ML031220085

Annual Radiological Environmental Operating Report for 2002

ML031220085
Person / Time
Site:	Indian Point
Issue date:	04/29/2003
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, NRC/FSME
References
NL03.075
Download: ML031220085 (132)

Text

Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 RO. Box 249 Entergy Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations INJL03. 076 4eij1 9A) goe's U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, D.C. 20555-0001

SUBJECT:

Indian Point Nuclear Power Plant Units No. 1, 2, and 3 Docket Nos. 50-03, 50-247 and 50-286 License Nos. DPR-5, DPR-26 and DPR-64 Annual Radiological Environmental Operating Report

Dear Sir:

This letter provides Entergy Nuclear Operations, Inc.'s (ENO's) Annual Environmental report is Operating Report for the period January 1, 2002 through December 31, 2002. This DPR-26, and DPR-64, for submitted in accordance with facility's operating license, DPR-5, Indian Point Units 1, 2, and 3, respectively.

ENO is making no new commitments in this letter.

Should you have any questions regarding this matter, please contact Mr. John McCann, Manager, Nuclear Licensing at (914) 734-5074.

Ve ours, Fred R Dacim Vice President, Operations Indian Point Energy Center Enclosure

,f -L" -- -6

Docket Nos: 50-03, 50-247, 50-286 NL-03-075 Page 2 of 2 cc: Mr. Hubert J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager Project Directorate 1-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, D.C. 20555-0001 Mr. R. Laufer, Project Manager Project Directorate I Division of Reactor Projects I/Il U.S. Nuclear Regulatory Commission Mail Stop 8G9 Washington, D.C. 20555 Mr. John L. Minns, Project Manager Division of Reactor Program Management U.S. Nuclear Regulatory Commission Mail Stop 10-D4 Washington, D.C. 20555 Senior Resident Inspector Indian Point Unit 2 U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, NY 10511 Senior Resident Inspector Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511 Mr. John P. Spath, Director Radioactive Waste Policy and Nuclear Coordination New York State Energy Research and Development Authority 2 Empire State Plaza, Suite 1901 Albany, NY 12233-1253

l-03-075 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR NORTHEAST INDIAN POINT NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 Docket No.50-003 Indian Point Unit 1 (IPI)

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

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

January 1 - December 31, 2002

TABLE OF CONTENTS Paqe 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 3-2 3.3.6 Broad Leaf Vegetation 3-3 3.3.7 Fish and Invertebrates 3-3 3.3.8 Hudson River Aquatic Vegetation (Non-RETS) 3-3 3.3.9 Hudson River Bottom Sediment (Non-RETS) 3-3 3.3.10 Precipitation (Non-RETS) 3-3 3.3.11 Soil (Non-RETS) 3-3 3.3.12 Land Use Census 3-4 3.4 Statistical Methodology 3-4 3.4.1 Lower Limit of Detection and Critical Level 3-4 3.4.2 Determination of Mean and Propagated Error 3-5 3.4.3 Table Statistics 3-6 3.5 Program Units 3-7 i

TABLE OF CONTENTS (continued)

Page 4.0 RESULTS AND DISCUSSION 4-1 4.1 Direct Radiation 4-3 4.2 Airborne Particulates and Radioiodine 4-4 4.3 Hudson River Water 4-5 4.4 Drinking Water 4-6 4.5 Hudson River Shoreline Soil 4-6 4.6 Broad Leaf Vegetation 4-6 4.7 Fish and Invertebrates 4-7 4.8 Additional Media Sampling 4-7 4.9 Land Use Census 4-8 4.10 Conclusion 4-8 5.0 QUALITY ASSURANCE 5-1

6.0 REFERENCES

6-1 APPENDICES:

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

SUMMARY

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

LIST OF FIGURES FIGURE TITLE Page A-1 RETS Sampling Locations (Within Two Miles) A-5 A-2 RETS Sampling Locations (Greater Than Two Miles) A-6 A-3 Non-RETS Sampling Locations A-7 C-1 Direct Radiation, 1992 to 2002 C-3 C-2 Radionuclides in Air - Gross Beta, 1992 to 2002 C-5 C-3 Hudson River Water-Tritium, 1992 to 2002 C-7 C-4 Drinking Water - Tritium, 1992 to 2002 C-9 C-5 Radionuclides in Shoreline Soil, 1992 to 2002 C-11I C-6 Broad Leaf Vegetation - Cs-137, 1992 to 2002 C-13 C-7 Fish and Invertebrates - Cs-137, 1992 to 2002 C-15 iii

LIST OF TABLES TABLE TITLE Page A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection Requirements for Environmental Sample Analysis A-8 A-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples A-9 B-1 Summary of Sampling Deviations, 2002 B-3 B-1a 2002 Air Sampling Deviations B4 B-1 b 2002 TLD Deviations B-4 B-1 c 2002 Other Media Deviations B-4 B-2 RETS Annual Summary, 2002 B-5 B-3 2002 Direct Radiation, Quarterly Data B-9 B-4 Direct Radiation, 1997 Through 2002 Data B-10 B-5 2002 Direct Radiation, Inner and Outer Rings B-1I1 B-6 Gross Beta Activity in Airborne Particulate Samples, 2002 B-12 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2002 B-16 B-8 1-131 Activity in Charcoal Cartridge Samples, 2002 B-21 B-9 Concentrations of Gamma Emitters in Hudson River Water Samples, 2002 B-23 B-10 Concentrations of Tritium in Hudson River Water Samples, 2002 B-25 B-1I1 Gross Beta Activity and Concentrations of Gamma Emitters in Drinking Water Samples, 2002 B-26 B-12 Concentrations of Tritium in Drinking Water Samples, 2002 B-28 B-13 Concentrations of Gamma Emitters in Shoreline Soil Samples, 2002 B-29 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation, 2002 B-30 B-15 Concentrations of Gamma Emitters in Fish and Invertebrate Samples, 2002 B-36 B-16 Annual Summary, Non-RETS Sample Results, 2002 B-37 B-17 Milch Animal Census, 2002 B-38 B-18 Land Use Census, 2002 B-39 iv

LIST OF TABLES (Continued)

TABLE TITLE PaEe C-1 Direct Radiation Annual Summary, 1992 to 2002 C-2 C-2 Radionuclides in Air, 1992 to 2002 C-4 C-3 Radionuclides in Hudson River Water, 1992 to 2002 C-6 C-4 Radionuclides in Drinking Water, 1992 to 2002 C-8 C-5 Radionuclides in Shoreline Soil, 1992 to 2002 C-10 C-6 Radionuclides in Broad Leaf Vegetation, 1992 to 2002 C-12 C-7 Radionuclides in Fish and Invertebrates, 1992 to 2002 C-14 D-1 2002 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 2002 Cr-51 Results D-6 D-4 Nonconformity No. 02-08 Fe-59 Results D-7 D-5 JAF Environmental Laboratory Summary D-8 D-6 EML Summary QAP-56 Cs-134 in Water D-9 D-7 Interlaboratory Comparison Program D-10 v

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2002 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 by Entergy Nuclear Northeast. Unit 1 was retired as a generating facility in 1974, and as such, its reactor is no longer operated.

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

The airborne pathway includes measurements of air, precipitation, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no increased radioactivity attributable to 2002 Indian Point Station operation.

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 were no significantly increased levels of radioactivity attributable to 2002 Indian Point Station operation.

This report contains a description of the REMP and the conduct of that program as required by the IP2 Radiological Environmental Technical Specifications and IP3 Radiological Effluent Controls, herein referred to as RETS. This 2002 AREOR also contains summaries and discussions of the results of the 2002 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2002, a total of 1323 analyses were performed. Table B-1 presents a summary of the collected sample results. The actual sampling frequency in 2002 was higher than required, due to the inclusion of additional (non-RETS) sample locations and media.

In summary, the levels of radionuclides in the environment surrounding Indian Point are significantly less than NRC limits as a result of Indian Point Station operations in 2002. The levels present in 2002 were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Consequently, Indian Point operations in 2002 did not result in approaching any environmental regulatory limits posed by the NRC, or result in any exposure to the public greater than environmental background levels.

1-1

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 Northeast.

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 Obiectives 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 into indicator and control locations. Indicator locations are established nearthe 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 2-1

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 2002, however, residual radioactivity from atmospheric bomb tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Nonetheless, analysis of the data verified that plant effluents were far below regulatory limits at environmental levels.

2-2

SECTION 3 PROGRAM DESCRIPTION

3.0 PROGRAM DESCRIPTION To achieve the objectives of the REMP and ensure compliance with the Radiological Environmental Technical Specifications and Radiological Effluent Controls (RETS),

sampling and analysis of environmental media are performed as outlined in Table A-1 and described in section 3.3. The Indian Point REMP consists of samples that are required by RETS and additional samples, Non-RETS, that are not required by RETS.

3.1 Sample Collection Entergy Nuclear Northeast (IP2) Nuclear Environmental Monitoring personnel perform collection of environmental samples for the entire Indian Point site.

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 two laboratories: James A. Fitzpatrick Nuclear Power Plant (JAFNPP)

Environmental Laboratory in Fulton, New York; and Framatome ANP, Environmental Laboratory, Massachusetts. The JAFNPP lab at Fulton analyzes all samples; however, tritium samples were processed by Framatome ANP, Environmental Laboratory, Massachusetts and verified by JAFNPP in 2002.

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 nearthe 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.

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.

3-1

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 and eight indicator locations. 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. The five required RETS air sample locations are designated by the codes A-1 through A-5, see Figures A-1 and A-2.

3.3.3 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (RETS designation Wal) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (RETS designation Wa2), see Figure A-1. An automatic sampling apparatus 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 Drinkinc Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, RETS designation WbM), see Figure A-2. 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.

3.3.5 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The designation for the RETS indicator location is Wcl and the RETS control location is designated Wc2, see Figures A-1 and A-2. The remaining two indicator and one control locations are non-RETS. 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.

3-2

3.3.6 Broad Leaf Veaetation Broad leaf vegetation samples are collected from three locations during the growing season. The designation forthe two RETS indicator locations are Ic1 and Ic2, and the RETS control location is designated Ic3, 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 RETS designation for the upstream sample point is lb2 and the downstream designation is Ibi, 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.

3.3.8 Hudson River Aquatic Vegetation (Non-RETS)

During the spring and summer, aquaticvegetation samples are collected from the Hudson River at two indicator locations and one control location, see Figure A-3. Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.

3.3.9 Hudson River Bottom Sediment (Non-RETS)

Bottom sediment and benthos are sampled at four locations, three indicator and one control, 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 (Non-RETS)

Precipitation samples are continuously collected at one indicator and one control location, 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 (Non-RETS)

Soil samples are collected from one control and two indicator locations, 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

3.3.12 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.

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 Table B-17). 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 B-1 8.

RETS allow sampling of vegetation in two sectors near the site boundary in lieu of a garden census.

3.4 Statistical Methodoloqy 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 (LLD) and Critical Level (LU)

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:

3-4

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

- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

- Chemical yield In the RETS 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 RETS required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the RETS 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 + Tb/TJ0 5 in cpm where: ka = 1.645 (corresponds to a 95% confidence level)

Sb = standard deviation of the background count rate = (Rb/Tb) 0 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 L_ 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 PropaQated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, which may be attributed to plant operations, at a value greater than the Lc, two 3-5

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 EXi

_ 1=1 N

where: X= value of each individual observation N = number of observations Z (ERRi)

PE -

N where: ERR, = I 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 beta radioactivity in air, which show positive monitoring results throughout the year.

3-6

In the data tables B-6 through B-15, values shown are based on the L.value, unless otherwise noted. If a radionuclide was detected at or above the L.

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 1992 through 2001. The 2002 average values are included in these historic tables for purposes of comparison.

3.5 Program Units The Radiological Environmental Monitoring Program uses standard radiological units to express program results. The units and their description are as follows:

Becquerel is a measure of radioactive material, abbreviated Bq, from the International System of Units (SI). A Becquerel is one atom disintegration per second. A Becquerel will normally be used with a volume or mass to express the radioactive concentration of some sample material.

Cubic meter is a metric volume slightly larger than a cubic yard. It is abbreviated m3 and is used in this report as the unit for the volume of air.

Curie is the basic unit used to describe the intensity of radioactivity. The curie is equal to 37 billion disintegrations per second.

Kilogram is a metric unit of mass; it is equivalent to 2.2 pounds. Kilogram is abbreviated kg and can be expressed as kg-wet or kg-dry. The wet or dry designation denotes whether the sample is dried or not before it is counted.

Liter is a metric unit of volume slightly larger than a quart. It is abbreviated L and is used as the volume for liquids.

Microsievert (uSv) is the SI unit for measure of radiation dose to humans. It is equal to 0.1 mrem.

Millirem is a measure of radiation dose to humans, abbreviated mrem; it is 1/1000 of a rem. Millirem expressed for some period of time is the dose rate.

The millirem is different from the milliroentgen in that the millirem is used for reporting radiation dose to humans and the milliroentgen is a measure of radiation in the environment or in air. Normal background radiation dose is approximately 300 mrem per year.

3-7

Milliroentgen is a measure of radiation exposure, abbreviated mR; it is 1/1000 of a roentgen. Milliroentgen expressed for some period of time is the exposure rate.

Milliroentgen (mR) per standard quarter is used for direct radiation or Thermoluminescent Dosimeter (TLD) results.

Picocurie is a measure of radioactive material, abbreviated pCi. A picocurie is 2.22 atom disintegrations per minute. A picocurie will normally be used with a volume or mass to express the radioactive concentration of some sample material.

Picocuries per cubic meter(pCi/m 3 ) is used to express concentration for all air samples.

Picocuries per kilogram (pCi/kg) is the expression used to express concentration for REMP vegetation, soil, shoreline soil, and bottom sediment samples.

Picocuries perliter(pCiIL) is used to express concentration for liquid samples such as, precipitation, drinking water, and river water samples.

Standard quarteris a measure of time (91 days). It is used as the unit of time for expression of mR for the direct radiation measurements from TLDs.

3-8

SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2002 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Radiological Environmental Technical Specifications and Radiological Effluent Controls, herein referred to as RETS. The RETS contain 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. Additional sampling conducted for the REMP is designated "non-RETS" because these samples are not required by the RETS.

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 (non-RETS) bottom sediment (non-RETS)

Airborne Particulates and Radioiodine Precipitation (non-RETS)

Drinking Water Terrestrial Broad Leaf Vegetation Soil (non-RETS)

Direct Gamma Radiation 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 2002 and assessed the significance of the findings.

A summary of the results of the 2002 REMP is presented in Table B-2. This table lists the mean and range of all positive results obtained for each of the media sampled at RETS 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 (with the exception of H-3 as discussed below), their presence is noted only in the data tables and will not be discussed further.

In addition to the naturally occurring radionuclides discussed above, H-3 (which may result from human activity as well as from natural occurrence), 1-131, Cs-1 34, and Cs-137 were detected above background levels in various RETS and non-RETS sample media in the vicinity of Indian Point. The sources and significance of the presence of these radionuclides are described in later sections.

The second group of radionuclides detected in 2002 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), remains detectable.

In 2002, the detected radionuclide(s) 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 2002 REMP comprises those that may be attributable to current plant operations. During 2002, H-3, Cs-1 34, and Cs-1 37 were the only potentially plant-related radionuclides detected in some of the RETS and non-RETS 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. The H-3 detected in 2002 resulted from a combination of sources. There was no H-3 detected at concentrations above the RETS required LLD. "Less than" values for H-3 are reported from the laboratory as less than the sample LLD, which are less than the RETS required LLD.

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. Only Cs-1 37 is found in weapons test debris.

4-2

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in the 1998, 2000, 2001, and 2002 AREOR.

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 nuclides in the past. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these nuclides 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 2002 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 2002 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 B-2) and further discussion.

4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by the JAFNPP Environmental Laboratory. The laboratory uses a Panasonic TLD system. In 2002, 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 B-2 and all the TLD data are presented in Tables B-3, B-4 and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table B-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 B-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 1997 through 2001. The 2002 means are also presented in Table B-4. Table B-5 presents the 2002 TLD data for the inner ring and outer ring of TLDs.

The 2002 mean value for the direct radiation sample points was 14.4 mR per standard quarter. In 2001, the mean value was 14.7 mR and the mean value for the period 1997 through 2001 was 14.8 mR per standard quarter. At those locations where the 2002 mean value was higher, they are within historical bounds for the respective locations.

4-3

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-1 6) 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 B-5. The annual average for the inner ring was 14.7 mR per standard quarter while the average for the outer ring was 14.6 mR per standard quarter. The control location average for 2002 was 14.2 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 2002 averages are consistent with the historical data. The 2002 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 2002 air particulate filter and charcoal cartridge analyses is presented in Table B-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 B-6, and the results of the gamma spectroscopy analyses of the quarterly composites of these samples are in Table B-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 0.015 pCi/M 3 and the average forthe control location was 0.015 pCi/M 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 nuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

The mean annual gross beta concentrations and Cs-1 37 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 2002 gross beta concentration was consistent with historical levels. Cs-137 has not been detected since 1987. This is consistent with the trend of decreasing ambient Cs-137 concentrations in recent years.

The charcoal cartridge analytical results are presented in Table B-8. "Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/lm3 ) in the charcoal cartridge samples, which is consistent with historical trends.

4-4

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2002.

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

In addition to naturally occurring radionuclides, tritium, whose presence may or may not be attributable to plant operations, was the only radionuclide detected in the Hudson River water in 2002. Tritium was detected in the discharge canal mixing zone at a maximum concentration of 783 pCi/L in 2002. The detected H-3 concentration was far below the RETS required LLD of 3000 pCiIL.

The relative insignificance of the H-3 concentration of 783 pCi/L can be seen by calculating the potential dose from the H-3. Using the guidelines set forth in the Offsite Dose Calculation Manual (Reference 22), it was conservatively calculated that the "maximum exposed individual" is an adult who would receive a dose of 0.0019 mrem/year. The insignificance of this dose becomes readily apparent when it is compared to the annual average dose of 300 mrem from background (Reference 21).

Dose calculation assumptions, which continue to provide conservative estimates of dose, still yield an insignificant dose result. The major assumptions are: all fish and invertebrates eaten in 2002 came from waters with 783 pCi/L H-3; the maximum exposed individual is an adult who consumed 21 kg of fish and 5 kg of invertebrates; and generic bioaccumulation factors for fish are representative. The potential dosimetric impact of 0.0019 mrem/year is insignificant.

Data on the radionuclides H-3 and Cs-137 detected in the Hudson River water over the past ten years, are summarized in Table C-3. From this table and Figure C-3, it can be seen that the average of the positive results for H-3 detected in the discharge canal was higher than the 10 year historical average; however, a review of the past twelve years indicates that the 783 pCi/I value is consistent with historical trends. The absense of detectable Cs-137 was consistent with the historical data trends.

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4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2002 drinking water sample analysis results. Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-11; results of tritium analysis of quarterly composites are in Table B-12.

Otherthan naturally occurring radionuclides, no radionuclides were detected in drinking water samples.

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

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

In addition to the naturally occurring nuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2002. Cs-1 37 was detected in three out of six samples from indicator locations. Cs-137 was detected at the control location in one out of four samples. The average concentration for the indicator locations was 221 pCi/kg-dry with a maximum concentration of 241pCi/kg-dry. The control location had a positive sample indicating 238 pCi/kg-dry.

Cs-1 37 has been detected in shoreline soil at indicator and control locations within the past ten years.

4.6 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. All the data from analysis of the 2002 samples are presented in Table B-14. Analyses of broad leaf vegetation samples revealed naturally occurring nuclides, and Cs-137 detected in one of forty-two samples from indicator locations at a concentration of 14.1 pCi/kg-wet and Cs-1 37 detected in one of twenty-one samples at a concentration of 15.3 pCi/kg. Historically, Cs-1 37 has been detected in both control and indicator broad leaf vegetation.

Table C-6 contains a summary and Figure C-6 an illustration, of the broad leaf vegetation analysis results for the past 10 years. The detection of low levels of Cs-1 37 is consistent with the sporadic detection at both indicator and control locations of relatively low concentrations for the past ten years.

4-6

4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table B-2. Table B-1 5 contains the results of the analysis of all fish and invertebrate samples for 2002. None of the indicator samples revealed radionuclide concentrations greater than Lc values. Only naturally occurring nuclides were detected. 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 Additional Media Sampling Although not required by the RETS, analyses were performed on aquatic vegetation, Hudson River bottom sediment, soil, precipitation samples, and various other special water samples. A summary of the analytical results obtained is presented in Table B-16. As shown by these data, the radionuclides detected were consistent with their respective historical levels.

Since these samples were not required by the RETS, individual tables and graphs are not presented for the data.

1-131 was detected in aquatic vegetation samples in one out of four indicator samples and one out of nine control samples with an average concentration of 7.1 and 17.6 pCi/kg-wet, respectively. The 1-131 detected was not due to station operations based on a review of plant discharge records during the sample months, but most likely due to medical administrations especially since the 1-131 was detected in both control and indicator locations. Cs-1 37 was detected in four out of four indicator samples and three out of nine control samples at an average concentration of 24.2 pCi/kg-wet and 6.35 pCi/kg-wet, respectively.

Soil samples were obtained at two indicator locations and one control location. Cs-1 37 was not detected in indicator and control samples.

Precipitation samples were analyzed for H-3 (tritium) and plant-related nuclides at two locations. No tritium or other plant related nuclides were detected at either location. Historically, tritium has been detected in precipitation at both indicator and control locations.

The Algonquin Outfall, Gypsum Plant Stream, Verplanck-5th Street Well, and Trap Rock Quarry samples were analyzed for tritium and plant-related nuclides. The samples did not show any tritium or other plant-related nuclides. The non-RETS sample location of Algonquin Outfall was designated in 1996 and the other special water samples were designated late in 2002.

The results from the non-RETS sampling show that the main detected anthropogenic activity is Cs-1 37, which is found at both indicator and control 4-7

locations. 1-131 was detected in both indicator and control locations for aquatic vegetation and was likely attributed to sources other than plant operations, such as medical administrations. The non-RETS sample data corroborate the RETS sample data in determining that the operation of the Indian Point station in 2002 had no detectable adverse radiological impact on the environment.

4.9 Land Use Census A census was performed in the vicinity of Indian Point in 2002. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables B-17 and B-18.

The results of the 2002 census were the same as the 2001 census results.

