Text

Transmittal of 2011 Annual Radiological Environmental Operating Report
	ML12144A412
Person / Time
Site:	Indian Point
Issue date:	05/15/2012
From:	Robert Walpole; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
	NL-12-009
	Download: ML12144A412 (146)
	v • d • e

Enterciy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB Entergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Licensing Manager NL-12-019 May 15, 2012 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

SUBJECT:

2011 Annual Radiological Environmental Operating Report Indian Point Unit Nos. 1, 2 and 3 Docket Nos. 50-03, 50-247, 50-286 License Nos. DPR-5, DPR-26, DPR-64

Dear Sir or Madam:

Enclosed please find one copy of the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Energy Center (IPEC) Annual Radiological Environmental Operating Report for the period January 1, 2011 to December 31, 2011.

This report is submitted in accordance with facility Technical Specification Appendix A section 6 of the provisional operating license for DPR-5 and section 5.6.2 for DPR-26, and DPR-64, Indian Point Unit Nos. 1, 2 and 3 respectively. There are no commitments are being made by this report.

Should you or your staff have any questions, please contact Mr. Robert Walpole, Manager, Licensing at 914-254-6710.

Sincerely, RW/mb cc: next page

,1/

NL-12-019 Docket Nos. 50-03, 50-247, 50-286 Page 2 of 2

Enclosure:

1. Annual Radiological Environmental Operating Report cc: Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL IPEC NRC Resident Inspector's Office Mr. Stephen Giebel, IPEC NRC Unit 1 Project Manager Mr. Francis J. Murray, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Department of Public Service Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Mgmt, NYSDEC

ENCLOSURE 1 TO NL-12-019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 1, 2, and 3 NUCLEAR POWER PLANTS DOCKET Nos. 50-03, 50-247, and 50-286

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

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

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

January 1 - December 31, 2011

TABLE OF CONTENTS Page 1.0 EXCEUTIVE

SUMMARY

1-1

2.0 BACKGROUND

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 3-2 3.3.7 Fish and Invertebrates 3-3 3.3.8 Hudson River Aquatic Vegetation 3-3 3.3.9 Hudson River Bottom Sediment 3-3 3.3.10 Precipitation 3-3 3.3.11 Soil 3-3 3.3.12 Groundwater Samples 3-3 3.3.13 Land Use Census 3-3 3.4 Statistical Methodology 3-5 3.4.1 Lower Limit of Detection and Critical Level 3-5 3.4.2 Determination of Mean and Propagated Error 3-6 3.4.3 Table Statistics 3-7

TABLE OF CONTENTS (continued)

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

5.0 REFERENCES

and BIBLIOGRAPHY 5-1 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

" JAF Environmental Laboratory

Teledyne Environmental Laboratory

TLD Dosimeter Testing E. ADDENDA E-1 ii

LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles) A-5 A-2 Sampling Locations (Greater Than Two Miles) A-6 A-3 Additional Sampling Locations A-7 C-1 Direct Radiation, Annual Summary, 2001 to 2011 C-3 C-2 Radionuclides in Air, 2001 to 2011 C-5 C-3 Radionuclides in Hudson River Water, 2001 to 2011 C-7 C-4 Radionuclides in Drinking Water, 2001 to 2011 C-9 C-5 Radionuclides in Shoreline Soil, 2001 to 2011 C-11 C-6 Broad Leaf Vegetation - Cs-1 37, 2001 to 2011 C-13 C-7 Fish and Invertebrates - Cs-137, 2001 to 2011 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-10 B-1 Summary of Sampling Deviations, 2011 B-2 B-ia 2011 Air Sampling Deviations B-3 B-1 b 2011 Other Media Deviations B-3 B-2 ODCM Annual Summary, 2011 B-4 B-3 2011 Direct Radiation, Quarterly Data B-8 B-4 Direct Radiation, 2001 through 2011 Data B-9 B-5 2011 Direct Radiation, Inner and Outer Rings B-1 0 B-6 Environmental Airborne Particulate Samples - 2011 Gross Beta Activity B-11 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Site Air Particulate Samples, 2011 B-13 B-8 Environmental Charcoal Cartridge Samples - 2011 1-131 Activity B-15 B-9 Concentrations of Gamma Emitters in Surface Water Samples, 2011 B-17 B-10 Concentrations of Tritium in Surface Water Samples, 2011 B-19 B-1 1 Concentrations of Gamma Emitters in Drinking Water Samples, 2011 B-20 B-12 Concentrations of Tritium in Drinking Water Samples, 2011 B-22 B-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2011 B-23 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples, 2011 B-25 iv

LIST OF TABLES (Continued)

TABLE TITLE Page B-15 Concentrations of Radionuclides in Fish Samples, 2011 B-34 B-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2011 B-38 B-17 Concentrations of Gamma Emitters in Bottom Sediment Samples, 2011 B-39 B-18 Concentrations of Radionuclides in Rainwater Samples, 2011 B-40 B-19 Concentrations of Gamma Emitters in Soil Samples, 2011 B-41 B-20 Concentrations of Radionuclides in Monitoring Well Samples, 2011 B-42 B-21 Land Use Census - Residence and Milch Animal Results, B-43 2011 B-22 Land Use Census, 2011 B-44 C-1 Direct Radiation Annual Summary, 2001 to 2011 C-2 C-2 Radionuclides in Air, 2001 to 2011 C-4 C-3 Radionuclides in Hudson River Water, 2001 to 2011 C-6 C-4 Radionuclides in Drinking Water, 2001 to 2011 C-8 C-5 Radionuclides in Shoreline Soil, 2001 to 2011 C-10 C-6 Broad Leaf Vegetation - Cs-137, 2001 to 2011 C-12 C-7 Fish and Invertebrates - Cs-137, 2001 to 2011 C-14 D-1 Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 Interlaboratory Comparison Program D-5 V

SECTION 1.0 EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

INTRODUCTION This report summarizes the results of the Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Indian Point Energy Center (IPEC) during the period from January 1 to December 31, 2011. This document has been prepared in accordance with the requirements of IPEC 1, Unit 2 and 3 Technical Specifications.

The REMP has been established to monitor the radiation and radioactivity released to the environment as a result of IPEC's operation. This program, initiated in 1958, includes the collection, analysis, and evaluation of radiological data in order to assess the impact of IPEC on the environment and on the general public.

SAMPLING AND ANALYSIS The environmental sampling media collected in the vicinity of IPEC and at distant locations included air particulate filters, charcoal cartridges, soil, drinking water, ground water, broadleaf vegetation, river water, precipitation, shoreline sediment, bottom sediment, aquatic vegetation, fish, and invertebrates.

During 2011, there were 1003 samples collected from the atmospheric, aquatic, and terrestrial environments. In addition, 164 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs).

A small number of inadvertent issues were encountered in 2011 in the collection of environmental samples in accordance with the IPEC Offsite Dose Calculation Manual (ODCM). Equipment failures and electrical outages resulted in a small number of instances in which lower than normal sampling volumes were collected at the airborne monitoring stations. A full description of all discrepancies encountered with the environmental monitoring program is presented in the Table B-1 of this report.

There were 1472 analyses performed on the environmental media samples. The analysis of the 2011 Indian Point environmental samples was performed by several laboratories.

General Engineering Labs (GEL) of Charlestown, SC, performed the ground water analyses.

Thermoluminescent dosimeters were analyzed by Environmental Dosimetry Company (formerly Stanford Associates) of Sterling, MA. The James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory in Fulton, NY, performed most of the remaining analyses for the first three quarters of 2011. Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the analyses of the fish samples, the Sr-90 analyses of sediments and most of the remaining analyses for the fourth quarter of 2011. Samples were analyzed as required by the IPEC ODCM.

LAND USE CENSUS The annual land use census in the vicinity of IPEC was conducted as required by the IPEC ODCM in May through October. No dairy animals within 5 miles of the Station were located during the census. Due to the difficulty of locating individual gardens and determining those having an area greater than 500 square feet, broadleaf sampling was performed. Monthly broad leaf sampling may be used in lieu of a garden census.

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RADIOLOGICAL IMPACT TO THE ENVIRONMENT Most samples collected as part of the IPEC REMP continued to contain detectable amounts of naturally-occurring and man-made radioactive materials. There was no plant related activity detected in any of the terrestrial samples. Offsite ambient radiation measurements using environmental TLDs beyond the site boundary ranged between 55 and 90 milliRoentgens (mR) per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for New York.

Monitoring of the aquatic environment in the area of the discharge indicated the presence of the following station related radionuclides: Tritium and Cs-137. These station related nuclide were only found in the mixing zone of the discharge at levels that were expected from routine plant operation. No other plant related activity was detected in any offsite samples. Trace amounts of 1-131 were seen as a result of the Fukushima incident. The predominant radioactivity for all samples was from non-plant related sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.

RADIOLOGICAL IMPACT TO THE GENERAL PUBLIC During 2011, radiation doses to the general public as a result of IPEC's operation continued to be well below the federal limits and much less than the dose due to other sources of man-made (e.g., X-rays, medical) and naturally-occurring (e.g., cosmic, radon) radiation.

The calculated total body dose to the maximally exposed member of the general public from radioactive effluents and ambient radiation resulting from IPEC operations for 2011 was approximately 0.2 millimrem (mrem) for the year. This conservative estimate is well below the Environmental Protection Agency's (EPA) annual dose limit to any member of the general public and is a fraction of a percent of the typical dose received from natural and other sources of man-made radiation.

CONCLUSIONS The 2011 Radiological Environmental Monitoring Program for IPEC resulted in the collection and analysis of over a thousand environmental samples and measurements. The data obtained were used to determine the impact of IPEC's operation on the environment and on the general public.

An evaluation of direct radiation measurements, environmental sample analyses, and dose calculations demonstrates that all applicable federal criteria were met. Furthermore, radiation levels and resulting doses from station operation were a small fraction of those attributed to natural and man-made background radiation.

In summary, the levels of radionuclides in the environment surrounding Indian Point were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, IPEC operations in 2011 did not result in exposure to the public greater than environmental background levels.

Based on this information, there is no radiological impact on the environment or on the general public due to IPEC's operation.

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SECTION 2 BACKGROUND

2.0 BACKGROUND

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 began operation in 1962 and was retired as a generating facility in 1974. Units 2 and 3 began operation 1974 and 1978. All three units 3 are owned and operated by Entergy Nuclear, although only Units 2 and 3 continue to operate.

2.2 Program Background Environmental monitoring and surveillance have been conducted at Indian Point since 1958, 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. Accumulation of this background data permits the detection and assessment of environmental activity attributable to plant operations.

Thus, as used in this report, background levels consist of those resulting from both natural and anthropogenic sources of environmental radioactivity Results of the analyses from the indicator and control locations and a comparison to preoperational data are summarized in Section 4 of this report.

2.3 Progqram Obiectives The current environmental monitoring program is designed to meet three primary objectives:

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

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

3. Compare plant related measurable results to those predicted by the effluent monitoring and modeling and determine if any adjustments need to be made to the effluent calculation methods or the environmental sampling program.

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 near the site, where the presence of environmental radioactivity of plant origin is most likely to be detected. Control locations are established 2-1

farther away (and upwind/upstream, where applicable) from the site, where the level would not generally be affected by plant discharges. The use of indicator and control locations enables the identification of potential sources of detected radioactivity, thus meeting one of the program objectives.

Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is the third program objective. Verifying projected concentrations through the REMP is difficult since the environmental concentrations resulting from plant releases are typically too small to be detected. Plant related radionuclides were detected in 2011 in very low levels; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2011 REMP sample results confirms that radiological effluents were well below regulatory limits.

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SECTION 3 PROGRAM DESCRIPTION

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

3.1 Sample Collection Entergy personnel perform collection of environmental samples for the Indian Point site, with the exception of groundwater and fish/invertebrate samples.

The groundwater (monitoring well) samples are collected by a contracted environmental vendor, GZA Geo Environmental, Inc. Collection of fish and invertebrate samples is performed by a contracted environmental vendor - Normandeau Associates, Inc.

3.2 Sample Analysis The analysis of the 2011 Indian Point environmental samples was performed by several laboratories. General Engineering Labs (GEL) of Charlestown, SC, performed the ground water analyses. Thermoluminescent dosimeters were analyzed by Environmental Dosimetry Company (formerly Stanford Associates) of Sterling, MA. The James A.

Fitzpatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory in Fulton, NY, performed most of the remaining analyses for the first three quarters of 2011. Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the analyses of the fish samples, the Sr-90 analyses of sediments and most of the remaining analyses for the fourth quarter of 2011.

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 milli-roentgen, mR) for a given period. The area surrounding the Indian Point site is divided into 16 compass sectors. Each sector has two TLD sample locations. The inner ring is located near the site boundary at approximately 1 mile (1.6 km).

The outer ring is located at approximately 5 miles (8 km) from the site (6.7- 8.0 km), see Figures A-1 and A-2.

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.

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3.3.2 Airborne Particulates and Radioiodine Air samples were taken at eight locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control at sampling station 23 (A5) and seven indicator locations. These indicator locations are at sampling stations 4 (Al), 5 (A4), 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown on Figures A-i, A-2, and A-

3. The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges. Both are changed on a weekly basis. The filter and cartridge samples are analyzed for gross beta and radioiodine, respectively. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters.

3.3.3 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (sampling station 9, Wal) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, Wa2); see Figure A-1. An automatic composite sampler is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly GSA, and quarterly for tritium analysis.

3.3.4 Drinking Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, sample station 7, sample designation Wbl) and New Croton Reservoir (6.3 Mi SE, sample station 8); see Figure A-3. Each monthly sample is approximately 4 liters and is analyzed for gross beta and gamma-emitting radionuclides. 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 indicator locations are at sampling stations 53 (Wcl), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-1, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by GSA and for strontium-90.

3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season.

The indicator locations are sampling stations 94 (Ic2) and 95 (Icl), and the control location is at sampling station 23 (Uc3). 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.

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3.3.7 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The indicator location (downstream sample point) is designated as sampling station 25 (Ibl) and the control location (upstream) is at sampling station 23 (Wb2). 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 as well as for Sr-90 and for Ni-63.

3.3.8 Hudson River Aquatic Veqetation During the spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations (sampling stations 17 and 28) and one control location (84);

see Figure A-3. Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.

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

3.3.10 Precipitation Precipitation samples are continuously collected at one indicator location (sampling station

44) and one control location (23); see Figure A-3. They are collected in sample bottles designed to hinder evaporation. They are composited quarterly and analyzed by GSA and for tritium.

3:3.11 Soil Soil samples are collected from two indicator locations (sampling stations 94 and 95), and one control location (23) on an annual basis; see Figure A-3. They are approximately 2 kg in size and consist of about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.

3.3.12 Groundwater Samples Groundwater samples were obtained semi-annually at Lafarge (106.) Samples are analyzed for tritium, Sr-90, Ni-63 and by gamma spectroscopy.

3.3.13 Land Use Census Each year a land use census consisting of milch animal and residence surveys is conducted during the growing season to determine the current utilization of land within 5 miles (8 km) of the site. These surveys are used to determine whether there are changes in existing conditions that warrant changing the sampling program.

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

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

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

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

" Rockland County was surveyed during summer and fall.

" Putnam County was surveyed during the summer and fall.

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

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

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

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

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

3.4.1 Lower Limit of Detection (LLD) and Critical Level (L0 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real' signal.

For a particular measurement system (which may include radiochemical separation):

2.71 3.29sý* ]+(T)

.LLD- T, T E*V*k*y* g wrnere:

LLD = The lower limit of detection as defined above (as picocurie per unit mass or volume)

T, = The sample counting time in minutes so = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

TIb = The background count time in minutes E= The counting efficiency (as counts per transformation)

V= The sample size (in units of mass or volume) k= A constant for the number of transformations per minute per unit of activity (normally, 222E+6 dpm per ,OCi)

Y The fractional radiochemical yield (v,,en applicable)

The radioactive decay constant for the particular radionuclide t= The elapsed lime between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times.

The Radiological Environmental Monitoring Program, REMP, uses an LLD formula that assumes equal background and sample count times, in accordance with the RECS.

When the above LUD formula is more appropriate for the effluents program, it may be used.

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The constants 2.71 and 3.29 and the general LLD equation were derived from the folloring two sources:

1) Currie, LA. "Limits for Qualitative Detection of Quantitatiive Determirnation". (Anal. Chem.

40:586-593, 1968); and,

2) Mayer, Dauer "Application of Systematic Error Bounds to Detection Limits for Practical Counting".

(HP Journal 65(1): 89-91, 1993)

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionudides normally present in the samples. Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be vAhin + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that the LLD is defined as an apriori (before the fact) limit representing the capability of a measurement process and not as an a posterior (after the fact) limit for a particular measurement.

To handle the a posterion problem, a decision level must be defined, which has been identified as the Critical Level. Following an experimental observation, one must decide whether or not a real signal was, in fact, detected. This type of binary qualitative decision is subject to two kinds of error--

deciding that the radioactive material is present when it is not (a: Type I error), and the converse, failing to decide that it is present when it is (b: Type It error). The maximum acceptable Type I error (a), together ,ith the standard deviation, Snet, of the net signal when the net signal equals zero, establish the Critical Level, Lc, upon which decisions may be based.

Operationally, an observed signal, S, must exceed L to yield the decision, detected.

_ = kasb(l+TJUi-,45 where:

k3 is related to the standardized normal distribution and corresponds to a probability level of 1-a.

For instance, selection of a = 0.01 corresponds to a 99% confidence level that activity is present.

When determining the Lc for different measurement processes, it is allowable to set a at less than or equal to 0.05 as long as the following condition is met:

To set a for Le determination at less than 0.05, the equation for the LLD (which places a less than or equal to 0.05) should be employed to verify that the calculated LLD is less than or equal to the LLDs specified in the RECS. This calculation, if necessary, will be performed on a case by case basis.

3.4.2 Determination of Mean and Propagated Error Recounts of positive samples are occasionally 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 recounts may be used to verify the positive results. The recounts are not performed on samples with expected positive results; for example: air samples with positive results from gross beta analysis, since the results are usually positive due to natural 3-6

background radioactive material in the air. When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean. In cases where more than one sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report.

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

N 3xi X= i=1 N

where: X= value of each individual observation N = number of observations IN (ERR,)i 2 PE= =

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

In the data tables B-6 through B-20, values shown are based on the Lc value, unless otherwise noted. If a radionuclide was detected at or above the Lc value in two or more counts, the mean and error are calculated as per Section 3.4.2, and reported in the data table. Values listed as "<" 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 2000 through 2010. The 2011 average values are included in these historic tables for purposes of comparison.

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SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2011 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manual ODCM. The ODCM contains requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity.

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

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

To evaluate the contribution of plant operations to environmental radioactivity levels, other man-made and natural sources of environmental radioactivity, as well as the aggregate of past monitoring data, must be considered. It is not merely the detection of a radionuclide, but the evaluation of the location, magnitude, source, and history of its detection that determines its significance. Therefore, we have reported the data collected in 2011 and assessed the significance of the findings.

A summary of the results of the 2011 REMP is presented in Table B-2. This Table lists the mean and range of all positive results obtained for each of the media sampled at ODCM indicator and control locations. Discussions of these results and their evaluations are provided below.

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

The environment contains a broad inventory of naturally occurring radionuclides which can be classified as, cosmic ray induced (e.g., Be-7, H-3) or geologically derived (e.g., Ra-226 and progeny, Th-228 and progeny, and K-40.) These radionuclides constitute the majority of the background radiation source and thus account for a majority of the annual background dose detected. Since the detected concentrations of these radionuclides were consistent at 4-1

indicator and control locations, and unrelated to plant operations, their presence is noted only in the data tables and will not be discussed further.

The second group of radionuclides detected in 2011 consists of those resulting from past weapons testing in the earth's atmosphere and more recent contamination resulting from the Fukushima event. Weapons 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 of some radionuclides, although diminishing with time (e.g., through radioactive decay and natural dispersion processes), remains detectable.

In 2011, the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-1 37 in several media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years. REMP samples for 2011 also indicated the presence of 1-131 in several of the airborne and rainwater samples. Although 1-131 can result from plant operation, this is not the case for these sample results. Given the following facts,.these detectable concentrations of 1-131are not a result of plant operation:

o The quantities of radioactive airborne effluents from IPEC during 2011 did not increase significantly compared to year 2010.

o The concentrations detected in the indicator samples were also identified in the control samples.

o When the 2011 positive levels of 1-131 were detected in the airborne samples, it was also detected throughout much of the world, including much higher levels in the western parts of the United States. These detectable levels were the result of the Fukushima event (Reference 2)

As such, the atypical detection of 1-131 in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from Dai-Ichi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of IPEC.

The final group of radionuclides detected by the 2011 REMP comprises those that may be attributable to current plant operations. During 2011, Cs-1 37 and tritium (H-3) were the only potentially plant-related radionuclides detected in some environmental samples.

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

Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2010, there were three detections of Cs-137 in shoreline soil (2 indicator samples and one control sample). In bottom sediment there were five positive detections of Cs-137 (all at indicator stations or near to plant.) The two discharge canal samples are consistent with historical values.

Shoreline sediment and bottom sediment samples showed detectable levels of Cs-137 somewhat higher at the indicator locations than at the control location at Cold Spring (distant location). The fact that there was no Cs-134 present (recent plant releases would contain Cs-1 34) and that there was detection also at a distant location indicates that the activity may 4-2

be due to atmospheric weapons testing, with some contribution from plant releases from several years past. Although there was an increase noted in several of the fourth quarter bottom sediment samples, this may be attributable to the significant redistribution of river sediments resulting from the historic flows in the Hudson River due to tropical storm Irene in the fall of 2011.

Strontium-90 (Sr-90) may also be present in the environment from atmospheric testing debris. None of the fish samples indicated any detectable levels of this isotope.

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in previous years. 1-131 was not detected in 2011 in aquatic or terrestrial vegetation indicator and control locations.

Co-58 and Co-60 are activation/corrosion products also related to plant operations. They are produced by neutron activation in the reactor core. As Co-58 has a much shorter half-life, its absence "dates" the presence of Co-60 as residual from releases of both radionuclides in the past. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is considered to be from recent releases. When significant concentrations of Co-60 are detected but no Co-58, there is an increased likelihood that the Co-60 is due to residual Co-60 from past operations. There was no Co-58 or Co-60 detected in the 2011 REMP, though they (Co-58 and Co-60) can be observed in historical data.

In the following sections, a summary of the results of the 2010 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 Environmental Dosimetry Company. In 2011, 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 2001 through 2010. The 2011 means are also presented in Table B-4. Table B-5 presents the 2011 TLD data for the inner ring and outer ring of TLDs.

The 2011 mean value for the indicator direct radiation sample points was 13.9 mR per standard quarter - which represents no change from 2010. At those locations where the 2011 mean value was higher than historical means, they are within historical bounds for the respective locations.

