nalysis I     0 fNISTW ater SAMPLE                             JAF ELAB RESULTS      REFERENCE LAB* RATIO DATE        10 NO.      MEDIUM  ANALYSIS         Bq/g +/-1 sigma        Bq/g +/-2 sigma     (1 )
4123/2007     1911-4       Water                     300.8    +/-  2.09 299.7    +/-  2.09 Co-57                              310.7 +/-    2.05 0.97    A 303.4    +/-  2.10 Mean =    301.3    +/-  1.21 306.4    +/-  2.38 312.7    +/-  2.35 Ba-133                              326.7 +/-     3.1 0.95    A 312.3    +/-  2.27 Mean =    310.4    +/-  1.35 283.8    +/-  2.32 290.1    +/-  2.31 Cs-137                              308.4  +/-   2.31 0.94    A 291.9    +/-  2.22 Mean =    288.6    +/-  1.32 190.6    +/-  1.69 196.5    +/-  1.69 Co-60                              202.4  +/-   1.01 0.96    A 193.9    +/-  1.57 Mean =    193.6    +/-  0.95 (1) Ratio = Reported/Analytics.
* Sample provided by NIST A=Acceptable U=Unacceptable 0-21

TABLE 0*3 (Continued)
INTERLABORATORY COMPARISON PROGRAM Gamma A narysrs I     0 f NIST Fit  r er SAMPLE                              JAF ELAB RESUL TS        REFERENCE LAB*       RATIO DATE        10 NO.      MEDIUM   ANALYSIS        Bq/filter +/-1 sigma      Bq/filter +/-2 sigma    (1 )
4/23/2007    1912-11        Filter                    1077       +/-    4.0 1073       +/-    4.6 Co-57                                 1089     +/-    10.9 1.01    A 1143       +/-    4.8 Mean =    1098       +/-    2.6 1006       +/-    5.2 1003       +/-    6.0 1048          10.5 0.96 Ba-133                                          +/-                 A 1006       +/-    5.4 Mean =    1005       +/-    3.2 743.7      +/-    4.9 725.2      +/-    5.7 Cs-137                                 766.1    +/-     7.7 0.98    A 777.0      +/-    5.0 Mean =    748.6      +/-    3.0 969.4      +/-    5.2 962.0      +/-    6.1 Co-60                                 987.0    +/-     9.9 0.98    A 976.8      +/-    4.9 Mean =    969.4      +/-    3.1 (1) Ratio = Reported/Analytics.
* Sample provided by NIST A=Acceptable U=Unacceptable D-22

==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}}