There were no animals producing milk for human consumption found within 5 miles (8 km) of the plant. The second part of this census revealed that the nearest residences are located 0.4 miles (0.64 km) ESE and 0.5 miles (0.75 km) E of the plant.

The Indian Point REMP does not include a garden census. RETS allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis results are discussed in section 4.6 and presented in Table B-14, Table C-6 and Figure C-6.

4.10 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 2002 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The results of the 2002 REMP also revealed that the impact on the environment of fallout from previous atmospheric weapons testing and Chernobyl continues to represent the greatest long-term radiological environmental impact from anthropogenic sources. The 2002 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. Overall, doses to humans are much more significant from non-plant related sources than those associated with plant operations.

4-8

SECTION 5 QUALITY ASSURANCE

5.0 QUALITY ASSURANCE The Indian Point Radiological Environmental Monitoring Program (REMP) includes a quality assurance (QA) program. The QA program ensures that the REMP fulfills its intended function and that results of the REMP are reliable. The QA program of the REMP consists of operational (i.e., day-to-day) activities as well as routine inspections and audits.

The operational quality assurance activities are:

• Submission for analysis of duplicate (split) samples to the radioanalytical laboratory to verify reproducibility (precision) of results, and Submission for analysis of environmental samples, spiked with known levels of radioactivity, to the radioanalytical laboratory to verify accuracy of results.

During 2002, 34 samples involving 76 individual analyses were requested of the JAFNPP Environmental Laboratory that processes the Indian Point REMP samples.

Spiked air, water, soil, and vegetation samples were submitted for analysis. The spiked samples were obtained from a commercial vendor laboratory and sent to the JAFNPP Environmental Laboratory to be analyzed as regular environmental samples.

The supply vendor certified the activity levels of the spikes at the time of preparation.

Of the 76 analyses, three air particulate filters were discounted; one was damaged in transit and two had incorrect lab requests that yielded incomparable results.

After the Environmental Laboratory analyzed the spiked samples, statistical tests were performed using both the spike vendor's and the Laboratory's data. In summary, 71 of the 73 individual analyses met the Indian Point acceptance criteria, which yields an overall laboratory performance rating of 97%.

A summary of the identified nonconforming samples:

• Two gross beta air particulate filters did not meet the criteria. This discrepancy has been documented in condition report #CR-IP2-2003-2402 and an investigation will be conducted and documented in response to this condition report. With the exception of these two filters, the remaining 23 samples of this type were within the acceptance range.

The Environmental Laboratory's performance in other comparable areas, notably the Interlaboratory Comparison Program, remains good. We conclude that results from the JAFNPP Environmental Laboratory are expected to remain reliable.

5-1

Reviews and audits of the Radiological Environmental Monitoring Program are conducted by Entergy Nuclear Northeast personnel and include:

• Audits of Indian Point and radioanalytical contractor procedures related to the Radiological Environmental Monitoring Program by Entergy Nuclear Northeast Quality Assurance (QA) personnel.

• Assessment of the radioanalytical contractor's performance in the Analytics Environmental Cross Check Program and the Environmental Measurements Laboratory Quality Assurance Program (see Appendix D).

• Audits of Indian Point sample collection and radioanalytical laboratory processes by QA personnel and program personnel.

Conduct of the quality assurance program in 2002 ensured that sampling and analysis of environmental media at Indian Point were conducted in accordance with quality assurance requirements specified in Regulatory Guide 4.15 (Reference 10) and internal procedures (Reference 2). Performance of routine audits demonstrates this compliance.

The quality assurance programs of Entergy Nuclear Northeast's Environmental Laboratory demonstrate that all requirements specified in 10 CFR Part 50 Appendix B and applicable sections of Regulatory Guide 4.15 are achieved. In addition, the JAFNPP Laboratory's performance in the Analytics Environmental Cross Check Program and the Environmental Measurements Laboratory Quality Assurance Program was satisfactory (see Appendix D).

In summary, the quality assurance program conducted in conjunction with the Indian Point Radiological Environmental Monitoring Program included audits and evaluations of in-house and contractor procedures, work functions, and quality assurance programs. Review of the 2002 quality assurance program indicated that the Radiological Environmental Monitoring Program was performed in accordance with the RETS.

5-2

SECTION 6 REFERENCES

6.0 REFERENCES

1. Radiological Environmental Technical Specifications, for Indian Point Nuclear Generating Stations 1, 2, and 3.

2. Entergy Nuclear Northeast, Nuclear Environmental Monitoring Procedures.

Radiological Support Procedures, Indian Point Station.

3. Environmental Analytical Procedures, Teledyne Isotopes, Inc., Westwood, NJ

- Knoxville, TN.

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

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

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

7. 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.

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

9. Entergy Nuclear Northeast, Quality Control Program for Environmental Monitoring Rev. 5 (RS - 8.500)

10. 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.

11. 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.

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

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

6-1

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

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

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

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

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

19. Dixon, Wilfred J., Introduction to Statistical Analysis, third edition, McGraw-Hill Inc., 1969.

20. 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.

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

22. Entergy Nuclear Northeast (IP3), Offsite Dose Calculation Manual - Part 1, Radiological Effluent Controls - Part 2 Offsite Dose Calculation Manual, Revision 15, December 2001.

23. Entergy Nuclear Northeast (IP2), Offsite Dose Calculation Manual Rev. 6, October, 1999.

24. Kuhn, W.,et al., 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.

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

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

6-2

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

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

29. Office of Environmental Management, Semi-Annual Report of the Department of Energy. Quality Assessment Program , EML 617, June 2002.

30. Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 618, December 2002.

31. McFarland, R.C., et al., The Countinq Room: Special Edition, Radioactivity and Radiochemistry, Caretaker Publications, Atlanta, Georgia, 1994.

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

6-3

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 Radiological Effluent Technical Specifications (RETS). These RETS 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, RETS designation and sample type. Non-RETS samples are also listed but have no RETS designation code. This table gives the complete listing of sample locations used in the 2002 REMP.

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

The RETS required lower limits of detection 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 the RETS environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-1 7 and B-1 8 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS RETSIRECS SAPIN iAMPLE LOAION -DISTANCESMLTY S

'STATION-I-_ 5 DESIGNATION ,_ ,_ ______________'

3 DR8 Service Center Building 0.35 Mi (SSE) at 158° Direct Gamma 4______ Al AlgonquinGas Gas Line n quinOnsite 0.28 Mi- (SW) at 2340 ArPriuae Radioiodine A1Algo A4 Air Particulate, 5 A4 NYU Tower Onsite - Radioiodine, DRIO 0.88 Mi (SSW) at 2080 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 51° Drinking Water 8 NR New Croton Reservoir 6.3 Mi (SE) at 124° Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* Onsit - HR Water 0.16 Mi (W) at 273H 10 a2 Discharge Canal (Mixing Zone) Onsite - HR Water, 10NR DshreCnl(iigZe) 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House Onsite - Direct Gamma

____ ___ ____ ____ ____ ____ ____ 0.3 M i (S E) at 1330 Dr c a m NR HR Aquatic Vegetation, 17 NR Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil, NR HR Bottom Sediment 20 DR38 Cortlandt Yacht Club 1.5 Mi (S) at 180° Direct Gamma (AKA Montrose Marina) 22 NR Lovett Power Plant 1.6 Mi (WSW) at 244° Air Particulate, NR Radioiodine NR Precipitation, A5 Air Particulate, A5 Radioiodine, 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma, 1c3 Broad Leaf Vegetation, NR Soil, Ib2 Fish & Invertebrates 25 Ibl Downstream Downstream Fish & Invertebrate NR Air Particulate, 27 NR Croton Point 6.36 Mi (SSE) at 1560 Radioiodine, DR41 Direct Gamma NR HR Shoreline Soil, 28 DNR4 Lent's Cove 0.45 Mi (ENE) at 0690 Bottom Sediment, NR HR Aquatic Vegetation

• = Control location HR = Hudson River NR = non RETS RIS = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS EhIRECS SAMPLINGa -SAMPLE LOCATION ,DISTANCE . 'SAMPLETPIES,--

STATION DESIGNATION _ _______X __________ __S. _

NR Air Particulate, 29 NR Grassy Point 3.37 Mi (SSW) at 1960 Radiojodine, DR39 Direct Gamma 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 0530 Direct Gamma 34 DR9 South East Corner of site Onsat 0 52 Mi -(5) at 1790 Direct Drc Gammaam 35 DR5 Broadway & Bleakley Avenue OnsitMi -(E) at 0920

~0.37 Direct iet Gamma am 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 1410 Direct Gamma NR Precipitation, 44 NR Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate, NR Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil 53 DR1 White Beach 0.92 Mi (SW) at 2260 HR Shoreline Soil, 56 DR37 Verplanck - Broadway & Sixth Street 1.25 Mi (SSW) at 2020 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 032° Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma Road _ _ _ _ _ _ _ _ _

61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 0520 Direct Gamma 62 DR19 Westbrook Drive 5.3M N)a 6"Direct Gamma (near the Community Center) 5.03 Mi (NE) at 0620 64 DR20 Lincoln Road - Cortlandt Direct Gamma (School Parking Lot) 4.6 Mi (ENE) at 0670 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma

• = Control location HR = Hudson River NR = non RETS R/S = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING RETSIRECS V S

-STAMTPION LE LOCATION.,v- D STANCE SAMPLE TYPES D ESIG N ATI N _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

75 DR28 Palisades Parkway 4.65 Mi (NW) at 31 O ° Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 2760 Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 2720 Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 2950 Direct Gamma 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 2960 Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 3170 Direct Gamma 81 DR31 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 2550 Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 3340 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 339° Direct Gamma NR HR Aquatic Vegetation, 84 NR Cold Spring

• 10.88 Mi (N) at 3560 HR Shoreline Soil, NR HR Bottom Sediment 88 DR6 R/S Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 2.89 Mi (NNE) at 0250 Direct Gamma

_________ ____ (near rock cut) _ _ _ _ _ _ _ _ _ _ _

90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 149° Direct Gamma A2 Air Particulate, 94 c2 IPEC Training Center Onsite- Radioiodine, 0.39 Mi (5) at 1930 Broadleaf Vegetation, NR Soil

• = Control location HR = Hudson River NR = non RETS RIS = Reuter Stokes A-4

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

IL Peekskill Westchester County Rockland County 4 Indian (

Point IbIl 7 I 1 mile go VIndlanc 1 ( Hudson ICSp ca2 River 1c2 (e)

Bu-n Verplanck )

338 Key: A - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# Ibl - Fish and Invertebrates (where available downstream)

El-Air Particulate & Radioiodine A#

-HR Shoreline Sediment Wc#

A-5

FIGURE A-2 RETS SAMPLING LOCATIONS Within 10 Miles of Indian Point N

Roseton (20.7 mi. N): E i Ic3 Upstream: Ib2 Orange County Putnam County

© Bear Mountain Bridge r, N les VJ0 0 0

09 I 5 miles I Rockland County Westchester County Key: o - Direct Radiation Sample Location DR# Ic3 - Broadleaf Vegetation al - Air Particulate & Radioiodine A# Ib2 - Fish and Invertebrates On- HR Shoreline Sediment Wc# (where available upstream)

C - Waterborne: Drinking Wb#

A-6

FIGURE A-3 NON-RETS SAMPLING LOCATIONS N

Roseton (20.7 mi. N): 23 : p*

Orange County Putnam County Cold Spring (10.88 mi. N) : 84 Bear Mountain Bridge 10: _ I 028:Y

/ O 99: sp 17: V 29: v 101 :sp Westchester County Rockland County 27: v 8: dw 5 miles Key: * - Air Particulate & Radioiodine C - HR Shoreline Sediment V - Aquatic Vegetation * - Soil

_ - HR Bottom Sediment sp - Special Water p - Precipitation dw - Drinking Water A-7

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

'AIRBORNE~

WATER,, PARTICULAE IS piJ,,MLK FO EDIMENT-'

ANLI (pC IlL) OR GASES J wet (CI) POUT (pCI kgj'wet),

Gross 0 4 0.01 H-3 2000 (c)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 .

Co-60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 (d) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) This list does not mean that only these nuclides are to be considered. Other identifiable peaks 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 28)

(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.

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE 6o:D~

NALss .I WATER(pII)

'PARTC ORGASES ES FISk(pCllkg, wet)

MILK; ,

(pIL ODUCTS (pI~ wt

. , (P H-3 20000 (a)

Mn-54 1000 30000 Fe-59 400 10000 Co-58 1000 30000 i Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 1-131 2 (b) 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-1 40 200 300 (a)For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used (b) If no dnnking 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 2002 Annual Radiological Environmental Monitoring Program Summary The results of the 2002 radiological environmental sampling program are presented in Tables B-2 through B-16. Table B-2 is a summary of the RETS samples and Table B-1 6 is a summary of the non-RETS samples. The format of these summary tables conforms to the reporting requirements of the RETS, 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 all the individual RETS samples are provided in Tables B-3 through B-15.

REMP samples were analyzed by various counting methods as appropriate. The methods are; gross beta, gamma spectroscopy analysis, liquid scintillation, and TLD processing. Gamma spectroscopy analysis was performed for the following radionuclides; Be-7, K-40, Mn-54, Co-58, Co-60, Fe-59, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Cs-134, Cs-137, Ba/La-140, Ce-141, Ce-144, Ra-226 and Ac/Th-228. Radiochemical (1-131) and tritium analyses were performed for specific media and locations as required in the RETS.

B.2 Land Use Census In accordance with Sections 4.11.B of the IP2 RETS and Part I Section 2.8 of the IP3 RECS, 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 censuses are presented in Tables B-17 and B-18, respectively. In lieu of identifying and sampling the nearest garden of greater than 50m2 , 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 2002, environmental sampling was performed for six media types required by RETS, five other media types and direct radiation. A total of 1338 samples (1245 RETS and 93 non-RETS) were scheduled. Of the scheduled samples, 99% 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-1 a for air samples, B-1 b for TLDs, and B-1 c for other environmental media.

B-1

B.4 Analytical Deviations During 2002, one fish sample could not meet the LLD for Cs-134/137 and one fish sample could not meet the LLD for Fe-59 due to sample receipt/shipment delays.

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

B-2

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2002 TOI1AL -, "'-UM~O

- SAMPLING"' REASON

'MEDIA SCHEDULED, N-BE- F FO MEDI RETS MEDIA IET lAMPES DEVIA- ONS EFFICIENCY- iDEVIATION SEE TABLE PARTICULATES IN AIR 468 3 99 B-la SEE TABLE CHARCOAL FILTER 468 3 99 B-la SEE TABLE TLD 164 3 98 B-lb HUDSON RIVER WATER 32 0 100 DRINKING WATER 32 0 100 SHORELINE SOIL 10 0 100 BROAD LEAF 63 0 100 VEGETATION SEE TABLE FISH & INVERTEBRATES 8 3 63 B-1c SUBTOTALS 1245 12 99 NON-RETS MEDIA SEE TABLE AQUATIC VEGETATION 15 2 87 B-1c HUDSON RIVER BOTTOM 010 SED IME NT 8 0 10 0 SOIL 3 0 100 PRECIPITATION 8 0 100 SPECIAL WATER 59 1 98 SAMPLES SUBTOTALS 93 3 97 OVERALL TOTALS 1338 15 99 TOTAL NUMBER OF ANALYSES REPORTED = 1323 B-3

TABLE B-1a / B-lbIB-lc TABLE B-1a 2002 Air Sampling Deviations a STATION -^ . WEEK PROBLEM I ACTIONS TO PREVENT RECURRENCE Electrical power was lost to the electrical feed panel at the Lovett

1. 22 Lovett Power Plant 13 & 14 Power Station during a steam leak I A temporary feed unit was (Air Particulate &Charcoal) installed by Lovett Station on 419/02 for this air sampler until the power could be returned to the electrical feed panel.

1. 29 Grassy Point 19 Sample holder was dropped into a puddle of water and the filters (Air Particulate & Charcoal) were destroyed. / Technician was coached on attention to detail.

TABLE B-lb 2002 TLD Deviations STATION QUARTER 7 PROBLEM I ACTIONS TO PREVENT RECURRENCE

1. 74 (DR-12) Westshore t QTR LD Uility pole was replaced which housed the TLD. I Replaced TLD Drive - South s (TD) and continued to trend missing TLDs for patterns.

1. 76 (DR-13) Westshore 2nd QTR LD Damaged TLD. I Replaced TLD and continue to track and trend Drive - North n (TD) damaged TLDs

1. 64 (DR-20) Lincoln Road 2nd QTR (TLD) TLD was missing I Replaced and relocated TLD. Continued to

-Cortlandt _ trend missing TLDs for patterns.

TABLE B-Ic 2002 Other Media Deviations STATION SAMPLE SCHEDULE PROBLEM / ACTIONS TO PREVENT RECURRENCE One species of fish caught at the Cold Spring control location. I

1. 28 Lent's Cove Spring (Fish) Performed a review of the NAI fishing practices and resolving the issue with a contract with NAI for IPEC fish sampling.

1. 17 - Off Verplanck Spring (Aquatic Vegetation) Aquatic vegetation was not available in this area this spring

1. 84 - Cold Spring Spring (Aquatic Vegetation) Aguatc vegetation was not available in this area this spring

1. 103 - 1P3 Trailer Well April (Special Water) Non-potable water was not available from the IP3 Trailer Well.

LLD for Cs-134/137 not met due to sample being >39 days old upon delivery to lab. / Performed a review of the NAI fishing

1. 23 - Roseton Summer (Fish) practices and resolving the issue with a contract with NAI for IPEC fish sampling.

LLD for Fe-59 not met due to sample being >60 days old upon delivery to lab. I Performed a review of the NAI fishing practices

1. 25 - Downstream Summer (Fish) and resolving the issue with a contract with NAI for IPEC fish sampling B4

TABLE B-2*

RETS ANNUAL

SUMMARY

- 2002

-~ LOCATION (b)OF HIGHEST,,

ANNUAL MEAN:

TYPE AND TOTAL MEIM(UNITS),I NUMBER OF LLD (cd INDICATOR LOCATIONS:LOCATIONSANDCONTROLLOCA

.- I- _.

NUMBER OF, NONROUTINE

,SEE TABLE, ANALSISl -,DESIGNATIONREOT PERFORMED (e)

MEA (a)MEAN (a) MEAN (a)'

- RANGE R -AN RANGE ,__-_MGE^__

DIRECT RADIATION #76 West Shore Drive North (mR /standard quarter) TLD Reads N/A 14.3 (157/157) / 7.2 - 20 5 1.21 Mi. (2760) DR13 14.2 (4/4) /12.6- 155 0 B-3 19 (4/4)117.9-20.5 AIR PARTICULATES #44 Peeksktill Gas Holder Bldg 0.015 (52152)/

AND RADIOIODINE GB (465) 0 01 0 015 (413/413) /0005-0.025 1.84 Mi. (520) 0 (pCim 3 ) B-6, B-7, B-8 0.016 (52152) /0008-0.023 0.006-0.022 1-131 (465) 0.07 <Lk < LC < LC 0 GSA (36)

Cs-134 0.05 <k < Lc < LC 0 Cs-137 006 < Lc <L < LC 0 SURFACE HUDSON #10 Discharge Canal Mixing RIVER WATER (pCi/L) H-3 (8) 3000 562 (2/4) /340-783 Zone(On-site) 432 (1/4) 1432-432 0 B-9, B-10 562(2/4) /340-783 GSA (24)

Mn-54 15 < L< < Lc < Lo 0 Co-58 15 < Lc < Lc <k 0 Fe-59 30 < Lc < Lo < Lc 0 Co-60 15 <L <cL < Lc 0 Zn-65 30 < Lc < Lc < Lc 0 Zr/Nb-95 15 < Le <ck < LC 0 1-131 15 <ce <tc <Ico 0 Cs-134 15 < Lc < Lc < Lc 0 Cs-137 18 < Lc < Lc < L, 0 Ba/La-140 15 cLc <k <t 0 DRINKING WATER #8 New Croton Reservoir (pCI/L) B-IG,B-12 GB (24) 4 2.19 (24/24) / 1.07-3.34 6.3 Mi (1240) N/A 0

_______ _____ _ 2 20 (12112) 1 1.07-3.34 _ _ _ _ _ _ _ _ _ _

H-3 (8) 2000 < LLD < LD N/A 0 GSA (24)

Mn-54 15 < Lc < Lc N/A 0 Co-58 15 <c <kLC N/A 0 Fe-59 30 <c <kLC N/A 0 Co-60 15 <' '

<k N/A 0 Zn-65 30 <L < Lk N/A 0 B-5

TABLE B-2*

RETS ANNUAL

SUMMARY

- 2002

- LO0CATION (b) OF HIGHEST AN ANNUALTMEAN

,NUMBER rTYPE ANDTOTAL OF

. NUMBER OF-eMEDIUMUNITS L LOCTIONS ND CONTROL LOCATION: NONROUTINE

- EE TABLE,'-, ANALYSIS LLD ,_) T LOCATIONS: - DESIGNATION -- EPORTS

.0`PERFORMED (el),

j- MEAN (a) MEANjWf-- MEAN (ia:

- RANGE- -'RANGE RANGE DRINKING WATER Zr/Nb-95 15 < Lc < Lc N/A 0 (CONT) 1-131 1 < L, < Lc N/A 0 Cs-134 15 < Lc < Lc N/A 0 Cs-137 18 < Lc <L N/A 0 Ba/La-140 15 < L, < Lc N/A 0 SHORELINE SOIL GSA (10)

(pCi/kg - dry) B-13 Cs-134 150 <KL <KL <Lc 0

1. 17 Off Verplanck 1.5 Mi.

Cs-137 180 221 (3/6) / 206-241 (202.50) 238 (1/4) / 238-238 0 229 (2/2)1217-241 BROADLEAF VEGETATION GSA (63)

(pCi/kg - wet) B-14 1-131 60 < Lc < Lc < Lc 0 Co-60 N/A < Lc <K < LC 0 Cs-134 60 <L, <KL <Lc 0

1. 94 IPEC Training Center Cs-137 80 14.1(1/42) / 14.1-14.1 0.39 Mi. (1930) 15 3 (1/21) / 15.3-15.3 0 14 1 (1/21) /14.1-14.1 FISH AND INVERTEBRATES GSA (5)

(pCi/kg - wet) B-15 Mn-54 130 < LK < Lc < Lc 0 Co-58 130 < Lc < LK < Lc 0 Fe-59 260 < Lc < Lc < L, 0 Co-60 130 < Lc < Lc < LK 0 Zn-65 260 < LK < LK < LK 0 Cs-134 130 < Lc < Lc < Lc 0 Cs-137 150 <Lc <KL <Lc 0 B-6

Table B-2 Notation 2002 RETS ANNUAL

SUMMARY

TABLE NOTES

• = Data for the Annual Summary Tables are based on RETS required samples, with the exception of Air Samples which include RETS and Non-RETS locations.