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-16) is close to the site boundary.

4-3

The outer ring (DR-1 7 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 13.6 mR per standard quarter and also average for the outer ring was 14.4 mR per standard quarter. The control location average for 2011 was 13.4 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 2011 averages are consistent with the historical data. The 2011 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 2011 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 GSA 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 0.014 pCi/m 3 and the average for the control location was 0.014 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. GSA of the quarterly composite air samples showed that no reactor-related radionuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

The mean annual gross beta concentrations and Cs-137 concentrations in air for the past 10 years are presented in Table C-2. From this table and Figure C-2, it can be seen that the average 2014 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). Excluding the previously discussed samples from the March and April samples affected by Fukushima, there was no 1-131 detected (LLD =

0.07 pCi/m 3) in the charcoal cartridge samples, which is consistent with historical trends.

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2011.

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.

4-4

The only plant related activity detected was H-3. The levels are consistent with occasional historical detection of H-3. Additionally, Table C-3 indicates the absence of Cs-137 which is consistent with historical data.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2011 drinking water sample analysis results. Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-1 1 and results of tritium analysis of quarterly composites are in Table B-12. Other than naturally occurring radionuclides, no radionuclides were detected in drinking water samples.

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

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

In addition to the naturally occurring radionuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2011. Cs-1 37 was detected at the Verplanck location in both samples from that location, for a total of two positive values out of seven samples from indicator locations. Cs-137 was not detected at the control location (Manitou Inlet). The average concentration for the indicator locations that had positive indication of Cs-137 was 108 pCi/kg (dry) with a maximum concentration of 112 pCi/kg (dry.)

An historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table C-5 and Figure C-5. Cs-137 has been and continues to be present in this media, both at indicator and occasionally at the control location, at a consistent level over the past ten years. Cs-134 and Cs-137 are both discharged from the plant in similar quantities. The lack of Cs-1 34 activity is an indication that the primary source of the Cs-1 37 in the shoreline soil is legacy contamination from weapons fallout.

No Sr-90 was detected in any collected shoreline soil samples.

4.6 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2011 samples are presented in Table B-14.

Table C-6 contains an historical summary and Figure C-6 is an illustration of the broad leaf vegetation analysis results. The detection of low levels of Cs-137 has occurred sporadically at both indicator and control locations at relatively low concentrations for the past ten years.

Cs-137 was not detected in 2011 4-5

4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table B-2.

Table B-15 contains the results of the analysis of fish and invertebrate samples for 2011.

There were no plant related radionuclides detected.

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

4.8 Aquatic Vegetation A summary of the aquatic sample analysis results is presented in Table B-2. Table B-16 contains the results of the analysis of aquatic vegetation samples for 2011. No plant related radionuclides were detected.

4.9 Hudson River Bottom Sediment A summary of the Hudson River bottom sediment analysis results is presented in Table B-2.

Table B-17 contains the results of the analysis of bottom sediment samples for 2011. Cs-137 was detected at 5 of 6 indicator station samples and 1 of 2 control station (Cold Spring) samples. This frequency of detection is not unusual. Cs-134 was not detected in any bottom sediment samples. The lack of Cs-134 suggests that the primary source of the Cs-137 in bottom sediment is from historical plant releases over the years and from residual weapons test fallout.

The discharge canal bottom sediments were 97 pCi/kg and 200 pCi/kg on samples taken four months apart (average = 251 pCi/kg.). There is nothing in release data and in monitoring well data that corresponds to this difference. The results are somewhat less than to the 2009 and 2010 results. The average of all indicator detections is 321 pCi/kg (553 pCi/kg in 2010 and 493 pCi/kg in 2009.) This is consistent with historical annual average concentration for indicator locations.

This detection of Cs-137 in bottom sediment generally decreased from an average of 1200 pCi/kg in the early 1990s to 500 pCi/kg in the mid-1990s to a recent value of about 320 pCi/kg. Cs-134 has not been detected in bottom sediment since 2002.

4.10 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table B-18 contains the results of the precipitation samples for 2011. Other than naturally occurring radionuclides, only 1-131 and H-3 were detected in the precipitation samples. As discussed earlier the 1-131 detected in the March 2011 rainwater samples was seen at both indicator and control locations and was due to the effects of Fukushima.

A review of historical data over the last 11 years indicates tritium had been detected in both indicator and control precipitation samples in 2000; however, there have been no instances of positive values until the 4 th quarter of 2011.

4-6

4.11 Soil A summary of the soil sample analysis results is presented in Table B-2. Table B-19 contains the results of the soil samples for 2011. Other than naturally occurring radionuclides, no activity was detected in any of the soil samples.

4.12 Groundwater A summary of the groundwater samples for 2011 is contained in Table B-2. Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, Ni-63 and Sr-90 are given in Table B-20.

No radionuclides other than naturally occurring ones were found in 2011.

4.13 Land Use Census A census was performed in the vicinity of Indian Point in 2011. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables B-21 and B-22.

The results of the 2011 census were generally same as the 2010 census results. The New York Agricultural Statistic Service showed there were no animals producing milk for human consumption found within 5 miles (8 km) of the plant. Field observations also yielded no milching animal locations within five miles.

The second part of this census revealed that the two nearest residences in different sectors are located 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant. The 2011 land use census indicated there were no new residences that were closer in proximity to IPEC.

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

4.14 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2011 REMP reveal that operations at the station did not result in an impact on the environment.

The 2011 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. The results indicate that the fallout from previous atmospheric weapons testing continues to contribute to detection of Cs-137 in some environmental samples. There are infrequent detections of plant related radionuclides in the environs; however, the radiological levels are very low and are significantly less than those from natural background and other anthropogenic sources.

4-7

SECTION 5 REFERENCES AND BIBLIOGRAPHY

5.1 REFERENCES

1. United States Nuclear Regulatory Commission, Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

2. Wetherbee, Gregory A., et.al., Wet Deposition of Fission-Product Isotopes to North America from the Fukushima Dai-ichi Incident, March 2011, Environmental Science and Technology.

5.2 BIBLIOGRAPHY

1. United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix A Criteria 64.

2. Donald T. Oakley, "Natural Radiation Exposure in the United States." U. S.

Environmental Protection Agency, ORP/SID 72-1, June 1972.

3. National Council on Radiation Protection and Measurements, Report No. 160, "Ionizing Radiation Exposures of the Population of the United States," March 2009.

4. National Council on Radiation Protection and Measurements, Report No. 94, "Exposure of the Population of the United States and Canada from Natural Background Radiation," December 1987.

5. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instructions Concerning Risks from Occupational Radiation Exposure," Revision 0, July 1981.

6. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

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

8. United States of America, Code of Federal Regulations, Title 10, Part 20.1301.

9. United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix I.

10. United States of America, Code of Federal Regulations, Title 40, Part 190.

11. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Program for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.

12. International Commission of Radiological Protection, Publication No. 43, "Principles of Monitoring for the Radiation Protection of the Population," May 1984.

13.United States Nuclear Regulatory Commission, NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," April 1991.

14.NRC Regulatory Guide 4.1, Radiological Environmental Monitoring for Nuclear Power Plants, Revision 2, June 2009.

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

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

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

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

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

5-1

20.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.

21. 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.

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

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

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

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

26. Kelly, J. J. (Ed.), Effluent and Environmental Radiation Surveillance, ASTM STP

698, Philadelphia, PA, 1978.

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

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

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

1969.

30. 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.

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

32. 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.

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

34. 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.

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

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

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

38. Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 618, December 2003.

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

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

41. ENN-LI-102, Corrective Action Process 42.Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC" 5-2

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

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

Table A-1 provides the sampling station number, location, sector, and distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2011 REMP.

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

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

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

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

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS I!SAMPLING STAPIONG SAMPLE SIGNATIN LOCATION STATION DESIGNATION DISTANCE SAMPLE TYPES.

3 DR8 Service Center Building OnsiteDirect Gamma 0.35 Mi (SSE) at 1580 Al Algonquin Gas Line Onsite - 0.28 Mi (SW) at Air Particulate Al 234' Radioiodine A4 Air Particulate 5 A4 NYU Tower Onsite - 0.88 Mi (SSW) Radioiodine at 208' DR1 0 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 510 Drinking Water 8 Croton Reservoir 6.3 Mi (SE) at 1240 Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* Onsite - HR Water 0.16 Mi (W) at 2730 Wa2 Discharge Canal (Mixing Zone) Onsite - HR Water 10

- 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House OnsiteDirect Gamma 0.3 Mi (SE) at 1330

- HR Aquatic Vegetation 17 Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil

- HR Bottom Sediment Cortlandt Yacht Club 20 DR38 (AKA Montrose Marina) 1.5 Mi (5) at 1800 Direct Gamma

- Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma Ic3 Broad Leaf Vegetation

- Soil Ib2 Fish & Invertebrates 25 Ibl Downstream Downstream Fish & Invertebrates

- Air Particulate 27 ** Croton Point 6.36 Mi (SSE) at 1560 Radioiodine DR41 Direct Gamma

- HR Shoreline Soil 28 DR4 Lent's Cove 0.45 Mi (ENE) at 069' Direct Gamma

- HR Bottom Sediment

- HR Aquatic Vegetation

- Air Particulate 29 ** Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine DR39 I I Direct Gamma

= Control location

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

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS

':SAMPLING -SAMPLE

STATION DESIGNATION LOCATION DISTANCE . SAMPLE TYPES 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053' Direct Gamma 34 DR9 South East Corner of Site OnsiteDirect Gamma 0.52 Mi (S) at 179D 35 DR5 Broadway & Bleakley Avenue OnsiteDirect Gamma 0.37 Mi (E) at 0920 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141' Direct Gamma

- Precipitation 44 ** Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate

- Radioiodine.

50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil WclHRSoeieSl 53 White Beach 0.92 Mi (SW) at 2260 HR Shoreline Soil DR11 Direct Gamma 56 DR37 Verplanck - Broadway & 6th Street 1.25 Mi (SSW) at 202' Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 0050 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 0320 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 62___DR19_ (near the Community Center) 5.03 Mi (NE) at 0620 Direct Gamma 64 DR20 Lincoln Road - Cortlandt 4.6 Mi (ENE) at 0670 Direct Gamma 64___DR20__ (School Parking Lot) 4._M_(N)_t_67_irctGam 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 226' Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR31 Palisades Parkway 4.65 Mi (NW) at 2250 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

= Control location 00 Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River RIS = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS

'SAMPLING SAMPLE LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION 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 DR28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 310' 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 3390 Direct Gamma

- HR Aquatic Vegetation 84 ** Cold Spring

10.88 Mi (N) at 3560 HR Shoreline Soil

- HR Bottom Sediment 88 DR6 Reuter Stokes 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 DR35 89 (near rock cut) 2.89_Mi_(NNE)_at_025_ DirectGamma 90 DR3 Charles Point 0.88 Mi (NE) at 047' Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate 94 A2 IPEC Training Center Onsite- 0.39 Mi (S) at Radioiodine Ic2 1930 Broad Leaf Vegetation

- - Soil A3 Air Particulate A3 Onsite - Radioiodine Icl 0.46 Mi (SSW) at 2080 Broad Leaf Vegetation

- Soil 106 ** Lafarge Monitoring Well 0.63 mi SW Groundwater

= Control location

- Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-4

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

Peekskill Rockland County Westchester County 1 mile Key:

lc# - Broadleaf Vegetation A - Waterborne. Surface (HR) Wa#

co>. HR Shoreline Soil Wc#

O- Direct Radiation Sample Location DR#

Ibi - Fish and Invertebrates

[3 - Airborne Particulate and Radiolodine A# (where available downstream)

A-5

FIGURE A-2 SAMPLING LOCATIONS Greater than Two Miles from Indian Point Roseton (20.7 mi. N) : N Elm e c3 Upstream; 1b2 Orange County Putnam County 0

Bear Mountain Bridge 0 00 I

( Westchester County 0

0 5 miles Rockland County Key: 0 - Direct Radiation Sample Location DR# Ic3 - &oadleat Vegetation r3 - Airborne Sampling Location A4 Q - Waterborne: Drinking Wb#

- Hudson River Shoreline Soil Wc# 112 - Fish and Invertebrates (where available upstream)

A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N

Rosetonr(20.7mi. N): 23 p

Orange County Putnam County Cold Spring (10.88 mi. N) : 84*

Bear Mountain Bridge Westchester 17: V, County GW: 106 29 : 0 Rockland County 27: Ia o 8: dw 5 miles Key: N - Air Particulate &,Radioiodine A - HR Shoreline Soil V - Aquatic Vegetation * - Soil W - HR Bottom Sediment GW - Monitoring Well, SW of p - Precipitation Site Boundary dw - Drinfing Water A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES AIRBORNEAIBONE FISH FIH MILK FOOD PRODUCTS SOIL or SEDIMENT RADIONUCLIDE WATER PARTIUCLATE ?R (pCi/kg, (pCifL) (pCilkg, wet) (pCiMkg, dry)

ANALYSIS (pCi/L) GASES (pCilm wet)

Gross Beta 4 0.01 H-3 2,000 (d)

Mnr-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 NI-63 (1) 30 100 Zn-65 30 260 Sr-90 (1) 1 5 5000 Zr-95 15 Nb-95 15 1-131 1 (d) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 006 150 18 80 180 Ba-140 15 15 La-140 15 15 A-8

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES (a) This list does not mean that only these nudides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specilication D 5.1.

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

(c) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a 'real" signal.

It should be recognized that the LLD is defined as an a_pqor (before the fact) limit representing the capability of a measurement system and not as an a posteriod (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to RECS D 5.1.

(d) These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 for H-3 and 15 for 1-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

(f) Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment, per References 45 and 46.

A-9

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES RADIONUCLDE WATER AIRBORNE OR PARTIUCLATE FISH MILK FOOD PRODUCTS ANALYSIS (pCUL) GASES (pCiftn) (pCi/kg, wet) (pCiIL) (pCi'kg, wet)

H-3 20.000' Mn-54 1.000 30.000 Fe-59 400 10,000 Co-58 1,004) 30.000 CoA-80 300 10,000 Ni-3 .. 30]0 1.000 Zn-66 300 20,000 Sr-90 "" a. 40 Zr-95 400 Nb-95 400 1-131 2- 0.0 3 100 Cs- 134 30 10 1,000 do 1.000 Cs-137 50 20 2.000 70 2,000 Ba-140 200 300 La-14D 200 300 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30.01) pCilL (This is a 4D CFR 141 value)

Sr-90 12 pCiVL 1-131 20 pCi61 These reporting levels are associa*ed only vwth the REMP requirements. The Rad~ological Ground Water Monitoring Program may involve unique repoerng level criteria. ,independentof the REMP. and defined in staton procedures-Sr-g91 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment, per References 45 and 46.

A-1O

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2011 Annual Radiological Environmental Monitoring Program Summary The results of the 2011 radiological environmental sampling program are presented in Tables B-2 through B-20. Table B-2 is a summary table of the sample results for 2011. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8 (Reference 4),

and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 14). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-20.

REMP samples were analyzed by various counting methods as appropriate.

The methods are; gross beta, gamma spectroscopy analysis, liquid scintillation, radiochemical analysis, and TLD processing. Gamma spectroscopy analysis was performed for the following radionuclides; Be-7, K-40, Mn-54, Co-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 analyses were performed for Ni-63 and Sr-90 for specific media and locations as required in the ODCM.

B.2 Land Use Census In accordance with Sections IP2-D3.5.2 and IP3-2.8 of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use census are presented in Tables B-21 and B-22, respectively. In lieu of identifying and sampling the nearest garden of greater than 50 M2 , at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-14).

B.3 Sampling Deviations During 2011, environmental sampling was performed for 12 unique media types addressed in the ODCM and for direct radiation. A total of 1167 samples of 1175 scheduled were obtained. Of the scheduled samples, 99.0% 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-la for the air samples and Table B-lb for other environmental media.

B.4 Analytical Deviations There were no analytical deviations in 2011.

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

B-1

TABLE B-1 Summary of Sampling Deviations - 2011

: "MEDIA'

: ... r TOA.

SC*HEDULED NUMBER OF DEVIATIONS*

SAMPLING EFFICIENCY %

INUMBER 1REASON

" ' OF ANALYSESI

SO FOR DEVIATION o

_____ ~~~SAMPLES, _ _ _ _ _ _

MEDIA PARTICULATES IN AIR 424 99.8% 455 See Table B-la CHARCOAL FILTER 424 99.8% 423 See Table B-la TLD 164 100% 328 HUDSON RIVER WATER 24 100% 32 See Table B-i b DRINKING WATER 24 100% 56 N/A SHORELINE SOIL 10 90% 18 See Table B-i b BROAD LEAF 54 100% 54 N/A VEGETATION FISH & INVERTEBRATES 24 96% 69 See Table B-lb AQUATIC VEGETATION 6 33% 2 See Table B-lb HUDSON RIVER BOTTOM 8 100% 8 N/A SEDIMENT SOIL 3 100% 3 N/A PRECIPITATION 8 100% 16 N/A GROUNDWATER 2 100% 8 N/A SAMPLES TOTALS 1175 8 99.3% 1472 TOTAL NUMBER OF SAMPLES COLLECTED = 1167

Samples not collected or unable to be analyzed.

- Several sample types require more than one analysis B-2

TABLES B-La / B-lb TABLE B-la 2011 Air Sampling Deviations STATION WEEK PROBLEM / ACTIONS TO PREVENT RECURRENCE Roseton 16 GFCI was trippped; 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months lost. The GFCI was reset. CR-IP2-2011-01846 The Roseton 20 44 hrs of sample time loss due to GFCI trip. Breaker was reset. CR-IP2-2011-02358 air sample was moved to a new location.

Roseton 31 64.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of sample lost; GFCI was tripped. The GFCI was reset and the air sampler was left running. CR-IP2-2011-03818 NYU tower 31 64 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months of sample lost; power was de-energilzed. Restored power. CR-IP2-2011-03817 Technician discarded both air and charcoal filters. Small hole (size of a pen tip) found in Training Building 42 air filter; CR-IP2-2011-05511. Technician instructed to consult supervision prior to discarding samples.

Croton Point 44 8.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of sample time lost due to loss of power. CR-IP2-2011-05485 Peekskill 44 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months of sample time lost due to loss of power. CR-IP2-2011-05491 Note: all but the one air particulate filter and one charcoal cartridge were analyzed TABLE B-1 b 2011 Other Media Deviations STATION Week PROBLEM [ACTIONS TO PREVENT RECURRENCE Hudson River Discharge 15 Composite sample container found empty; appeared to result from the failure of the hose on the peristaltic pump. Grab sample was taken. Hose repaired. CR-IP3-2011-02260 Cole Spring, Lents Cove, The attempt to collection aquatic vegetation this spring was unsuccessful. There was no vegetation to be found at all the locations. CR-IP2-2011-03007 Verplank Roseton 20-26 Eel sample not availlable at this location (typically a seasonal species)

Cole Spring, Lents Cove, Hurricane Irene resulted in flooding conditions in the river causing it to be unsafe to take.

Discharge Canal, 39 out the boat. The bottom sediment and aquatic vegetation samples were collected when Verplank conditions improved. CR-1P2-2011-04591 Lents Cove 42 Aquatic vegetation not avaiable at this location Lents Cove 39-52 Only sediments accessible from the shore were obtained during week 39.

Note: The only samples not obtained were the 1st half of 2011 blue crab sample at Roseton, the Week 25 aquatic vegetation and the Lents Cove aquatic vegetation and shoreline sediment samples.