N/A = Not applicable.

(a) = (Detectable activity measurements) / (Total measurements.)

(b) = Location is distance in miles and direction in compass degrees.

(c) = RETS Required LLD, see Table A-2 (d) = RETS Required LLD > Critical Level (Lc).

(e) "Less then" results for tritium are reported as <sample LLD, which is less than RETS requires LLD.

GB = Gross Beta Analysis.

GSA = Gamma Spectroscopy Analysis.

The format of Table B-2, RETS Annual Summary, is dictated by regulations. To help understand this table, one section of Table B-2 is presented in narrative. The following explanation for the Shoreline Soil section of Table B-2 should help the reader understand all of the summaries in Table B-2.

1. The left-hand column reports the sample media, media reporting units, and the table containing the detailed sample results. For Shoreline Soil, the reporting units are pCi/kg-dry and the detailed sample results are in Table B-13.

2. The second column tells how the samples are analyzed and how many samples were analyzed. In this case, the samples are analyzed by gamma spectroscopy analysis (GSA) for the nuclides Cs-134 and Cs-137 and there were a total of 10 samples.

B-7

Table B-2 Notation (Continued) 2002 RETS ANNUAL

SUMMARY

TABLE NOTES

3. The third column lists the RETS required lower limit of detection for the type of analysis performed. These values are also listed in Table A-2.

4. The column labeled Indicator Locations gives the results for all the indicator sites.

Three out of six samples from indicator locations had Cs-1 37. The mean of the Cs-137 from the three indicator location sample results that were > Lc was 221 pCi/kg-dry. The range of the samples results > Lc was 206 to 241 pCi/kg-dry.

5. The location of the highest indicator is the next column. The indicator site with the highest mean is reported here. For shoreline soil samples, the highest indicator mean for Cs-137 is from sample location 17, Off Verplanck, 1.5 miles from Indian Point at compass direction 202.5 degrees. The mean for this indicator sample site is 229 pCi/kg-dry Cs-137, two samples were taken and both sample results were

>Lc. The range of the samples results that were > Lc was 217 to 241 pCi/kg-dry.

6. The control location column is next. For 2002, Cs-1 37 was detected in one of the four samples at 238 pCi/kg-dry.

7. The right hand column gives the number of non-routine reports that are required because of sample results at or above the reporting level. The reporting levels are given in Table A-3.

8. All the sample media reported in Table B-2 follow this general format.

B-8

TABLE B-3 2002 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER) 1ST"~ A1,11D, p3R 4TH 2 Station ID, Sector 6ut Qa rter~Quarter ,-Quarter ,,Quarter 2002 0 v DR-01 N 15.4 15.9 17.2 17.3 16.5 DR-02 NNE 13.2 15.4 15.3 15.2 14.8 DR-03 NE 11.0 12.2 13.1 11.5 12.0 DR-04 ENE 13.2 16.3 14.1 13.7 14.3 DR-05 ENE 13.2 13.7 14.5 13.3 13.7 DR-06 ESE 12.8 14.1 12.7 13.5 13.3 DR-07 SE 16.0 17.5 17.8 15.1 16.6 DR-08 SSE 12.8 15.1 12.5 13.9 13.6 DR-09 S 13.1 13.0 13.5 14.0 13.4 DR-10 SSW 13.5 16.8 14.8 14.7 15.0 DR-11 SW 10.8 12.6 11.7 11.3 11.6 DR-12 WSW 19.2 18.2 19.6 19.0 DR-13 WSW 17.9 18.7 20.5 19.0 DR-14 WNW 13.7 15.9 14.9 11.5 14.0 DR-15 NW 13.2 14.2 14.4 12.1 13.5 DR-16 NNW 15.5 15.2 17.7 13.2 15.4 DR-17 N 15.8 16.6 15.4 13.1 15.2 DR-18 NNE 15.0 14.6 13.3 12.4 13.8 DR-19 NE 15.5 18.0 15.6 12.3 15.4 DR-20 ENE 13.7 13.1 13.5 13.4 DR-21 E 14.2 16.0 13.5 12.5 14.1 DR-22 ESE 11.8 12.5 . 11.1 10.6 11.5 DR-23 SE 14.1 15.3 14.1 13.2 14.2 DR-24 SSE 13.0 15.6 14.8 12.3 13.9 DR-25 S 13.3 14.9 12.2 12.5 13.2 DR-26 SSW 13.9 14.8 13.6 13.0 13.8 DR-27 SW 14.2 15.6 14.0 15.2 14.8 DR-28 NW 15.0 14.8 14.1 13.3 14.3 DR-29 W 17.6 19.3 18.6 18.1 18.4 DR-30 SNS 17.5 17.1 16.6 14.0 16.3 DR-31 WSW 18.5 20.1 18.6 14.6 18.0 DR-32 NNW 13.5 14.7 13.9 10.7 13.2 DR-33 NE 9.5 9.1 8.5 7.2 8.6 DR-34 SE 14.2 14.9 13.2 12.4 13.7 DR-35 NNE 14.0 15.9 14.7 11.9 14.1 DR-36 NE 15.1 17.4 14.9 13.5 15.2 DR-37 SSW 14.5 15.6 13.2 12.4 13.9 DR-38 S 12.6 13.7 12.3 11.1 12.4 DR-39 SSW 16.6 16.8 16.1 13.2 15.7 DR-40** N 14.6 15.5 14.1 12.6 14.2 DR-41 SSE 12.6 13.5 12.5 12.2 12.7 AVERAGE 14.1 15.4 14.5 13.4 14.4

• Data not available

• • Control Location B-9

TABLE B-4 DIRECT RADIATION, 1997 THROUGH 2002 DATA (mR per Standard Quarter)

Mean ~Stnard~

I De.teann MinimumValue MaxImu Value Station ID ( 9 1997-2001 l (i997-2001) . (1997-2i001) 2002Average DR-01 16.1 0.6 15.4 17.0 16.5 DR-02 17.9 2.3 14.9 19.8 14.8 DR-03 12.3 0.3 11.9 12.6 12.0 DR-04 13.5 0.8 12.8 14.7 14.3 DR-05 13.3 1.9 10.0 14.5 13.7 DR-06 13.9 0.5 13.1 14.4 13.3 DR-07 16.4 0.6 15.7 17.2 16.6 DR-08 13.2 0.6 12.4 14.1 13.6 DR-09 13.4 0.7 12.6 14.5 13.4 DR-10 14.0 0.5 13.3 14.6 15.0 DR-11 11.7 0.3 11.3 12.1 11.6 DR-12 16.4 0.4 15.9 17.0 19.0 DR-13 19.6 0.9 18.2 20.3 19.0 DR-14 14.1 0.9 12.8 15.1 14.0 DR-15 14.5 0.4 14.0 15.0 13.5 DR-16 15.3 0.5 14.7 15.9 15.4 DR-17 15.2 1.0 14.0 16.7 15.2 DR-18 14.7 0.4 14.2 15.2 13.8 DR-19 15.5 0.3 15.2 15.9 15.4 DR-20 14.5 0.3 14.1 14.8 13.4 DR-21 14.2 0.8 13.1 15.2 14.1 DR-22 12.4 0.6 11.6 13.0 11.5 DR-23 14.5 0.2 14.2 14.7 14.2 DR-24 14.4 0.5 14.0 14.9 13.9 DR-25 12.6 0.4 12.2 13.3 13.2 DR-26 14.2 0.6 13.2 14.7 13.8 DR-27 14.2 0.7 13.6 15.4 14.8 DR-28 15.5 1.0 14.6 17.3 14.3 DR-29 18.2 0.9 16.8 19.3 18.4 DR-30 17.3 0.4 16.9 17.8 16.3 DR-31 19.3 0.6 18.6 20.1 18.0 DR-32 13.9 0.3 13.5 14.3 13.2 DR-33 10.0 1.5 8.5 12.0 8.6 DR-34 14.1 0.7 13.4 15.2 13.7 DR-35 15.1 0.3 14.7 15.3 14.1 DR-36 16.4 0.7 16.0 17.6 15.2 DR-37 14.4 0.5 13.9 15.0 13.9 DR-38 13.4 0.8 12.5 14.6 12.4 DR-39 16.5 0.2 16.1 16.7 15.7 DR-40 16.3 0.8 15.5 17.6 14.2 DR-41* 14.0 0.6 13.4 14.7 12.7 Average 14.8 0.7 14.0 15.6 14.4 B-1 0

TABLE B-5 2002 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter)

Inner Ring Outer Ring Sector , InnerkRing O uter Ring ID +- tID Annual Average Annual Average DR-01 DR-17 N 16.5 15.2 DR-02 DR-18 NNE 14.8 13.8 DR-03 DR-19 NE 12.0 15.4 DR-04 DR-20 ENE 14.3 13.4 DR-05 DR-21 E 13.7 14.1 DR-06 DR-22 ESE 13.3 11.5 DR-07 DR-23 SE 16.6 14.2 DR-08 DR-24 SSE 13.6 13.9 DR-09 DR-25 S 13.4 13.2 DR-10 DR-26 SSW 15.0 13.8 DR-1I DR-27 SW 11.6 14.8 DR-12 DR-31 WSW 19.0 14.3 DR-13 DR-29 W 19.0 18.4 DR-14 DR-30 WNW 14.0 16.3 DR-15 DR-28 NW 13.5 18.0 DR-16 DR-32 NNW 15.4 13.2 Average 14.7 14.6 B-11

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2002 (pCi/m3+/- 1 sigma)

STATION #

Week EndDate- -4 5 27 94- --- 95 1 1/7/2002 0.019 + 0.001 0.017 + 0.001 0.019 + 0.001 0.016 + 0.001 0.020 + 0.002 2 1/15/2002 0.016 + 0.001 0.013 + 0.001 0.015 + 0.002 0.014 + 0.002 0.017 + 0.002 3 1/22/2002 0.017 + 0.001 0.018 + 0.002 0.019 + 0.002 0.018 + 0.002 0.020 + 0.002 4 1/29/2002 0.016 + 0.001 0.017 + 0.002 0.021 + 0.002 0.020 + 0.002 0.021 + 0.002 5 2/5/2002 0.016 + 0.001 0.015 + 0.001 0.014 + 0.001 0.015 + 0.002 0.012 + 0.001 6 2/12/2002 0.023 + 0.002 0.024 + 0.002 0.024 + 0.002 0.024 + 0.002 0.022 + 0.002 7 2/19/2002 0.013 + 0.001 0.011 + 0.001 0.012 + 0.001 0.013 + 0.001 0.011 + 0.001 8 2/26/2002 0.013 + 0.001 0.012 + 0.001 0.012 + 0.001 0.015 + 0.002 0.015 + 0.002 9 3/5/2002 0.014 + 0.001 0.013 + 0.001 0.015 + 0.002 0.017 + 0.002 0.016 + 0.002 10 3/12/2002 0.020 + 0.001 0.023 + 0.002 0.020 + 0.002 0.022 + 0.002 0.022 + 0.002 11 3/19/2002 0.015 + 0.001 0.017 + 0.002 0.013 + 0.001 0.018 + 0.002 0.020 + 0.002 12 3/26/2002 0.015 + 0.001 0.015 + 0.002 0.013 + 0.002 0.017 + 0.002 0.014 + 0.002 13 4/2/2002 0.011 + 0.001 0.012 + 0.001 0.011 + 0.001 0.010 + 0.001 0.014 + 0.002 14 4/9/2002 0.016 + 0.001 0.014 + 0.002 0.017 + 0.002 0.016 + 0.002 0.015 + 0.002 15 4/16/2002 0.014 + 0.001 0.011 + 0.001 0.016 + 0.002 0.015 + 0.002 0.013 + 0.002 16 4/23/2002 0.016 + 0.001 0.020 + 0.002 0.018 + 0.002 0.014 + 0.002 0.018 + 0.002 17 4/30/2002 0.012 + 0.001 0.012 + 0.001 0.014 + 0.001 0.013 + 0.001 0.012 + 0.001 18 5/7/2002 0.016 + 0.001 0.013 + 0.001 0.011 + 0.001 0.012 + 0.001 0.012 + 0.001 19 5/14/2002 0.010 + 0.001 0.010 + 0.001 0.011 + 0.001 0.012 + 0.002 0.013 + 0.002 20 5/21/2002 0.011 + 0.001 0.011 + 0.001 0.010 + 0.001 0.013 + 0.002 0.012 + 0.001 21 5/28/2002 0.011 + 0.001 0.012 + 0.001 0.013 + 0.001 0.012 + 0.001 0.012 + 0.001 22 6/4/2002 0.016 + 0.001 0.014 + 0.002 0.014 + 0.002 0.015 + 0.002 0.015 + 0.002 23 6/11/2002 0.011 + 0.001 0.013 + 0.001 0.006 + 0.001 0.012 + 0.001 0.009 + 0.001 24 6/18/2002 0.010 + 0.001 0.010 + 0.001 0.009 + 0.001 0.012 + 0.001 0.012 + 0.001 25 6/25/2002 0.015 + 0.001 0.018 + 0.002 0.018 + 0.002 0.018 + 0.002 0.019 + 0.002 26 7/1/2002 0.017 + 0.001 0.018 + 0.002 0.015 + 0.002 0.019 + 0.002 0.018 + 0.002

• Sample deviation.

• • Control location. B-12

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2002 (pCi/M 3 +/- 1 sigma)

STATION #

Week # End Date- - -4

-5 , .27--.- 94, - 95-27 7/9/2002 0.024 + 0.002 0.020 + 0.002 0.022 + 0.002 0.022 + 0.002 0.025 + 0.002 28 7/16/2002 0.013 + 0.001 0.016 + 0.002 0.015 + 0.002 0.014 + 0.002 0.017 + 0.002 29 7/22/2002 0.025 + 0.002 0.017 + 0.002 0.020 + 0.002 0.018 + 0.002 0.020 + 0.002 30 7/30/2002 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 0.020 + 0.002 0.021 + 0.002 31 8/6/2002 0.018 + 0.002 0.017 + 0.002 0.020 + 0.002 0.015 + 0.002 0.012 + 0.001 32 8/13/2002 0.013 + 0.001 0.013 + 0.002 0.015 + 0.002 0.024 + 0.002 0.022 + 0.002 33 8/20/2002 0.024 + 0.002 0.020 + 0.002 0.021 + 0.002 0.013 + 0.001 0.011 + 0.001 34 8/27/2002 0.018 + 0.001 0.016 + 0.002 0.017 + 0.002 0.015 + 0.002 0.015 + 0.002 35 9/3/2002 0.008 + 0.001 0.005 + 0.001 0.008 + 0.001 0.017 + 0.002 0.016 + 0.002 36 9/9/2002 0.016 + 0.002 0.015 + 0.002 0.013 + 0.002 0.022 + 0.002 0.022 + 0.002 37 9/17/2002 0.020 + 0.001 0.016 + 0.001 0.016 + 0.002 0.018 + 0.002 0.020 + 0.002 38 9/24/2002 0.018 + 0.001 0.016 + 0.002 0.016 + 0.002 0.017 + 0.002 0.014 + 0.002 39 9/30/2002 0.016 + 0.001 0.019 + 0.002 0.018 + 0.002 0.010 + 0.001 0.014 + 0.002 40 10/8/2002 0.018 + 0.002 0.019 + 0.002 0.017 + 0.002 0.016 + 0.002 0.015 + 0.002 41 10/15/2002 0.009 + 0.001 0.011 + 0.002 0.010 + 0.001 0.015 + 0.002 0.013 + 0.002 42 10/21/2002 0.012 + 0.001 0.012 + 0.002 0.012 + 0.001 0.014 + 0.002 0.018 + 0.002 43 10/29/2002 0.010 + 0.001 0.012 + 0.002 0.011 + 0.001 0.013 + 0.001 0.012 + 0.001 44 11/5/2002 0.016 + 0.001 0.014 + 0.002 0.019 + 0.002 0.012 + 0.001 0.012 + 0.001 45 11/11/2002 0.020 + 0.002 0.018 + 0.002 0.019 + 0.002 0.012 + 0.002 0.013 + 0.002 46 11/19/2002 0.012 + 0.001 0.011 + 0.001 0.013 + 0.001 0.013 + 0.002 0.012 + 0.001 47 11/26/2002 0.017 + 0.001 0.018 + 0.002 0.019 + 0.002 0.012 + 0.001 0.012 + 0.001 48 12/3/2002 0.016 + 0.001 0.016 + 0.002 0.013 + 0.002 0.015 + 0.002 0.015 + 0.002 49 12/10/2002 0.016 + 0.001 0.007 + 0.002 0.012 + 0.001 0.012 + 0.001 0.009 + 0.001 50 12/17/2002 0.013 + 0.001 0.010 + 0.001 0.012 + 0.001 0.012 + 0.001 0.012 + 0.001 51 12/23/2002 0.013 + 0.001 0.012 + 0.002 0.010 + 0.002 0.018 + 0.002 0.019 + 0.002 52 12/30/2002 0.013 + 0.001 0.014 + 0.002 0.012 + 0.001 0.019 + 0.002 0.018 + 0.002

• Sample deviation.

• • Control location. B-13

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2002 (pCi/M 3 i 1 sigma)

STATION #

Week# -EndDate -l '22,- 23* 29 - 44--

1 1/8/2002 0.019 + 0.001 0.018 + 0.002 0.019 + 0.001 0.019 + 0.002 2 1/1412002 0.014 + 0.001 0.016 + 0.002 0.015 + 0.001 0.016 + 0.002 3 1/22/2002 0.014 + 0.001 0.020 + 0.001 0.014 + 0.001 0.015 + 0.001 4 1/28/2002 0.016 + 0.002 0.016 + 0.002 0.016 + 0.001 0.017 + 0.002 5 2/5/2002 0.016 + 0.001 0.018 + 0.002 0.017 + 0.001 0.017 + 0.002 6 2/11/2002 0.024 + 0.002 0.020 + 0.002 0.022 + 0.001 0.023 + 0.002 7 2/19/2002 0.012 + 0.001 0.014 + 0.001 0.015 + 0.001 0.013 + 0.001 8 2/25/2002 0.014 + 0.001 0.012 + 0.002 0.012 + 0.001 0.014 + 0.002 9 3/4/2002 0.012 + 0.001 0.012 + 0.001 0.012 + 0.001 0.015 + 0.002 10 3/11/2002 0.022 + 0.002 0.021 + 0.002 0.021 + 0.001 0.020 + 0.002 11 3/18/2002 0.019 + 0.001 0.017 + 0.002 0.018 + 0.001 0.021 + 0.002 12 3/25/2002 0.006 + 0.001 0.012 + 0.001 0.013 + 0.001 0.012 + 0.002 13 4/1/2002 0.012 + 0.001 0.012 + 0.001 0.014 + 0.002 14 4/8/2002 0.020 + 0.002 0.014 + 0.001 0.018 + 0.002 15 4/15/2002 0.015 + 0.002 0.014 + 0.002 0.014 + 0.001 0.017 + 0.002 16 4/22/2002 0.020 + 0.002 0.017 + 0.002 0.017 + 0.001 0.022 + 0.002 17 4/29/2002 0.009 + 0.001 0.011 + 0.001 0.011 + 0.001 0.012 + 0.001 178 5/6/2002 0.011 + 0.001 0.012 + 0.001 0.013 + 0.001 0.013 + 0.001 1_9 5/13/2002 0.015 + 0.001 0.013 + 0.002 0.016 + 0.002 20 5/20/2002 0.011 + 0.001 0.012 + 0.001 0.008 + 0.001 0.013 + 0.002 21 5/28/2002 0.011 + 0.001 0.012 + 0.001 0.011 + 0.001 0.013 + 0.001 22 6/3/2002 0.015 + 0.002 0.014 + 0.002 0.016 + 0.002 0.016 + 0.002 23 6/10/2002 0.011 + 0.001 0.010 + 0.001 0.012 + 0.001 0.015 + 0.002 24 6/17/2002 0.013 + 0.002 0.007 + 0.001 0.009 + 0.001 0.009 + 0.001 25 6/25/2002 0.016 + 0.001 0.018 + 0.002 0.016 + 0.001 0.017 + 0.002 26 7/2/2002 0.016 + 0.002 0.015 + 0.002 0.014 + 0.001 0.015 + 0.002

• Sample deviation.

• • Control location. B-14

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2002 (pCi/M3 +/- 1 sigma)

STATION #

Week EndDate-, 22, -23 29 - 44-27 7/8/2002 0.018 + 0.001 0.022 + 0.002 0.021 + 0.002 0.023 + 0.002 28 7/15/2002 0.014 + 0.001 0.015 + 0.002 0.014 + 0.001 0.018 + 0.002 29 7/23/2002 0.019 + 0.001 0.021 + 0.002 0.020 + 0.001 0.022 + 0.002 30 7/29/2002 0.012 + 0.001 0.007 + 0.002 0.010 + 0.001 0.009 + 0.002 31 8/5/2002 0.023 + 0.002 0.018 + 0.002 0.019 + 0.001 0.019 + 0.002 32 8/12/2002 0.015 + 0.001 0.011 + 0.001 0.014 + 0.001 0.014 + 0.002 33 8/19/2002 0.022 + 0.002 0.017 + 0.002 0.022 + 0.002 0.020 + 0.002 34 8/26/2002 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 0.014 + 0.002 35 9/3/2002 0.008 + 0.001 0.006 + 0.001 0.009 + 0.001 0.008 + 0.001 36 9/9/2002 0.021 + 0.002 0.014 + 0.002 0.016 + 0.002 0.016 + 0.002 37 9/16/2002 0.019 + 0.002 0.018 + 0.002 0.016 + 0.001 0.017 + 0.002 38 9/25/2002 0.020 + 0.002 0.018 + 0.002 0.017 + 0.001 0.017 + 0.002 39 10/1/2002 0.015 + 0.001 0.018 + 0.002 0.013 + 0.001 0.015 + 0.002 40 10/7/2002 0.017 + 0.001 0.018 + 0.002 0.021 + 0.002 0.020 + 0.002 41 10/14/2002 0.010 + 0.001 0.012 + 0.001 0.009 + 0.001 0.010 + 0.001 42 10/22/2002 0.010 + 0.001 0.009 + 0.001 0.010 + 0.001 0.013 + 0.001 43 10/29/2002 0.011 + 0.001 0.011 + 0.001 0.012 + 0.001 0.013 + 0.002 44 11/4/2002 0.012 + 0.001 0.014 + 0.002 0.015 + 0.001 0.015 + 0.002 45 11/12/2002 0.017 + 0.001 0.022 + 0.002 0.021 + 0.001 0.022 + 0.002 46 11/18/2002 0.015 + 0.001 0.014 + 0.002 0.014 + 0.001 0.013 + 0.002 47 11/25/2002 0.017 + 0.001 0.016 + 0.002 0.015 + 0.001 0.017 + 0.002 48 12/2/2003 0.014 + 0.001 0.016 + 0.002 0.014 + 0.001 0.015 + 0.002 49 12/9/2002 0.015 + 0.001 0.016 + 0.002 0.015 + 0.001 0.016 + 0.002 50 12/16/2002 0.014 + 0.001 0.012 + 0.001 0.013 + 0.001 0.011 + 0.001 51 12/23/2002 0.011 + 0.001 0.011 + 0.001 0.013 + 0.001 0.014 + 0.002 52 12/30/2002 0.013 + 0.001 0.010 + 0.001 0.014 + 0.001 0.013 + 0.001

• Sample deviation.

• • Control location. B-15

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2002 3

(RESULTS IN UNITS OF 103 pCi/M +/- I SIGMA)

1. 4 ALGONQUIN GAS LINE RADIONUCLIDES _FIRSTQUARTER E DR THIRDQUARTER FOURTH QUARTER Be-7* 106.5+12.18 115.5+/-12.56 100.9+/-10.45 74.18+8.29 K-40* <9.07*** <3.81 33.35+/-6.83 <37.0***

Mn-54 <0.36 <0 25 <0.42 <0 40 Co-58 <0.73 <0.51 <0.52 <0 69 Fe-59 <2.73*** <2.53 <2.33 <2.76 Co-60 <0.57*** <0.5 <0.51 <0 59 Zn-65 <1.29 <1.35 <1.04 <1.45 Zr-95 <2 20 <1.52 <1.18 <1.05 Nb-95 <0.70 <0.78 <1.14 <1.06 Ru-103 <0 73 <1.16 <0.58 <0.58 Ru-106 <3 84 <6.94 <4.86 <5.28 1-131 <6 26 <7.37 <6.79 <7.95 Cs-134 <0.46 <0 54 <0 61 <0.55 Cs-137 <0 44 <0.32 <0.54 <0.36 Ba/La-140 <9 07 <8 15 <2.73 <3 87 Ce-141 <0.98 <0.87 <1.32 <0.74 Ce-144 <1.87 <2.15 <2.7 <1.48 Ra-226* <6.88 <5 48 <8 2 <5 92 AclTh-228* <1.33 <1.95 <1.18 <1.22 OTHERS <LC <Lc <Lc <Lc

1. 5 NYU TOWER f RADIONUCLIDESi-, FIRSTQUARTER tlSECONDQUARTER,' iTHIRDQUARTER- lK"FOURTHQUARTER-Be-7* 84 72+12 29 111.4+/-12.7 95.9+/-11.69 61.65+7.98 K.40* <6.42 <5 53*** 35 24+/-7.9 23.42+6 4 Mn-54 <0.41 <0.68 <0.64 <0 41 Co-58 <0.42 <0 78 <0.91 <0 66 Fe-59 <2.89 <3.16 <2.89 <16.7***

Co-60 <0 85 <0 44 <0.63 <0.30 Zn-65 <1.30 <0.97 <1.12 <0.76 Zr-95 <1.52 <0 95 <1.86 <1.39 Nb-95 <1 25 <1.2 <1.07 <0.93 Ru-103 <1.14 <1.14 <1.13 <0.87 Ru-106 <5.03 <3.06 <6.46 <4.82 1-131 <9.27 <6 02 <7.87 <7.73 Cs-134 <0.74 <0.73 <0.91 <0.65 Cs-137 <0.54 <0.4 <0.73 <0 24 Ba/La-140 <4.79 <10.16 <7.59 <4.3***

Ce-141 <1.20 <1.33 <1.46 <1.11 Ce-144 <2.75 <2 <3.36 <1.55 Ra-226* <6.52 <6.48 14.98+/-6 91 <5.61 Ac/Th-228* <2.59 <1.41*** <1.46 <1 26 OTHERS <Lc <Lc <Lc Lc

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (L),unless otherwise noted. B-16

• • • Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2002 (RESULTS IN UNITS OF 103 pCi/m 3 +/- 1 SIGMA)

1. 27 CROTON POINT

,RADIONUCLIDES,: FIRSTZQUARTERl SECOND QUARTER -,THIRD QUARTER FOURTH QUARTERn Be-7* 106.7+12.11 104.6+/-13.33 103.5+/-11.95 60.67+7.51 K-40* <5.16 <5.39*** <6.58 <3.0***

Mn-54 <0 61 <0.64 <0 63 <0.31 Co-58 <0.71 <0.44 <0.63 <0.54 Fe-59 <2.48 <2 5 <2.33 <1.38 Co-60 <0.67 <0 5 <0.72 <0.47 Zn-65 <0.83 <1.24 <1.28 <0.83 Zr-95 <1.91 <0.98*** <1.59 <0.61 Nb-95 <1.22 <1.16 <1.5 <0.64 Ru-103 <0.78 <1.1 <1.06 <0.77 Ru-106 <5.65 <3.15*** <3.19 <3.98 1-131 <6.17 <11.16 <7.16 <7.27 Cs-134 <0.74 <0 51 <0.67 <0.45 Cs-137 <0.59 <0.39 <0.55 <0.21 Ba/La-140 <5.45*** <5.73 <6.71 <4.63 Ce-141 <1.11 <1.56 <1.4 <0.96 Ce-144 <2.17 <2.39 <3.32 <1.81 Ra-226* <6.06 <7.17 <9.65 <5.40 AclTh-228* <1.60 <1.67 <1.44 <1.59 OTHERS <L <L'c <L' 'Lc

1. 94 IP TRAINING CENTER RADIONUCLIDES FIRSTQUARTER SECONDQUARTER: THIRDQUARTER FOURTHQUARTER Be-7* 99 02+11.51 126+/-13.86 99.96+/-12.85 75 47+8.64 K-40* <4.78 <7.06 <7.06 19 32+5.09 Mn-54 <0.59 <0 36 <0.68 <0.49 Co-58 <0.85 <0 91 <1.11 <0.66 Fe-59 <2.30 <2.71*** <3.55 <2.26 Co-60 <0 67 <0 86 <0.38 <0.39 Zn-65 <1.68 <5 36*** <1.82 <0.98 Zr-95 <1.74 <1.62 <1.85 <1.38 Nb-95 <1.47 <0 81 <1.28 <0.91 Ru-103 <1.04 <1.14 <0.85 <0.85 Ru-106 <4.58 <6 21 <6.41 <4 86 1-131 <5.57 <12.28 <9 6 <7.79 Cs-134 <0.26 <0.77 <1.13 <0.48 Cs-137 <0 65 <0 26 <0.39 <0.43 Ba/La-140 <6 63 <5.73 <3.96*** <5.73 Ce-141 <1.33 <1.63 <1.71 <1.09 Ce-144 <1.96 <2 25 <3.36 <1.49 Ra-226* <7.04 <5.86 <11.26 <5.20 Ac/Th-228* <2.12 <1.92 <1.9 <1.23 OTHERS <Lc <Lc <C <Lc

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (Lc), unless otherwise noted B-17

• • • Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2002 (RESULTS IN UNITS OF 10' pCi/m 3 i 1 SIGMA)

1. 95 METEOROLOGICAL TOWER 1RADIONUCLIDES, FIRSTQUARTERE' l<SECOND QUARTER- -sTHIRDQUARTER  ;,SFOURTH QUARTER,-

Be-7* 114.8+14.19 105.7+/-12.89 109 8+/-13.05 61.7+8.53 K.40* 40 63+10.44 <8 59 28 88+/-6.8 <3 09 Mn-54 <0.58 <0 55 <0.61 <0 50 Co-S8 <1.09 <0 94 <0.86 <1.00 Fe-59 <4.04 <2.89*** <2.99 <2.94 Co-60 <0.56.*. <0 46 <0.53 <0 50 Zn-65 <1.58 <1.43 <1.64 <0.73 Zr-95 <1.92 <0 99 <1.8 <1.21 Nb-95 <1.25 <0 72 <1.24 <0.74 Ru-103 <0.77 <0.75 <0.83 <1.26 Ru-106 <4.55 <3 19 <7.82 <5.92 1-131 <6 07 <12.58 <7.87 <6 48 Cs-134 <0.90 <0.5 <0.7 <0.71 Cs-137 <0.54 <0 42 <0.58 <0 52 BalLa-140 <5.76 <6.13 <3.52 <7.30 Ce-141 <1.79 <1.27 <1.81 <1.13 Ce-144 <2.93 <2 95 <2.58 <2.19 Ra-226* <9.36 <4.51 <11.16 <6.67 AclTh-228* <2.97 <1.79 <1.85 <1.49 OTHERS <Lc Lc <Lc Lc

1. 22 LOVETT POWER PLANT RADIONUCLIDES lFIRST QUARTER', SECOND QUARTER ,THIRD QUARTER 7 FOURTH QUARTER Be-7* 73.64+10.32 86.13+/-11.69 86 08+/-10 31 58 3+6.98 K-40* 33 35+8.03 34 63+/-7.76 <4.44 <3.07 Mn-54 <0.42 <0.64 <0.43 <0.31 Co-58 <0.79 <0.88 <0 81 <0 51 Fe-59 <3.73 <3.79 <1.39 <1.19 Co-60 <0 57 <0.87 <0.3 <0 33 Zn-65 <1.34 <1.99 <1.51 <0.83 Zr-95 <0.89 <0.91 <1.09 <0.98 Nb-95 <1.31 <1.26 <1.1 <0.91 Ru-103 <1.12 <1.33 <0.85 <0.75 Ru- 06 <5 58 <5.57 <6.76 <4.20 1-131 <8.61 <10 3 <8.6 <6 27 Cs-134 <0.78 <0.75 <0.77 <0.39 Cs-137 <0.55 <0 47 <0 46 <0.32 Ba/La-140 <3.95*** <6 39 <3.24*** <4 02 Ce-141 <1.66 <1.49 <1.44 <0.97 Ce-144 <2.63 <2.67 <2.91 <1.30 Ra-226* <7.58 <8.46 <7.81 <4 07 Ac/Th-228* <2.18 <1.64 <1.69 <0 96 OTHERS <Lc <Lc <Lc <Lc

• Indicates naturally occurring.

• • "Less than' values expressed as Critical Level (L),unless otherwise noted. B-18

• • • Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2002 (RESULTS IN UNITS OF 103 pCirM3 +/- 1 SIGMA)

1. 23 ROSETON RADIONUCLDES FIRSTQUARTER SECONDOUARTER THIRD QUARTER FOURTH QUARTER Be-7* 97.21+11.21 127.2+/-13.78 119 2+/-16 85 71.1+7.8 K-40* <6.27 <8.17 <7.64 <3.48 Mn-54 <0.45 <0.61 <0.55*t* <0.45 Co-58 <0.92 <1.11 <1.04 <0.47 Fe-59 <2.34*** <3 9 <3.86*** <2.34 Co-60 <0.44 <0.44 <0.76 <0.37 Zn-65 <1.75 <1.67 <2.92 <1.15 Zr-95 <1.41 <1.01*** <1.29 <1.32 Nb-95 <0.69 <1.57 <1.08 <0.96 Ru-103 <0.87 <1.15 <1.19 <0.71 Ru-106 <6.95 <8.05 <3.9 <3.53 1-131 <7.24 <9.98 <7.12 <7.16 Cs-134 <0.49 <0.47 <1.02 <0.35 Cs-137 <0.39 <0.49 <0.73 <0.36 Ba/La-140 <5.3*** <7.17*** <8.24*** <5.58 Ce-141 <1.01 <1.46 <1.32 <1.05 Ce-144 <1.63 <2.09 <3.19 <1.49 Ra-226* <6.53 <7.11 <7.5 <5.83 Ac/Th-228* <0.98 <1.40*** <1.91 <1.26 OTHERS <Lc L7c <Lc <Lc

1. 29 GRASSY POINT RADIONUCLIDES FIRST QUARTER SECONDQUARTER'i THIRD QUARTER FOURTH QUARTER Be-7* 96.5+11.22 137.2+/-13.73 109.6+/-10.85 75.73+7.28 K-40* <5 36 <3.84 <6.5 24.05+4.39 Mn-54 <0.35 <0.65 <0.41 <0.32 Co-58 <0.62 <0.64 <0.59 <0.48 Fe-59 <2 45 <2 97 <1.66 <1.35 Co-60 <0.53 <0.44*** <0 43*** <0.22***

Zn-65 <0.95 <1.26 <1.31 <0.50 Zr-95 <1.27 <1.46 <0.71 <1.14 Nb-95 <0.93 <1.14 <1.01 <0.81 Ru-103 <0.81 <0 59 <0.37 <0.78 Ru-106 <4.32 <5.5 <2.4 <3.71 1-131 <5.93 <8.91 <6.11 <4.06 Cs-134 <0.50 <0.59 <0.43 <0 33 Cs-137 <0.31 <0.45 <0.22 <0 23 Ba/La-140 <4.44 <5 84*** <4.32*** <2.83***

Ce-141 <1.00 <0 82 <1.04 <0.84 Ce-144 <2.16 <1.69 <1.98 <1.20 Ra-226* <8 63 <5.94 <4.82 <3 67 Ac/Th-228* <1.69 <1.39 <1.35 <0 63 OTHERS <Lc RLC <Lc Lc

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (L), unless otherwise noted B-19

• • • Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2002 (RESULTS IN UNITS OF 10-3 pCi/M 3 +/-i 1SIGMA)

1. 44 PEEKSKILL GAS HOLDER BUILDING

..RADIONUCLIDESb ' FIRST QUARTERI aSECOND QUARTER \ THIRD QUARTER -wFOURTH QUARTER Be-7* 83 71+12.71 112.8+/-13 51 104.9+/-13.37 55.64+8.27 K-40* <6 47 <8 43 <5.7*- 44.27+8.18 Mn-54 <0.48 <0.61 <0.75 <0.27 Co-58 <0.57 <0.9 <0.89 <0.80 Fe-59 <3 45 <4.97 <2.48 <2.76 Co-60 <0.75 <0 53*** <0.52 <0.38 Zn-65 <1.36 <1.01.** <1.07*** <0.97 Zr-95 <1.43 <0.92 <1.11 <0.80 Nb-95 <1.22 <1.8 <1.6 <0.90 Ru-103 <1.28 <1.24 <1.46 <0.84 Ru-106 <7.07 <2 72 <8.23 <4.28 1-131 <8.40 <10.35 <9.97 <7.82 Cs-134 <0.91 <0.76 <0.75 <0 49 Cs-137 <0.54 <0.43 <0 5 <0 46 Ba/La-140 <6.13 <5.91 <4.86 <5.63 Ce-141 <1.74 <1.25 <1.11 <1.31 Ce-144 <3.23 <2.2 <2.61 <1.27 Ra-226* <9.05 <5.72 <9.12 <5.97 Ac/Th-228* <3.02 <1.87 <2.49 <1.39 OTHERS <LCLc Lc <Lc

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (L),unless otherwise noted. B-20

• • • Reported as sample LLD.

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2002*

(pCi/m 3 + 1 sigma)

Week#. End Date 4- z l 94t - - - 22 e-23*** - -29 44-1 1/8/2002 <0.010 <0.005 <0.010 <0 012 <0.008 <0.012 <0.017 <0.006 <0 006 2 1/14/2002 <0.004** <0.009 <0.012 <0.010 <0.013 <0.010 <0.015 <0.006 <0.012 3 1/22/2002 <0.005 <0.010 <0 012 <0.011 <0.009 <0.005 <0.005 <0.007 <0.009 4 1/28/2002 <0.009 <0.007 <0.011 <0.013 <0011 <0.005 <0.007** <0.012 <0.015 5 2/512002 <0.005 <0.013 <0.009 <0.008 <0.009 <0.010 <0.007 <0.007 <0 014 6 2/11/2002 <0.006 <0.009 <0.008 <0.008 <0.009 <0.009 <0.012 <0.011 <0.009 7 2/19/2002 <0.005 <0.006 <0.014 <0.012 <0.016 <0.009 <0.007 <0.006 <0 011 8 2/25/2002 <0.008 <0.005 <0.010 <0.014 <0.008** <0.009 <0.009 <0.008 <0.011 9 3/4/2002 <0.009 <0.015 <0.010 <0.008 <0.009 <0.007** <0.010 <0.007 <0.010 10 3/11/2002 <0.006** <0.010 <0.012 <0.009 <0 019 <0.009 <0.010 <0.008 <0.012 11 3/18/2002 <0.005 <0.009 <0.007 <0.016 <0.016 <0.006 <0.013 <0.015 <0.016 12 3/25/2002 <0.008 <0.004 <0 007 <0.010 <0.014 <0.012 <0 010 <0.007 <0 008 13 4/1/2002 <0.005 <0 006** <0.007 <0 006** <0.005 **** <0.012 <0.013 <0.011 14 4/8/2002 <0.010 <0.010 <0.010 <0.011 <0.010 ** <0.016 <0.010 <0.012 15 4/15/2002 <0.006 <0.008** <0.010 <0.007 <0.005 <0.005 <0.014 <0.008 <0 012 16 4/22/2002 <0.011 <0.012 <0.011 <0.011 <0.014 <0.011 <0.005 <0.012 <0.012 17 4/29/2002 <0.010 <0.012 <0.006 <0.009 <0.014 <0.012 <0.008 <0.008 <0 011 18 5/6/2002 <0 006 <0.009 <0 008 <0.012 <0.012 <0.009 <0 017 <0 010 <0 016 19 5/13/2002 <0.006 <0.008 <0.011 <0.013 <0.011 <0 010 <0.008 **** <0 012 20 5/20/2002 <0 006 <0.009 <0.006 <0.015 <0.009 <0.009 <0.011 <0.010 <0.008 21 5/28/2002 <0.006 <0.010 <0.008 <0.006 <0.013 <0.008 <0.012 <0.004 <0.011 22 6/3/2002 <0 013 <0.005 <0 014 <0.015 <0.013 <0 010 <0 016 <0 009 <0 019 23 6/10/2002 <0.006 <0 008 <0.012 <0.013 <0.007 <0.009 <0.009 <0.009 <0.012 24 6/17/2002 <0.008 <0.012 <0.011 <0.009 <0.010 <0.020 <0.008 <0.005 <0.015 25 6/25/2002 <0.008 <0.005 <0.009 <0.011 <0.011 <0.005 <0 008 <0 009 <0 011 26 7/2/2002 <0.007 <0.012 <0.010 <0.015 <0.015 <0.012 <0.014 <0.011 <0.015

• "Less than' values expressed as sample Critical Level (L,) unless otherwise noted.

• • Reported as sample LLD.

• • • Control location.

• • • • Sample deviation. B-21

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2002*

(pCI/M 3 +/- 1 sigma)

Week#. EndDate 4 57 27- 94- 95 - -t 22 -~'23*** :29 - 44 27 7/9/2002 <0.011 <0.015 <0.016 <0.015 <0.011 <0.012 <0.014 <0.006 <0.011 28 7/16/2002 <0.007 <0.006** <0 007 <0.006 <0.016 <0.007 <0.005 <0.012 <0.010 29 7/22/2002 <0.008** <0.015 <0.016 <0.010 <0.017 <0.008 <0.010 <0.005 <0.014 30 7/30/2002 <0.008 <0.008 <0.010 <0.010 <0.005 <0.009 <0.007 <0.017 <0 021 31 8/6/2002 <0.013 <0.009 <0.005 <0.010 <0.011 <0.013 <0.011 <0.012 <0 011 32 8/13/2002 <0.008 <0.009** <0.011 <0.008 <0.008 <0.010 <0.009 <0.012 <0.016 33 8/20/2002 <0.007** <0.011 <0.009 <0.009 <0.011 <0.007 <0.012 <0.004 <0.017 34 8/27/2002 <0.007 <0.011 <0.011 <0.007 <0.005 <0.012 <0.012 <0.004 <0 014 35 9/3/2002 <0.013 <0.011 <0.020 <0.020 <0.015 <0.008 <0.012 <0.006** <0.010 36 9/9/2002 <0.009 <0.011 <0.013 <0.013 <0.016 <0.009 <0 013 <0.013 <0.016 37 9/17/2002 <0.009 <0.006** <0.014 <0.011 <0.008** <0.010 <0.014 <0.012 <0 017 38 9/24/2002 <0.007 <0.010 <0.008 <0.006 <0.012 <0.009 <0.012 <0.010 <0.012 39 9/30/2002 <0.008 <0.008 <0.014 <0.019 <0.008 <0.011 <0.009 <0.006 <0.009 40 10/8/2002 <0.008 <0.014 <0.010 <0.009 <0 011 <0.009 <0 012 <0.008 <0 011 41 10/15/2002 <0.008 <0.005 <0.009 <0.009 <0.010 <0.007 <0.005 <0.005 <0.007 42 10/21/2002 <0.006 <0.012 <0.007 <0.011 <0 008 <0.011 <0.009 <0.009 <0 010 43 10/29/2002 <0.005 <0.009 <0.007 <0 010 <0 009 <0.005 <0.009 <0.008 <0 007 44 11/5/2002 <0 006 <0.009 <0.003 <0.009 <0.007 <0.010 <0.008 <0.007 <0.012 45 11/11/2002 <0.006 <0.009 <0.008 <0.009 <0.007 <0.008 <0.009 <0.010 <0.007 46 11/19/2002 <0.011 <0.007 <0.010 <0.007 <0 010 <0.007 <0.008 <0.009 <0 008 47 11/26/2002 <0.005 <0.009 <0.007 <0.005 <0.007 <0.007 <0.008 <0.006 <0.010 48 12/3/2002 <0 007 <0.007 <0.007 <0.008 <0 009 <0.006 <0.011 <0.006 <0.009 49 12/10/2002 <0.006 <0.011 <0.007 <0.007 <0.010 <0.007 <0.007 <0.008 <0.010 50 12/17/2002 <0.007 <0.010 <0.007 <0.009 <0.008 <0 014 <0 009 <0.006 <0.008 51 12/23/2002 <0.007 <0.006 <0.008 <0.011 <0.008 <0 006 <0 008 <0.005 <0.009 52 12/30/2002 <0.007 <0.010 <0.008 <0.016 <0.017 <0.011 <0.011 <0.010 <0.007

• "Less than' values expressed as sample Critical Level (La) unless otherwise noted.