B-3

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2011 LOCAT'ION OF HIGHEST TYPE AND TQTAL INDICA TOR LOCATIONS: ANNUALMEA NUMBERNF iEPDIM(-NIT)lu**** NUMBER)OF

. * *. , LOCAOTIONSAND CONTROL

. . N UTIE NON-ROUTINE SEE SE:',AL :****

TABLE*i ** NALYSIS : ! LDb :*: :,: .. .. DESI~GNATIONý LOCATION: REPORTS REOT PERFORMED . MEAN (a) MEAN.(a) MEAN (a)

______- ______ __________ _ _RANGQE RAkNGE RANGE

81 Palisades Parkway DIRECT RADIATION TLD Reads NA 13.9 (160/160) / (Lake Welch Exit - DR28) 13.4 (4/4) /

(mR/standard quarter) 164 9.7- 20.1 4.96 Mi (WSW) at 3100 12.7- 13.9 B-3 19.4 (4/4) 118.6 - 20.1 AIR PARTICULATES #4 Algonquin Gas Line 00135(53/53) 0 AND RADIOIODINE GB (423) 0.01 0014 0/37 0.28 Mi (SW) at 2340 0.004-0.024 (pCi/m 3) B-6, B-7, B-8 0.0138 (53/53) / 0.003-0.027 1-131 (423) 0.07 <Lc <Lc <Lc 0 GSA (32) 0.05 <Lc <Lc <Lc 0 Cs-134 GSA (32) 0.06 <Lc <Lc <Lc 0 Cs-137 SURFACE HUDSON 661 (1/4) / #10 Discharge Canal RIVER WATER (pCi/L) H-3 (8) 3000 (c) <L, -661 0.3 Mi (WSW) at 249' <Lc 0 B-9, B-10 661 (1/4) / <Lc - 661 GSA (24)

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

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2011 LOCATION OF HIGHEST

.TYPE.AND.TOTAL ANNUAL MEAN:

M~EDIUJM(UNITS) ýNUMBER OF LL IDCTRLCTOS~ LOCATIONS AND CONTROL NO-UTE SEE TABLE ANALYSIS L (b) DESIGNATION LOCATION: NO;REORTSN INDICATOR LOATON:TUMERO PERFORMED MEAN (a) MEAN (a) MEAN,-,(a)

__________ ________RANGE RANG3E RANGE _____

DRINKING WATER H-3 (8) 2000 <Lc <Lc N/A 0 (pCi/L) B-11, B-12 GSA (24)

Mn-54 15 <Lc <Lc N/A 0 Co-58 15 <Lc <Lc N/A 0 Fe-59 30 <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Zn-65 30 <Lc <Lc N/A 0 Zr/Nb-95 15 <Lc <Lc N/A 0 1-131 15 <Lc <Lc N/A 0 Cs-134 15 <Lc <Lc N/A 0 Cs-137 18 <Lc <Lc N/A 0 Ba/La-140 15 <Lc <Lc N/A 0 HUDSON RIVER SHORELINE SOIL GSA (9)

(pCi/kg - dry) B-13 Cs-134 150 <Lc <Lc <Lc 0 108 (2/7)/ #17 Off Verplanck Cs-137 180<L - 112 1.5 Mi(2/2)

(SSW) at 202.50 <Lc 0 108 / 104 - 112 Sr-90 (10) 5000 <Lc <Lc <Lc 0 B-5 (a) Positive values above L,; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2011 LOCATION OF HIGHEST TYP LOCATIONS ANNUAL MEAN':NMEO LOCATINS AN D CONTROL NON-OU MEDIU(NITS) NUMBEOF LLD (b) INDICATOR LOCATION ANAL'SISDESIGNATION SEE TA~BL LOCATION: REOT PMEAN (a) MEAN (a) MEAN (a)

., RANGE RANGE RANGE _ __

BROADLEAF VEGETATION GSA (54)

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

(pCi/kg - wet) B-15 Mn-54 130 <Lc <Lc <Lc 0 Co-58 130 <Lc <Lc <Lc 0 Fe-59 260 <Lc <Lc <Lc 0 Co-60 130 <Lc <Lc <Lc 0

<Lc 0 Zn-65 260 <Lc <Lc

<Lc 0 Cs-134 130 <Lc <Lc

<Lc Cs-137 150 <Lc <Lc 0

<Lc 0 Ni-63 (24) 100 <Lc <Lc

<Lc <Lc <Lc n Sr-90 (24) 5 AQUATIC VEGETATION GSA(2)

(pCi/kg - WET)

B-16 Co-60 NONE <Lc <Lc <Lc 1-131 NONE <Lc <Lc <Lc Cs-134 NONE <Lc <Lc <Lc Cs-137 NONE <Lc <Lc <Lc <Lc B-6 (a) Positive values above L,; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2011 PE A~D TTALLOCATION OF HIGH4EST TYPE ACAOLOC .INS ANNUAL MEAN: NUMBER OF OF LOCATIONS AND 'CONTROL NON-ROUTINE MEDIUM(UNITIS)

SEE TAI LE i'> ANALY'SIS .. LLO(b) DESINATON DEINTO OCAION LOCATION:..... REPORTS 3/4PEERFORMED MEAN (a) MEAN (a) MEAN-(a)

....... _____ ... ___...__.. .. .... ...RANGE RANGE RANGE BOTTOM SEDIMENT (pCi/kg - DRY) GSA(8)

B-17 Co-60 NONE <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0 321 (6/6) / #17 Off Verplanck 10.88 Mi (N)Spring

84 Cold at 3560 Cs-137 180 97 1.5 Mi (SSW) at 202.50 0 366 (2/2) / 325 - 406 238 (1/2)/ <L, -

238 PRECIPITATION GSA(8)

(pCi/L)

B-18 H-3 (8) 3000 (c) <Lc <Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 SOIL (pCi/kg - DRY) GSA(3)

B-19 Co-60 NONE <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0 Cs-137 180 <Lc <Lc <Lc 0 GROUNDWATER GSA(2)

(pCi/L) B-20 H-3 (2) 3000 (c) <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Ni-63 (2) 30 <Lc <Lc N/A 0 Cs-137 18 <Lc <Lc N/A 0 Sr-90 (2) 1 <Lc <Lc N/A 0 B-7 (a) Positive values above L,; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L

TABLE B-3 2011 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER)

Si, .. .' .. .. .o<,* _ Ann . , 1i/

Station ID Sector 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MA DR-01 N 14.50 +/- 1.16 13.93 +/- 0.82 14.96 +/- 0.79 14.93 +/- 0.65 14.6 58.3 DR-02 NNE 14.37 +/- 1.09 13.51 +/- 0.85 14.37 +/- 0.65 14.54 +/- 0.68 14.2 56.8 DR-03 NE 12.07 +/- 1.03 10.35 +/- 0.62 11.78 +/- 0.59 11.68 +/- 0.61 11.5 45.9 DR-04 ENE 13.93 +/- 1.23 12.26 +/- 0.62 13.54 +/- 0.90 13.44 +/- 0.88 13.3 53.2 DR-05 ENE 14.51 +/- 1.07 12.46 +/- 0.74 13.48 +/- 0.84 1333 +/- 0.74 13.4 53.8 DR-06 ESE 14.34 +/- 1.11 13.02 +/- 0.70 14.37 +/- 0.77 14.06 +/- 0.60 14.0 55.8 DR-07 SE 15.33 +/- 1.16 14.51 +/- 0.85 16.06 +/- 0.69 16.10 +/- 1.24 15.5 62.0 DR-08 SSE 12.73 +/- 1.25 10.82 +/- 0.59 12.10 +/- 0.77 11.58 +/- 0.57 11.8 47.2 DR-09 S 13.69 +/- 1.08 12.02 +/- 0.75 13.59 +/- 0.91 12.54 +/- 0.78 13.0 51.8 DR-10 SSW 14.90 +/- 1.23 13.02 +/- 0.89 14.57 +/- 0.56 13.84 +/- 0.71 14.1 56.3 DR-11 SW 11.89 +/- 0.96 9.65 +/- 0.51 11.19 +/- 0.52 10.91 +/- 0.80 10.9 43.6 DR-12 WSW 16.05 +/- 1.23 14.19 +/- 0.83 14.81 +/- 0.60 15.43 +/- 0.78 15.1 60.5 DR-13 WSW 16.79 +/- 1.30 14.82 +/- 0.73 16.37 +/- 0.86 17.62 +/- 0.71 16.4 65.6 DR-14 WNW 13.03 +/- 1.08 12.00 +/- 0.76 12.63 +/- 0.75 13.38 +/- 0.81 12.8 51.0 DR-15 NW 13.59 +/- 1.42 11.94 +/- 0.83 13.09 +/- 0.67 13.59 +/- 0.70 13.1 52.2 DR-16 NNW 14.22 +/- 1.32 13.06 +/- 0.67 14.20 +/- 0.64 14.85 +/- 0.83 14.1 56.3 DR-17 N 14.83 +/- 1.10 13.38 +/- 0.71 14.27 +/- 0.66 14.86 +/- 0.78 14.3 57.3 DR-18 NNE 14.18 +/- 1,15 13.12 +/- 0.75 14.80 +/- 0.60 14.39 +/- 1.24 14.1 56.5 DR-19 NE 15.42 +/- 1.19 14.52 +/- 0.80 14.88 +/- 0.77 14.76 +/- 0.86 14.9 59.6 DR-20 ENE 13.67 +/- 1.13 13.18 +/- 0.78 14.09 +/- 0.70 14.20 +/- 0.93 13.8 55.1 DR-21 E 14.22 +/- 1.09 12.95 +/- 0.71 13.11 +/- 0.91 14.02 +/- 1.38 13.6 54.3 DR-22 ESE 11.90 +/- 1.10 11.33 +/- 0.59 10.98 +/- 0.79 11.02 +/- 0.54 11.3 45.2 DR-23 SE 14.02 +/- 1.03 13.92 +/- 0.81 14.20 +/- 0.84 13.77 +/- 0.72 14.0 55.9 DR-24 SSE 14.90 +/- 1.22 14.45 +/- 0.91 14.63 +/- 0.67 14.82 +/- 0.79 14.7 58.8 DR-25 S 13.07 +/- 1.15 12.24 +/- 0.75 11.97 +/- 0.54 13.18 +/- 1.84 12.6 50.5 DR-26 SSW 14.89 +/- 1.16 14.18 +/- 0.87 13.99 +/- 0.96 14.34 +/- 0.78 14.4 57.4 DR-27 SW 14.17 +/- 1.19 13.38 +/- 0.74 12.74 +/- 0.82 14.59 +/- 0.76 13.7 54.9 DR-28 NW 18.56 +/- 1.36 19.48 +/- 1.23 19.36 +/- 1.02 20.06 +/- 0.86 19.4 77.5 DR-29 W 13.84 +/- 1.16 14.46 +/- 0.86 14.02 +/- 0.73 14.47 +/- 0.86 14.2 56.8 DR-30 SNS 14.32 +/- 1.20 14.17 +/- 0.71 18.07 +/- 0.98 15.31 +/- 1.11 15.5 61.9 DR-31 WSW 16.26 +/- 1.25 16.82 +/- 1.00 16.12 +/- 0.70 17.21 +/- 0.91 16.6 66.4 DR-32 NNW 13.67 +/- 1.40 13.35 +/- 1.04 12.96 +/- 0.52 13.33 +/- 0.61 13.3 53.3 DR-33 NE 14.51 +/- 1.35 13.00 +/- 0.65 14.06 +/- 0.59 13.21 +/- 0.77 13.7 54.8 DR-34 SE 13.18 +/- 1.20 12.64 +/- 0.76 12.63 +/- 0.56 12.93 +/- 0.55 12.8 51.4 DR-35 NNE 13.18 +/- 1.25 12.73 +/- 0.78 12.61 +/- 0.75 12.80 +/- 0.85 12.8 51.3 DR-36 NE 15.93 +/- 1.26 14.65 +/- 0.87 15.22 +/- 0.89 14.38 +/- 0.73 15.0 60.2 DR-37 SSW 14.12 +/- 1.04 13.51 +/- 0.80 13.94 +/- 0.61 13.68 +/- 0.79 13.8 55.2 DR-38 S 12.23 +/- 1.05 12.26 +/- 0.69 12.74 +/- 0.61 11.97 +/- 0.64 12.3 49.2 DR-39 SSW 17.10 +/- 1.24 14.77 +/- 0.75 14.21 +/- 0.80 14.87 +/- 0.87 15.2 60.9 DR-40** N 13.25 +/- 1.08 12.72 +/- 0.76 13.89 +/- 0.58 13.78 +/- 0.73 13.4 53.6 DR-41 SSE 13.49 +/- 1.10 12.27 +/- 0.75 12.86 +/- 0.76 12.94 +/- 0.83 12.9 51.6 AVERAGE (Indicator Locations) 14.3 13.3 14.0 14.1 13.9 557

- Control Location B-8

TABLE B-4 DIRECT RADIATION, 2000 THROUGH 2010 DATA (mR per Year)

Mean Standard Minimum Value Maximum Value Station ID Deviation 2011 Mean (2001-2010) (2001 (2001-2010) (2001-2010)

DR-01 62.3 2.9 58.4 68.0 58.3 DR-02 58.0 1.9 53.6 60.0 56.8 DR-03 47.7 1.8 44.0 50.0 45.9 DR-04 54.3 315 46.8 58.8 53.2 DR-05 54.2 2.3 48.4 56.8 53.8 DR-06 54.2 3.3 46.4 57.6 55.8 DR-07 63.9 3.6 55.6 68.8 62.0 DR-08 50.8 3.2 46.6 56.4 47.2 DR-09 53.3 2.8 47.2 58.0 51.8, DR-10 57.0 2.2 53.2 60.0 56.3 DR-11 44.2 2.0 40.8 47.2 43.6 DR-12 66.1 4.5 60.8 76.0 60.5 DR-13 75.5 4.3 68.0 82.0 65.6 DR-14 53.1 1.9 50.0 56.0 51.0 DR-15 52.7 2.9 46.4 57.6 52.2 DR-16 58.4 2.0 55.2 61.6 56.3 DR-17 59.6 3.1 56.4 66.8 57.3 DR-18 56.6 2.2 52.4 59.1 56.5 DR-19 59.3 2.2 55.2 61.6 59.6 DR-20 53.1 2.8 47.6 58.8 55.1 DR-21 54.6 2.4 50.0 57.6 54.3 DR-22 45.3 2.6 40.4 50.8 45.2 DR-23 55.4 2.6 49.6 58.8 55.9 DR-24 56.6 2.8 49.2 58.8 58.8 DR-25 49.3 2.3 44.8 52.8 50.5 DR-26 55.1 2.4 50.4 58.8 57.4 DR-27 54.2 3.2 46.8 59.2 54.9 DR-28 70.9 8.9 57.2 79.1 77.5 DR-29 60.1 6.1 54.8 73.6 56.8 DR-30 59.7 4.4 52.4 68.0 61.9 DR-31 67.9 3.6 62.0 74.4 66.4 DR-32 52.0 2.9 46.0 57.2 53.3 DR-33 50.1 8.1 34.4 55.2 54.8 DR-34 51.8 4.4 43.2 60.8 51.4 DR-35 54.5 3.2 48.8 60.8 51.3 DR-36 59.2 3.2 52.4 65.6 60.2 DR-37 54.3 2.7 48.8 58.0 55.2 DR-38 51.7 3.3 48.0 58.4 49.2 DR-39 60.8 3.0 55.2 66.0 60.9 DR-40** 62.7 7.4 51.9 75.2 53.6 DR-41 51.0 2.9 44.4 55.2 51.6 Average 56.2 50.3 61.3 55.7

- Control Location B-9

TABLE B-5 2011 DIRECT RADIATION INNER AND OUTER RINGS (mR per Year)

Inner Ring Outer Ring Inner Ring Outer Ring, ID D1Sector Annual Average Annual Average DR-01 DR-17 N 58.3 57.3 DR-02 DR-18 NNE 56.8 56.5 DR-03 DR-19 NE 45.9 59.6 DR-04 DR-20 ENE 53.2 55.1 DR-05 DR-21 E 53.8 54.3 DR-06 DR-22 ESE 55.8 45.2 DR-07 DR-23 SE 62.0 55.9 DR-08 DR-24 SSE 47.2 58.8 DR-09 DR-25 S 51.8 50.5 DR-10 DR-26 SSW 56.3 57.4 DR-11 DR-27 SW 43.6 54.9 DR-12 DR-28 WSW 60.5 77.5 DR-13 DR-29 W 65.6 56.8 DR-14 DR-30 WNW 51.0 61.9 DR-15 DR-31 NW 52.2 66.4 DR-16 DR-32 NNW 56.3 53.3 Average 54.4 57.6 B-10

TABLE B-6 IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2011 GROSS BETA ACTIVITY pCi/ m 3 +/- I Sigma SAMPLE STATION #

Week , Week End 45 94 95 1 23** 27 29 44 Number Date I I I I I 1 1/4/2011 0.021 +/- 0.001 0.024 +/- 0.002 0.023 +/- 0.001 0.022 +/- 0.001 0.024 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.001 0.020 +/- 0.001 2 1/10/2011 0.020 +/- 0.002 0.018 +/- 0.001 0.020 +/- 0.002 0.017 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.002 0.019 +/- 0.001 0.018 +/- 0.002 3 1/18/2011 0.007 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 4 1/24/2011 0.011 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.002 0.015 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.002 5 1/31/2011 0.016 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 6 2/7/2011 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 7 2/14/2011 0.015 +/- 0.001 0.014 +/- 0.001 0.010 +/- 0.002 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 8 2/22/2011 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 9 2/28/2011 0.010 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 10 3/6/2011 0.018 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 11 3/13/2011 0.011 +/- 0.001 0.006 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 12 3/20/2011 0.007 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.009 - 0.001 13 3/27/2011 0.020 +/- 0.001 0.018 +/- 0.001 0.023 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 14 4/3/2011 0.027 +/- 0.002 0.025 +/- 0.002 0.027 0.001 0.024 +/- 0.001 0.024 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.001 0.026 +/- 0.002 15 4/11/2011 0.023 +/- 0.001 0.022 +/- 0.001 0.023 +/- 0.001 0.023 +/- 0.001 0.022 +/- 0.001 0.021 +/- 0.001 0.022 +/- 0.001 0.022 +/- 0.001 16 4/18/2011 0.011 +/- 0.001 0.011 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.002 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 17 4/25/2011 0.014 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 18 5/2/2011 0.006 +/- 0.001 0.005 +/- 0.001 0.007 = 0.001 0.005 +/- 0.001 0.006 +/- 0.001 0.005 +/- 0.001 0.006 +/- 0.001 0.004 +/- 0.001 19 5/9/2011 0.007 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.006 +/- 0.001 20 5/16/2011 0.003 +/- 0.001 0.005 0.001 0.004 +/- 0.001 0.005 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.006 +/- 0.001 21 5/23/2011 0.005 +/- 0.001 0.005 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0.001 0.004 +/- 0.001 22 5/31/2011 0.017 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.002 23 6/6/2011 0.012 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 24 6/13/2011 0.016 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 25 6/20/2011 0.009 1 0.001 0.008 +/- 0.001 0.008 - 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 26 6/27/2011 0.007 +/- 0.001 0.007 +/- 0.001 0.006 0.001 0.005 .+/- 0.001 0.008 +/- 0.001 0.005 +/- 0.001 0.009 +/- 0.001 0.006 +/- 0.001

- Control sample location B-11

TABLE B-6 IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2011 3

GROSS BETA ACTIVITY pCi/ M ++/- I Sigma SAMPLE STATION #

Week, Week End 4 5 94 95 23** 27 29 44 Number Date I I I I I 27 7/5/2011 0.010 +/- 0.001 0.009 +/- 0.001 0.011 - 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 28 7/11/2011 0.015 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.002 29 7/18/2011 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 30 7/25/2011 0.023 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.001 0.021 +/- 0.001 0.018 +/- 0.001 0.022 +/- 0.002 0.021 +/- 0.001 0.022 +/- 0.002 31 8/1/2011 0.011 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.002 0,012 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 32 8/8/2011 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 33 8/15/2011 0.010 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 34 8/22/2011 0.013 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.015, = 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 35 8/29/2011 0.012 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 36 9/6/2011 0.016 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 37 9/13/2011 0.009 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 38 9/19/2011 0.015 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.002 0.017 +/- 0.001 0.013 +/- 0.001 39 9/26/2011 0.008 +/- 0.001 0.004 +/- 0.001 0.006 +/- 0.001 0.005 +/- 0.001 0.009 +/- 0.001 0.004 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 40 10/3/2011 0.012 +/- 0.001 0.012 +/- 0.001 0.011 0.001 0.009 = 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 41 10/11/2011 0.022 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.001 0.021 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.001 42 10/17/2011 0.017 +/- 0.001 0.012 +/- 0.001 no data 0.015 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 43 10/24/2011 0.012 +/- 0.001 0.011 +/- 0.001 0.011 = 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 0.014 +/- 0.001 44 10/31/2011 0.012 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.002 0.012 +/- 0.001 0.010 +/- 0.001 45 11/7/2011 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 46 11/14/2011 0,023 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.001 0.024 0.001 0.023 +/- 0.002 0.024 +/- 0.002 0.025 +/- 0.001 0.021 +/- 0.002 47 11/21/2011 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0,001 0.021 +/- 0,002 0.016 +/- 0.001 0.019 +/- 0.002 48 11/28/2011 0.018 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 49 12/5/2011 0.012 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.010 0.001 50 12/12/2011 0.015 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 51 12/19/2011 0.026 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.001 0.021 +/- 0.001 0.024 +/- 0.002 0.022 +/- 0.002 0.021 +/- 0.001 0.023 +/- 0.002 52 12/27/2011 0.014 +/- 0.001 0.015 +/- 0.001 0.014 + 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 53 1/3/2012 0.012 +/- 0.001 0.014 +/- 0.001 0.013 = 0.001 0.013 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001

locations 4,5,27,94 & 95 were changed out on 10/26 (9 day samples for this week and 5 day samples thefollowing week)

- Control sample location B-1i2

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2011 Results in Units of IOE-3 pCi/ m++/- I Sigma SAMPLE LOCATIONS - IST QTR 2011 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton** #23 Grassy Point #29 Peekskill #44 Be-7 94.2 +/- 12.0 104.3 +/- 12.3 112.1 +/- 12.5 100.2 +/- 12.5 104.8 +/- 11.3 134.3 +/- 13.3 90.0 +/- 9.7 97.8 +/- 12.4 Cs-134 < 0.9 < 0.7 < 0.5 < 0.8 < 0.6 < 0.7 < 0.3 < 0.9 Cs-137 < 0.5 < 0.5 < 0.5 < 0.5 < 0.7 < 0.6 < 0.4 < 0.3 Zr-95 < 1.2 < 1.6 < 1.2 < 1.9 < 1.4 < 0.7 < 0.8 < 1.7 Nb-95 < 1.3 < 1.1 < 0.6 < 1.7 < 0.8 < 0.6 < 0.8 < 0.9 Co-58 < 0.6 < 0.6 < 0.7 < 1.2 < 1.0 < 0.4 < 0.6 < 0.4 Mn-54 < 0.4 < 0.6 < 0.7 < 0.5 < 0.6 < 0.8 < 0.3 < 0.7 Zn-65 < 1.6 < 1.1 < 0.8 < 2.0 < 1.2 < 1.3 < 1.6 < 1.0 Co-60 <0.4 < 0.4 < 0.6 < 0.6 < 0.7 < 0.5 < 0.3 < 0.6 K-40 < 7.4 < 7.7 < 3.8 < 5.8 < 5.0 < 4.3 < 4.2 < 6.7

- Control Sample Location SAMPLE LOCATIONS - 2ND QTR 2011 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton** #23 Grassy Point #29 Peekskill #44 Be-7 102.2 +/- 12.3 82.3 +/- 11.9 118.7 +/- 13.0 93.3 +/- 11.7 104.9 +/- 12.1 88.7 +/- 12.7 94.6 +/- 10.2 94.5 +/- 12.7 Cs-134 < 0.7 < 1.1 < 0.9 < 0.8 < 0.7 < 0.9 < 0.6 < 0.6 Cs-137 < 0.6 < 0.5 < 0.6 < 0.5 < 0.4 < 0.5 < 0.3 < 0.5 Zr-95 < 1.9 < 1.4 < 1.2 < 1.0 < 0.6 < 1.1 < 0.7 < 1.5 Nb-95 < 1.5 < 1.6 < 1.9 < 0.9 < 0.6 < 2.3 < 0.6 < 1.1 Co-58 < 0.9 < 0.8 < 0.8 < 0.6 < 1.0 < 1.0 < 0.6 < 0.9 Mn-54 < 0.3 < 0.7 < 0.6 < 0.4 < 0.5 < 0.8 < 0.5 < 0.7 Zn-65 < 1.4 < 2.0 < 1.0 < 1.4 < 0.8 < 0.7 < 1.1 < 1.4 Co-60 < 0,8 < 0.8 < 0.4 < 0.3 < 0.5 < 0.6 < 0.3 < 0.5 K-40 < 4,6 42.5 +/- 9.3 < 7.6 < 3.0 < 3.6 < 5.6 < 3.5 < 5.1

- Control Sample Location B-13

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2011 m3 Results in Units of 10E-3 pCi/m 1 Sigma SAMPLE LOCATIONS - 3RD QTR 2011 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton** #23 Grassy Point #29 Peekskill #44 Be-7 111.7 +/- 13.1 118.7 +/- 12.7 110.9 +/- 12.0 88.5 +/- 10.7 102.5 +/- 12.4 87.9 +/- 12.9 80.6 +/- 10,0 106.5 +/- 13.9 Cs-134 < 1.1 < 0.9 < 0.5 < 0.6 < 0.7 < 0.9 < 0.6 < 0.4 Cs-137 < 0.6 < 0.6 < 0.3 < 0.2 < 0.7 < 0.6 < 0.2 < 0.8 Zr-95 < 2.2 < 1.9 < 1.4 < 1.1 < 1.3 < 1.4 < 1.2 < 1.1 Nb-95 < 1.4 < 1.4 < 1.2 < 1.0 < 1.5 < 1.2 < 1.3 < 0.9 Co-58 < 0.8 < 0.7 < 0.5 < 0.4 < 1.0 < 0.7 < 0.5 < 1.0 Mn-54 < 0.4 < 0.3 < 0.3 < 0.3 < 0.6 < 0.4 < 0.4 < 0.6 Zn-65 < 1.6 < 1.5 < 1.6 < 1.2 < 1.9 < 1.7 < 1.2 < 1.5 Co-60 < 0.6 < 0.7 < 0.5 < 0.6 < 0.9 < 0.6 < 0.6 < 0.5 K-40 <10.3 < 4.2 < 5.3 < 4.8 < 5.7 < 8.4 < 4.3 < 4.7

- Control Sample Location SAMPLE LOCATIONS - 4TH QTR 2011 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton** #23 Grassy Point #29 Peekskill #44 Be-7 50.9 +/- 9.2 50.1 +/- 5.9 75.4 +/- 7.3 70.6 +/- 6.0 54.3 +/- 6.0 58.6 +/- 7.3 45.7 +/- 6.7 59.8 +/- 5.0 Cs-134 < 2.4 < 1.3 < 1.9 < 1.7 < 1.5 < 2.3 < 1.7 < 1.4 Cs-137 < 1.7 < 1.1 < 1.4 < 1.5 < 1.3 < 1.5 < 1.3 < 1.1 Zr-95 < 2.7 < 2.2 < 2.9 < 2.2 < 1.9 < 3.4 < 2.5 < 1.7 Nb-95 < 2.1 < 1.3 < 2.2 < 1.7 < 1.6 < 1.8 < 1.7 < 1.3 Co-58 < 1.8 < 0.9 < 2.0 < 1.6 < 1.4 < 1.7 < 1.4 < 1.1 Mn-54 < 1.6 < 0.9 < 1.3 < 1.5 < 1.0 < 1.5 < 1.1 < 0.8 Zn-65 < 3.5 < 2.5 < 4.5 < 4.4 < 3.5 < 5.0 < 3.4 < 3.6 Co-60 < 1.9 < 1.3 < 1.3 < 1.8 < 1.4 < 1.5 < 1.4 < 1.1 K-40 < 19.2 < 22.5 < 26.9 < 17.8 < 23.4 < 29.8 < 21.6 < 19.6

- Control Sample Location I

B-14

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2011 3

1-131 ACTIVITY pCi/ m =LI Sigma SAMPLE STATION #

Week Week End 4 5 94 95 23** 27 29 44 Number Date I I I 2 2 2 44 01/04/11 < 0.019

0.019 < 0.023

0.021

0.016 < 0.023

0.013 < 0.015 01/10/11 < 0.019

0.017 < 0.026

0.028

0.018 < 0.033

0.012 < 0.030 01/18/11 < 0.020 < 0.019 < 0.022

0.019

0.017 < 0,020

0.013 < 0.019 01/24/I1 < 0.023

0.023 < 0.032

0.017

0.026 < 0.025

0.025 < 0.021 01/31/l1 < 0.021

0.021 < 0.023

0.016

0.021 < 0.026

0.020 < 0.029 02/07/1I < 0.019

0.016 < 0.010

0.019

0.017 < 0.014

0.014 < 0.016 02/14/I1 < 0.020

0.023 < 0.063

0.023

0.025 < 0.022

0.014 < 0.020 02/22/11 < 0.022

0.018 < 0.030

0.012

0.017 < 0.019

0.010 < 0.014 02/28/I1 < 0.022

0.024 < 0.020

0.021

0.027 < 0.027

0.011 < 0.028 03/06/Il < 0.025

0.023 < 0.014

0.022

0.021 < 0.019

0.013 < 0.032 03/13/11 < 0.023

0.018 < 0.012

0.015

0.018 < 0.017

0.015 < 0.021 03/20/I1 < 0.018

0.016 < 0.018

0.023

0.020 < 0.031

0.016 < 0.018 03/27/11 0.057+0.01 0.044+0.01 0.051+0.01 0.039+0.01 0.045+0.01 0.041+0.01 0.059+0.01 0.042+0.01 04/03/I1 0.065+0.008 0.080+0.009 0.084+0.007 0.076+0.008 0.062+0.008 0.064+0.008 0.064+0.007 0,062+0.008 04/11/1 0.047+0.006 0.043+0.006 0.042+0.005 0.051+0.006 0.050+0.007 0.044+0.006 0.041+0.0004 0.044+0.007 04/18/11

0.026

0.023 < 0.019

0.019

0.035 < 0.021

0.012 < 0.034 04/25/11

0.027

0.018 < 0.018

0.020

0.020 < 0.025

0.015 < 0.018 05/02/I1

0.020

0.023 < 0.018

0.014

0.021 < 0.025

0.019 < 0.028 05/09/11

0.027

0.021 < 0.019

0.023

0.027 < 0.019

0.017 < 0.032 05/16/1I

0.022

0.019 < 0.019

0.025

0.030 < 0.021

0.013 < 0.021 05/23/I1

0.022

0.023 < 0.023

0.018

0.025 < 0.014

0.024 < 0.023 05/31/1I

0.020

0.029 < 0.016

0.017

0.021 < 0.021

0.016 < 0.019 06/06/11

0.022

0.012 < 0.016

0.028

0.024 < 0.029

0.014 < 0.027 06/13/11

0.020

0.019 < 0.016

0.027

0.024 < 0.022

0.013 < 0.028 06/20/I1

0.025

0.025 < 0.014

0.030

0.022 < 0.011

0.014 < 0.023 06/27/1I

0.019

0.018 < 0.019

0.019

0.024 < 0.020

0.016 < 0.024

- Control sample location B-15

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2011 1-131 ACTIVITY pCi/rm 3 +/- I Sigma SAMPLE STATION #

Week I WeekEd 4 5 94 95 23** 27 29 44 Number Date I I I 07/05/11 0.024 0.023 0.016 < 0.027 < 0.015 < 0.019 < 0.014 0.013 07/11/I1 0.021 0.033 0.018 < 0.028 < 0.022 < 0.021 < 0.015 0.024 07/18/11 0.024 0.023 0.020 < 0.024 < 0.021 < 0.018 < 0.014 0.028 07/25/1I 0.032 0.014 0.019 < 0.019 < 0.025 < 0.014 < 0.019 0.015 08/01/11 0.025 0.031 0.018 < 0.019 < 0.036 < 0.016 < 0.017 0.027 08/08/11 0.017 0.018 0.018 < 0.018 < 0.020 < 0.018 < 0.019 0.025 08/15/1I 0.015 0.016 0.024 < 0.017 < 0.020 < 0.021 < 0.014 0.019 08/22/I1 0.025 0.019 0.022 < 0.019 < 0.026 < 0.004 < 0.017 0.025 08/29/11 0.026 0.018 0.020 < 0.023 < 0.020 < 0.011 < 0.018 0.023 09/06/11 0.020 0.014 0.015 < 0.022 < 0.020 < 0.012 < 0.011 0.015 09/13/1I 0.023 0.022 0.013 < 0.020 < 0.020 < 0.014 < 0.018 0.025 09/19/I1 0.018 0.028 0.029 < 0.019 < 0.027 < 0.024 < 0.017 0.020 09/26/11 0.017 0.027 0.020 < 0.019 < 0.017 < 0.027 < 0.017 0.025 10/03/11 0.024 0.018 0.020 < 0.020 < 0.025 < 0.026 < 0.019 0.028 10/11/11 0.025 0.026 0.024 < 0.020 < 0.022 < 0.025 < 0.017 0.024 10/17/11 0.007 0.006 < 0.006 < 0.010 < 0.006 < 0.008 0.011 10/24/11 0.028 0.028 <K 0.026 < 0.021 < 0,036 < 0.027 < 0.027 0.038 K

10/31/11 0.030 0.030 0.027 < 0.044 < 0.035 < 0.031 < 0.026 0.043 K

11/07/11 0.026 0.026 0.024 < 0.028 < 0,031 < 0.025 < 0.024 0.033 K

11/14/11 0.043 0.043 0.040 < 0.049 < 0,056 < 0.042 < 0.041 0.059 11/21/I1 K2 0.040 0.040 0.037 < 0.022 < 0.025 < 0.040 < 0.018 0.026

<K 11/28/11 0.019 0.018 0.017 < 0.017 < 0,018 < 0.018 < 0.014 0.019 12/05/11 K 0.029 0.029 0.027 < 0.033 < 0.036 < 0.029 < 0.027 0.038 K

12/12/11 0.020 0.020 0.018 < 0.020 < 0.022 < 0.019 < 0.017 0.024 12/19/11 <K 0.021 0.022 0.020 < 0.022 < 0.024 < 0.021 < 0.018 0.025 12/27/11 K 0.018 0.018 0.017 < 0.017 < 0.018 < 0.018 < 0.013 0.018 01/03/12 0.020 <

0.019 0.018 < 0.020 < 0.022 < 0.019 < 0.016 0.024

locations 4,5.27,94 & 95 were changed out on 10/26 (9 day samples for this week and 5 day samples the following week)

- Control sample location *** Small puncture on particulate filter, both filter and cartridge discarded by REMP technician B-16

TABLE B-9 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter +/- I Sigma

9 PLANT INLET (HUDSON RIVER INTAKE)

Date 1/31/2011 2/28/2011 3/27/2011 4/25/2011 5/31/2011 6/27/2011 NUCLIDE 1-131 < 4.05 < 3.13 < 3.85 < 3.23 < 3.64 < 2.96 Cs-134 < 0.61 < 0.67 < 0.73 < 0.73 < 0.67 < 0.69 Cs-137 < 0.83 < 0.92 < 1.10 < 0.92 < 0.96 < 0.95 Zr-95 < 1.60 < 1.90 < 2.18 < 1.94 < 1.84 < 1.67 Nb-95 < 1.15 < 1.09 < 1.33 < 1.14 < 1.24 < 1.12 Co-58 < 0.97 < 0.95 < 1.17 < 1.14 < 1.08 < 0.86 Mn-54 < 0.82 < 0.85 < 1.18 < 0.96 < 0.89 < 0.88 Fe-59 < 2.52 < 2.68 < 2.52 < 2.48 < 3.10 < 2.79 Zn-65 < 1.03 < 1.95 < 2.28 < 2.14 < 2.14 < 1.91 Co-60 < 0.84 < 0.81 < 1.08 < 0.92 < 0.99 < 0.94 K-40 51.66 +/- 7.39 36.68 +/- 7.34 114.8 +/- 11.91 35.61 +/- 8.21 45.21 +/- 8.13 < 8.64 Ba/La-140 < 2.50 < 2.14 < 2.73 < 2.12 < 2.43 < 2.03 Date 7/25/2011 8/30/2011 9/26/2011 1/1/2011 11/28/2011 12/27/2011 NUCLIDE 1-131 < 3.02 < 3.78 < 4.08 < 7.58 < 7.79 < 10.4 Cs-134 < 1.09 < 0.83 < 1.47 < 4.60 < 4.59 < 4.49 Cs-137 < 1.06 < 1.07 < 1.19 < 4.45 < 4.35 < 6.64 Zr-95 < 2.03 < 2.14 < 2.27 < 8.95 < 6.56 < 9.38 Nb-95 < 1.48 < 1.48 < 1.41 < 4.98 < 3.76 < 5.75 Co-58 < 1.11 < 1.27 < 1.38 < 3.47 < 3.88 < 5.54 Mn-54 < 1.02 < 1.16 < 1.29 < 4.77 < 3.26 < 4.53 Fe-59 < 2.95 < 3.33 < 3.44 < 11.3 < 8.20 < 11.3 Zn-65 < 2.22 < 1.60 < 2.68 < 8.49 < 8.25 < 11.1 Co-60 < 1.10 < 1.05 < 1.24 < 4.25 < 4.38 < 5.64 K-40 183.2 +/- 12.94 120.0 +/- 12.63 19.46 +/- 9.87 < 68.90 < 61.8 < 60.3 Ba/La-140 < 2.32 < 3.04 < 3.12 < 9.32 < 5.33 < 9.17 B-17

TABLE B-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES -2011 Results in Units of pCi/liter +/- 1 Sigma

10 DISCHARGE CANAL (MIXING ZONE)

Date 1/31/2011 2/28/2011 3/27/2011 4/25/2011 5/31/2011 6/27/2011 NUCLIDE 1-13t < 3.92 < 3.40 < 2.68 < 3.73 < 3.48 < 2.92 Cs-134 < 1.08 < 0.85 < 1.17 < 1.39 < 0.77 < 0.83 Cs-137 < 1.10 < 1.04 < 1.03 < 1.07 < 1.11 < 1.17 Zr-95 < 1.77 < 2.08 < 2.05 < 2.12 < 2.22 < 1.82 Nb-95 < 1.20 < 1.27 < 1.28 < 1.63 < 1.54 < 1.25 Co-58 < 1.11 < 1.16 < 1.10 < 1.34 < 1.17 < 1.09 Mn-54 < 0.98 < 1.02 < 0.99 < 1.17 < 1.16 < 1.10 Fe-59 < 3.37 < 3.18 < 2.97 < 3.52 < 3.44 < 2.94 Zn-65 < 2.39 < 2.48 < 2.20 <. 1.40 < 2.60 < 2.63 Co-60 < 0.86 < 0.98 < 1.11 < 1.00 < 1.15 < 1.13 K-40 122.4 +/- 10.77 119.5 +/- 12.16 202.3 +/- 13.17 131.2 +/- 12.81 75.98 +/- 10.99 131.9 +/- 11.99 Ba/La-140 < 2.57 < 2.53 < 2.09 < 2.62 < 2.69 < 2.92 Date 7/25/2011 T 8/30/2011 T 9/26/2011 11/1/2011 11/28/2011 12/27/2011 NUCLIDE 1-131 < 2.79 < 4.34 < 3.40 < 8.81 < 13.3 < 8.60 Cs-134 < 0.70 < 1.39 < 0.87 < 5.43 < 6.32 < 5.12 Cs-137 < 0.93 < 1.15 < 1.12 < 5.65 < 6.69 < 4.66 Zr-95 < 1.72 < 2.43 < 2.26 < 9.95 < 15.4 < 8.76 Nb-95 < 1.25 < 1.49 < 1.51 < 6.23 < 6.81 < 5.05 Co-58 < 0.98 < 1.25 < 1.14 < 3.92 < 7.09 < 5.51 Mn-54 < 0.90 < 1.24 < 1.10 < 5.65 < 6.84 < 4.31 Fe-59 < 2.67 < 4.29 < 3.17 < 10.8 < 14.4 < 9.45 Zn-65 < 1.13 < 2.50 < 1.38 < 12.0 < 10.2 < 8.82 Co-60 < 0.84 < 1.12 < 1.03 < 4.67 < 6.09 < 4.70 K-40 40.59 +/- 8.03 79.5 +/- 12.38 144.2 +/- 12.97 < 46.7 < 60.1 < 84.2 Ba/La-140 < 1.70 < 3.47 < 2.23 < 8.40 < 10.0 < 9.10 B-18

TABLE B-10 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2011 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/! +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM Start End First Quarter 12/28/10 03/27/11 <417 PLANT INTAKE (HUDSON RIVER) Second Quarter 03/27/11 06/27/11 < 424 (09, INLET) ** Third Quarter 06/27/11 09/26/11 < 412 Fourth Quarter 09/26/11 01/00/00 < 190 First Quarter 12/28/10 03/27/11 661 +/- 92 DISCHARGE CANAL Second Quarter 03/27/11 06/27/11 < 424 (10, MIXING ZONE) Third Quarter 06/27/11 09/26/11 < 412 Fourth Quarter 09/26/11 01/00/00 < 182

- Control Sample location B-19

TABLE B-11 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter +/- I Sigma CAMP FIELD RESERVOIR Date T 1/19/2011 2/14/2011 3/13/2011 4/11/2011 5/16/2011 6/20/2011 NUCLIDE 1-131 < 4.22 < 2.44 < 2.31 < 2.31 < 2.10 < 4.03 Cs-134 < 2.05 < 2.38 < 2.30 < 1.44 < 2.02 < 1.94 Cs-137 < 3.23 < 1.95 < 1.90 < 2.08 < 2.43 < 3.44 Zr-95 < 4.83 < 2.91 < 3.93 < 2.63 < 3.39 < 5.54 Nb-95 < 3.46 < 2.22 < 2.53 < 1.91 < 2.03 < 3.16 Co-58 < 2.94 < 2.21 < 2.25 < 1.79 < 1.92 < 3.02 Mn-54 < 3.26 < 1.97 < 1.79 < 1.75 < 1.76 < 2.86 Fe-59 < 9.55 < 5.02 < 5.74 < 4.38 < 5.39 < 9.15 Zn-65 < 9.84 < 5.29 < 4.89 < 4.91 < 4.01 < 8.42 Co-60 < 4.10 < 2.02 < 2.37 < 1.56 < 2.16 < 3.35 K-40 290.6 +/- 44.90 162.7 +/- 24.10 88.56 +/- 22.31 < 17.84 179.5 +/- 26.11 292.3 +/- 42.31 Ba/La-140 < 4.74 < 2.89 < 3.11 < 1.93 < 3.08 < 3.76 Gross Beta 1.97 +/- 0.53 2.58 +/- 0.60 2.70 +/- 0.90 1.14 +/- 0.20 1.58 +/- 0.50 1.74 +/- 0.40 Date 7/11/2011 8/8/2011 9/26/2011 10/18/2011 11/15/2011 12/21/2011 NUCLIDE 1-131 < 3.01 < 2.32 < 3.55 < 13.6 < 6.29 < 8.01 Cs-134 < 2.01 < 1.06 < 2.03 < 5.89 < 5.91 < 3.93 Cs-137 < 1.88 < 2.20 < 2.92 < 5.99 < 6.43 < 4.37 Zr-95 < 4.47 < 2.97 < 3.48 < 9.60 < 9.29 < 8.07 Nb-95 < 2.82 < 1.26 < 2.49 < 7.23 < 6.46 < 6.17 Co-58 < 2.25 < 1.68 < 2.45 < 5.66 < 5,71 < 4.46 Mn-54 < 2.58 < 1.87 < 2.25 < 5.95 < 6.00 < 5.16 Fe-59 < 6.18 < 4.76 < 6.92 < 12.5 < 11.1 <8.86 Zn-65 < 4.95 < 3.92 < 7.05 < 10.6 < 11.4 < 11.0 Co-60 < 2.38 < 1.87 < 2.59 < 4.79 < 5.15 < 4.15 K-40 146.8 +/- 25.17 < 13.63 203.6 +/- 37.55 < 53.0 < 107 < 48.7 Ba/La-140 < 1.78 < 2.84 < 4.40 < 8.44 < 7.23 <9.02 Gross Beta 2.61 +/- 0.50 3.86 +/- 0.57 2.10 +/- 0.50 < 2.29 < 1.74 1.52 +/- 0.50 B-20

TABLE B-I 1l(Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter +/- 1 Sigma NEW CROTON RESERVOIR Date 1/19/2011 2/14/2011 3/13/2011 4/11/2011 5/16/2011 6/20/2011 NUCLIDE 1-131 < 2.66 < 4.08 < 2.70 < 2.11 < 2.02 < 3.50 Cs- 134 < 1.42 < 2.00 < 2.50 < 2.93 < 1.33 < 3.17 Cs-137 < 1.85 < 2.41 < 2.52 < 2.53 < 1.49 < 2.41 Zr-95 < 3.42 < 4.50 < 3.77 < 3.43 < 2.63 < 3.82 Nb-95 < 1.75 < 2.91 < 2.59 < 1.73 < 2.05 < 2.18 Co-58 < 1.87 < 2.97 < 2.58 < 2.20 < 1.95 < 2.53 Mn-54 < 1.38 < 2.71 < 2.75 < 1.79 < 1.87 < 3.10 Fe-59 < 2.97 < 6.53 < 6.64 < 3.76 < 3.64 < 9.11 Zn-65 < 4.36 < 6.11 < 7.88 < 5.06 < 4.52 < 5.67 Co-60 < 1.37 < 2.76 < 2.69 < 1.61 < 2.14 < 1.69 K-40 < 17.08 186.7 +/- 36.59 < 20.25 76.98 +/- 20.98 < 19.94 206.8 +-37.01 Ba/La-140 < 2.62 < 2.56 < 4.69 < 2.10 < 2.91 <2.81 Gross Beta 1.90 +/- 0.50 2.42 +/- 0.50 2.07 +/- 0.80 0.87 +/- 0, 19 2.17 +/- 0.50 2.03 +-0.40 Date 7/11/2011 8/8/2011 9/26/2011 10O/18/2100 11/15/2011 12/19/2011I NUCLIDE 1-131 < 2.30 < 2.36 < 2.71 < 10.6 < 7.85 < 14.1 Cs-134 < 1.25 < 2.66 < 1.19 < 5,03 < 6.33 < 3.27 Cs-137 < 1.95 < 2.15 < 1.75 <5,40 < 7.52 < 4.07 Zr-95 < 2.82 < 3.27 < 3.51 < 9.07 < 7.74 < 6.85 Nb-95 < 1.91 < 2.13 < 2.31 < 6,65 < 6.26 < 4.22 Co-58 < 1.85 < 2.02 < 1.82 < 5.84 < 5.75 < 2.78 Mn-54 < 1.08 < 2.11 < 1.72 < 5.13 < 6.34 < 3.58 Fe-59 < 4.77 < 3.81 < 5.86 < 11.6 < 13.9 < 9.27 Zn-65 < 4.20 < 5.40 < 4.87 < 11,0 < 11.8 < 8.44 Co-60 < 2.08 < 2.08 < 1.92 < 5.86 < 6.18 < 4.85 K-40 < 17.08 83.5 +/- 23.16 177 +/- 26.76 < 51.7 < 118 < 34.1 Ba/La-14 < 2.17 < 2.95 < 3.42 < 10.2 < 8.03 < 9.49 Gross Beta 2.52 +/- 0.50 4.03 +/- 0.50 2.80 +/- 0.50 < 2.24 < I1..72 2.5 3 +/- =0.55 B-21

TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES - 2011 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM First Quarter 12/13/10 03/13/11 < 409 CAMP FIELD RESERVOIR Second Quarter 03/13/11 06/20/11 < 425 Third Quarter 06/20/11 09/26/11 < 412 Fourth Quarter 09/26/11 12/19/11 < 194 First Quarter 12/13/10 03/13/11 < 409 NEW CROTON RESEVOIR Second Quarter 03/13/11 06/20/11 < 425 Third Quarter 06/20/11 09/26/11 < 412 Fourth Quarter 09/26/11 12/19/11 < 193 B-22