• • Reported as sample LLD.

• • • Control location.

• • • • Sample deviation. B-22

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2002 (pCi/L +/- 1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

Radionuclide iJanuary Februay,l 'Marchn, l,-April,,I',, May -,June Be-7* <7.75 <7.49 <11.81 <7.22 <10.32 <7.97 K-40* 209+10.3 197.2+106 255 2+14.9 253.8+/-8 44 261.7+/-15.3 158 4+/-9.46 Mn-54 <05 <079 <1.15 <0.73 <1.03 <0.8 Co-58 <0.95 <0.91 <1.25 <0 83 <1.33 <0 95 Fe-59 <2.97 <2 71 <3.74 <2.2 <3.29 <2.94 Co-60 <0.77 <0 79 <1.12 <0.7 <1.2 <0 86 Zn-65 <1.65 <1.69 <2.51 <09 <2.4 <1.73 Zr-95 <1.71 <1.62 <2.29 <1.42 <2.15 <1.57 Nb-95 <1.24 <1.01 <1.45 <1.02 <1.4 <1.17 Ru-103 <1.28 <1.19 <1.54 <0.6 <1.56 <1.21 Ru-106 <7.95 <7.65 <11.09 <7.33 <11.45 <8.17 1-131 <4.27 <3 52 <4.31 <3 09 <4 98 <5 Cs-134 <0 77 <0 78 <1.02 <0 44 <1.18 <0.77 Cs-1 37 <0 75 <0.8 <1.03 <0 66 <1.09 <0.72 BalLa-140 <2.74 <2.38 <2.06 <1.97 <4.04 <2.66 Ce-141 <1.24 <1.13 <2.22 <1.76 <2.38 <1 21 Ce-144 <5 56 <5 61 <6 8 <5.62 <7.18 <5.48 Ra.226* 89 6+13 3 106 9+12 8 113.9+16.9 82.85+/-13.25 88.32+/-17.08 125 4+/-14 23 AclTh-228* <2 59 5 26+2 3 13 0+3 2 12 84+/-2.15 10 14+/-2 93 3 59+/-1.95

1. 10 DISCHARGE CANAL (MIXING ZONE)

-Radlonuclldeo January 4 f gFebruary March - ApriH' T.May June -

Be-7* <10 59 <10.46 <7.83 <11.22 <8 52 <10.67 K-40* 391+14.11 385.5+14 33 190 6+10.23 269.9+/-15 61 172 8+/-10.21 316.9+/-13 09 Mn-54 <1.02 <0.91 <0.78 <1.1 <0.79 <0.96 Co-58 <1.23 <1.1 <0.92 <1.24 <09 <1.08 Fe-59 <3.19 <3.3 <2.43 <3.77 <2 63 <3.28 Co-60 <1.06 <1.1 <0.83 <1.17 <0 82 <0.98 Zn-65 <1.36 <1.26 <1.99 <2.4 <1.97 <2.38 Zr-95 <2 08 <1.95 <1.66 <2.13 <1.67 <1.98 Nb-95 <1.47 <1.23 <1.09 <1.5 <1.05 <1.38 Ru-103 <1.54 <1.45 <1.15 <0 99 <1.29 <1.51 Ru-106 <9 14 <9.89 <8 67 <11 51 <8 26 <9.2 1-131 <5 11 <4.19 <3 31 <4 64 <3.95 <5.84 Cs-134 <0 64 <0.87 <074 <1.05 <0.74 <0.61 Cs-137 <0 9 <0.91 <0.85 <1.06 <0.83 <0.84 Ba/La-140 <3 49 <3.06 <2.42 <3 7 <3 02 <3.98 Ce-141 <1.79 <1.69 <1.9 <1.63 <1.99 <2.73 Ce-144 <7.78 <7.61 <5.89 <7.19 <5 85 <7.8 Ra-226* 124 6+16 36 103.4+17.32 53 88+13.56 110.7+/-17.46 63 76+/-14.96 89 54+/-16.1 AcJTh-228* 4.87+2.66 8 06+2 74 <2.59 5.86+/-3.11 3.68+/-2 21 12.16+/-2 67

• Indicates naturally occurring B-23

• • "Less than' values expressed as Critical Level (Lj)

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2002 (pCi/L +/- I SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

Radionuclide' July August', September~z.% rOctober 5' - November, -December Be-7* <10.21 <8.77 <10 61 <16.26 <9.76 <12.28 K-40* 220.3+/-14.22 223 8+/-10 78 244 3+/-14 64 407.2+22 69 173 4+13 2 187.2+14 59 Mn-54 <1.1 <0.74 <1.06 <1.51 <1.03 <1.1 Co-58 <1.2 <0.92 <1.19 <1.69 <1.12 <1.37 Fe-59 <3 35 <2.57 <3.47 <4.75 <3.77 <3.98 Co-60 <1.13 <0 83 <1.18 <1 59 <1.02 <1.1 Zn-65 <2.12 <1.62 <2.45 <3 82 <2.43 <2.51 Zr-95 <2 39 <1.82 <2.23 <3 36 <2.25 <2.49 Nb-95 <1.5 <1.14 <1.46 <2.09 <1.54 <1.52 Ru-103 <1.45 <1.24 <1.42 <2.54 <0.87 <1.94 Ru-106 <1027 <8 55 <11.67 <15.1 <9.02 <12.17 1-131 <5 47 <5 04 <4.51 <7.31 <4.75 <6.4 Cs-134 <0 56 <0.78 <1.01 <1.01 <0 6 <1.11 Cs-137 <1.05 <071 <1.04 <1.48 <0.96 <1.14 Ba/La-140 <3.93 <3 09 <2.75 <5 8 <3.6 <4 25 Ce-141 <2.26 <1.94 <2.2 <4 09 <2.12 <1.8 Ce-144 <6.85 <5 69 <6 78 <12.49 <6.97 <8.18 Ra-226* 71.13+/-16 51 114.5+/-15.02 77.2+/-16 61 148 2+27.84 117.5+17.8 <25.1 Ac/Th-228* 11.02+/-3 23 4 96+/-2 03 12.18+/-3.19 8.03+4 2 5 37+3 03 <3 97

1. 10 DISCHARGE CANAL (MIXING ZONE)

-Radlonuclide -. July;  ;-

ciAugust September October November December',

Be-7* <8 03 <10 83 <7.93 <11.36 <8.15 <12.34 K-40* 222.5+/-10.91 385 5+/-14.44 261.5+/-11.58 288.5+14.11 194.2+10 55 166 4+14 82 Mn-54 <0 83 <0.98 <0.81 <1.05 <0 8 <1.29 Co-58 <0 87 <1.11 <0 84 <1.25 <0.9 <1.59 Fe-59 <2.6 <3.31 <2.76 <3 71 <2 52 <4 45 Co-60 <0.79 <1.12 <0 76 <1.03 <0 81 <1.42 Zn-65 <2.01 <2.33 <1.93 <1.36 <2.01 <3.08 Zr-95 <1.63 <1.91 <1.58 <2.22 <1.76 <2.78 Nb-95 <1.17 <1.43 <1.02 <1.52 <1.02 <1.82 Ru-103 <0.7 <1.54 <1.15 <1.55 <1.19 <1.75 Ru-106 <8 42 <9 88 <8.56 <11.18 <7.96 <13.7 1-131 <3 94 <5 89 <2.99 <5 35 <3.32 <7.35 Cs-134 <0 76 <0.61 <0.81 <0 67 <0 46 <1.15 Cs- 137 <0.78 <0.87 <0 85 <0.92 <0.85 <1.27 Ba/La-140 <2.93 <3.77 <2.28 <3 37 <2.48 <5.09 Ce-141 <1.92 <2.69 <1.91 <2.93 <1.87 <2.87 Ce-144 <5 82 <7.47 <5.95 <8 69 <5.83 <8.31 Ra-226* 62.89+/-14.65 99 24+/-17.68 50.25+/-13 59 77.33+19 49 70 94+16 42 113.8+21.79 ActTh-228* 10 41+/-2.43 9.35+/-2.65 6 29+/-2.16 9.09+2 67 8.36+2.4 <4 46

• Indicates naturally occurring B-24

• • 'Less than' values expressed as Critical Level (Lj).

TABLE B-10 CONCENTRATION OF TRITIUM IN HUDSON RIVER WATER SAMPLES*- 2002 (QUARTERLY COMPOSITES)

(pCi/L i 1 sigma)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

(Control Location) 1X-Radionuclide Ietl 41ST Quarter [T2ND.'Quarter 1it3RD Quarter- 4TH Quarter TRITIUM <290 <270 <290 432+76

1. 10 DISCHARGE CANAL (MIXING ZONE)

I -Radionuclide' IISTQuarterIl2NDQuarter I .3RD Quarter *I 4TH Quarter TRITIUM <290 <270 340+94 783+79

• 'Less than" values expressed as Lower Limit of Detection (LLD). B-25

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2002 (pCi/L +/- 1 sigma)

1. 7 CAMP FIELD RESERVOIR

,RadlonucIlIde '.January' February March" X' " Aprll ,May, 'KJune>

Gross Beta 2.63+0.52 2.66+0.59 2.24+0.54 2.74+/-0.58 2.02+/-0.49 1.66+/-0.49 Be-7* <29.55 <19.31 <17.35 <15.5 <19.72 <21.89 K-40* 405.1+53.31 142.2+26.47 159.3+28.64 162.1+/-25.3 237.1+/-37.35 359.6+/-36.03 Mn-54 <4.06 <2.52 <2.72 <1.84 <2.78 <2.71 Co-58 <3.96 <2.33 <2.32 <1.97 <2.66 <2.34 Fe-59 <8.95 <5.4 <6.22 <5.58 <7.6 <5.92 Co-60 <3.85 <3.28 <2.32 <2.32 <2.94 <2.57 Zn-65 <9.33 <5.68 <6.14 <4.87 <7.06 <6.73 Zr-95 <5.45 <4.74 <4.34 <3.88 <4.48 <4.3 Nb-95 <3.94 <3.07 <2.75 <2.19 <2.73 <2.6 Ru-1 03 <3.54 <2.8 <2.39 <2.35 <2.95 <2.96 Ru-1 06 <33.52 <25.98 <25.55 <21.8 <27.81 <25.77 1-131 <0.27 <0.22 <0.32 <0.26 <0.23 <0.21 Cs-134 <2.47 <2.51 <2.35 <2.25 <2.63 <2.51 Cs-137 <3.3 <2.06 <1.81 <2.15 <2.5 <2.74 BatLa-140 <5.14 <3.92 <3.63 <3.66 <4.2 <3.21 Ce-141 <6.52 <4.25 <4.65 <3 54 <4.29 <4.56 Ce-144 <27.04 <15.65 <16.37 <14.94 <17.22 <18.73 Ra-226* <96.23 163.5+46.87 87.01+43.75 <45.29 <63.98 112+/-44.05 AcIrh-228* <11.03 <8.21 <7.94 <8.57 <11.94 <8.62

1. 7 CAMP FIELD RESERVOIR Radionuclide ' July > >, August, September -October ,November,, -December Gross Beta 2.58+0.52 2.10+0.44 2.46+0.49 1.66+/-0.48 2.29+/-0.56 1.08+0.55 Be-7* <21.74 <21 <20.97 <23.01 <18.44 <25.29 K-40* 167.7+30.77 <29.65 203.6+31.49 173.8+/-34.58 205.7+/-36.57 185.9+/-28.36 Mn-54 <2.47 <2.39 <2.73 <2.99 <2.36 <2.61 Co-58 <2.97 <2.45 <2.54 <2.81 <2.68 <2.32 Fe-59 <6.96 <6.44 <6.32 <7.06 <6.14 <7.41 Co-60 <2.63 <2.53 <2.32 <3.56 <3.39 <2.4 Zn-65 <5.66 <5.68 <6 <6.17 <6.83 <7.12 Zr-95 <4 <4.13 <4.49 <4.24 <4.2 <4.95 Nb-95 <2.6 <1.92 <2.45 <2.84 <3.75 <3 82 Ru-103 <2.89 <2.67 <2.56 <2.73 <2.55 <3.19 Ru-106 <27.62 <25.86 <23.56 <23.96 <25.46 <28.51 1-131 <0.2 <0.23 <0.23 <0.21 <0.28 <0.22 Cs-134 <2.9 <2.24 <2.52 <2.48 <2.96 <2.91 Cs-137 <2.93 <2.74 <2.42 <2.72 <2.5 <2.58 Ba/La-140 <3.58 <2.29 <3 <2.97 <3.8 <4.45 Ce-141 <3.93 <3.73 <3.95 <4.15 <3.85 <4.5 Ce-144 <16.98 <16.48 <15.48 <18.72 <16.98 <16.98 Ra-226* 102.1+41.69 <48.25 <49.43 81.51+/-45.57 <55.19 <54.88 Acrrh-228* <9.57 <7.23 <7.88 <10.41 <9.57 <6.48

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (Lj). B-26

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2002 (pCi/L i I sigma)

1. 8 NEW CROTON RESERVOIR

,Radlonuclide (,January h Februaryi, March-:',', -, AprIl> to . Mayr uJune-_,

Gross Beta 2.52+0.49 1.73+0.53 2.32+0.53 1.07+/-0.53 2.66+/-0.52 2.41+/-0.52 Be-7* <29.96 <25.42 <18.12 <17.12 <18.12 <16.84 K-40* 159.4+42.33 322.8+45.02 210+26.06 112+/-24.02 187.6+/-26.24 191.9+/-31.89 Mn-54 <3.26 <3.06 <2.00 <2.46 <2.14 <2.23 Co-58 <3.23 <2.98 <2.03 <2.12 <1.97 <2.33 Fe-59 <8.81 <8.10 <5.54 <5.31 <5.41 <7.64 Co-60 <3.27 <3.07 <1.83 <1.94 <2.32 <3.14 Zn-65 <4.80 <6.83 <5.64 <4.42 <6.47 <5.04 Zr-95 <5.51 <6.73 <4.01 <3.69 <4.97 <3.45 Nb-95 <3.04 <3.04 <2.37 <1.81 <2 <2.36 Ru -103 <2.54 <3.24 <2.31 <2.2 <2.63 <2.28 Ru-106 <36.23 <29.89 <19.70 <21.7 <25.56 <22.68 1-131 <0.24 <0.21 <0.30 <0.24 <0.20 <0.19 Cs-134 <3.35 <2.07 <1.36 <2.54 <2.22 <2.22 Cs-137 <3.31 <2.55 <2.19 <1.82 <2.29 <2.14 Ba/La-140 <2.89 <4.85 <2.93 <2.71 <2.58 <2.91 Ce-141 <5.32 <5.31 <4.08 <3.82 <3.41 <3.97 Ce-144 <23.18 <25.28 <16.25 <16.96 <16.23 <17.17 Ra-226* 121.2+53.66 <78.07 <46.45 <45.36 <45.77 145.4+/-44.49 Ac/Th-228* <9.50 <11.43 <7.89 <7.34 <6.86 <6.94

1. 8 NEW CROTON RESERVOIR

-Radionuclide July August -~ September iOctober; November, December Gross Beta 2.89+0.52 2.22+0.45 3.34+0.5 1.51+/-0.48 2.08+/-0.54 1.67+0.66 Be-7* <18.51 <22.15 <17.12 <14.59 <16.5 <18.77 K-40* 152.4+24.73 159.7+29.89 263.1+27.32 148.1+/-26.16 140.7+/-27.26 158.1+/-23.69 Mn-54 <2.42 <2.32 <2.18 <2.14 <2.33 <2.26 Co-58 <2.12 <2.41 <1.93 <2.11 <2.09 <2.12 Fe-59 <5.55 <5.23 <4.84 <5.29 <5.41 <5.03 Co-60 <1.94 <2.75 <1.96 <1.7 <2.47 <1.61 Zn-65 <4.55 <5.31 <4.86 <5.17 <5.67 <4.65 Zr-95 <2.35 <4.43 <3.11 <2.77 <3.97 <4 Nb-95 <1.94 <2.22 <1.99 <2.11 <2.26 <2.41 Ru-103 <2.29 <2.69 <2.10 <2.39 <1.97 <2.37 Ru-1 06 <25.60 <28.30 <19.50 <23.16 <23.96 <22.78 1-131 <0.21 <0.23 <0.31 <0.23 <0.23 <0.21 Cs-134 <2.36 <2.49 <1.27 <2.06 <1.84 <1.86 Cs-137 <2.41 <2.85 <2.00 <2.42 <1.9 <1.73 Ba/La-140 <2.57 <3.61 <2.05 <3.13 <3.1 <3.38 Ce-141 <3.68 <3.92 <3.60 <3.66 <3.54 <3.22 Ce-144 <16.80 <18.81 <17.48 <14.91 <15.68 <14.23 Ra-226* 75.69+29.97 <59.13 105.9+38.21 <43.32 <46.95 169.3+/-42.03 Acrrh-228* <6.70 <6.10 <6.61 <7.48 <8.4 <7.01

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (L). B-27

TABLE B-12 CONCENTRATION OF TRITIUM IN DRINKING WATER SAMPLES*- 2002 (QUARTERLY COMPOSITES)

(pCi/L +/- 1 sigma)

1. 7 CAMP FIELD RESERVOIR l . Radionuclide,. I ASTQuarteri l,I2ND Quarter I 3RD Quarter I 4TH Quarter I I TRITIUM l <270 l <280 l <280 l <270

1. 8 NEW CROTON RESERVOIR 7P4TH Quarter S I -Radionuclideo, I 1ST Quarter: II.2ND Quarter .Xl / . 3RD Quarter 1',l I TRITIUM l <290 l <280 l <280 1 <270

• "Less than" values expressed as Lower Limit of Detection (LLD). B-28

TABLE B-13 CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SOIL SAMPLES**-2002 (pC0iKg ,dry +/- 1 sigma)

1. 17 OFF VERPLANCK 618/2002"* -17703+290 <19.7 <17.3 217+10.78 1174+170 1687.07+38 251 <L 9112J2002"* 16316+307 <21.72 <1846 241.4+11.9 1185+168.7 622.5+40 59 <Lc

1. 28 LENrS COVE 61812002** 17880+433 <27.24 <32.92 205 6+1605 2252+262 494.5+53 85 <Lc 9116/2002* 34440+763 <22.77 <29.66 <23 96 1196+348 545.5+88 52 <Lc

[,Collection Dat 61812002**

9112/2002*"

J -0 14863+344 12460+540 Co <32.22

<38.21

1. 50 MANITOU INLET (control location C-134

<20.62

<36.1 Cs17Rs26

<30 82 237.8+26.6 4710+317 2726+437 cT 28 1749+72.2 869.7+106 ters

<Lc Lc

1. 53 WHITE BEACH

'Collection Date, -, K-40 Co60 i Cs-134 Cs-137, Ra-22 Ac/Th-228*  ; Others 61812002** 6984+3166 <12.36 <11.44 <9.89 484.4+176.7 81.64+31.13 <Lc 9112l2002** 8566.5+297 <21.41 <14.41 <16.55 473.5+153 144.2+53.8 <Lc

1. 84 COLD SPRING (control loration) l Collecton Date K-40 Co-60 .,Cs134 Cs;137 , l Ra.226* AclTh-228* Others 61812002** 34450+698.7 [ <22.53 <16.63 <19.77 968 6+397.8 [ 481.6+69 <L 911/2/2002* 34440+763 3 <20.78 <25.43 <19.34 1292+322.9 [559 2+73.981 <L

• Indicates naturally occurring

- 'Less than' values expressed as Critical Level (Lj)

• • • Indicates the average of the positive sample results reported for samples with recounts performed. B-29

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2002 (pCi/Kg, wet +/- I sigma)

1. 23 Roseton**

April May

,.. .Comrmon .. Common Radlonuclide Ragweed Peppermint ,,Mulleil L Radionuclide+Mulleln ' Ragweed . Burdock Be-7' 593 6+/-29.49 390+/-20 26 497 4+/-40 29 Be-7* 1310+/-61 48 404 6+/-39 24 1329+/-56 3 K.40* 6372+/-107.1 4887+/-73 31 4147+/-120 K-40' 6111+/-171 3 7480+/-1658 8570+/-186 1 Mn-54 <3 26 <2 7 <4 87 Mn-54 <6 02 <5 97 <6 2 Co-58 <3 53 <2.82 <4 35 Co-58 <6.26 <5 32 <6 17 Fe-59 <11 33 <7.26 <14 36 Fe-59 <1765 <16 81 <17.06 Co-60 <4 33 <2 81 <5 21 Co-60 <6 31 <5 75 <6 41 Zn-65 <9 33 <3 95 <12 11 Zn-65 <18 14 <14 61 <14 86 Zr-95 <5 87 <4 76 <9 5 Zr-95 <10 38 <9 2 <9 89 Nb-95 <3 99 <2.94 <5 28 Nb-95 <59 <5 24 <6 66 Ru-103 <3 38 <2 82 <4 72 Ru-103 <6 35 <5 23 <5 86 Ru-106 <30 18 <25 99 <44 31 Ru-106 <72 03 <54 72 <52 6 1-131 <5 53 <4 41 <8 89 1-131 <7.21 <6 16 <6 98 Cs-134 <3 48 <1 86 <5 3 Cs-134 <7 <5 73 <6 42 Cs-137 <2 93 <2 49 <4 55 Cs-137 <6 88 <5 26 <5 39 Ba/La-140 <5 42 <3 19 <5 46 BalLa-140 <8 84 <5 13 <6 01 Ce-141 <5 16 <4 11 <4 23 Ce-141 <8 29 <7.12 <4.67 Ce-144 <18 97 <15 52 <26 18 Ce-144 <36 22 <29 61 <2983 Ra-226* 200 5+/-47.75 130 5+/-40 84 491+/-65 6 Ra-226' 352+/-102 138 4+/-78 57 365 3+/-80 05 AciTh-228* 25.24+/-10 19 44 03+/-7.98 <16 16 AclTh-228' 39 72+/-16 13 <22 27 38 6+/-19 16 June July Comrn~on & rf Qs 4 tS 1, > Fs ACommon Radlonucilde Mullein ,'Ragweed Clover'- RadIonucilde -Ragweed. i -Reeds Mullion, Be-7* 1643+/-95 25 277 9+/-58 12 139 5+/-38.31 Be-7* 1027+/-53 75 1168+/-78 95 <67.79 K-40' 7804+/-236 1 9543+/-226 4 4605+/-124 4 K-40* 10309 7+/-149 13630+/-305.3 7801+/-225 3 Mn-54 <10 05 <7 96 <6 66 Mn-54 <10.7 <9 39 <8 62 Co-58 <10 39 <8 44 <6 27 Co-58 <10 58 <9 95 <7 87 Fe-59 <28 58 <20 75 <13 42 Fe-59 <25 82 <29 97 <24 1 Co-60 <12 32 <9 93 <5 91 Co-60 <10.26 <1096 <9 01 Zn-65 <28 45 <25 17 <8 03 Zn-65 <24.37 <27 12 <21 67 Zr-95 <19 <14 28 <10 8 Zr-95 <16.86 <1739 <16 41 Nb-95 <10 23 <8 74 <6 53 Nb-95 <11.48 <9 35 <8 12 Ru-103 <10 58 <8.4 <6 07 Ru-103 <8 99 <9 78 <9 29 Ru-106 <97.82 <86.57 <67.74 Ru-106 <102 3 <106 <92 47 1-131 <12.64 <9 95 <7 61 1-131 <18 03 <10 2 <1023 Cs-134 <10.95 <5 56 <4 43 Cs-134 <1 1.88 <10 86 <10 99 Cs-137 <9 58 <8 15 <6 Cs-137 <8 49 <10 22 <8 73 BalLa-140 <14.08 <11.64 <7.68 BatLa-140 <13 59 <11.19 <10 57 Ce-141 <14.22 <14.26 <8 75 Ce-141 <12.56 <11.7 <11 78 Ce-144 <59 21 <53 67 <37 43 Ce-144 <51.22 <48 09 <49 51 Ra-226* 638 6+/-159 <243 5 677+/-95 92 Ra-226* 870 5+/-158 9 474 1+/-137 6 444.7+/-116 8 AcITh-228* 51 73+/-29 41 <33 52 117+/-18 73 AclTh-228 375 9+/-42 55 77.47+/-30 29 <32 59

• Indicates naturally occurring

• • Indicates control location.

.'Less than' values expressed as Critical Level (LC) B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2002 (pCi/Kg, wet : I sigma)

1. 23 Roseton (continued)**

August September Radionuclide iRagweed l ,Clover I.l-Loose Strife Radlonuclide , Ragweed Golden Rod Catalpa ,

Be 963 9+/-78 71 861.6+/-80.09 804 1+/-60 51 Be-7* 1105+/-68 02 1417+/-83 4 483 8+/-45 13 K-40^ 11270+/-313 3 11250+/-304 6 7391+/-199 2 K-40* 8371+/-219.1 10470+/-260 5490+/-1328 Mn-54 <10 72 <1085 <7 21 Mn-54 <8 15 <9 55 <6 06 Co-58 <11 48 <11 52 <6 51 Co-58 <8 87 <10.31 <5 63 Fe-59 <33 13 <33 85 <18 38 Fe-59 <23 98 <27.84 <15 87 Co-60 <12 4 <11.26 <7 95 Co.60 <8.31 <11 27 <647 Zn-65 <27.45 <30 29 <17.71 Zn-65 <20 97 <28 51 <13 26 Zr-95 <18 89 <18 74 <11 84 Zr-95 <15 68 <17.17 <10 04 Nb-95 <10 54 <10 36 <7.18 Nb-95 <8.64 <10 25 <6 08 Ru-103 <9 25 <11 37 <6 93 Ru-103 <7.62 <10 04 <5 7 Ru-106 <96 12 <117.5 <70 93 Ru-106 <80 04 <98 78 <65 53 1-131 <12 11 <11 68 <8 7 1-131 <10 38 <12 6 <8 37 Cs-134 <10 97 <6 91 <4 98 Cs-134 <7 9 <7 17 <4 39 Cs-137 <8 81 <12 34 <7 25 Cs-137 <74 <9 01 <6 15 Ba/La-140 <15 21 <13 18 <8 83 Ba/La-140 <10 64 <14 94 <7 96 Ce-141 <12 <14 24 <10.3 Ce-141 <9 9 <13 86 <9 05 Ce-144 <48 8 <55 06 <44 69 Ce-144 <40 1 <55 22 <39 11 Ra-226* 640 1+/-143 1 705 6+/-155 5 574 3+/-112.7 Ra-226' 898 9+/-123 5 689 3+/-145 1 628 6+/-106 1 Acrrh-228* <41 31 <41 47 <26 96 Acrrh-228* <29 38 82 95+/-27 66 84 71+/-16 4 October

-, .-,Common,,

Radionuclide Alum Root 'Mulilen' Golden Rod Be-7* 614 5+/-48 43 1270+/-109 2348 67+/-52 56 K 6954+/-176 9 7699+/-302 7 8910+/-131.31 Mn-54 <5 76 <12.89 <6 92 Co-58 <6 46 <11 6 <7 32 Fe-59 <18.03 <38.67 <20 6 Co-60 <7.44 <14 18 <7 04 Zn-65 <17.91 <34 98 <18 16 Zr-95 <11.22 <22 71 <12 9 Nb-95 <5 97 <14 15 <7 98 Ru-103 <5 42 <11.57 <7 34 Ru-106 <69 39 <128 9 <73 89 1-131 <6 84 <18 95 <14 95 Cs-134 <6 01 <12 91 <4 9 Cs-137 <6 75 <11.13 <6 78 Ba/La-140 <7.89 <16 96 <11 78 Ce-141 <8 18 <15 28 <12 07 Ce-144 <33 71 <6088 <4406 Ra-226- 154 9+/-88 18 861 8+/-164 5 610 73+/-73 15 Acrrh-2281 26 43+/-15 62 93.94+/-41 58 84 46+/-19.71

• Indicates naturally occurring.

• • Indicates control location.

• • • 'Less than' values expressed as Critical Level (La) B-31

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2002 (pCi/Kg, weti 1 sigma)

1. 94 IPEC Training Center April May

• ;~omrorki, p,i*,* s,,, , , pt5ormmon- ,- .b *^' '  :

Radlonucilde ,Alum Root Ragweed ' uen Radlonuclide -Mullein Ragweed .c8urdock.

Be-7* 626 8+/-47 21 942 2+/-38 31 923 3+/-55 07 Be-7* 923 8+/-55 04 527+/-30 75 1369+/-66 K-40* 7145+/-167 8 7628+/-135 2 5609+/-171.1 K-40* 6523+/-181 3 6461+/-124 5 8825+/-199 7 Mn-54 <6 11 <3 84 <6 13 Mn-54 <6 91 <3 92 <7.42 Co-58 <5 73 <3 88 <7.05 Co-58 <6 46 <3 57 <6.99 Fe-59 <18 58 <13 31 <22.68 Fe-59 <19 26 <12 22 <21.12 Co-60 <6 41 <4 43 <5 95 Co-60 <8 55 <4 11 <8.37 Zn-65 <14 44 <11 65 <15.68 Zn-65 <18 05 <10.47 <20 47 Zr-95 <9 64 <7.3 <10 48 Zr-95 <10 29 <6.5 <12.91 Nb-95 <6 51 <4 37 <7.27 Nb-95 <6 69 <4.3 <7.47 Ru-103 <5 62 <3 87 <6 61 Ru-103 <6 33 <3 59 <6 9 Ru-106 <61 86 <38 98 <56.42 Ru-106 <73 37 <35.56 <67 4 1-131 <9 75 <5 88 <9 94 1-131 <8 5 <4 27 <8.31 Cs-134 <6 17 <2 58 <6 08 Cs-134 <8 95 <4 05 <4 88 Cs-137 <5 92 <4 09 <5 94 Cs-137 <6 91 <3 59 <6.75 Ba/La-140 <7.72 <503 <11 3 Ba/La-140 <9 03 <3 85 <9.18 Ce-141 <8 66 <5 15 <8 04 Ce-141 <9 65 <4 53 <9.91 Ce-144 <31 53 <19 97 <30.34 Ce-144 <41 81 <19 32 <42 21 Ra-226* 318 4+/-75 59 276 1+/-62 64 372 9+/-95 07 Ra-226* 3712+/-95 32 375 9+/-54 04 449 4+/-101 9 Acfrh-228* <22 72 28 03+/-10 55 52 68+/-17.99 AcrTh-228' <25 56 17.9+/-9 36 55 51+/-2426 June July

< i rA 'I ,,i's .>iL <i Csomon.

prn Radlonucllde Ragweed Muleln" uReeds Ronucllde _'Ragweed_ Reeds IGrape Leaves Be 1643+/-95 25 829 6+/-42 08 311.9+/-33 41 Be-7* 509 7+/-53 28 <86 6 236 6+/-49 54 K 7804+/-236 1 7969+/-158 5 4954+/-130 6 K 10910+/-235 8808+/-236 9 5844+/-148 1 Mn-54 <10 05 <4 57 <4 64 Mn-54 <8 73 <9 82 <6 55 Co-58 <10 39 <4 79 <4 61 Co-58 <8 36 <9 91 <7.31 Fe-59 <28 58 <15 62 <14 17 Fe-59 <23 26 <30 42 <19 54 Co-60 <12 32 <4 93 <6 08 Co-60 <8 58 <12 <7.18 Zn-65 <28 45 <14 52 <10 46 Zn-65 <21.12 <27.75 <9 31 Zr-95 <19 <8 87 <8 24 Zr-95 <14.66 <1811 <13 12 Nb-95 <10 23 <4 74 <4 45 Nb-95 <8 48 <11 66 <7.96 Ru-103 <10 58 <4 58 <4 44 Ru-103 <7 42 <1028 <7 25 Ru-106 <97.82 <47.82 <54 13 Ru-106 <74.57 <96 29 <75 62 1-131 <12 64 <5 02 <5 41 1-131 <12.42 <15 3 <12 36 Cs-134 <10 95 <4 83 <3 37 Cs-134 <8 54 <1036 <4 91 Cs-137 <9 58 <4 85 <5 19 Cs-137 <7 82 <9 14 <7 26 Ba/La-140 <14 08 <6 65 <6 36 Ba/La-140 <11.73 <14 67 <1043 Ce-141 <14 22 <6 04 <6 67 Ce-141 <601 <1352 <11 54 Ce-144 <59 21 <25 23 <26 38 Ce-144 <38.01 <52 33 <44 65 Ra-226- 638 6+/-159 263 4+/-76 26 188 6+/-67 69 Ra-226 696 7+/-99 37 670 6+/-139 9 552+/-109 9 AciTh-228* 51 73+/-29 41 20.46+/-13 07 <17 13 Ac/Th-228- <28.98 110 6+/-29 29 118 8+/-20 84

• Indicates naturally occurring.

• • Indicates control location.

- 'Less than' values expressed as Critical Level (Lj). B-32

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2002 (pCi/Kg, wet i 1 sigma)

1. 94 IPEC Training Center (continued)

August September Y

1, r Common 4 *, , ,{<., . ,, t ,Comm -

ompn Radionuclide Ragweed' - Burdock Mullen Radlonucilde Ragweed, ' Burdock: :Muillen Be-7' 850 5+/-59 24 489 8+/-53.31 431 8+/-19 32 Be-7* 1832+/-84 02 781.1+/-48 8 828 2+/-47.12 K.40* 9705+/-228.1 8379+/-195 8 6221.6+/-73.7 K-40' 9945+/-242 6 7117+/-171 3 7074+/-144 9 Mn-54 <8 73 <7.06 <3 59 Mn-54 <9 04 <6 36 <6 03 Co-58 <6 99 <7.1 <3 65 Co-58 <8 27 <6 67 <5 55 Fe-59 <24 2 <22 25 <10 21 Fe-59 <21 72 <18 28 <16 19 Co-60 <9 58 <8 41 <3 87 Co-60 <9 6 <7 89 <6 16 Zn-65 <18 48 <18 53 <8 72 Zn-65 <20 99 <17 33 <8 59 Zr-95 <13 <128 <5 97 Zr-95 <1456 <11 07 <10.7 Nb-95 <7 6 <7 5 <3 68 Nb-95 <9.28 <6 5 <6 18 Ru-103 <6 97 <6.39 <3 49 Ru-103 <7.93 <6 28 <5 88 Ru-106 <85 82 <67.47 <39 74 Ru-106 <82 61 <61 74 <65 59 1-131 <8 41 <7.86 <4 65 1-131 <11 12 <78 <785 Cs-134 <8 77 <7.61 <2 46 Cs.134 <9 <6 83 <4 41 Cs-137 <7 63 <6.26 14.07+/-11.92 Cs.137 <7.78 <5 64 <6 Ba/La-140 <10 26 <8.92 <4 02 Ba/La-140 <12 15 <8 64 <6 87 Ce-141 <10 51 <9 24 <5 37 Ce-141 <10 69 <9 1 <9 44 Ce-144 <42 8 <40 23 <22 97 Ce-144 <44 63 <36 46 <38 92 Ra.226 435 6+/-122 3 467.7+/-110 5 311.7+/-37 6 Ra-226* 928 5+/-125 8 387 5+/-86 27 556 2+/-94 9 AclTh-228' <29 11 <27 41 48.78+/-8 57 Acrrh-228* 73 28+/-23 54 36 91+/-19 04 137 7+/-18 56 October Common Radlonudide rMuloImn Blttersweet ,' Burdock s Be-7* 1566+/-97 07 288 2+/-46 44 1370+/-67.01 K-40* 8415+/-274 7 3924+/-145 6 7058+/-180 6 Mn-54 <10 44 <7.28 <6 88 Co-58 <10 25 <7.22 <7 28 Fe-59 <30 45 <20 83 <19 08 Co-60 <13 58 <6 49 <8 03 Zn-65 <26 36 <18 75 <19 21 Zr-95 <19 25 <13 22 <11 36 Nb.95 <11 2 <7.61 <7 08 Ru-103 <9 7 <6 5 <7 47 Ru-106 <1056 <71 82 <71.52 1-131 <158 <8 91 <9 64 Cs-134 <11 08 <4 64 <7.37 Cs-137 <10 21 <7.07 <6 68 BalLa-140 <14 <1265 <11.28 Ce-141 <12 46 <9 33 <10 03 Ce-144 <50 55 <35 52 <39 76 Ra-226- 304 2+/-132 9 172 3+/-100 7 521 9+/-109 1 AcIrh-228* 69 31+/-31.53 107.4+/-21 27 48 32+/-21 01

• Indicates naturally occurring.

• • Indicates control location.

"*'Less than' values expressed as Critical Level (L,). B-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2002 (pCI[Kg, wet +/- 1 sigma)

1. 95 Meteorological Tower April May a - s a i a aai ,-sfaa y n-T- .,ste ,', iti.

, t1 .wRaig~oed>

Radlonuclide ThtiO a Ragw,,ed Mulleln i Radlonucide afi.Roods Ragweed Bittersweet Be-7* 818.3+/-48 5 354 6+/-31 76 613 7+/-44 43 Be <61.52 575 3+/-42 8 202 9+/-36 99 K-40* 6728+/-156 9 8884+/-1555 5235+/-140 4 K.40* 8030+/-194 7355+/-177.5 4996+/-148.9 Mn-54 <4.74 <5 17 <5 26 Mn-54 <7 22 <5 22 <6 14 Co-58 <4.83 <4 13 <5 08 Co-58 <7.31 <5 41 <5 91 Fe-59 <169 <17.44 <1586 Fe-59 <22.13 <1849 <17.42 Co-60 <4.89 <5 28 <6 51 Co-60 <8 83 <6 99 <6 42 Zn-65 <15 12 <11 8 <13 18 Zn-65 <20.33 <16 <15 13 Zr-95 <9.59 <8 32 <9 88 Zr-95 <13 04 <8 88 <11 04 Nb-95 <5.75 <4 68 <5 95 Nb-95 <7 59 <5 36 <5 88 Ru-103 <5.21 <4 31 <5 59 Ru-103 <7 28 <4 78 <5 93 Ru-106 <58 39 <45 06 <51 41 Ru-106 <69.19 <49 11 <65 51 1-131 <8.36 <7.49 <9 46 1-131 <7.94 <5 27 <5 94 Cs-134 <6 <4 61 <5 17 Cs-134 <5 14 <5 47 <6 36 Cs-137 <5 48 <4 11 <5 65 Cs-137 1 <6 72 <5 19 <5 96 Ba/La-140 <9.19 <6 87 <8 72 Ba/La-140 <11 03 <7.94 <7.37 Ce.141 <7.56 <6 49 <7.19 Ce-141 <9 53 <6 13 <7 53 Ce-144 <29 41 <24 43 <27.18 Ce-144 <41 36 <24 91 <31.9 Ra-226' 193 7+/-78 86 257.3+/-61 63 566 8+/-69 92 Ra-226* 460 5+/-106 1 266 4+/-75 08 235 1+/-8468 Ac/Th-228* 47 82+/-16 47 27 27+/-12 9 <19 04 Acrrh-228* 67 63+/-20 06 52 8+/-18 3 56.35+/-1976 June July Radionucide Ragweed Grape Leaves Bittersweet n Radionucide - Ragweed a Grape Leaves -eBittersweet Be-7* 1135+/-46 03 681.2+/-51 63 315 8+/-45 32 Be-7* 357.4+/-60 13 325 4+/-50 03 236 8+/-46 81 K 9599+/-156 9 5091+/-164 8 4848+/-155 4 K.40* 9357+/-262 6 4913+/-161.5 4861+/-157 4 Mn-54 <5 61 <6 23 <7.12 Mn-54 <8 85 <6 77 <6 87 Co-58 <5 1 <6 34 <6 53 Co-58 <9 56 <7.18 <6 28 Fe-59 <14 33 <16 22 <18 17 Fe-59 <26 43 <20 77 <20 99 Co-60 <5.79 <7 11 <7 71 Co-60 <10.19 <7.04 <7 29 Zn-65 <8.35 <17.79 <1595 Zn-65 <22.45 <18 25 <1763 Zr-95 <10 05 <13 05 <11 34 Zr-95 <16 42 <11 8 <12 35 Nb-95 <5.41 <5 88 <7.31 Nb-95 <9 25 <7 44 <7.42 Ru-103 <4 9 <6 22 <6 43 Ru-103 <8 55 <7 29 <7.12 Ru-106 <57.96 <72 61 <68 36 Ru-106 <74 8 <76 84 <73 8 1-131 <6.53 <6 88 <7 03 1-131 <13.76 <10 78 <10 79 Cs-134 <3 87 <7.49 <6 57 Cs-134 <8 87 <7.21 <7 84 Cs-137 <5.35 <7.03 <6 25 Cs-137 <8 38 <6 69 <5 87 Ba/La-140 <5 92 <8 98 <9 23 BalLa-140 <12 52 <9 49 <10 41 Ce-141 <7 94 <9 <8 43 Ce-141 <9 99 <9 35 <9 26 Ce-144 <34 01 <35 35 <34 22 Ce-144 <40 57 <37.13 <39 04 Ra-226 386 9+/-90.25 227.9+/-97 28 666+/-97.84 Ra-226- 260 4+/-109 7 394 4+/-87.46 371 3+/-90 39 AcrTh-228* 80 15+/-16.34 53 4+/-21 17 35 3+/-17.77 AcIrrh-2281 <35 4 <24 43 <2542

• Indicates naturally occumng.

• • Indicates control location.

- 'Less than' values expressed as Critical Level (Lc). B-34

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2002 (pCiIKg, wet i 1 sigma)

1. 95 Meteorological Tower (continued)

August September

.Grape ii immon Radlonucilde Ragweed- Grape Leaves Muflen :Radionucilde Ragweed Leaves  ? uMulilen Be 728 9+/-66 26 416 4+/-46 01 630 6+/-65.67 Be-7* 1088+/-80 34 580 1+/-65 62 1137+/-85 35 K-40^ 9850+/-242 5 5829+/-140 6 7735+/-232 3 K 7172+/-237.1 6335+/-205 6 8435+/-262 8 Mn-54 <9 67 <6 61 <8.44 Mn-54 <9 51 <7.63 <12 25 Co-58 <9 65 <6 29 <8.95 Co-58 <9 37 <8 07 <9.72 Fe-59 <25 19 <17.37 <27.33 Fe-59 <24 05 <23 16 <33 81 Co-60 <10 72 <6 8 <10 92 Co-60 <10 03 <8 61 <10 81 Zn-65 <25 91 <8 96 <24 61 Zn-65 <23 46 <22 54 <27 46 Zr-95 <16 32 <10 99 <16 23 Zr-95 <16 71 <15 74 <17 93 Nb-95 <9 94 <6 31 <8.43 Nb-95 <10 36 <8 81 <11 1 Ru-103 <9 03 <6 04 <8.57 Ru-103 <7.73 <8 03 <10 28 Ru-106 <91.14 <68 12 <101 9 Ru-106 <91 65 <89 28 <118 3 1-131 <10 17 <7 46 <9.78 1-131 <11 52 <945 <1344 Cs-134 <9 81 <4 76 <10 69 Cs-134 <10 26 <8 95 <12.73 Cs-137 <8 2 <6 46 <8.54 Cs-137 <8 06 <8 65 <11 94 Ba/La-140 <10 94 <8 78 <9.24 Ba/La-140 <11 48 <9 83 <15 91 Ce-141 <12 61 <9 43 <11 03 Ce-141 <9 97 <10 93 <15 36 Ce-144 <50 82 <40 62 <4709 Ce-144 <42 2 <43 77 <60 3 Ra-226' 896 3+/-144 9 800 4+/-116 1 3208L+/-141.8 Ra-226' 390 8+/-115 5 387 7+/-115 5 466 4+/-156 AcITh-228* <33 21 91+/-18 42 <30 24 Acrrh-228* 53+/-30 51 88 39+/-27 83 53 43+/-30.24 October Radionucilde Bittersweet Grape Leaves Cormon Mullien Be-7' 676 4+/-58 49 1030+/-48 71 1495+/-73 79 K 5835+/-168 2 4277+/-107.7 7262+/-205 6 Mn-54 <7.49 <4 99 <7.24 Co-58 <7 09 <5 31 <7.74 Fe-59 <20 97 <14 27 <29 04 Co-60 <7.7 <5 53 <9.53 Zn-65 <19 09 <6 8 <18 86 Zr-95 <13 84 <9 26 <14 11 Nb-95 <8 16 <5 75 <9 5 Ru-103 <7 34 <5 41 <7.71 Ru-106 <65 2 <55 44 <85 39 1-131 <9 58 <7 88 <11.17 Cs-134 <7 19 <3 71 <7.81 Cs-137 <6 94 <5 32 <6.31 BalLa-140 <9 39 <7 33 <12 75 Ce-141 <10.5 <8 03 <6.36 Ce-144 <41 64 <33 84 <40 96 Ra-226* 473 7+/-116.1 418 6+/-89 53 713 2+/-120 1 Acrrh-228 129 1+/-24 04 84 39+/-15 47 <27 32

• Indicates naturally occumng

• • Indicates control location.