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SEDIMENT SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma Sample COLD SPRING LENTS COVE MANITOU VERPLANCK WHITE BEACH Location SHORELINE SHORELINE SHORELINE SHORELINE SHORELINE Date 6/14/2011 6/16/2011 6/14/2011 6/16/2011 6/16/2011 Client ID Req. ISS842511 ISS282511 ISS502511 ISS172511 ISS532511 CL Radionuclide (pCi) I Be-7 < 282.9 < 338.9 < 387.0 < 214.9 < 118.1 1-131 < 65.1 < 48.9 < 71.6 < 34.4 < 26.1 Cs-134 75 < 19.2 < 32.8 < 37.2 < 19.6 < 15.7 Cs-137 90 < 39.0 < 45.8 < 45.9 104.1 +/- 25.4 < 19.8 Zr-95 < 64.6 < 70.4 < 82.0 < 40.5 < 36.2 Nb-95 < 48.6 < 43.8 < 70.3 < 26.1 < 19.0 Co-58 < 43.8 < 40.4 < 46.3 < 23.5 < 15.4 Mn-54 < 41.2 < 42.8 < 53.3 < 20.8 < 17.7 Zn-65 < 68.1 < 53.6 < 77.3 < 36.0 < 64.5 Fe-59 < 135.5 < 108.1 < 129.7 < 64.0 < 48.3 Co-60 < 44.0 < 37.6 < 42.1 < 26.9 < 22.3 Ba/La-1 40 < 73.0 < 50.0 < 97.4 < 21.7 < 20.6 Ru-103 < 34.4 < 44.5 < 54.6 < 23.3 < 23.2 Ru-106 < 327.1 < 407.0 < 515.6 < 246.5 < 208.1 Ce-141 < 51.6 < 57.4 < 82.0 < 38.5 < 31.7 Ce-144 < 190.5 < 235.1 < 333.1 < 182.6 < 117.1 AcTh-228 574.3 +/- 122.3 1627.0 +/- 170.0 1818.0 +/- 215.1 691.3 +/- 94.3 131.6 +/- 64.9 Ra-226 < 703.2 5046.0 +/- 796.3 5336.0 +/- 965.7 2077.0 +/- 475.1 619.3 +/- 299.7 K-40 _ 36910.0 +/- 1270.0 13900.0 +/- 861.4 13430.0 +/- 1073.0 16240.0 +/- 682.4 12230.0 +/- 644.9 Sr-90 I_ I_ < 27.2 < 34.9 < 29.9 < 31.0 < 31.5 B-23

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SEDIMENT SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma Sample COLD SPRING MANITOU VERPLANCK WHITE BEACH Location SHORELINE SHORELINE SHORELINE SHORELINE Date 9/20/2011 9/20/2011 9/20/2011 9/20/2011 Client ID ISS843911 ISS503911 ISS173911 1SS533911 Req. CL Radionuclide (pCi)

Be-7 < 248.7 < 226.0 < 166.0 < 186.0 1-131 < 55.5 < 61.1 < 46.0 < 37.2 Cs-134 75 < 21.2 < 41.4 < 17.9 < 13.6 Cs-137 90 < 31.2 < 29.1 111.6 +1- 24.3 < 19.8 Zr-95 < 52.1 < 44.6 < 43.5 < 35.4 Nb-95 < 38.6 < 44.1 < 30.4 < 19.9 Co-58 < 30.3 < 35.2 < 29.2 < 17.5 Mn-54 < 33.0 < 31.1 < 22.0 < 18.8 Zn-65 < 101.4 < 46.4 < 96.9 < 42.5 Fe-59 < 128.5 < 83.8 < 82.6 < 65.9 Co-60 < 35.1 < 29.0 < 22.6 < 18.0 Ba/La-140 < 43.9 < 60.2 < 34.9 < 27.6 Ru-103 < 31.3 < 35.8 < 24.8 < 21.6 Ru-106 < 261.9 < 339.5 < 272.9 < 216.1 Ce-141 < 49.0 < 64.5 < 39.9 < 31.1 Ce-144 < 176.5 < 217.9 < 144.8 < 119.5 AcTh-228 281.4 +/- 96.4 713.2 +1- 116.3 535.7 +1- 103.6 237.1 +/- 60.8 Ra-226 < 631.6 1813.0 +/- 564.9 1474.0 +/- 428.0 752.6 +/- 348.9 K-40 36860.0 +/- 1174.0 14370.0 +/- 823.5 16930.0 +/- 771.5 8437.0 +/- 509.1 Sr-90 < 32.0 < 33.9 < 27.7 < 29.4 B-24

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES- 2011 Results in Units of pCi/kg +/- I Sigma

95 Meteorological Tower Sample MET TOWER MET TOWER MET TOWER MET TOWER Location MET TOWER MET TOWER Date 5/23/2011 5/23/2011 5/23/2011 6/27/2011 6/27/2011 6/27/2011 Client ID IBV952111SI IBV9521 IIS2 IBV95211 IS3 IBV952611SI IBV95261 IS2 1BV95261 IS3 Req. CL RAGWEED MULLEN BURDOCK BURDOCK RAGWEED MULLEIN Radionuclide (pCi) I I I I I Be-7 1349.0 +/- 95.1 888.5 +/- 132.1 1129.0 +/- 110.2 1459.0 -+/- 120.9 1437.0 +/- 140.5 1555.0 +/- 157.0 1-131 50 < 13.56 < 22.61 < 13.80 < 12.13 < 15.44 < 20.00 Cs-134 50 < 12.10 < 11.49 < 13.04 < 8.87 < 17.79 < 13.42 Cs-137 50 < 8.56 < 16.76 < 9.76 < 13.07 < 14.04 < 14.46 Zr-95 < 11.77 < 27.70 < 17.57 < 21.31 < 27.83 < 20.73 Nb-95 < 9.59 < 22.20 < 10.66 < 13.57 < 16.50 < 13.73 Co-58 < 8.77 < 14.23 < 10.98 < 12.95 < 12.63 < 14.66 Mn-54 < 7.84 < 16.12 < 11.70 < 11.47 < 13.89 < 13.17 Zn-65 < 27.49 < 22.58 < 31.74 < 32.24 < 38.65 < 43.86 Fe-59 < 28.14 < 47.10 < 27.17 < 27.01 < 40.42 < 42.57 Co-60 < 9.12 < 15.76 < 10.31 < 10.43 < 14.94 < 14.49 BaILa-140 < 7.60 < 22.55 < 10.67 < 16.35 < 15.89 < 21.53 Ru-103 < 9.32 < 15.10 < 11.23 < 11.21 < 14.30 < 15.74 Ru-106 < 90.08 < 143.60 < 96.31 < 120.50 < 129.00 < 162.90 Ce-141 < 12.33 < 22.52 < 14.28 < 15.66 < 19.28 < 20.46 Ce-144 < 45.40 < 74.92 < 58.30 < 60.63 < 74.01 < 90.20 AcTh-228 < 34.36 < 67.16 < 40.81 < 42.96 < 57.08 < 54.34 Ra-226 < 134.90 < 278.20 < 217.60 468.2 +/- 191.5 < 271.10 < 293.50 K-40 5477.0 +/- 239.1 5916.0 +/- 374.2 5222.0 +/- 277.1 8440.0 +/- 357.4 9785.0 +/- 436.3 7137.0 +/- 380.6 B-25

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- I Sigma

95 Meteorological Tower Sample MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER Location MET TOWER Date 7/18/2011 7/18/2011 7/18/2011 8/15/2011 8/15/2011 8/15/2011 Client ID IBV95291 ISI IBV95291 IS2 IBV952911 S3 IBV95331 ISI IBV95331 IS2 IBV95331 IS3 Req. CL RAGWEED BITTERSWEET COTTONWOOD COTTON WILD GRAPE RAGWEED Radionuclide (pCi) I I IIII Be-7 1656.0 +1- 119.1 232.7 +/- 146.0 1057.0 +1- 115.5 1923.0 +1- 117.1 1583.0 +1- 127.2 3374.0 +1- 200.6 1-131 50 < 13.50 < 25.40 < 15.10 < 11.23 < 15.04 < 15.67 Cs-134 50 < 15.86 < 16.10 < 17.71 < 13.96 < 9.10 < 14.28 Cs-137 50 < 9.58 < 26.89 < 15.55 < 11.03 < 12.68 < 16.33 Zr-95 < 16.52 < 30.80 < 22.70 < 19.61 < 20.53 < 26.43 Nb-95 < 9.74 < 23.53 < 13.04 < 13.70 < 12.22 < 18.86 Co-58 < 11.53 < 18.76 < 15.26 < 9.96 < 9.97 < 18.11 Mn-54 < 12.08 < 19.82 < 10.92 < 11.23 < 11.68 < 16.70 Zn-65 < 31.65 < 79.78 < 35.03 < 21.96 < 26.23 < 46.86 Fe-59 < 25.48 < 84.76 < 35.30 < 34.77 < 32.02 < 52.57 Co-60 < 12.62 < 29.72 < 15.17 < 8.81 < 11.39 < 19.47 Ba/La-140 < 7.80 < 35.30 < 15.84 < 14.60 < 18.27 < 20.82 Ru-103 < 12.62 < 23.84 < 12.99 < 10.27 < 12.62 < 16.28 Ru-106 < 93.55 < 224.70 < 143.20 < 109.30 < 133.50 < 165.70 Ce-141 < 15.73 < 28.22 < 15.41 < 13.89 < 15.85 < 21.27 Ce-144 < 63.09 < 113.30 < 69.71 < 56.37 < 70.68 < 86.64 AcTh-228 < 49.57 < 94.14 < 51.62 < 40.60 < 39.73 < 70.16 Ra-226 < 229.30 < 421.80 771.7 +/- 222.9 650.7 +/- 213.7 490.6 +/- 196.3 < 308.10 K-40 8857.0 +/- 352.2 5841.0 +/- 454.4 7578.0 +/- 359.5 4843.0 +/- 265.9 2415.0 +/- 196.5 7804.0 +/- 430.6 B-26

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- I Sigma

95 Meteorological Tower Sample MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER Location MET TOWER Date 9/13/2011 9/13/2011 9/13/2011 10/11/2011 10/11/2011 10/11/2011 Client ID IBV95371 ISI 1BV95371 IS2 IBV95371 IS3 IBV9541 I ISI IBV954111S2 IBV9541 I IS3 Req. CL RAWE Raq.uCLdRAGWEED COTTONWOOD GRAPE LEAVES KNOTWEED RAGWEED SAWGRASS lRadionuclidel (pCi)IIIIII Be-7 5209.0 +/- 188.6 2353.0 +/- 165.2 1233.0 +/- 124.7 1136.0 +/- 141.2 7182.0 +/- 219.9 4786.0 +/- 209.0 1-131 50 < 15.04 < 13.58 < 12.80 < 22.90 < 21.43 < 23.51 Cs-134 50 < 8.82 < 11.81 < 10.91 < 9.89 < 9.32 < 18.69 Cs-137 50 < 10.63 < 10.09 < 12.47 < 15.14 < 13.09 < 17.57 Zr-95 < 17.83 < 19.25 < 19.92 < 25.68 < 21.79 < 25.26 Nb-95 < 12.07 < 15.63 < 11.44 < 16.82 < 11.15 < 18.40 Co-58 < 10.63 < 14.12 < 12.99 < 15.06 < 13.07 < 16.41 Mn-54 < 12.01 < 12.90 < 10.73 < 13.00 < 10.86 < 15.49 Zn-65 < 30.07 < 42.44 < 32.71 < 35.56 < 36.36 < 21.03 Fe-59 < 30.43 < 42.71 < 35.48 < 37.81 < 32.14 < 47.72 Co-60 < 12.51 < 13.78 < 15.06 < 15.97 < 14.07 < 13.31 Ba/La-140 < 11.05 < 15.41 < 17.64 < 23.56 < 12.26 < 22.62 Ru-103 < 11.30 < 10.27 < 11.37 < 14.36 < 12.57 < 16.79 Ru-106 < 116.60 < 159.60 < 149.50 < 121.80 < 118.50 < 147.50 Ce-141 < 14.55 < 15.87 < 14.96 < 16.22 < 19.66 < 21.55 Ce-144 < 72.96 < 75.00 < 63.45 < 70.39 < 73.09 < 85.36 AcTh-228 52.7 +/- 28.8 < 56.35 < 25.05 < 56.50 < 37.13 < 49.19 Ra-226 497.5 +/- 185.0 < 226.30 < 231.10 < 250.20 562.6 +/- 199.4 1030.0 +/- 273.0 K-40 8162.0 +/- 333.4 6658.0 +/- 372.8 3420.0 +/- 276.7 4449.0 +/- 309.3 9078.0 +/- 339.1 6694.0 +/- 340.1 B-27

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- I Sigma

94 IPEC Training Center Sample Location TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Date 5/23/2011 5/23/2011 5/23/2011 6/27/2011 6/27/2011 6/27/2011 Client ID IBV9421 ISI IBV9421 11S2 1BV9421 I 1S3 IBV94261 ISI 1BV94261 I S3 IBV94261 IS2 Req. CL BURDOCK RAGWEED MULLEIN GRAPE MULLEIN RAGWEED Radionuclide (pCi) I I II Be-7 1914.0 +/- 168.4 1439.0 +/- 123.3 913.3 +/- 50.8 725.5 +/- 107.1 531.8 +1- 115.1 1767.0 +/- 168.0 1-131 50 < 24.93 < 15.88 < 6.87 < 14.41 < 21.29 < 22.46 Cs-134 50 < 13.90 < 17.22 < 3.06 < 19.08 < 20.25 < 25.66 Cs-137 50 < 23.49 < 13.33 < 4.27 < 10.46 < 16.33 < 21.04 Zr-95 < 35.71 < 21.20 < 6.66 < 23.39 < 29.08 < 34.52 Nb-95 < 16.79 < 12.57 < 4.53 < 12.48 < 17.28 < 20.47 Co-58 < 23.20 < 15.42 < 4.62 < 11.33 < 15.15 < 18.13 Mn-54 < 19.56 < 12.48 < 4.37 < 13.00 < 14.39 < 20.51 Zn-65 < 33.67 < 35.05 < 6.72 < 41.47 < 50.71 < 62.54 Fe-59 < 71.48 < 29.37 < 10.83 < 37.98 < 52.35 < 63.49 Co-60 < 23.58 < 13.64 < 4.47 < 12.18 < 6.70 < 23.11 Ba/La-140 < 21.81 < 19.31 < 5.69 < 14.55 < 20.25 < 29.58 Ru-103 < 18.95 < 13.84 < 4.58 < 11.76 < 17.51 < 19.86 Ru-106 < 202.20 < 119.30 < 37.17 < 176.80 < 173.60 < 231.00 Ce-141 < 23.39 < 15.90 < 5.88 < 17.94 < 22.81 < 23.67 Ce-144 < 105.60 < 67.48 < 26.99 < 80.28 < 87.05 < 93.09 AcTh-228 < 68.28 < 49.46 < 11.81 < 60.89 < 70.47 < 83.86 Ra-226 < 399.10 769.3 +/- 211.9 < 84.09 < 216.50 < 328.80 483.5 +/- 256.0 K-40 7086.0 +/- 433.2 6067.0 +/- 315.6 3191.0 +/- 118.5 4764.0 +/- 318.4 5666.0 +/- 415.2 9661.0 +/- 520.1 B-28

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma

94 IPEC Training Center Sample TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Location TRAINING BLDG Date 7/18/2011 7/18/2011 7/18/2011 8/15/2011 8/15/2011 8/15/2011 Client ID IBV94291 ISI 1BV94291 IS2 IBV94291 IS3 IBV94331 ISI IBV94331 IS2 IBV94331 IS3 Req. CL COMMON MU RAGWEED BITTERSWE COTTON RAGWEED CATALPA Radionuclide (pCi) I I I Be-7 558.1 +1- 74.5 907.9 +/- 103.3 554.6 +/- 76.4 2205.0 +1- 128.4 3519.0 +/- 156.0 1946.0 +1- 119.9 1-131 50 < 12.46 < 13.87 < 10.13 < 9.69 < 12.08 < 11.09 Cs-134 50 < 7.83 < 8.69 < 7.52 < 13.41 < 15.58 < 14.84 Cs-137 50 < 7.86 < 13.18 < 8.87 < 6.74 < 10.40 < 10.87 Zr-95 < 18.77 < 20.92 < 14.86 < 13.44 < 17.10 < 17.69 Nb-95 < 9.85 < 13.23 < 9.16 < 9.53 < 9.51 < 10.09 Co-58 < 8.40 < 11.13 < 7.27 < 8.59 < 11.37 < 11.12 Mn-54 < 8.80 < 13.95 < 8.89 < 8.94 < 10.03 < 9.47 Zn-65 < 26.26 < 39.74 < 25.54 < 25.81 < 30.29 < 32.36 Fe-59 < 22.56 < 51.18 < 25.37 < 25.93 < 26.22 < 31.78 Co-60 < 11.11 < 18.07 < 7.94 < 7.88 < 10.24 < 13.66 Ba/La-140 < 11.47 < 11.17 < 9.51 < 11.42 < 8.53 < 8.04 Ru-103 < 9.10 < 10.87 < 8.16 < 8.29 < 9.91 < 8.39 Ru-106 < 104.90 < 118.80 < 86.00 < 122.30 < 109.50 < 105.20 Ce-141 < 13.72 < 14.06 < 11.92 < 13.98 < 15.06 < 13.52 Ce-144 < 56.94 < 58.09 < 46.55 < 59.44 < 59.50 < 54.81 AcTh-228 < 34.11 < 51.04 < 28.98 < 35.86 < 36.82 < 37.75 Ra-226 456.9 +1/- 161.2 323.6 +/- 188.9 < 135.70 < 187.70 < 225.20 < 223.00 K-40 5476.0 +/- 243.8 9259.0 +/- 377.5 3765.0 +/- 228.1 3599.0 +/- 245.1 6024.0 +/- 295.3 2353.0 +/- 204.3 B-29

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma

94 IPEC Training Center Sample Location TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Date 9/13/2011 9/13/2011 9/13/2011 10/11/2011 10/11/2011 10/11/2011 Client ID IBV94371 IS1 1BV943711S2 IBV94371 IS3 IBV9441 I ISI IBV94411IS2 IBV9441 I IS3 Req. CL RAGWEED C GRAPE LE RAGWEED SAWGRASS BURDOCK Radionuclide (pCi) CATALPA Be-7 5820.0 +/- 275.4 4618.0 +/- 245.0 1544.0 +/- 146.4 6242.0 +/- 255.2 6935.0 +/- 284.9 874.9 +/- 78.1 1-131 50 < 23.83 < 25.83 < 19.09 < 22.19 < 24.89 < 12.44 Cs-134 50 < 17.22 < 14.82 < 10.20 < 20.30 < 11.84 < 6.64 Cs-137 50 < 18.58 < 20.89 < 13.42 < 14.80 < 20.04 < 8.51 Zr-95 < 36.86 < 27.58 < 20.89 < 23.80 < 28.71 < 14.95 Nb-95 < 20.46 < 16.07 < 17.54 < 14.48 < 16.47 < 7.87 Co-58 < 21.24 < 22.46 < 16.20 < 16.21 < 16.50 < 7.43 Mn-54 < 19.67 < 21.15 < 14.17 < 14.32 < 13.37 < 7.01 Zn-65 < 31.77 < 30.37 < 46.52 < 43.76 < 53.12 < 24.84 Fe-59 < 56.30 < 52.99 < 41.80 < 41.87 < 63.63 < 29.33 Co-60 < 14.71 < 24.31 < 10.61 < 17.67 < 14.66 < 9.10 Ba/La-140 < 22.15 < 35.23 < 14.48 < 22.42 < 24.91 < 14.73 Ru-103 < 19.83 < 22.15 < 16.04 < 12.25 < 17.73 < 7.91 Ru-106 < 172.50 < 184.00 < 157.30 < 154.80 < 160.90 < 97.62 Ce-141 < 27.45 < 25.62 < 18.01 < 19.55 < 22.89 < 14.78 Ce-144 < 106.70 < 95.49 < 69.38 < 74.32 < 93.29 < 51.66 AcTh-228 < 69.74 < 75.56 < 62.02 < 40.83 130.2 +/- 47.8 < 33.91 Ra-226 < 388.40 < 427.50 < 264.20 < 306.40 < 344.90 < 187.10 K-40 16668.0 +/- 417.3 3334.0 +/- 327.4 4473.0 +/- 318.8 7570.0 +/- 403.9 5212.0 +/- 362.7 5841.0 +/- 252.7 B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton **

Lample ROSETON ROSETON ROSETON ROSETON Location ROSETON ROSETON Date 5/23/2011 5/23/2011 5/23/2011 6/27/2011 6/27/2011 6/27/2011 Client ID IBV23211 ISI IBV2321 IIS2 IBV2321 I IS3 1BV23261 IS2 IBV23261 IS3 1BV23261 ISI Req. CL MULLEIN RAGWEED CATALPA RAGWEED BURDOCK MULLEIN Radionuclide (pCi) I I I _I Be-7 904.9 +/- 68.0 1211.0 +/- 72.7 317.1 +/- 51.4 949.2 +/- 104.1 690.4 +/- 85.1 678.1 +/- 119.5 1-131 50 < 10.12 < 9.10 < 13.98 < 13.00 < 11.63 < 16.35 Cs-134 50 < 7.93 < 7.95 < 5.69 < 16.81 < 13.35 < 10.69 Cs-137 50 < 4.96 < 5.91 < 7.45 < 8.49 < 11.38 < 11.58 Zr-95 < 10.57 < 8.90 < 13.61 < 21.74 < 18.67 < 26.78 Nb-95 < 6.35 < 7.25 < 7.16 < 11.52 < 10.50 < 15.07 Co-58 < 5.64 < 5.95 < 8.64 < 11.42 < 9.47 < 15.68 Mn-54 < 5.76 < 5.22 < 7.14 < 10.26 < 8.81 < 14.63 Zn-65 < 16.07 < 16.10 < 27.22 < 29.78 < 27.61 < 43.18 Fe-59 < 16.39 < 22.22 < 32.43 < 36.95 < 29.72 < 37.77 Co-60 < 6.45 < 5.69 < 8.64 < 13.89 < 10.27 < 13.30 BaILa-140 < 7.00 < 6.02 < 11.50 < 16.81 < 13.75 < 16.80 Ru-103 < 5.44 < 6.60 < 8.57 < 9.22 < 8.82 < 14.03 Ru-106 < 58.32 < 54.50 < 72.92 < 131.40 < 120.30 < 142.90 Ce-141 < 8.79 < 8.35 < 11.20 < 16.66 < 11.70 < 20.78 Ce-144 < 36.11 < 31.72 < 38.98 < 61.61 < 53.65 < 74.59 AcTh-228 < 22.81 < 20.92 < 27.53 < 46.72 < 44.98 < 51.01 Ra-226 < 114.30 < 115.60 < 152.60 < 223.00 662.3 +/- 154.4 < 287.80 K-40 2777.0 +/- 161.1 4883.0 +/- 186.8 2503.0 +/- 168.2 7693.0 +/- 385.7 7370.0 +/- 318.1 6315.0 +/- 356.4