- "Less than' values expressed as Critical Level (Lj) B-35

TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES - 2002 (pCi/Kg, wet +/- 1 sigma)

1. 23 ROSETON icontrol)

Radjlonudllde, ' 612I 02 Eel 8119102 Be-7' <83 17 <243.9 K-40* 4541+/-220 1 6855+/-276 9 Mn-54 <11.8 <16 93 Co-58 <10 12 <23 06 Fe-59 <32 96 <92 51 Co-60 <12 69 <17.68 Zn-65 <23 87 <43 72 Zr-95 <20 01 <47.87 Nb-95 <11.19 <41 94 Ru-103 <11 93 <4067 Ru-106 <103 4 <194 5 1-131 <17.7 <1062 Cs-134 <8 49 <16 46 Cs-137 <9 35 <16 97 Ba/La-140 <15 14 <270 3 Ce-141 <14 07 <58 56 Ce-144 <54 32 <100 9 Ra-226* 822.7+/-156 1 1425+/-277.8 Ac/Th-228* <36.74 115.9+/-48 3

1. 25 DOWNSTREAM (HUDSON RIVER)

(Idicator)

RlouPorc h White Porch

________ _ ,6/13/02 ,M, 8121102 9116/02 Be-7* <91 04 <228 6 <125 7 K-40* 4188+/-204 8 4811+/-290 4 4892+/-239 9 Mn-54 <9 01 <16 22 <12 49 Co-58 <11 8 <24 39 <1075 Fe-59 <29 13 <97 37 <44 85 Co-60 <11.74 <1393 <11 28 Zn-65 <29 <42 39 <29 63 Zr-95 <18 95 <42 17 <27 61 Nb-95 <11 01 <37 07 <17 61 Ru-103 <11.77 <30 68 <15 27 Ru-106 <103.3 <202 5 <135 9 1-131 <16 95 <952 3 <82 41 Cs-134 <10 07 <17 72 <1288 Cs-137 <1073 <1705 <11.74 Ba/La-i40 <20 63 <202 <40 7 Ce-141 <15 21 <50 69 <21 97 Ce-144 <55 55 <91 72 <62 54 Ra-226* 689.9+/-161 2 463 2+/-242 864.1+/-182.1 Ac/Th-228* <40 24 <61 7 <42 28

• Indicates naturally occurring B-36

TABLE B-16 ANNUAL

SUMMARY

, NON-RETS SAMPLE RESULTS 2002

- - INDICATOR LOCATIONS - CONTROL LOCATIONS - HISTORICAL AVG VALUE*

AVG. OF HiGHEST" LOWEST NO. OF TOTAL AVG. OF HIGHEST' LOWEST- NO. OF TOTAL SAMPLEMEDIUMR*INUCLID- POSrnVE' POSmVE POSTITIVE POSITIVE NO. OF- POSITIVE POSITIVE POSmVE POSITIVE NO. OF

,-UNITS)

_ _, _DETECTED1

_ __ __ LLD-

___ SAMPLES SAMPLE SAMPLE- SAMPLES SAMPLES SAMPLES SAMPLE -SAMPLE SAMPLES'SAMPLES INDICATOR -CONTROL .

AQUATIC VEGETATION (pClkg - WET) Co-60 NONE <'b, <bL, < L, 0 4 <bL <bL < 0 9 198 1-131 100 71 71 7.1 4 176 176 176 1 9 114 33 1 Cs-134 100 <'L <bL <9L5 0 4 <bL <Le < 0 9 <29 <73 Cs-137 100 24 2 33 9 53 4 4 635 734 565 3 9 29 2 70 3 BOTTOM SEDIMENT (pCi/kg - DRY) Co-60 NONE <L <bL <bL 0 6 <L <bc <bL 0 2 1312 <b Cs-134 150 483 539 428 2 6 <bc <bL <bC 0 2 502 397--

Cs-137 180 493 791 200 6 6 59 3 59 3 59 3 1 2 726 131 SOIL (pCi/kg - DRY) Co-60 NONE <b <bL <bc 0 2 <bL <b, <bL 0 1 <bL <bL Cs-134 150 <bL <bL <bL 0 2 <bC <bL <bL 0 1 <bc <L, Cs-137 180 <L <bL <bL 0 2 <L <bL <bc 0 1 141 75.7 PRECIPITATION (pC#L) H-3 2000 < LLD < LLD < LLD 0 4 < LLD < LLD < LLD 0 4 254 341 Co-60 15 <bL <bL <bC 0 4 <L <bC <bC 0 4 <L <

Cs-134 15 <bL <bL <bc 0 4 <bL <bL <bC 0 4 <bL <bL Cs-137 18 <bL <bL <bL 0 4 <bL <bL <bL 0 4 <bL <bL SPECIAL WATER (pCiL) H-3 2000 < LLD < LLD < LLD 0 25 NA NA NA NA NA 167 NA Co-60 15 <L <bC <bL 0 33 NA NA NA NA NA <L <bC Cs-134 15 <b <bc <bc 0 33 NA NA NA NA NA < C <bL Cs-137 18 <bc <bc <bc 0 33 NA NA NA NA NA <bL <bL I Average of positive values for 1991 - 2001

• - Detected at control location, 1992, 1999, AND 2001.

NA - Data not available Lc - Cnrtical Level, which is less than the required Lower Limit of Detection (LLD), unless otherwise noted B-37

TABLE B.17 MILCH ANIMAL CENSUS 2002 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

B-38

TABLE B-18 LAND USE CENSUS 2002

.;1Sectorle Location of Neare t

- ~Residence 1- N 1.14 Ayers Road, Jones Point 2 - NNE 1.95 St. Mary's School, Peekskill 3 - NE 1.21 South Street, Peekskill 4 - ENE I South Street, Peekskill 5-E 0.47 Bleakley Avenue, Buchanan 6 - ESE 0.39 Broadway, Buchanan 7- SE 7 - S 0.73 0.73Buchanan Westchester Avenue, 8 - SSE 8 - SS 0.73 0.73Buchanan Westchester Avenue, 9-S 0.71 Broadway, Verplanck St. Partricks Rectory, 10 - SSW 0.97 Verplanck 11 - SW 1.8 Elm Avenue, Tomkins Cove West Shore Drive South, 12 - WSW 1.36 Tomkins Cove West Shore Drive North, 13 - W 1.21 Tomkins Cove 14 - WNW 1.09 Route 9W, Tomkins Cove 15 - NW 1.04 Route 9W, Tomkins Cove 16 - NNW 0.98 Jones Point B-39

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 2002 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.

Averaging only the positive values in these tables can result in a biased high value, especially, when the radionuclide is detected in only one or two quarters for the year. This bias can be seen in Table C-3 and Figure C-3. A comparison between Hudson River average tritium values for 2002 and 1992 would indicate a 28%

increase in 2002 for average tritium detected; however, when the maximum tritium values are compared there is only a 4% difference in values.

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

1992 to 2002 C-2

FIGURE C-1 DIRECT RADIATION 40 - 1992 to 2002 35 -

30 25 t

a 20 E

15 -7 10 N 5-0-

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1992 to 2002 (pCi/m3 )

GrossCBeta. Cs137 AlRS Control AIRES Control Year Indicator' Cnr Indicator' Loctin Locations Locations 1992 0.02 0.02 1993 0.02 0.02 1994 0.02 0.01 1995 0.01 0.01 1996 0.01 0.01 1997 0.01 0.01 1998 0.02 0.01 1999 0.02 0.01 2000 0.01 0.01 2001 0.02 0.02 2002 0.02 0.02 <1,L Historical Averag 0.02 0.01 <L <

1992-2001 Critical Level (Lj) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1992 to 2002 0.05 0.04 0.03 C-,

0.02 0.01 0.00 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002

• Includes RETS and non-RETS indicator locations.

Gross Beta RETS required LLD = 0.01 pCIIm 3 C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1992 to 2002 (pCi/L)

Ttum(-3) Cs- 37, Year Inlet Inet I Dischae iischargec 1992 170 437 <LLD <LLD 1993 240 270 <LLD <LLD 1994 230 280 <LLD <LLD 1995 370 270 <LLD <LLD 1996 < LLD 280 <LLD <LLD 1997 <LLD 430 <LLD <LLD 1998 <LLD 220 <LLD <LLD 1999 191 318 <LLD <LLD 2000 190 267 <LLD <LLD 2001 <LLD 323 <LLD <LLD 2002 432 562 <LLD <LLD Historical 232 310 <LLD <LLD

<LLD is less than the RETS required LLD, unless otherwise noted.

C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1992 to 2002 9nnn 180 N Inlet (H-3) 1800 El Discharge (H-3) 1600 -

1400 -

1200 -

Z5 1000 -

c0 800 -

600 -

400 -

RR.'. ... ... ......

200 - ... ... ......

... I ......

I... ...

0- 1\M..'.1

... .. '.'.1' i X.,

I.I .'.'. oe.

r1 - as____. *,* -,.- . _

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 Tritium RETS required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1992 to 2002 (pCilL)

'Year r~*iizm (H-3) Cs-I37 1992 < LLD < Le 1993 < LLD < Lc 1994 < LLD <k 1995 < LLD <k 1996 < LLD < Lc 1997 < LLD < Lc 1998 < LLD <L 1999 < LLD < Lc 2000 < LLD < Lc 2001 < LLD < Lc 2002 < LLD < Lc HistoricalFAverage

, 99-01 j

i< LLD < Lc

<LLD is less than the RETS required LLD, unless otherwise noted.

C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1992 to 2002 2000 1800- N Camp Field Reservior (H-3) 1600-1400 -

1200 -

-j A, 1000-NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR HISTORY 800 -

600 400-200 0

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 Tritium RETS required LLD = 2000 pCi/L C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1992 - 2002 (pCi/Kg, dry) ar :

bAadic soeX- l A4'

• a Cs- 1237 ; I--

. -Year P ndicator EmI; ISjCnT 3rnol Indicator .Con trole 1992 56 < Le 207 433 1993 46 < Le 137 135 1994 < Lc < Le 485 516 1995 < Lc < Le 176 335 1996 < Lc < Le 173 453 1997 < Lc < Le 203 340 1998 < Lc < Le 143 < Lc 1999 46 < Le 200 238 2000 58 < Le 179 231 2001 45 < Le 230 427 2002 < Le <L 221 238 Historical A A <L 214 345 I1992-20 01 5 L 1 4 Critical Level (La) 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 1500 1400 1300 1200 1100 1000 900 a 800 o 700 0.

600 500 400 300 200 100 0

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 Cs-134 RETS required LLD = 150 pCi/Kg, dry Cs-137 RETS required LLD = 175 pCi/Kg, dry C-1I

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1992 to 2002 (pCi/Kg, wet)

's-137, Year, Idicator/ ,i' Control.

1992 28 < Lc 1993 44 18 1994 22 < Lc 1995 28 < Lc 1996 17 < Lc 1997 < Lc < Lc 1998 < Lc < Lc 1999 < Lc 27 2000 28 < Lc 2001 7 < Lc 2002 14 15 2 2HistoricaL3Aerage i992-2001 Critical Level (Lc) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1992 to 2002 100 -

80 -

60 -

C) l I 4-1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 RETS required LLD = 80 pCi/Kg, wet C-1 3

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 1992 to 2002 (pCilKg, wet)

Cs-137-Year ' indcator Control-; ,,

1992 < Lc < Lc 1993 23 < Lc 1994 < Lc < Le 1995 16 < Lc 1996 ' Lc < Lc 1997 < Lc < Lc 1998 < Lc < Lc 1999 < Lc < Lc 2000 < Lc < Lc 2001 < Lc < Lc 2002 < L, < Lc HistoricaliAverage 20

- - . o,

. I I 1992-2001- `,

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

<Lc indicates no positive values above sample critical level.

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1992 to 2002 200 -

180 - N Indicator (Cs-1 37)

E Control (Cs-1 37) 160 140 120 80 60 40 20 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 Cs-137 RETS required LLD = 150 pCi/Kg, wet C-15

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX D D.1 PROGRAM DESCRIPTION Radiological Effluent Technical Specification (RETS) and Radiological Effluent Controls (RECS) require that each licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and forwhich 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 Technical Specification 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 Energy's Environmental Measurements Laboratory (EML) in New York City.

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

In addition to the Analytics Program, the JAF Environmental Laboratory participated in the Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP). EML supplies sample media as blind sample spikes to approximately 127 laboratories worldwide. These samples, containing a spiked amount of low level activity, are analyzed using standard laboratory procedures.

The results are submitted to the Environmental Measurements Laboratory for statistical evaluation. Reports are provided to each participating laboratory, which provide an evaluation of the laboratory's performance.

During 2002, tritium analyses for the JAF Environmental Laboratory were performed by Framatome, ANP.

D-1

D.2 PROGRAM SCHEDULE TABLE D-1 2002 QA Program Schedule I Sample Provider.

Sample Media . Laborato rAalysist AnalcsE EML Yearly Total Water Gross Beta 0 2 2 Water Trtium 1 2 3 Water 1-131 2 0 2 Water Mixed Gamma 2 2 4 Air Gross Beta 2 2 4 Air 1-131 2 0 2 Air Mixed Gamma 2 2 4 Milk 1-131 2 0 2 Milk Mixed Gamma 2 0 2 Soil Mixed Gamma 1 0 1 Vegetation Mixed Gamma 1 0 1 OTAL SAMPLE INVENTORYa, 17 10 27 D.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The evaluation method for the QA sample results is dependent on the supplier of the sample. The sample evaluation methods are discussed below.

D.3.1 ANALYTICS SAMPLE RESULTS Samples provided by Analytics are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known Value (reference result).

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 D-2

Using the appropriate row under the Error Resolution column in Table D-2 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

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

TABLE D-2 Ratio of Agreement

-ERROR RESOLUTION !RATIO OF AGREEMENT

<3 0.4 to 2.5 3.1 to 7.5 0.5 to 2.0 7.6 to 15.5 0.6 to 1.66 15.6 to 50.5 0.75 to 1.33 50.6 to 200 0.8 to 1.25

>200 0.85 to 1.18 Again, this acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in JAFNPP procedure DVP-04.01 and was taken from the Criteria of Comparing Analytical Results (USNRC) and Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). The NRC method generally results in an acceptance range of approximately

+/-25% of the Known Value when applied to sample results from the Analytics Inc. Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a nonconformity report when results are unacceptable.

D.3.2 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

The laboratory's analytical performance is evaluated by EML based on the historical analytical capabilities for individual analyte/matrix pairs.

The statistical criteria for Acceptable Performance, "A", has been chosen by EML to be between the 15th and 85th percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements. The Acceptable With Warninq criteria, "W", is between the 5th and 15th percentile and between the 85th and 95th percentile. In other words, the middle 70% of all reported values are acceptable, while the other 5th-15th (10%) and 85th-95th percentiles (10%) are in the warning area. The Not Acceptable criteria, "N", is established at less than the 5th percentile D-3

and greater than the 95th percentile, that is, the outer 10% of the historical data. Using five years worth of historical analytical data, the EML, determined performance results using the percentile criteria summarized below:

Result Cumulative Normalized Distribution Acceptable ("A") 15% - 85%

Acceptable with Warning ("W") 5% - 15% or 85% - 95%

Not Acceptable ("N") <5% or >95%

D.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table D-7.

D.4.1 ANALYTICS QA SAMPLES RESULTS Seventeen QA blind spike samples were analyzed as part of Analytics' 2002 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

• Soil, Mixed Gamma Emitters

• Milk, 1-131 Mixed Gamma Emitters

• Vegetation, Mixed Gamma Emitters The JAF Environmental Laboratory performed 79 individual analysis on the seventeen QA samples. Of the 79 analysis performed, 77 were in agreement using the NRC acceptance criteria for a 97.5% agreement ratio.

Sample non-conformities are discussed in Section D.4.2.

D-4

D.4.2 ANALYTICS SAMPLE NONCONFORMITIES D.4.2.1 Analytics Sample E-3286-05, Cr-51 in Milk Nonconformity No. 02-09 A spiked mixed gamma in milk sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified. Eight of the nine radionuclides were quantified within the acceptable range. The results for Cr-51 were determined to be outside the QA Acceptance Criteria.

The milk sample was analyzed on three different detectors with the mean Cr-51 results reported as 176.7 pCi/I. The known results for the sample was 227 pCi/l as determined by the supplier.

An evaluation of the Cr-51 result was performed. The spectrum and peak search results were examined with no abnormalities identified. Cr-51 decays by electron capture with a 27.7 day half-life and a gamma ray energy of 320 KeV with a yield of 9.8%. No secondary gamma energies are produced in the Cr-51 decay scheme. This low gamma energy yield and short half-life will result in very low net counts for samples containing environmental levels of Cr-51. The average net count rate of the three analyses ranged from a high of 1.9 counts per minute to a low of 0.68 counts per minute. One of the three reported results was 244 pCi/I and resulted in an agreement when compared to the known of 227 with a ratio of 1.07. This result had an associated counting error of 13.1 %.

The remaining two counts had ratios of 0.55 and 0.71 with high associated counting errors of 29.3% and 21.2% respectively.

The combination of the following; low sample activity, very small net count rate, short half-life, low gamma energy, and small gamma yield, resulted in an inaccurate sample result.

The wide range of the associated counting errors demonstrates the low confidence level in the reported results. The poor analytical results for this sample is not routine and does not indicate a programmatic deficiency in the analysis of Cr-51 in milk samples or other environmental media. Confidence in the accurate analysis of Cr-51 can be demonstrated by other Cr-51 analytical results, both in the sample results for the 2002 QA program and historical Cr-51 QA results. The Cr-51 results for the other Quality Assurance samples analyzed as part of the D-5

2002 Interlaboratory Comparison Program were all acceptable and are summarized below:

TABLE D-3 2002 Cr-51 Results SampleD 'Mediuml JAF Lab Ratio-"

E-3051-05 WATER pCi/liter 234+/-20 198+/-10 1.18 E-3284-05 WATER pCi/liter 324+/-23 304+/-15 1.07 E-3052-05 FILTER pCi/filter 187+/-13 203+/-10 0.92 E-3285-05 FILTER pCi/filter 157+/-13 141+/-7 1.11 E-3215-05 MILK pCi/liter 239+/-19 235+/-12 1.02 E-3218-05 VEGETATION pCi/kg 408+/-23 403+/-20 1.01 E-3216-05 SOIL pCi/kg 370+75 318+16 1.16 Mean Ratio 1.07 A review of historical QA data for 2001 was also performed to determine if this is a recurring systematic error or bias. In 2001, eleven QA samples were analyzed which contained Cr-51. The mean ratio for these samples relative to the known (reference) value is 98.5. There were two Cr-51 nonconformities in the 2001 Interlaboratory Comparison Program and were determined not to be systematic or programmatic errors. The historic Cr-51 nonconformities were a low percentage of the overall gamma spectroscopy QA program and have been determined to be the result of the low sample activity and low gamma yields for Cr-51 in the spiked samples. Analytical methods and system calibrations are not the cause of this nonconformity, based on the accurate results achieved for the analysis of the other eight radionuclides present in the sample. No corrective actions were implemented as a result of this nonconformity.

D.4.2.2 Analytics Sample E-3285-05 Nonconformity No. 02-08, Air Particulate Gamma Emitters The gamma spectral analysis of sample E-3285-05 resulted in the quantification of nine radionuclides. Results for eight of the identified radionuclides were in agreement with the reference value and one measurement was in disagreement. The Fe-59 results had a calculated ration of 1.29, which places the results outside the acceptable limit. The sample ratio of 1.29 demonstrates that the Fe-59 sample result is biased high. An evaluation of the Fe-59 result was performed. Fe-59 D-6

concentrations were detected in three of the three analysis reported for this sample. The spectrum and peak search results were examined with no abnormalities identified. Fe-59 decays with a 44.5 day half-life with two gamma ray energies of 1099 KeV and 1291 KeV with yields of 57% and 43%

respectively. Fe-59 concentrations were identified at both the 1099 KeV and 1291 KeV peaks in all three analysis with the following results.

TABLE D-4 Nonconformity No. 02-08 Fe-59 Results it > , s 9nc~ntrat:L !r K PC i lfilter : _____________

Detector Peak I Peak 2 Mean Number 1099 KeV 1291 KeV Concentration 1 69.9 79.3 73.5 2 68.5 61.4 65.4 8 74.7 73.0 73.9 Men 71.0 71.2 70.9 1l29. _ 1 0 _ 1-_'.2I'9"_X_ i_.

ii>wfRatio a<> r 1.29 1.30 1.29 There were no significant differences for the activity that was measured at either of the two Fe-59 peaks. The number of total counts measured in both of these peaks maybe biased high due to coincidence counting as the result of other radionuclides that are present inthe sample. The relatively low gamma yield and low activity of 55 pCi/Kg may have also contributed to the inaccuracy of this sample result.

Fe-59 was measured in seven other samples analyzed as part of the 2002 Interlaboratory Comparison Program. All of these samples were in agreement with the reference laboratory with a mean agreement ration of 1.09. This mean ratio of greater than 1.09 would indicated that these samples were biased high and the bias was the possible result of coincidence counting from other radionuclides in the sample. The amount of biased experienced in most Interlaboratory Comparison Program samples due to coincidence counting has been limited to less than 20 percent and has resulted in sample results which were statistically acceptable when compared to the reference value.