- Control Sample Location B-31

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES- 2011 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton **

Sample ROSETON ROSETON ROSETON ROSETON ROSETON Location ROSETON Date 7/18/2011 7/18/2011 7/18/2011 8/15/2011 8/15/2011 8/15/2011 Client ID IBV23291 IS2 IBV23291 IS3 IBV232911 S1 IBV233311S I IBV233311 S2 IBV23331 IS3 Req. CL CATALPA BURDOCK RAGWEED RAGWEED CATALPA MULLEIN Radionuclide (pCi) I III Be-7 2330.0 +/- 183.7 715.9 +/- 135.6 1205.0 +/- 150.1 2656.0 +/- 127.2 1058.0 +/- 83.2 2202.0 +/- 121.0 1-131 50 < 18.00 < 17.66 < 22.23 < 9.30 < 7.98 < 9.13 Cs-134 50 < 16.48 < 9.28 < 14.26 < 11.51 < 6.06 < 13.53 Cs-137 50 < 17.59 < 10.47 < 20.50 < 11.28 < 7.96 < 9.87 Zr-95 < 26.04 < 25.44 < 28.65 < 18.05 < 13.89 < 15.83 Nb-95 < 15.32 < 16.11 < 17.28 < 10.11 < 5.57 < 9.41 Co-58 < 16.33 < 19.57 < 16.72 < 8.20 < 9.07 < 11.30 Mn-54 < 17.21 < 20.67 < 18.76 < 8.50 < 7.97 < 10.92 Zn-65 < 27.79 < 49.26 < 25.71 < 27.76 < 18.91 < 31.40 Fe-59 < 50.45 < 61.77 < 47.04 < 29.30 < 21.40 < 28.41 Co-60 < 18.35 < 20.28 < 15.64 < 9.90 < 8.64 < 9.54 Ba/La-140 < 23.58 < 23.54 < 18.32 < 6.89 < 7.54 < 10.22 Ru-103 < 14.58 < 15.01 < 14.74 < 9.23 < 7.50 < 8.89 Ru-106 < 184.90 < 170.80 < 180.80 < 92.92 < 73.89 < 108.30 Ce-141 < 21.76 < 20.40 < 23.19 < 12.42 < 11.34 < 10.80 Ce-144 < 83.02 < 87.85 < 112.50 < 50.57 < 48.51 < 49.32 AcTh-228 < 57.16 < 67.11 < 66.09 < 34.83 < 21.93 < 34.46 Ra-226 < 312.50 938.8 +/- 251.0 660.7 +/- 255.1 634.2 +/- 166.3 406.5 +/- 133.2 < 144.50 K-40 3321.0 +/- 305.5 6679.0 +/- 435.1 8424.0 +/- 416.2 7377.0 +/- 293.8 2256.0 +/- 152.8 3330.0 +/- 220.7

- Control Sample Location B-32

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton **

Sample ROSETON ROSETON ROSETON ROSETON Location ROSETON ROSETON Date 9/13/2011 9/13/2011 9/13/2011 10/11/2011 10/11/2011 10/11/2011 Client ID IBV233711S] IBV23371 IS2 1BV23371 IS3 IBV23411 ISI IBV2341 IIS2 IBV234111S3 Req.RAGWEED CATALPA BURDOCK RAGWEED CATALPA WILD GRAPE Radionuclide (pCi) RAGWEED Be-7 " _ 6154.0 +/- 202.8 5367.0 +/- 235.2 1346.0 +/- 107.0 8723.0 +/- 254.6 3114.0 +/- 147.8 2841.0 +/- 141.7 1-131 50 < 13.36 < 15.63 < 11.28 < 23.12 < 11.34 < 19.41 Cs-134 50 < 13.19 < 11.02 < 7.89 < 9.05 < 10.62 < 9.64 Cs-137 50 < 10.30 < 13.18 < 8.77 < 11.52 < 9.12 < 12.93 Zr-95 < 16.01 < 23.38 < 17.70 < 19.18 < 15.03 < 19.49 Nb-95 < 14.35 < 14.64 < 10.89 < 14.44 < 9.93 < 9.95 Co-58 < 13.47 < 10.86 < 11.46 < 13.08 < 8.31 < 13.41 Mn-54 < 11.68 < 13.25 < 10.68 < 11.51 < 8.07 < 11.70 Zn-65 < 28.52 < 48.03 < 34.65 < 33.87 < 19.60 < 15.08 Fe-59 < 39.00 < 42.81 < 28.05 < 41.35 < 30.89 < 26.69 Co-60 < 11.92 < 11.26 < 9.26 < 12.44 < 6.46 < 8.77 BaILa-140 < 13.74 < 15.28 < 10.69 < 15.20 < 14.98 < 15.28 Ru-103 < 12.16 < 11.41 < 10.05 < 11.34 < 10.11 < 11.48 Ru-106 < 103.20 < 158.00 < 84.11 < 137.80 < 90.44 < 113.50 Ce-141 < 16.84 < 20.50 < 15.32 < 19.78 < 12.35 < 19.81 Ce-144 < 64.70 < 83.81 < 53.59 < 86.65 < 50.37 < 77.81 AcTh-228 < 38.60 < 51.28 < 36.66 < 46.06 < 27.06 < 46.03 Ra-226 435.8 +/- 196.1 < 278.10 414.3 +/- 177.8 < 281.30 294.3 +/- 134.9 < 235.70 K-40 7803.0 +/- 333.6 3508.0 +/- 297.7 5912.0 +/- 277.5 7034.0 +/- 335.7 2317.0 +1- 177.5 2206.0 +/- 181.4

- Control Sample Location B-33

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH/INVERTEBATES - 2011 Results in pCi/kg dry +/- 1 Sigma

23 Roseton (Control)

Sample Date: 5/27/2011 6/2/2011 6/9/2011 6/9/2011 6/9/2011 8/10/2011 STRIPED BASS WHITE PERCH SUNFISH CATFISH AMERICAN EEL SUNFISH Nuclide Req.

CL Be-7 < 1340 < 1190 < 1050 < 877 < 688 < 94 K-40 3660 +/- 545 3540 +/- 438 3610 +/- 477 3210 +/- 399 2920 +/- 332 2830 +/- 60 Mn-54 65 < 85 < 66 < 56 < 43 < 54 < 5 Co-58 65 < 117 < 110 < 74 < 65 < 73 < 9 Fe-59 130 < 490 < 324 < 221 < 236 < 215 < 31 Co-60 65 < 77 < 48 < 53 < 54 < 55 < 7 Zn-65 130 < 159 < 139 < 131 < 123 < 114 < 12 Zr-95 < 219 < 198 < 180 < 139 < 148 < 17 Nb-95 < 140 < 112 < 102 < 84 < 97 < 10 Ru-103 < 231 < 178 < 151 < 139 < 108 < 15 Ru-106 < 693 < 590 < 475 < 483 < 387 < 44 1-131 < 39400 < 18300 < 10400 < 8430 < 8440 < 3100 Cs134 65 < 63 < 61 < 58 < 48 < 43 < 4 Cs137 75 < 74 < 59 < 47 < 53 < 50 < 5 Ba-140 < 12400 < 7550 < 5020 < 4430 < 3890 < 869 Ce-141 < 369 < 337 < 275 < 243 < 219 < 28 Ce-144 < 377 < 388 < 354 < 315 < 283 < 29 Ra-226 < 1230 < 1190 < 1200 < 1040 < 1010 < 89 Th-228 < 123 < 110 < 100 < 82 < 82 < 7 Ni-63 100 < 38 < 46 < 49 < 37 < 40 < 52 Sr-90 5 < 4.0 < 1.2 < 4.0 < 3.7 < 3.6 < 4.2 B - 34

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH/INVERTEBATES - 2011 Results in pCi/kg dry +/- 1 Sigma

23 Roseton (Control)

Sample Date: 8/10/2011 8/16/2011 8/19/2011 8/19/2011 8/19/2011 CATFISH WHITE PERCH AMERICAN EEL BLUE CRAB STRIPED BASS Nuclide Req.

CL Be-7 < 653 < 906 < 1450 < 633 < 714 K-40 3010 +/- 369 3980 +/- 421 3300 +/- 505 2180 +/- 253 3790 +/- 323 Mn-54 65 < 52 < 48 < 59 < 40 < 41 Co-58 65 < 78 < 91 < 125 < 55 < 75 Fe-59 130 < 237 < 236 < 254 < 196 < 233 Co-60 65 < 38 < 58 < 56 < 36 < 45 Zn-65 130 < 115 < 114 < 131 < 85 < 80 Zr-95 < 150 < 176 < 223 < 105 < 133 Nb-95 < 78 < 104 < 98 < 66 < 87 Ru-103 < 145 < 151 < 169 < 99 < 113 Ru-106 < 442 < 478 < 605 < 321 < 424 1-131 < 9950 < 21300 < 20400 < 11300 < 17400 Cs134 65 < 49 < 47 < 65 < 32 < 42 Cs137 75 < 48 < 54 < 63 < 31 < 39 Ba-140 < 5220 < 7840 < 8800 < 5300 < 5650 Ce-141 < 215 < 237 < 351 < 173 < 236 Ce-144 < 249 < 287 < 367 < 218 < 260 Ra-226 < 978 < 985 < 1280 < 721 < 925 Th-228 < 73 < 85 < 126 < 59 < 76 Ni-63 100 < 38 < 47 < 45 < 59 < 43 Sr-90 5 < 5.0 < 2.6 < 4.6 < 4.7 < 4.6 B - 35

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH/INVERTEBATES - 2011 Results in pCi/kg dry +/- 1 Sigma

25 Downstream (Hudson River)

Sample Date: 5/27/2011 5/27/2011 6/1/2011 6/5/2011 6/14/2011 6/17/2011 STRIPED BASS WHITE PERCH AMERICAN EEL SUNFISH BLUE CRAB CATFISH Nuclide Req.

CL Be-7 < 1370 < 1170 < 833 < 859 < 640 < 681 K-40 4510 +/- 515 2980 +/- 436 4300 +/- 460 3870 +/- 450 2870 +/- 327 3060 +/- 389 Mn-54 65 < 76 < 64 < 56 < 57 < 39 < 45 Co-58 65 < 131 < 102 < 91 < 65 < 78 < 59 Fe-59 130 < 415 < 266 < 241 < 251 < 190 < 150 Co-60 65 < 72 < 54 < 46 < 42 < 59 < 54 Zn-65 130 < 199 < 93 < 106 < 116 < 87 < 98 Zr-95 < 254 < 213 < 166 < 138 < 138 < 117 Nb-95 < 136 < 101 < 96 < 93 < 79 < 66 Ru-103 < 234 < 186 < 162 < 141 < 104 < 92 Ru-106 < 602 < 542 < 458 < 497 < 409 < 374 1-131 < 33100 < 34400 < 19500 < 14600 < 5390 < 4550 Cs134 65 < 69 < 51 < 49 < 48 < 35 < 45 Cs137 75 < 72 < 53 < 42 < 45 < 39 < 41 Ba-140 < 13200 < 11300 < 7750 < 5690 < 3220 < 2850 Ce-141 < 379 < 348 < 282 < 256 < 269 < 198 Ce-144 < 368 < 403 < 292 < 346 < 387 < 313 Ra-226 < 1320 < 1260 < 1030 < 949 < 1080 < 1010 Th-228 < 118 < 95 < 86 < 102 < 86 < 81 Ni-63 100 < 36 < 47 < 40 < 45 < 100 < 38 Sr-90 5 < 3.6 < 2.8 < 4.0 < 2.5 < 3.3 < 3.4 B - 36

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH/INVERTEBATES - 2011 Results in pCi/kg dry +/- 1 Sigma

25 Downstream (Hudson River)

Sample Date: 8/10/2011 8/11/2011 8/11/2011 8/22/2011 8/24/2011 8/25/2011 CATFISH WHITE PERCH SUNFISH BLUE CRAB STRIPED BASS AMERICAN EEL Nuclide Req.

CL Be-7 < 632 < 932 < 795 < 782 < 704 < 794 K-40 3720 +/- 290 3090 +/- 465 3470 +/- 457 2050 +/- 375 3600 +/- 500 3920 +/- 457 Mn-54 65 < 34 < 48 < 76 < 41 < 58 < 55 Co-58 65 < 60 < 79 < 88 < 73 < 75 < 74 Fe-59 130 < 227 < 240 < 200 < 213 < 171 < 186 Co-60 65 < 39 < 49 < 58 < 51 < 82 < 63 Zn-65 130 < 80 < 134 < 141 < 88 < 149 < 132 Zr-95 < 139 < 176 < 142 < 135 < 139 < 143 Nb-95 < 57 < 104 < 106 < 81 < 101 < 86 Ru-103 < 101 < 159 < 137 < 134 < 103 < 103 Ru-106 < 329 < 437 < 434 < 324 < 555 < 530 1-131 < 31100 < 26000 < 2760 < 15500 < 2610 < 2170 Cs134 65 < 30 < 49 < 58 < 39 < 55 < 50 Cs137 75 < 32 < 45 < 67 < 46 < 60 < 64 Ba-140 < 7710 < 8720 < 2180 < 6680 < 1870 < 1940 Ce-141 < 176 < 279 < 189 < 223 < 167 < 157 Ce-144 < 181 < 292 < 368 < 263 < 313 < 309 Ra-226 < 579 < 1030 < 1110 < 949 < 1190 < 1110 Th-228 < 42 < 99 < 113 < 73 < 91 < 101 Ni-63 100 < 40 < 51 < 52 < 57 < 42 < 41 Sr-90 5 < 4.3 < 4.2 < 2.9 < 4.4 < 4.5 < 4.05 B - 37

TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma Sample VERPLANK LENTS COVE COLD SPRING Location Date 10/18/2012 10/18/2012 Client ID L48193-1 148193-2 148193-3 Req. CL Radionuclide (pCi)

Be-7 233 +/- 57.5 198 +/- 54.5 1-131 30 < 28.3 < 31.3 Cs-134 30 < 12.7 < 11.5 Cs-137 40 < 16.2 < 12.3 Zr-95 < 24.0 No < 23.1 Nb-95 < 14.9 < 14.9 Co-58 < 13.3 Sample < 11.9 Mn-54 < 12.0 < 10.7 Zn-65 < 25.8 Available < 27.8 Fe-59 < 29.8 < 27.4 Co-60 < 14.8 < 13.8 BalLa-140 < 20.7 < 21.4 Ru-103 < 14.7 < 13.1 Ru-106 < 128 < 107 Ce-141 < 25.1 < 26.8 Ce-144 < 92.5 < 101 AcTh-228 54.4 +/- 15.1 61.0 +/- 9.4 Ra-226 < 309.0 < 361.0 K.40 2350 +/- 145 2180.0 +/- 123.0

all sites did not have available samples in first half of 2011 B-38

TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2011 Results in Units of pCi/kg + I Sigma Sample COLD SPRING LENTS COVE VERPLANCK DISCHARGE COLD SPRING LENTS COVE VERPLANK DISCHARGE Location CANAL CANAL Date 6/14/2011 6/14/2011 6/16/2011 6/16/2011 10/18/2011 10/18/2011 10/18/2011 10/18/2011 Client ID IBS84251i IBS28251i IBS1725fi I BS102511 _

Req. CL Radionuclide (pCi) I Be-7 < 297.1 < 398.5 < 430.7 < 243.2 < 733 < 685 < 819 < 655 1-131 < 54.3 < 79.1 < 91.4 < 36.5 < 325 < 317 < 350 < 196 Cs-134 75 < 43.0 < 37.9 < 40.4 < 30.4 < 67.1 < 67.9 < 83.7 < 53.7 Cs-137 90 < 38.9 255.7 +/- 48.0 325.1 +/- 58.3 96.9 +/- 28.3 238 +/- 33.1 437 +/- 42.0 406 +/- 61.5 200 +/- 30.6 Zr-95 < 65.8 < 85.6 < 89.8 < 63.4 < 153 < 152 < 195 < 104 Nb-95 < 42.4 < 57.7 < 61.1 < 36.2 < 89.0 < 93.4 < 112 < 77.8 Co-58 < 32.8 < 45.5 < 59.7 < 26.2 < 69.7 < 71.1 < 93.0 < 58.4 Mn-54 < 29.7 < 46.1 < 52.8 < 30.4 < 74.3 < 75.5 < 96.7 < 50.6 Zn-65 < 58.1 < 149.5 < 213.7 < 87.4 < 169 < 161 < 242 < 146 Fe-59 < 122.7 < 75.3 < 188.9 < 95.4 < 186 < 181 < 206 < 171 Co-60 < 33.9 < 49.0 < 87.4 < 35.4 < 93.7 < 85.4 < 105 < 74.5 BalLa-140 < 33.8 < 63.4 < 94.7 < 49.1 < 160 < 130 < 209 < 131 Ru-103 < 39.5 < 51.3 < 72.3 < 25.3 < 91.4 < 84.8 < 103 < 60.6 Ru-106 < 407.5 < 468.2 < 658.5 < 312.2 < 631 < 695 < 708 < 524 Ce-141 < 53.2 < 79.9 < 57.8 < 37.6 < 156 < 147 < 163 < 91.7 Ce-144 < 226.4 < 315.5 < 312.0 < 174.1 < 465 < 469 < 459 < 285.0 AcTh-228 856.1 +/- 140.8 1051.0 +/- 191.1 1336.0 +/- 219.1 < 111.6 1220 +/- 66.5 1200 +/- 62.0 1540 +/- 72.0 710 +/- 39.1 Ra-226 2495 +1- 723 2039 +1- 811 2406 +1- 937 1208 +1- 495 < 1950 2430 +1- 665 2800 +1- 735 < 913.0 K-40 35500 +/- 1232 21140 +/- 1181 25220 +/- 1505 16710 +/- 936 20200 +/- 860 18600 +/- 890 16700 +/- 1010 19000 +/- 860 B-39

TABLE B-18 CONCENTRATIONS OF GAMMA EMITTERS IN RAINWATER SAMPLES - 2011 Results in Units of pCi/L +/- I Sigma Sample ROSETON ROSETON ROSETON ROSETON PEEKSKILL PEEKSKILL PEEKSKILL PEEKSKILL Location RAINWATER RAINWATER RAINWATER RAINWATER RAINWATER RAINWATER RAINWATER RAINWATER End Date 3/27/2011 6/27/2011 9/26/2011 12/27/2011 3/27/2011 6/27/2011 9/26/2011 12/27/2011 Client ID Req. CL IRF231QI IRF232QI I IRF233911 IRF441QII IRF442QI I IRF443911 Radionuclide (pCi)

H-3 < 410 < 424 < 412 < 190 < 410 < 424 < 412 396 +/- 70.5 Be-7 40.2 +/- 5.9 < 23.8 < 24.4 < 42.2 32.9 +1- 6.1 < 45.3 < 29.5 < 44.3 1-131 14.3 +/- 4.6 < 20.0 < 22.7 < 8.1 25.8 +/- 3.9 < 27.9 < 20.9 < 9.2 Cs-134 7.5 < 0.6 < 1.5 < 2.3 < 3.8 < 1.2 < 4.3 < 2.5 < 4.6 Cs-137 9 < 0.9 < 2.2 < 2.0 < 3.9 < 0.9 < 3.4 < 2.5 < 4.4 Zr-95 < 2.1 < 5.6 < 3.6 < 8.3 < 2.5 < 7.9 < 6.1 < 8.5 Nb-95 < 1.7 < 4.5 < 3.7 < 5.2 < 1.9 < 6.4 < 4.8 < 4.9 Co-58 < 1.2 < 3.2 < 2.4 < 4.2 < 1.4 < 4.6 < 3.6 < 4.7 Mn-54 < 0.9 < 2.4 < 1.7 < 3.4 < 1.1 < 3.5 < 2.4 < 4.4 Zn-65 < 2.1 < 5.6 < 4.2 < 8.8 < 2.1 < 11.6 < 4.5 < 8.2 Fe-59 < 4.0 < 8.8 < 8.0 < 7.3 < 3.9 < 18.2 < 10.1 < 8.8 Co-60 7.5 < 0.9 < 2.0 < 2.0 < 3.9 < 1.1 < 3.2 < 2.5 < 4.8 Ba/La-140 < 5.0 < 11.1 < 11.3 < 6.3 < 6.9 < 8.2 < 9.8 < 7.0 Ru-103 < 1.9 < 2.6 < 4.3 < 5.0 < 2.0 < 6.8 < 5.2 < 5.4 Ru-106 < 10.2 < 25.2 < 19.7 < 35.4 < 10.7 < 35.7 < 24.5 < 46.0 Ce-141 < 3.1 < 8.0 < 6.4 < 8.9 < 3.8 < 11.2 < 8.8 < 8.9 Ce-144 < 6.8 < 18.2 < 15.5 < 32.6 < 8.4 < 23.5 < 16.3 < 35.0 AcTh-228 < 3.2 < 6.9 19.1 +/- 5.4 < 7.3 < 3.5 < 11.6 < 7.2 < 10.1 Ra-226 92.5 +/- 9.3 < 44.8 95.6 +/- 32.5 < 97.5 80.1 +/- 9.8 < 73.3 113 +/- 39.7 < 119 K-40 73.9 +/- 5.1 78.0 +/- 23.1 < 18.6 < 61.6 34.6 +/- 4.6 271 +/- 41.2 51.8 +1- 20.3 < 85.9 B-40

TABLE B-19 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL SAMPLES - 2011 Results in Units of pCi/kg +/- 1 Sigma Sample ROSETON MET TOWER Location TRAINING BLDG Date 9/19/2011 9/19/2011 9/19/2011 Client ID IS0233811 IS0953811 IS0943811 Req. CL Radionuclide (pCi) _ I I Be-7 402.1 +/- 160.2 < 274.3 < 175.1 1-131 < 32.5 < 45.8 < 21.3 Cs-134 75 < 19.8 < 46.8 < 20.5 Cs-137 90 < 24.7 < 38.0 < 21.2 Zr-95 < 43.4 < 54.0 < 32.2 Nb-95 < 28.2 < 35.8 < 33.5 Co-58 < 25.8 < 39.5 < 21.4 Mn-54 < 25.6 < 37.9 < 26.0 Zn-65 < 36.9 < 132.2 < 27.8 Fe-59 < 61.4 < 108.0 < 59.4 Co-60 < 27.0 < 40.4 < 26.2 Ba/La-140 < 29.1 < 23.0 < 24.4 Ru-103 < 27.1 < 32.4 < 22.0 Ru-106 < 267.4 < 346.3 < 230.8 Ce-141 < 47.8 < 51.0 < 34.4 Ce-144 < 213.1 < 244.1 < 151.5 AcTh-228 726.6 +/- 109.2 689.4 +/- 133.2 419.9 +/- 84.5 Ra-226 < 711.6 1428.0 +/- 546.5 1264.0 +/- 422.8 K-40 118210.0 +/- 782.6 13070.0 +/- 980.3 12920.0 +/- 674.1

_________ A _______ a L ________________ .1 ________________

B-41

TABLE B-20 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L + 3 sigma Monitoring Well MW-LAF MW-LAF Sample Name MW-LAF-002-015 MW-LAF-002-016 Sample Date 5/2/2011 12/13/2011 Radionuclide Req. MDC H-3 < 343 < 479 Cs-137 18 < 8.6 < 11.1 Co-60 < 7.7 < 12.9 Sr-90 I < 1.66 < 1.75 Ni-63 < 18.3 < 12.2 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

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

B-42

Table B-21 LAND USE CENSUS - RESIDENCE and MILCH ANIMAL RESULTS 2011 The 2011 land use census indicated there were no new residences that were closer in proximity to IPEC. NEM maintains a complete nearest residence survey with updated distances.