Changes to the radionuclide librarywere made in2001 to direct D-7

the gamma spectroscopy software to calculate the mean concentration value based on both the 1099 KeV and 1291 KeV peaks. In most gamma spectrums, this has reduced the effect of the coincidence count on the Fe-59 analytical results as the 1291 KeV peak may be less affected by the coincidence counting inmultiple radionuclide samples. No corrective actions were implemented as a result of this nonconformity.

D.4.3 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

In 2002, JAF Environmental Laboratory participated in both the EML Quality Assessment Programs, QAP-56 and QAP-57. Sample sets consisted of the following sample media:

• Water - Gross Beta/Mixed Gamma Emitters

• Water - Tritium

• Air Particulate Filter- Mixed Gamma Emitters/Gross Beta A total of 10 samples containing 18 individual radionuclides were evaluated for the samples included in QAP-56 and QAP-57. Using the EML acceptance criteria, 17 of 18 radionuclides analyses (94.4%) were evaluated to be acceptable. Results for the EML Cross Check Program can be viewed on-line at www.eml.doe.cov. A summary of the JAF Environmental Laboratory results is as follows:

TABLE D-5 JAF Environmental Lab Summary Matrix tAalyses Total Acceptable ' Not Acceptable t Air 10 10 0 Water 8 7 1 Total 18 17 1 Percentage j 94.4% 5.6%

D-8

D.4.3.1 EML Sample QAP-56, Cs-134 in Water Nonconformity No. 02-02 The QAP-56 gamma in water sample contained three radionuclides for evaluation; Cs-I 37, Cs-I 34 and Co-60. Two of the three radionuclides present, Co-60 and Cs-137, were quantified with agreement ratios of 1.02 and 0.99, respectively.

The JAF laboratory reported a Cs-1 34 result of 2.6 +/- 0.5 Bq/L (70.3 pCi/1). The EML known activity was reported as 3.357 Bq/L (90.74 pCi/L). The agreement ratio for the Cs-I 34 analysis was 0.77, which placed the result outside the acceptable range. The cause of the nonconformity is attributed to several factors. The concentration of Cs-134 in the sample was very small at 3.36 Bq/L and resulted in a one sigma counting error of approximately 20%. By comparison the one sigma counting errors for the Co-60 result was 1.0% and the one sigma counting error for the Cs-1 37 result was 1.3%. The high associated counting error was the result of the low count rate measured for the Cs-134 peak and resulted in poor counting statistics. The measurement of the Cs-134 concentration in this sample was further complicated by the presence of an interference peak at 609 KeV. The combination of the low concentration and interference from 609 KeV peak were both contributing factors in the non-conforming result. A review of the EML summary statistics for this sample showed a relatively high failure or nonconformity rate for other laboratories participating in this sample comparison. Their statistics are as follows:

TABLE D-6 EML Summary QAP-56 Cs-134 in Water Isotope: NoLabs -,in,jnotin

/with

___ lxRepoting

, Agreement Warning -Agreement Cs-I 34 116 60.3 23.3 16.40 Cs-137 146 87.0 11.0 2.10 As the table shows for the 116 laboratories reporting results, only 60.3% were in agreement with the known value. 16.4% of the participating laboratories were not in agreement and 23.3%

of laboratories reporting results were in the warning range for the reported results. An additional 30 laboratories reported no results for the Cs-134 concentration. By comparison, the statistics for the Cs-137 concentration showed a failure rate of D-9

only 2.1% and acceptable results for 87% of the results reported for the study.

The Cs-134 results reported for the 2002 QAP-57 study, conducted in the second half of the year, were acceptable with an agreement ratio of 1.0. Cs-1 34 was measured in nine other comparison samples analyzed as part of the 2002 Interlaboratory Comparison Program. The mean ratio for all the reported results was 0.96 and there were no nonconformities.

These results demonstrate that there is no programmatic or systematic error inherent to the analyses of Cs-134 in environmental sample medium. No corrective action was implemented as a result of this nonconformity.

D-10

TABLE D-7 INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pCilfilter)

~J O I V ~ E R 27.5+/-1.3 25+/-1 1.04, A 06/13/02 E-3214-05 AIR GROSS BETA 24.8+/-1.3 pCi/filter 25.9+/-1.3 Mean = 26.1+/-0.8 12/05/02 E-3467-05 AIR GROSS BETA 114.7+/-1.2 127+/-6 0.90, A pCi/filter 114.3+/-1.2 113.1+/-1.2 Mean = 114.0+/-0.7 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-10

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (pCi/liter) vv I-E I9c pCi/liter 9880+/-140 10130+/-140 Mean = 10030+/-81 I i (1) Results reported as activity +/- 1 sigma. Sample Analyzed by Framatome, ANP.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Samples provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-11

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Iodine Analysis of Water, Air and Milk WATER 58.5+/-1.6 pCi/liter 1-131** 57.6+/-1.8 60.9+/-1.2 Mean = 59.0+/-0.9 06/13/02 E-3217-05 AIR 1-131 80.2+/-7.4 93+/-5 1.06, A pCilcc 104.0+/-8.1 112.0+/-8.5 Mean = 98.7+/-4.6 06/13/02 E-3215-05 MILK 75.8+/-1.0 87+/-4 0.90, A pCi/liter 1-131** 80.4+/-1.2 76.8+/-1.3 Mean = 77.7+/-0.7 09/12/02 E-3287-05 AIR 1-131 84.4+/-7.1 81+/-4 1.01, A pCi/cc 78.8+/-8.8 83.2+/-7.0 Mean = 82.4+/-4.4 09/12/02 E-3284-05 1-131** 76.8+/-1.2 79+/-4 0.95, A WATER 72.6+/-1.2 pCi/liter 75.3+/-1.1 Mean = 74.9+/-0.7 09/12/02 E-3286-05 1-131** 69.8+/-1.5 80+/-4 0.90, A MILK 73.8+/-1.3 pCi/liter 72.1+/-1.5 Mean = 71.9+/-0.8 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Samples provided by Analytics, Inc.

(**) Result determined by Resin Extraction/Gamma Spectral Analysis.

(A) Evaluation Results, Acceptable.

D-12

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (pCi/liter) 248.0+/-9.5 03/14/02 E-3051-05 WATER 251.0+/-8.3 pCi/liter 249.0+/-8.3 Mean = 249.0+/-5.0 Cr-51 222.0+/-35.5 198+/-10 1.18,A 249.0+/-35.6 232.0+/-33.4 Mean = 234.3+/-20.1 Cs-1 34 80.8+/-5.1 91+/-5 0.89, A 82.6+/-4.3 79.1+/-4.3 Mean = 80.8+/-2.6 Cs-1 37 184.0+/-6.6 197+/-10 0.94, A 183.0+/-6.4 191.0+/-6.4 Mean = 186.0+/-3.7 Mn-54 183.0+/-6.8 166+/-8 1.08, A 172.0+/-6.4 185.0+/-6.4 Mean = 180.0+/-3.8 Fe-59 91.4+/-7.0 86+/-4 1.13,A 110.0+/-6.7 89.8+/-6.1 Mean = 97.1+/-3.8 Zn-65 160.0+/-11.1 164+/-8 1.04,A 182.0+/-9.9 167.0+/-10.6 Mean = 169.7+/-6.1 Co-60 109.0+/-4.3 117+/-6 0.97, A 124.0+/-4.3 110.0+/-4.0 I

Mean = 114.3+/-2.4 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-13

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (pCilliter)

Z3iU.U+/-i.

pCi/liter 221.0+/-7.6 224.0+/-9.7 Mean = 225.0+/-5.1 Cr-51 321.0+/-38.1 304+/-15 1.07, A 264.0+/-34.9 389.0+/-46.1 Mean = 324.7+/-23.1 Cs-1 34 172.0+/-6.9 176+/-9 0.97, A 171.0+/-6.4 167.0+/-7.9 Mean = 170.0+/-4.1 Cs-1 37 150.0+/-6.4 169+/-8 0.98, A 171.0+/-6.2 174.0+/-7.9 Mean = 165.0+/-4.0 Mn-54 208.0+/-7.1 204+/-10 1.07, A 217.0+/-7.2 232.0+/-9.1 Mean = 219.0+/-4.5 Fe-59 120.0+/-7.0 119+/-6 1.07, A 133.0+/-7.1 127.0+/-8.8 Mean = 126.7+/-4.5 Zn-65 271.0+/-13.1 251+/-13 1.04, A 272.0+/-12.8 242.0+/-15.9 Mean = 261.7+/-8.1 Co-60 191.0+/-5.3 199+/-10 0.95, A 185.0+/-5.3 191.0+/-6.6 Mean = 189.0+/-3.3 Co-58 130.0+/-6.2 130+/-7 1.02, A 139.0+/-6.1 130.0+/-8.0 h i Mean = 133.0+/-3.9 i I (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-14

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

FILTER pCi/filter 226.0+/-5.6 236.0+/-6.5 Mean = 232.0+/-3.5 Cr-51 186.0+/-22.2 203+/-10 0.92, A 217.0+/-22.3 158.0+/-24.2 Mean = 187.0+/-13.2 Cs-1 34 75.7+/-4.7 93+/-5 0.89, A 93.5+/-4.9 80.5+/-5.7 Mean = 83.2+/-2.9 Cs-1 37 205.0+/-6.4 202+/-10 1.00, A 204.0+/-6.4 193.0+/-7.3 Mean = 200.7+/-3.9 Mn-54 175.0+/-6.3 170+/-9 1.04, A 178.0+/-6.5 178.0+/-7.6 Mean = 177.0+/-4.0 Fe-59 93.9+/-6.5 88+/-4 1.11, A 98.9+/-6.9 101.0+/-7.9 Mean = 97.9+/-4.1 Zn-65 178.0+/-11.1 168+/-8 1.02, A 169.0+/-11.2 167.0+/-12.9 Mean = 171.3+/-6.8 Co-60 113.0+/-4.3 120+/-6 0.98, A 120.0+/-4.6 121.0+/-5.3

.1. 1 Mean = 118.0+/-2.7 &

(1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-15

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCilfilter)

FILTER 109.0+/-4.2 pCi/filter 104.0+/-4.3 109.0+/-4.1 Mean = 107.3+/-2.4 Cr-51 159.0+/-21.4 141+/-7 1.11, A 175.0+/-22.5 137.0+/-21.3 Mean = 157.0+/-12.6 Cs-1 34 82.8+/-5.0 82+/-4 1.02, A 82.60+/-5.2 87.50+/-4.9 Mean = 84.3+/-2.9 Cs-137 92.2+/-4.7 79+/-4 1.16, A 91.2+/-5.0 91.2+/-4.6 Mean = 91.5+/-2.8 Mn-54 114.0+/-5.6 95+/-5 1.20, A 116.0+/-5.8 112.0+/-5.4 Mean = 114.0+/-3.2 Fe-59 73.5+/-6.0 55+/-3 1.29, D 65.4+/-6.5 NC-02-08 73.9+/-5.9 Mean = 70.9+/-3.5 Zn-65 140.0+/-10.2 117+/-6 1.24, A 143.0+/-10.8 153.0+/-10.4 Mean = 145.3+/-6.0 Co-60 91.2+/-4.1 92+/-5 1.04, A 98.0+/-4.3 99.4+/-4.2 Mean = 96.2+/-2.4 Co-58 76.0+/-4.7 60+/-3 1.18, A 72.0+/-4.9 65.7+/-4.4 I I Mean = 71.2+/-2.7 .1. J _______

(1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Disagreement.

(NC) Nonconformity Report Number.

D-16

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Milk (pCi/liter)

-05 pCi/liter 93.5+/-5.9 82.7+/-6.7 Mean = 89.5+/-3.8 Cr-51 230.0+/-33.5 235+/-12 1.02, A 206.0+/-30.6 282.0+/-32.8 Mean = 239.3+/-18.7 Cs-134 111.0+/-5.4 120+/-6 0.94, A 112.0+/-5.3 115.0+/-5.1 Mean = 112.7+/-3.0 Cs-1 37 93.9+/-5.1 91+/-5 0.99, A 88.0+/-4.8 87.5+/-5.1 Mean = 89.8+/-2.9 Mn-54 98.8+/-5.3 95+/-5 1.03, A 93.1+/-5.1 103.0+/-5.3 Mean = 98.3+/-3.0 Fe-59 83.3+/-6.4 81+/-4 1.06, A 88.8+/-6.4 84.4+/-6.7 Mean = 85.5+/-3.8 Zn-65 187.0+/-11.7 180+/-9 0.99, A 157.0+/-10.4 192.0+/-11.7 Mean = 178.7+/-6.5 Co-60 115.0+/-4.4 125+/-6 0.97, A 124.0+/-4.4 124.0+/-4.4 Mean_ 121.0+/-2.5 Co-58 92.4+/-5.6 100+/-5 0.95, A 99.4+/-5.3 93.8+/-5.1 l _

Mean = 95.2+/-3.1 _

(1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-17

TABLE D-7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Milk (pCi/liter)

VAiNU IIr%

IP..q.... lp.P.'W 't

-)I-F.ERF-JUR 09/12/02 MU-M-6151k.-A 1,

E-3286-05 II10" Irallwill I MILK Ce-141 159.0+/-6.7

.MEN==

I 160+/-8 0.99, A pCi/liter 153.0+/-8.6 162.0+/-7.0 Mean = 158.0+/-4.3 Cr-51 244.0+/-32.0 227+/-11 0.78, D 125.0+/-36.6 NC 161.0+/-34.1 09 Mean = 176.7+/-19.8 Cs-1 34 120.0+/-5.7 132+/-7 0.89, A 118.0+/-7.0 115.0+/-5.6 Mean = 117.7+/-3.5 Cs-1 37 111.0+/-5.5 127+/-6 0.95, A 129.0+/-6.9 124.0+/-5.6 Mean = 121.3+/-3.5 Mn-54 159.0+/-6.2 152+/-8 1.00, A 146.0+/-7.6 151.0+/-6.0 Mean = 152.0+/-3.8 Fe-59 93.7+/-6.5 89+/-4 1.08, A 102.0+/-8.4 91.8+/-6.4 Mean = 95.8+/-4.1 Zn-65 192.0+/-11.4 187+/-9 1.01, A 179.0+/-14.9 192.0+/-11.2 Mean = 187.7+/-7.3 Co-60 143.0+/-4.8 149+/-7 0.97, A 145.0+/-6.0 147.0+/-4.7 Mean = 145.0+/-3.0 _

Co-58 98.1+/-5.2 97+/-5 1.04, A 99.4+/-7.0 104.0+/-5.4 Mean = 100.5+/-3.4 _

(1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Disagreement.

(NC) Nonconformity Report Number.

D-18

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Soil (pCilgram)

U.1 14+/-U.Uz0 pCi/grarn 0.186+/-0.024 0.0141+/-0.022 Mean = 0.147+/-0.014 Cr-51 0.427+/-0.142 0.318+/-0.016 1.16, A 0.349+/-0.125 0.334+/-0.122 Mean = 0.370+/-0.075 Cs-1 34 0.158+/-0.020 0.163+/-0.008 0.98, A 0.126+/-0.020 0.192+/-0.020 Mean = 0.159+/-0.012 Cs-137 0.240+/-0.019 0.208+/-0.010 1.05, A 0.214+/-0.022 0.204+/-0.020 Mean = 0.219+/-0.012 Mn-54 0.133+/-0.015 0.129+/-0.006 1.09, A 0.157+/-0.017 0.132+/-0.018 Mean = 0.141+/-0.010 Fe-59 0.107+/-0.027 0.109+/-0.005 1.07, A 0.099+/-0.029 0.145+/-0.030 Mean = 0.117+/-0.016 Zn-65 0.227+/-0.027 0.243+/-0.012 1.09, A 0.292+/-0.034 0.279+/-0.034 Mean = 0.266+/-0.019 _

Co-60 0.156+/-0.012 0.168+/-0.008 0.92, A 0.165+/-0.014 0.142+/-0.013 Mean = 0.154+/-0.008 Co-58 0.115+/-0.016 0.135+/-0.007 0.87,A 0.114+/-0.017 0.125+/-0.017 J

Mean = 0.118+/-0.010 I (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-19

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Veaetation (DCi/aram) ttl/ IM I R 0.175+/-0.006 pCi/gram 0.161+/-0.007 0.176+/-0.008 Mean = 0.171+/-0.004 Cr-51 0.414+/-0.038 0.403+/-0.020 1.01, A 0.424+/-0.040 0.385+/-0.042 Mean = 0.408+/-0.023 Cs-1 34 0.227+/-0.007 0.206+/-0.010 1.09, A 0.218+/-0.007 0.229+/-0.008 Mean = 0.225+/-0.004 Cs-1 37 0.162+/-0.006 0.156+/-0.008 1.06, A 0.154+/-0.007 0.178+/-0.007 Mean = 0.165+/-0.004 Mn-54 0.186+/-0.007 0.163+/-0.009 1.15, A 0.184+/-0.007 0.193+/-0.001 Mean = 0.188+/-0.004 Fe-59 0.154+/-0.009 0.138+/-0.007 1.09, A 0.141+/-0.009 0.156+/-0.010 Mean = 0.150+/-0.006 Zn-65 0.327+/-0.016 0.308+/-0.015 1.07, A 0.343+/-0.016 0.324+/-0.017 Mean = 0.331+/-0.009 Co-60 0.233+/-0.006 0.213+/-0.011 1.08, A 0.229+/-0.006 0.230+/-0.006 Mean = 0.231+/-0.004 Co-58 0.187+/-0.007 0.171+/-0.009 1.08, A 0.183+/-0.007 0.184+/-0.008 i h Mean = 0.185+/-0.004 i I (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = Reported/Analytics (See Section D.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-20

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (Bq/liter)

VVr,%I woI Z.5i1.U U.[U, U Bq/liter 2.4+/-0.8 NC-02-02 3.0+/-0.6 2.7+/-1.1 2.3+/-1.4 Mean = 2.6+/-0.5 Cs-1 37 57.1+/-1.8 56.1+/-2.9 0.99, A 52.9+/-1.7 57.0+/-1.7 53.7+/-1.7 55.5+/-1.9 Mean = 55.7+/-0.8 Co-60 352.0+/-3.0 347.3+/-12.4 1.02, A 355.9+/-3.1 353.0+/-3.0 352.6+/-3.8 354.5+/-3.6 Mean =

I 353.8+/-1.5 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/Environmental Measurements Lab (EML)(See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Disagreement.

(NC) Nonconformity Report Number.

D-21

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (Bqlliter)

I_

flTM i _ _

IMM&

_ _ _ _R JMff1ihAAORAA OUR HU 'liiM A A RI. I I.AV;F:_%1 9OR "LTI L

I__ I 7 REFRE

, I~f 1 2 TOm

.  :: r=_= . _ _ r __ _ _ _ .

X 09/01/02 s

QAP-57 WATER Cs-1 34 62.9+/-2.2 60.2+/-1.9 1.01, A Bq/liter 61.1+/-2.3 59.9+/-2.2 57.7+/-2.7 60.7+/-1.7 62.2+/-2.1 Mean = 60.7+/-0.9 Cs-1 37 81.0+/-2.5 81.4+/-4.3 0.95, A 77.7+/-2.5 78.1+/-2.4 73.3+/-2.9 77.8+/-1.8 78.8+/-2.5 Mean = 77.7+/-1.0 Co-60 265.7+/-3.4 268.7+/-9.7 1.00, A 271.6+/-3.6 275.7+/-3.5 258.6+/-4.2 268.3+/-2.5 270.5+/-3.4

- a Mean = 268.4+/-1.4 a a -

(1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML(See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-22

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Air Particulate Filters (Bqlfilter)

I ILa L.I X 2b.4+/-U.4 Bq/filter 29.5+/-0.4 30.0+/-0.4 29.6+/-0.5 29.2+/-0.4 Mean = 29.3+/-0.2 Mn-54 40.3+/-0.6 38.5+/-0.9 1.04, A 39.6+/-0.6 40.0+/-0.6 40.7+/-0.7 40.0+/-0.6 Mean = 40.0+/-0.3 _

Cs-1 37 28.2+/-0.5 28.2+/-0.7 0.99, A 28.0+/-0.5 27.5+/-0.5 27.8+/-0.5 27.8+/-0.4 Mean = 27.9+/-0.2 09/01/02 QAP-57 FILTER Mn-54 58.1+/-1.0 52.2+/-1.2 1.11, A Bq/filter 57.7+/-1.1 58.5+/-1.0 58.1+/-1.3 58.5+/-0.9 57.0+/-1.0 Mean = 58.0+/-0.4 Co-60 24.0+/-0.5 23.0+/-0.1 1.00, A 23.5+/-0.6 22.6+/-0.5 23.0+/-0.7 22.4+/-0.5 22.9+/-0.5 Mean = 23.1+/-0.2 _

Cs-1 37 33.6+/-0.7 32.5+/-0.8 1.04, A 34.3+/-0.8 33.8+/-0.7 34.6+/-0.9 32.9+/-0.7 34.2+/-0.7

__ ____ __ _ ____ ___ M ean_= 33.9+/-0.3 _ _ _ _ _ _ _ _ _ _ _ _

(1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-23

TABLE D-7 Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Water (Bq/liter) 03/01/02 QAP-56 WATER GROSS 1099+/-17 1030+/-130 1.08, A Bq/liter BETA 1125+/-17 1110+/-17 Mean = 1111+/-10 09/01/02 QAP-57 WATER GROSS 782+/-20 900+/-90 0.89, A Bq/liter BETA 787+/-20 823+/-20 Mean = 797.0+/-11.32 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-24

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (Bqlliter) 03/01/02 QAP-56 WATER H-3 3255 283.7+/-3.4 1.11, A Bq/liter 310+/-6 313+/-7 Mean = 316+/-3 09/01/02 QAP-57 WATER H-3 249+/-10 227.3+/-5.6 0.88, A Bq/liter 241+/-10 239+/-10 Mean = 243+/-6 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-25

TABLE D-7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air (Bq/filter) mIWI Aww=KIUi I T _ _rRFFFRINRII 03/01/02 QAP-56 AIR GROSS 1.21+/-0.003 1.30+/-0.13 0.92, A Bq/filter BETA 1.18+/-0.03 1.21+/-0.03 Mean = 1.20+/-0.02 09/01/02 QAP-57 AIR GROSS 0.84+/-0.03 0.87+/-0.09 0.95, A Bq/filter BETA 0.80+/-0.03 0.85+/-0.03 Mean = 0.83+/-0.02 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-26