No milch animals were observed during this reporting period within the 5-mile zone.

There are no animals producing milk for human consumption within five miles of Indian Point.

B-43

TABLE B-22 LAND USE CENSUS 2011 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES I Y r I Distance to Distance to site Distance to site nearest resident, Boundary from Boundary from from Unit 1 Unit 2 Plant Vent Unit 3 Plant Vent superheater Address of nearest resident, Last Compass Point (meters) (meters) (meters) Census N RIVER RIVER 1788 41 River Road Tomkins Cove NNE RIVER RIVER 3111 Chateau Rive Apts. John St. Peekskill NE 550 636 1907 211 Viewpoint Terrace, Peekskill ENE 600 775 1478 1018 Lower South St. Peekskill E 662 785 1371 1103 Lower South St. Peekskill ESE 569 622 715 461 Broadway Buchanan SE 553 564 1168 223 First St. Buchanan SSE 569 551 1240 5 Pheasant's Run Buchanan S 700 566 1133 320 Broadway Verplanck SSW 755 480 1574 240 Eleventh St. Verplanck SW 544 350 3016 8 Spring St. Tomkins Cove WSW RIVER RIVER 2170 9 West Shore Dr. Tomkins Cove W RIVER RIVER 1919 712 Rt. 9W Tomkins Cove WNW RIVER RIVER 1752 770 Rt. 9W Tomkins Cove NW RIVER RIVER 1693 807 Rt. 9W Tomkins Cove NNW RIVER RIVER 1609 4 River Rd. Tomkins Cove B-44

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 graphical form to facilitate the comparison of 2011 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.

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

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

2001-2011 Average Quarterly Dose (mR/Quarter)

YearYearnner ingQuter Ring Control nner ing ocation 2001 15.0 15.0 17.0 2002 15.0 15.0 14.0 2003 14.3 13.9 14.7 2004 13.0 13.0 14.0 2005 14.1 14.1 15.9 2006 13.9 14.3 17.5 2007 14.4 14.6 18.8 2008 14.5 14.2 17.3 2009 14.5 14.2 17.3 2010 14.0 14.3 13.0 2011 13.6 14.4 13.4 14.3 14.3 15.9 C-2

FIGURE C-1 DIRECT RADIATION, ANNUAL

SUMMARY

2001 to 2011 40.0 35.0 -

30.0 25.0 I 20.0 E

15.0 10.0 5.0 .

0.0 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 C-3

TABLE C-2 RADIONUCLIDES IN AIR 2001 to 2011 (pCi/m3)

Gross Beta CS-I37 Y'rAll Indicator Control All Indicator Control Year Locatis Location Locations', LocatiOn 2001 0.02 0.02 < Lc < Lc 2002 0.02 0.02 < Lc < Lc 2003 0.01 0.01 < Lc < Lc 2004 0.01 0.01 < Lc < Lc 2005 0.02 0.02 < Lc < Lc 2006 0.01 0.01 < Lc < Lc 2007 0.01 0.01 < Lc < Lc 2008 0.01 0.01 < Lc < Lc 2009 0.01 0.01 < Lc < Lc 2010 0.01 0.01 < Lc < Lc 2011 0.014 0.014 < Lc < Lc

Historical Avegra'ge' 0.1.1 L 2001201101ý Critical Level (Lj)is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 2001 to 2011 0.05 MAIl Indicator Locations

- Control Location 0.04 0.03 C.)

0.02 1 0.01 -

0 i iAiO 0 0.00 I Ii 2001 2002 I

2003

Includes ODCM and non-ODCM indicator locations.

I 2004 i

2005 2006 2007 2008 2009 2010 i

2011 3

Gross Beta ODCM required LLD = 0.01 pCi/m C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 2001 to 2011 (pCi/L)

A >Tritium A (H-3) 2 CsA Year ><Inlet Disc~harge Inlet Dischiarge 2001 < Lc 323 < Lc < Lc 2002 432 562 < Lc < Lc 2003 < Lc < Lc < Lc < Lc 2004 < Lc 553 < Lc < Lc 2005 < Lc 618 < Lc < Lc 2006 < Lc 386 < Lc < Lc 2007 < Lc < Lc < Lc < Lc 2008 < Lc < Lc < Lc < Lc 2009 < Lc < Lc < Lc < Lc 2010 428 < Lc < Lc < Lc 2011 < Lc " Lc " Lc 661 430 488 < Lc < L, Critical Level (L,) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-6

FIGURE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 2001 to 2011 2000

Inlet (H-3) 1800

Discharge (H-3) 1600 1400 1200

-J C. 1000 800 600 400 200 0

2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Tritium ODCM required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 2001 to 2011 (pCi/L)

Year Tritium (H-3) Cs-137 2001 < Lc < Lc 2002 < Lc < Lc 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 < Lc < Lc 2011 < Lc < Lc Historical Average 2001-2010 Critical Level (Lo) is less than the ODCM required LLD.

<L, indicates no positive values above sample critical level.

C-8

FIGURE C-4 RADIONUCLIDES IN DRINKING WATER 2001 to 2011 2000 I 1800 -

1600 -

1400 -

1200

,.J C.) 1000 NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEARS HISTORY 800 600 400 200 0- I I T I I --

2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Tritium ODCM required LLD = 2000 pCi/L C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 2001 to 2011 (pCi/Kg, dry)

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

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 750 2001 to 2011 EIndicator (Cs-134) 650 =7Control (Cs-134)

= Indicator (Cs-1 37) 550

- Control (Cs-137) 450 350 250 150 50 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011

-50 Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry C-11

TABLE C-6 BROAD LEAF VEGETATION - Cs-137 2001 to 2011 (pCi/Kg, wet)

Cs-I,37 Year Indicator Control 2001 7 < Lc 2002 14 16 2003 14 < Lc 2004 10 < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 31 < Lc 2011 < Lc < Lc

HistorAr 15 16 Critical Level (L) is less than the ODCM required LLD.

<L, indicates no positive values above sample critical level.

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 2001 to 2011 100 80 60 4-di CL 0.

40 20 -

2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 ODCM required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 FISH AND INVERTEBRATES - Cs-137 2001 to 2011 (pCi/Kg, dry)

Cs-1 37 Year Indii a1tor Control 2001 < Lc < Lc 2002 < Lc < Lc 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 < Lc < Lc

< Lc 2011

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

<Lc indicates no positive values above sample critical level.

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 2001 to 2011 200 -

180 - 9 Indicator (Cs-1 37) 180 El Control (Cs-1 37) 160 140 120 S100 C-)

80 NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEARS HISTORY 60 40 20 0 2 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-15

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX D INTERLABORATORY COMPARISON PROGRAM This section presents the results of the interlaboratory comparison program for the J. A.

Fitzpatrick Environmental Laboratory, Teledyne Brown Engineering Environmental Services and Environmental Dosimetry Company. Since General Engineering Labs only analyzed 2 samples, their interlaboratory data is not presented. However, their results can be provided upon request.

D.1 Program Description - JA Fitzpatrick Interlaboratory Comparison Program The J.A. Fitzpatrick Environmental Laboratory participates in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program includes sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the James A. FitzPatrick Nuclear Power Plant (JAF) Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia.

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

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

D.2 Proqram Schedule SAMPLE LABORATORY SAMPLE PROVIDER MEDIA ANALYSIS ANALYTICS Water Gross Beta 3 Water Tritium 5 Water 1-131 4 Water Mixed Gamma 4 Air Gross Beta 3 Air 1-131 4 Air Mixed Gamma 2 Milk 1-131 3 Milk Mixed Gamma 3 Soil Mixed Gamma 1 Vegetation Mixed Gamma 2 TOTAL SAMPLE INVENTORY 34 D.3 Acceptance Criteria Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.

D.3.1 Sample Results Evaluation Samples provided by Analytics are evaluated using what is specified as the NRC method.

This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

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

The value for the error resolution is calculated.

Error Resolution = Reference Result Reference Results Error (1 sigma)

Using the appropriate row under the Error Resolution column in Table D.3-1, 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.3-1 ERROR RESOLUTION RATIO OF AGREEMENT

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

>200 0.85-1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria are contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires' the generation of a deviation from QA/QC program report when results are unacceptable.

D.4 Program Results Summary The Interlaboratory Comparison Program numerical results are provided on Section D.4.2.

D.4.1 Eckert & Ziegler Analytics QA Samples Results Thirty-four QA blind spike samples were analyzed as part of Analytics 2011 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

" Air Charcoal Cartridge: 1-131

Air Particulate Filter: Gross Beta, Mixed Gamma Emitters

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

Milk: 1-131, Mixed Gamma Emitters

Vegetation: Mixed Gamma Emitters

Soil: Mixed Gamma Emitters The JAF Environmental Laboratory performed 133 individual analyses on the 34 QA samples. Of the 133 analyses performed, 133 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no nonconformities in the 2011 program.

D.4.2 Numerical Results Tables Data tables in this section were obtained from Section 8 of the annual QA Report for the J.A. Fitzpatrick Environmental Laboratory.

Table D.4-1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma RATIO (1) 9.32E+01 +/- 1.36E+00 Air Particulate9.1+1+/-.3+0 06/16/2011 E7633-05 Gross Beta 9.11E+01 +/- 1.34E-00 8.55E+01 +/- 1.43E+00 1.08 A Filter 9.17E+01 +/- 1.35E+00 Mean = 9.20E+01 +/- 7.79E-01 7.61 E+01 +/- 1.20E+00 Air Particulate 7.93E+01 +/- 1.30E+00 06/16/2011 E7618-09 Gross Beta 7.29E+01 +/- 1.22E+00 1.06 A Filter 7.64E+01 +/- 1'20E+00 Mean = 7.73E+01 +/- 7.10E-01 1.01 E+02 + 2.74E+00 9.96E+01 +/- 2.72E+00 1.01E+02 +/- 2.74E+00 9.98E+01 +/- 2.72E+00 9.89E+01 +/- 2.71 E+00 Air Particulate 9.79E+01 +/- 2.69E+00 12/08/2011 E8254-05 Filter Gross Beta 1.05E+02 +/- 2.78E+00 8.96E+01 +/- 1.50E+00 1.11 A 1.08E+02 +/- 2.81 E+00 9.97E+01 +/- 2.70E+00 9.14E+01 +/- 2.69E+00 9.14E+01 +/- 2.71E+00 9.81 E+01 +/- 2.79E+00

_Mean = 9.94E+01 +/- 8.OOE-01 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable Table D.4-1 (Continued) 1-131 Gamma Analysis of Air Charcoal SAMPLE MEDIUM ANALYSIS JAF ELAB RESULTS REFERENCE LAB* RATIO (1)

DATE ID NO. pCi +/-1 sigma pCi +/-1 sigma 9.63E+01 +/- 3.30E+00 03/17/2011 E7437-09 Air Charcoal 1-131 9.73E+01 +/- 1.50E+00 9.62E+01 +/- 1.61E+00 1.01 A Cartridge 9.80E+01 +/- 3.20E+00 Mean = 9.72E+01 +/- 1.57E+00 9.53E+01 +/- 2.70E+00 Air Charcoal 1.OOE+02 +/- 2.70E+00 Cartridge 8.61E+01 +/- 2.80E+00 8.67E+O1 +/- 1.45E+00 1.08 A Mean = 9.38E+01 +/- 1.57E+00 8.05E+01 +/- 3.OOE+00 09/15/2011 E8125-05 Air Charcoal 1-131 8.32E+01 +/- 3.20E+00 8.05E+01 +/- 1.34E+00 1.03 A Cartridge 8.40E+01 +/- 3.1OE+00 Mean = 8.26E+01 +/- 1.80E+00 7.23E+01 +/- 4.30E+00 09/15/2011 E8127-09 Air Charcoal 1-131 7.21E+01 4.50E+00 8.05E+01 +/- 1.34E+00 0.93 A Cartridge 8.06E+01 +/- 4.60E+00 Mean = 7.50E+01 +/- 2.60E+00 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Page 4

Table D.4-1 (Continued)

Gross Beta Analysis of Water DATE SAMPLE MEDIUM ANALYSIS JAF ELAB RESULTS REFERENCE LAB* RATIO (1)

ID NO. pCi/liter +/-1 sigma pCi/liter +/-1 sigma 2.51 E+02 +/- 2.50E+00 2.52E+02 +/- 2.50E+00 03/17/2011 E7479-05 Water Gross Beta 2.54E+02 +/- 2.50E+00 2.47E+02 +/- 4.13E+00 1.02 A 2.55E+02 +/- 2.50E+00 Mean = 2.53E+02 + 1.30E+00 2.33E+02 +/- 2.40E+00 06/16/2011 E7638-05 Water Gross Beta 2.32E+02 2.40E+00 2.51E+02 +/- 4.18E+00 0.93 A 2.34E+02 +/- 2.40E+00 Mean = 2.33E+02 +/- 1.39E+00 2.54E+02 +/- 3.30E+00 09/15/2011 E8126-05 Water Gross Beta 2.57E+02 t 3.30E+00 2.49E+02 +/- 4.16E+00 1.02 A 2.50E+02 +/- 3.30E+00 I_ I I Mean = 2.54E+02 +/- 1.90E+00 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable Table D.4-1 (Continued)

Tritium Analysis of Water DATE SAMPLE MEDIUM ANALYSIS JAF ELAB RESULTS REFERENCE LAB RATIO (1)

DATE_ ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma 4.31E+03 +/- 1.63E+02 03/17/2011 E7476-05 Water H-3 4.67E+034.53E+03 +/- 757E+01 1.00 A 4.65E+03 +/- 1.66E+02 Mean = 4.55E+03 +/- 9.50E+01 8.33E+02 +/- 1.34E+02 9.23E+02 +/- 1.35E+02 06/16/2011 E7632-05 Water H-3 9.05E+02 +/- 1.51E+01 0.98 A 9.08E+02 +/- 1.35E+02 Mean = 8.88E+02 +/- 7.78E+01 9.15E+02 +/- 1.31E+02 09/15/2011 E8121-05 Water H-3 1.OOE+03 +/- 1.32E+02 7.92E+02 +/- 1.32E+02 1.21 A 9.57E+02 +/- 1.32E+02 Mean = 9.58E+02 +/- 7.60E+01 1.06E+04 +/- 2.09E+02 12/08/2011 E8181-09 Water H-3 1.02E+04 +/- 2.08E+02 1.09E+04 +/- 1.82E+02 0.94 A 1.01 E+04 +/- 2.11EE+02 Mean = 1.03E+04 +/- 1.21E+02 1.03E+04 +/- 2.06E+02 12/08/2011 E8182-09 Water H-3 1.03E+04 +/- 2.08E+02 1.09E+04 +/- 1.82E+02 0.94 A 1.01 E+04 +/- 2.10E+02 Mean = 1.03E+04 +/- 1.20E+02 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Pacje 5

Table D.4-1 (Continued)

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

DATE ID NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma RATIO (1) 2.21E+02 +/- 1.59E+01 Cr-51 2.24E+02 +/- 1.80E+01 2.30E+02 +/- 3.84E+00 0.98 A 2.33E+02 +/- 1.37E+01 Mean = 2.26E+02 +/- 9.22E+00 1.17E+02 +/- 4.50E+00 1.11E+02 +/- 4.90E+i00 Cs-134 1.01E+02 +/- 1.68E+00 1.13 A 1.15E+02 +/- 3.80E+00 Mean = 1.14E+02 +/- 2.55E+00 1.69E+02 +/- 4.50E+00 Cs-1371.59E+-02 +- 4.80E+00 Cs-137 1.65E+02 +/- .80E+00 1.5E+02

+/- 3.80E+00 158E+02 +/- 2.64E+00 1.04 A Mean = 1.64E+02 _ 2.52E+00 9.00E+01 +/- 3.50E+00 Co-58 8.40E+01 +/- 4.10E+00 8.73E+01 +/- 1.46E+00 1.01 A 9.00E+01 +/- 3.20E+00 E7478-05 Air Particulate Mean = 8.81 E+01 +/- 2.08E+00 03/17/2011 Filter 2.11 E+02 +/- 5.20E+00 Mn-54 2.21E+02 t 5.80E+00 2.05E+02 + 3.43E+00 1.06 A 2.18E+02 +/- 4.50E+00 Mean = 2.17E+02 +/- 2.98E+00 1.44E+02 +/- 5.20E+00 Fe-59 1.38E+02 +/- 6.10E+00 1.34E+02 - 2.24E+00 1.09 A 1.56E+02 +/- 4.60E+00 Mean = 1.46E+02 +/- 3.09E+00 2.26E+02 +/- 8.80E+00 Zn-65 2.12E+02 +/- 9.80E+00 2.01E+02 +/- 3.36E+00 1.07 A 2.08E+02 +/- 7.60E+00 Mean = 2.15E+02 +/- 5.04E+00 1.27E+02 +/- 3.40E+00 Co-60 1.32E+02 +/- 3.80E+00 1.32E+02 t 2.21E+00 0.98 A 1.30E+02 +/- 2.90E+00

[Mean = 1.30E+02 +/- 1.94E+00 (1) Hatio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Paqe 6

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma AnalysIs of Air Particulate Filter DATE SAMPLE I ID NO.

I MEDIUM ANALYSIS ANALYSIS JAF ELAB RESULTS pCi +/-1 sigma REFERENCE LAB RATIO (1) pCi +/-1 sigma RAIO(1) 6.84E+01 +/- 2.80E+00 7.11E+01, +/- 2.70E+00 Ce-141 6.96E+01 +/- 1.16E+00 1.02 A 7.35E+01 +/- 2.80E+00 Mean = 7.1OE+01 +/- 1.60E+00 2.17E+02 +/- 1.84E+01 Cr-51 2.32E+02 +/- 1.79E+01 2,36E+02 +/- 3.94E+00 0.96 A 2.28E+02 +/- 1.80E+01 Mean = 2.26E+02 +/- 1.05E+01 1.15E+02 +/- 8.70E+00 Cs-134 1.15E+02 +/- 8.50E+00 1.34E+02 +/- 2.23E+00 0.85 A 1.11E+02 +/- 8.20E+00 Mean = 1.14E+02 +/- 4.89E+00 1.24E+02 +/- 4.30E+00 Cs-137 1.14E+02 +/- 4.20E+00 1.19E+02 +/- 1.98E+00 0.99 A 1.15E+02 +/- 4.OOE+00 Mean = 1.18E+02 +/- 2.41E+00 1.04E+02 +/- 4.1OE+00 E8123-05 Air Particulate Co-58 1.08Ei02 +/- 4.10E+00 1.02E+02 +/- 1.70E+00 1.05 A 09/15/2011 I I Filter 1.08E+02 +/- 4.OOE+00 Mean = 1.07E+02 +/- 2.35E+00 1.75E+02 +/- 5.20E+00 Mn-54 1.67E+02 +/- 5.10E+00 1.57E+02 +/- 2.63E+00 1.11 A 1.79E+02 +/- 4.80E+00 Mean = 1.74E+02 +/- 2.91 E+00 6.17E+01 +/- 4.90E+00 Fe-59 6.86E+01 +/- 4.80E+00 5.72E+01 +/- 9.55E-01 1.13 A 6.35E+01 +/- 4.30E+00 Mean = 6.46E+01 +/- 2.70E+00 1.97E+02 +/- 1.01E+01 Zn-65 2.18E+02 +/- 9.80E+00 1.88E+02 +/- 3.14E+00 1.13 A 2.25E+02 +/- 9.OOE+00 Mean = 2.13E+02 +/- 5.57E+00 1.61 E+02 +/- 4.20E+00 1.59E+02 +/- 4.10E+00 Co-60 1.64E+02 +/- 2.74E+00 0.98 A 1.64E+02 +/- 3.90E+00 Mean = 1.61 E÷02 +/- 2.35E+00 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Page 7

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil DATE SAMPLE MEDIUM ANALYSIS JAF ELAB RESULTS REFERENCE LAB* RATIO (1)

I ID NO. I pCi/g +/-1 sigma pCig +/-1 sigma I 1.89E-01 +/- 2.20E-02 1.89E-01 +/- 2.OOE-02 Ce-141 1.54E-01 +/- 2.57E-03 1.24 A 1.93E-01 +/- 2.09E-02 Mean = 1.90E-01 +/- 1.21 E-02 3.16E-01 +/- 9.66E-03 Cr-51 365E01 +/- 9.37E-03 3.97E-01. +/- 6.63E-03 0.86 A 3.42E-01 +/- 9.45E-03 Mean = 3.41 E-01 +/- 5.48E-03 3.58E-01 +/- 3.38E-03 Cs-134 3.63E-01 +/- 3.32E-03 3.66E-01 +/- 6.10E-03 0.97 A 3.49E-01 +/- 3.86E-03 Mean = 3.57E-01 +/- 2.04E-03 3.08E-01 +/- 1.90E-02 Cs-137 3.54E-01 +/- 1.90E-02 3.55E-01 +/- 5.93E-03 0.95 A 3.47E-01 +/- 2.09E-02 Mean = 3.36E-01 +/- 1.13E-02 2.92E-01 +/- 1.78E-02 Co-58 2.95E-01 +/- 1.74E-02 2.92E-01 +/- 4.88E-03 1.00 A 06/16/2011 E7635-05 Soil 2.90E-01 +/- 1.95E-02 Mean = 2.92E-01 +/- 1.05E-02 3.04E-01 +/- 1.74E-02 Mn-54 2.81E-01 1.70E-02 266E-01 +/- 4.44E-03 1.09 A 2.85E-01 +/- 1.98E-02 Mean = 2.90E-01 +/- 1.05E-02 2.33E-01 +/- 1.96E-02 Fe-59 2.53E-01 +/- 2.07E-02 2.38E-01 +/- 3.97E-03 1.03 A 2.48E-01 +/- 2.28E-02 Mean = 2.45E-01 +/- 1.22E-02 5.22E-01 +/- 3.25E-02 Zn-65 5.57E-01 +/- 3.39E-02 5.02E-01 +/- 8.39E-03 1.08 A 5.53E-01 +/- 3.85E-02 Mean = 5.44E-01 +/- 2.02E-02 I I 4.02E-01 +/- 1.46E-02 3.86E-01 +/- 1.49E-02 Co-60 3.75E-01 +/- 6.26E-03 1.03 A 3.69E-01 +/- 1.65E-02 Mean = 3.86E-01 +/- 8.87E-03 n I J. I. - a &

(1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Page 8

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation DATE DATE_

SAMPLE I ID NO.

MD MEDIUM 1 ANALYSIS ANALYSIS JAF ELAB RESULTS pCi/g +/-1 sigma REFERENCE LAB*

pCi/g +/-1 sigma RATIO (1)

RAIO_(1) 2.74E-01 +/- 1.29E-02 2.70E-01 +/- 1.52E-02 Ce-141 3.07E-01 +/- 5.13E-03 0.92 A 3.04E-01 +/- 1.36E-02 Mean = 2.83E-01 +/- 8.04E-03 7.39E-01 +/- 7.34E-02 Cr-51 7.67E-01 t 8.79E-02 7.92E-01 +/- 1.32E-02 1.00 A 8.63E-01 +/- 7.11E-02 Mean = 7.90E-01 + 4.49E-02 6.64E-01 +/- 3.52E-02 Cs-1 34 6.60E-01 4.13E-03 7.29E-01 +/- 1.22E-02 0.89 A 6.29E-01 +/- 2.84E-03 Mean = 6.51E-01 +/- 1.19E-02 4.94E-01 +/- 1.63E-02 Cs-137 5.0E01 +/- 1.91E-02 5.30E-01 +/- 8.86E-03 0.95 A 5.11E-01 +/- 1.52E-02 Mean = 5.04E-01 t 9.78E-03 5.79E-01 +/- 1.71E-02 06/16/2011 E7637-05 Vegetation Co-58 5.56E-01 +/- 1.92E-02 5.83E-01 +/- 9.73E-03 0.99 A 5.95E-01 +/- 1.54E-02 Mean = 5.77E-01 +/- 9.99E-03 5.20E-Oi +/- 1.66E-02 Mn-54 5.12E-01 1.93E-02 5.30E-01 +/- 8.85E-03 0.96 A 4.87E-01 +/- 1.48E-02 Mean = 5.06E-01 +/- 9.82E-03 4.87E-01 +/- 1.89E-02 Fe-59 5.14E-01 2.30E-02 4.74E-01 +/- 7.91E-03 1.03 A 4.70E-01 +/- 1.67E-02 Mean = 4.90E-01 +/- 1.14E-02 1.1OE+00 +/- 3.70E-02 Zn-65 9.41E-01 t 4.33E-02 1.00E+00 +/- 1.67E-02 1.01 A 9,83E-01 +/- 3.14E-02

_Mean = 1.01E+00 +/- 2.17E-02 7,18E-01 +/- 1.52E-02 7.16E-01 +/- 1.74E-02 Co-60 7.48E-01 +/- 1.25E-02 0.94 A 6.80E-01 +/- 1.30E-02 Mean = 7.05E-01 +/- 8.84E-03 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Paae 9

Table 0.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation DATE SAMPLE ANALYSIS JAF ELAB RESULTS REFERENCE LAB* RATIO (1)

I ID NO. I pCi/g +/-1 sigma pCi/g +/-1 sigma I 1.51E-01 +/- 1.34E-02 1.67E-01 +/- 1.73E-02 Ce-141 1.69E-01 +/- 2.82E-03 0.95 A 1.63E-01 +/- 1.48E-02 Mean= 1.60E-01 +/- 8.81 E-03 6.32E-01 +/- 8.21 E-02 Cr-51 5.53E-01 +/- 1.14E-01 5.73E-01 +/- 9.57E-03 1.07 A 6.62E-01 +/- 9.49E-03 Mean = 6.16E-01 +/- 4.69E-02 3.32E-01 +/- 2.88E-02 Cs-134 3.43E-01 +/- 3.18E-02 3.25E-01 +/- 5.42E-03 0.97 A 2.71E-01 +/- 3.27E-02 Mean = 3.15E-01 +/- 1.80E-02 2.99E-01 +/- 1.41 E-02 Cs-137 2.56E-01 +/- 1.61 E-02 2.88E-01 +/- 4.81 E-03 0.97 A 2.81E-01 +/- 1.59E-02 Mean = 2.79E-01 +/- 8.89E-03 2.73E-01 +/- 1.44E-02 Co-58 2.56E-01 +/- 1.61E-02 2.47E-01 +/- 4.12E-03 1.06 A 09/15/2011 E8128-09 Vegetation 2.58E-01 +/- 1.64E-02 Mean = 2.62E-01 +/- 9.04E-03 4.OOE-01 +/- 1.57E-02 Mn-54 4.30E-01 +/- 1.98E-02 3.82E-01 +/- 6.38E-03 1.04 A 3.66E-01 +/- 1.89E-02 Mean = 3.99E-01 +/- 1.05E-02 1.58E-01 +/- 1.64E-02 Fe-59 1.55E-01 2,13E-02 1.39E-01 +/- 2.32E-03 1.01 A 1.09E-01 +/- 1.93E-02 Mean = 1.41E-01 _ 1.10E-02 4.19E-01 +/- 2.89E-02 Zn-65 4.93E-01 +/- 3.85E-02 4.57E-01 +/- 7.63E-03 1.01 A 4.77E-01 +/- 3.56E-02 FMean = 4.63E-01 +/- 2.OOE-02 3.88E-01 +/- 1.26E-02 3.66E-01 +/- 1.52E-02 Co-60 3.97E-01 +/- 6.64E-03 0.96 A 3.95E-01 +/- 1.51E-02 Mean = 3.83E-01 +/- 8.29E-03 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable Page 10

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analvsis of Milk DATE SAMPLE M ANALYSIS JAF ELAB RESULTS REFERENCE LAB* RATIO (1)

ID NO. I pCi/liter +/-1 sigma pCilliter +/-1 sigma I 2.64E+02 +/- 4.13E+01 3.12E+02 +/- 2.32E+01 Cr-51 2.98E+02 +/- 4.98E+00 0.97 A 2.95E+02 +/- 5.59E+01 Mean = 2.90E+02 +/- 1.60E+01 1.35E+02 +/- 7.50E+00 Cs-134 1.33E+02 +/- 4.70E+00 1.30E+02 +/- 2.18E+00 1.04 A 1.36E+02 +/- 9.80E+00 Mean = 1.35E+02 +/- 3.10E+00 2.06E+02 +/- 8.80E+00 Cs-137 2.08E+02 +/- 5.00E+00 2.05E+02 +/- 3.43E+00 1.03 A 2.19E+02 +/- 1.06E+01 Mean = 2.11E+02 +/- 3.50E+00 1.26E+02 +/- 7.20E+00 Co-58 1.22E+02 +/- 4.OOE+00 1.13E+02 +/- 1.89E+00 1.07 A 1.16E+02 +/- 9.30E+00 Mean = 1.21 E+02 +/- 2.90E+00 2.82E+02 +/- 1.00E+01 Mn-54 2.75E+02 +/- 5.60E+00 2.66E+02 +/- 4.45E+00 1.05 A 2.79E+02 +/- 1.20E+01 Mean = 2.79E+02 +/- 5.50E+00 03/17/2011 E7438-09 Milk 1.74E+02 +/- 1.07E+01 Fe-59 1..84E+02 +/- 6.OOE+00 1 75E+02 +/- 2.91 E+00 1.06 A 1.98E+02 +/- 1.40E+01 Mean = 1.85E+02 +/- 6.20E+00 2.75E+02 +/- 1.71E+01 Zn-65 2.87E+02 +/- 9.60E+00 2.61E+02 +/- 4.36E+00 1.13 A 3.24E+02 +/- 2.13E+01 Mean = 2.95E+02 +/- 9.60E+00 1.84E+02 +/- 6.60E+00 Co-60 1.69E+02 +/- 3.60E+00 1.72E+02 +/- 2.87E+00 1.00 A 1.61E+02 +/- 7.80E+00 Mean = 1.71E+02 +/- 3.60E+00 1.08E+02 +/- 8.40E+00 1-1311.04E+02 +/- 4.50E+00 1-131 +/- 4.50E+00 9.69E+01 +/- 1.62E+00 1.07 A 9.75E+01 +/- 9.50E+00 Mean = 1.03E+02 +/- 4.50E+00 9.54E+01 +/- 6.50E+00 1.03E+02 +/- 2.60E+00 1-131** 9.69E+01 +/- 1.62E+00 1.00 A 9.18E+01 +/- 3.60E+00 Mean= 9.67E+01 +/- 2.60E+00 n a a u a (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable Result determined by Resin Extraction/Gamma Spectral Analysis.

Page 11

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk DATE SAMPLE ID NO, I MEDIUM ANALYSIS JAF ELAB RESULTS pCi/liter +/-1 sigma REFERENCE LAB*

pCiAiter +/-1 sigma RATIO (1) 8.61E+01 +/- 5.92E+00 8.57E+01 +/- 7.98E+00 Ce-141 7.99E+01 +/- 1.33E+00 1.07 A 8.47E+01 +/- 7.23E+00 Mean = 8.55E+01 +/- 4.10E+00 2.09E+02 +/- 2.64E+01 Cr-51 2.21E+02 +/- 4.24E+01 2.06E+02 +/- 3.44E+00 1.08 A 2.38E+02 +/- 3.70E+01 Mean = 2.23E+02 +/- 2.07E+01 1.81 E+02 +/- 9.37E+00 Cs-134 1.79E+02 +/- 1.25E+01 1.90E+02 +/- 3.17E+00 0.91 A 1.59E+02 +/- 1.31E+01 Mean = 1.73E+02 +/- 6.80E+00 1.35E+02 +/- 4.67E+00 Cs-137 1.45E+02 +/- 6.51E+00 1.38E+02 +/- 2.30E+00 1.00 A 1.36E+02 +/- 6.38E+00 Mean = 1.39E+02 +/- 3.41 E+00 1.58E+02 +/- 4.86E+00 Co-58 1.53E+02 +/- 6.56E+00 1.52E+02 +/- 2.53E+00 1.02 A 1.53E+02 +/- 6.98E+00 Mean = 1.55E+02 +/- 3.58E+00 1.36E+02 + 4.79E+00 Mn-54 1.41 E+02 t 6.81 E+00 1.38E+02 +/- 2.30E+00 1.00 A 06/16/2011 1 E7634-05 Milk 1.38E+02 +/- 6.46E+00 Mean = 1.38E+02 +/- 3.51 E+00 1.33E+02 +/- 5.64E+00 Fe-59 1.45E+02 +/- 8.64E+00 1.23E+02 +/- 2.06E+00 1.10 A 1.27E+02 +/- 7.70E+00 Mean = 1.35E+02 +/-t 4.29E+00 2.66E+02 +/- 9.97E+00 Zn-65 2.62E+02 t 1.44E+01 2.61 E+02 +/- 4.35E+00 1.01 A 2.61 E+02 +/- 1.38E+01 Mean = 2.63E+02 +/- 7.43E+00 1.96E+02 +/- 4.09E+00 Co-60 1.96E+02 +/- 5.91 E+00 Co-60 2.05E+02 5.9E+00 1+/-

t 5.69E+00 1.95E+02 +/- 3.25E+00 1.02 A Mean = 1.99E+02 +/- 3.06E+00 1.12E+02 +/- 5.24E+00 1-131 9.23E+01 +/- 7.65E+00 1.03E+02 +/- 1.72E+00 0.99 A 1.01E+02 +/- 8.95E+00 Mean = 1.02E+02 +/- 4.30E+00 9.23E+01 +/- 1.18E+00 8.98E+01 +/- 1.68E+00 1-131" 1.03E+02 +/-t 1.72E+00 0.89 A 9.25E+01 t 1.26E+00 Mean = 9.15E+01 +/- 8.03E-01 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable Result determined by Resin Extraction/Gamma Spectral Analysis.

Page 12

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk DATE SAMPLE M JAF ELAB RESULTS REFERENCE LAB* IRATIO(1)

DATE_ ID NO. MEDIUM pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO_(1) 7.92E+01 " 7.50E+00 6.47E+01 +/- 5.20E+00 Ce-141 6.67E+01 +/- 1.11E+00 1.07 A 6.98E+01 :t 6.40E+00 Mean = 7.12E+01 +/- 3.72E+00 1.87E+02 +/- 3.55E+01 Cr-51 2.43E+02 +/- 2.58E+01 2.26E+02 +/- 3.78E+00 0.96 A 2.24E+02 +/- 2.93E+01 Mean = 2.18E+02 +/- 1.76E+01 1.12E+02 +/- 1.17E+01 Cs-134 1.24E+/-02 +/- 8.50E+00 1.28E+02 +/- 2.14E+00 0.92 A 1.16E+02 +/- 9.50E+00 Mean = 1.17E+02 +/- 5.77E+00 1.11 E+02 +/- 6.OOE+00 Cs-137 1.11E+02 +/- 4.50E+00 1.14E+02 +/- 1.90E+00 0.99 A 1.15E+02 +/- 4.90E+00 Mean = 1.12E+02 +/- 2.99E+00 1.04E+02 +/- 5.80E+00 Co-58 1.07E+02 +/- 4.40E+00 9.75E+01 +/- 1.63E+00 1.04 A 9.31 E+01 +/- 4.50E+00 Mean = 1.01EE+02 +/- 2.85E+00 1.68E+02 +/- 6.90E+00 Mn-54 1.57E+02 +/- 5.1OE+00 1.51E+02 +/- 2.52E+00 1.06 A 09/15/2011 E8124-05 Milk 1.54E+02 +/- 5.60E+00 Mean = 1.60E+02 +/- 3.42E+00 6.19E+01 +/- 7.OOE+00 Fe-59 6.58E+01 +/- 4.90E+00 5.48E+01 +/- 9.15E-01 1.11 A 5.52E+01 +/- 5.40E+00 Mean = 6.10E+01 +/- 3.37E+00 1.94E+02 +/- 1.36E+01 Zn-65 1.91E+02 +/- 9.40E+00 1.80E+02 +/- 3.01E+00 1.08 A 1.99E+02 +/- 1.06E+01 Mean = 1.95E+02 +/- 6.55E+00 1.59E+02 +/- 5.30E+00 Co-60 1.65E+02 +/- 4.1OE+00 1.57E+02 +/- 2.62E+00 1.02 A 1.55E+02 +/- 4.40E+00 Mean = 1.60E+02 +/- 2.67E+00 8.69E+01 +/- 6.60E+00 1-131 9.79E+01 +/- 5.30E+00 8.92E+01 +/- 1.49E+00 1.06 A 9.77E+01 +/- 5.80E+00 Mean = 9.42E+01 +/- 3.42E+00 7.98E+01 +/- 1.10E+00 7.95E+01 " 1.00E+00 1-131"" 8.92E+01 +/- 1,49E+00 0.89 A 7.85E+01 +/- 1.60E+00 Mean = 7.93E+01 +/- 7.28E-01 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

Page 13

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water DATE SAMPLE ID NO.

r MEDIUM AL ANALYSIS I JAF ELAB RESULTS pCi/liter +/-1 sigma REFERENCE LAB*

pCi/liter +1 sigma RATIO (1)

R 1.86E+02 " 1.85E+01 2.05E+02 " 1.OOE+01 Cr-51 1.96E+02 +/- 3.27E+00 1.04 A 2.22E+02 " 2.57E+01 Mean = 2.04E+02 +/- 1.11E+01 9.40E+01 +/- 3.32E+00 Cs-134 9.20E+01 +/- 2.32E+00 8.56E+01 +/- 1.43E+00 1.08 A 9.10E+01 +/- 5.06E+00 Mean = 9.22E+01 +/- 2.16E+00 1.43E+02 +/- 3.86E+00 Cs-1371.42E+02 +/- 2.49E+00 Cs-137 1.34E+02 +/- .E+00 1.4E+02

+/- 5.55E+00 1.35E+02 +/- 2.25E+00 1.04 A Mean = 1.40E+02 +/- 2.40E+00 8.10E+01 +/- 2.96E+00 Co-58 7,70E+01 +/- 1.97E+00 7.44E+01 +/- 1.24E+00 1.04 A 7.40E+01 +/- 4.54E+00 Mean = 7.72E+01 +/- 1.92E+00 1.87E+02 +/- 4.33E+00 Mn-54 1.83E+02 +/- 2.82E+00 1.75E+02 +/- 2.92E+00 1.06 A 1.89E+02 +/- 6.38E+00 Mean = 1.86E+02 +/- 2.74E+00 03/17/2011 E7477-05 Water 1.21 E+02 +/- 4.09E+00 Fe-59 1.28E+02 +/- 2.83E+00 1.15E+02 +/- 1.91E+00 1.05 A 1.15E+02 +/- 6.22E+00 Mean = 1.21E+02 +/- 2.65E+00 1.98E+02 +/- 7.05E+00 Zn-65 1.91E+02 +/- 4.62E+00 1.72E+02 +/- 2.87E+00 1.12 A 1.87E+02 +/- 1.03E+01 Mean = 1.92E+02 +/- 4.44E+00 1.17E+02 +/- 2.65E+00 Co-60 1.15E+02 +/- 1.80E+00 1.13E+02 +/- 1.88E+00 1.03 A 1.16E+02 +/- 3.97E+00 Mean = 1.16E+02 +/- 1.70E+00 9.26E+01 +/- 3.25E+00 1-131 9.59E+01 +/- 2.12E+00 9.40E+01 +/- 1.57E+00 1.01 A 9.53E+01 +/- 4.53E+00 Mean = 9.46E+01 +/- 1.99E+00 9.OOE+01 +/- 9.50E-01 8.41 E+01 +/- 2.19E+00 1-131* 9.40E+01 +/- 1.57E+00 0.94 A 9.09E+01 +/- 2.14E+00 Mean = 8.83E+01 +/- 1.07E+00 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable Result determined by Resin Extraction/Gamma Spectral Analysis.

Page 14

Table D.4-1 (Continued)

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

DATE DATE IDNO. MEDIUM YIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma R-TIO_(1 9.16E+01 " 7.08E+00 9.17E+01 +/- 7.37E+00 Ce-141 8.77E+01 +/- 7.26E+00 9,35E+01 +/- 1,56E+00 0.95 A 8.70E+01 +/- 7.68E+00 Mean = 8.96E+01 t 4.26E+00 1.97E+02 +/- 3,18E+01 1.83E+02 +/- 3.68E+01 Cr-51 2.67E+02 +/- 3121E+01 2.41E+02 +/- 4.03E+00 0.96 A 2.77E+02 +/- 4.54E+01 Mean = 2.31 E+02 +/- 2.22E+01 2.11E+02 +/- 1.18E+01 2.22E+02 +/- 1.16E+01 Cs-134 2.08E+02 +/- 1.06E+01 2.22E+02 - 3.71E+00 0.98 A 2.25E+02 +/- 1.39E+01 Mean = 2.17E+02 +/- 7.20E+00 1.68E+02 +/- 5.77E+00 1.56E+02 +/- 5373E+00 Cs-137 1.64E+02 +/- 5.25E+00 1.61E+02 +/- 2.70E+00 1.00 A 1.56E+02 +/- 6.66E+00 Mean = 1.61 E+02 +/- 3.50E+00 1.90E+02 +/- 6.17E+00 1.75E+02 +/- 5.95E+00 Co-58 1.88E+02 +/- 5.93E+00 1,77E+02 +/- 2.96E+00 1,04 A 1.83E+02 +/- 7.07E+00 Mean = 1.84E+02 +/- 3.70E+00 1.65E+02 +/- 5.71 E+00 1.83E+02 +/- 6.12E+00 06/16/2011 E7617-09 Water Mn-54 1.69E+02 +/- 5.41E+00 1.61E+02 +/- 2.69E+00 1.07 A 1.74E+02 +/- 7.25E+00 Mean = 1.73E+02 .t 3.70E+00 1.57E+02 +/- 6.81E+00 1.45E+02 +/- 6.86E+00 Fe-59 1.73E+02 t 8.93E+00 1.44E+02 +/- 2.41E+00 1.10 A 1.55E+02 +/- 6.68E+00 Mean = 1.58E+02 +/- 4.40E+00 3.16E+02 +/- 1.24E+01 2.98E+02 +/- 1.21E+01 Zn-65 3.23E+02 +/- 1.20E+01 3.05E+02 +/- 5.09E+00 1.03 A 3.16E+02 +/- 1.53E+01 Mean = 3.13E+02 t 7.70E+00 2.26E+02 +/- 5.07E+00 2.32E+02 +/- 5.17E+00 Co-60 2.43E+02 +/- 4.79E+00 2.28E+02 +/- 3.80E+00 1.02 A 2.25E+02 +/- 6.21 E+00 Mean = 2.32E+02 +/- 3.20E+00 1.10E+02 +/- 7.24E+00 1.01 E+02 +/- 7.44E+00 1-131 1.06E+02 +/- 7.37E+00 1.01E+02 +/- 1.68E+00 1.07 A 1.15E+02 +/- 9.22E+00 Mean = 1.08E+02 +/- 3.90E+00 9.73E+01 " 1.33E+00 9.78E+01 " 1.52E+00 I-131 ** 1.01E+02 +/- 1.68E+00 0.96 A 9.43E+01 " 1.47E+00 Mean = 9.65E+01 +/- 8.33E-01 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable Result determined by Resin Extraction/Gamma Spectral Analysis.

Page 15

Table D.4-1 (Continued)

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

DATE ID NO. pCi/liter +/-1 sigma /ie___im 4.75E+01 +/- 4.70E+00 5.28E+01 +/- 4.90E+00 Ce-141 5.32E+01 -+/- 8.88E-01 1.00 A 5.99E+01 +/- 4.20E+00 Mean = 5.34E+01 +/- 2.70E+00 1.65E+02 +/- 2.39E+01 Cr-51 1.75E+02 +/- 2.35E+01 1.80E+02 _ 3.01E+00 0.97 A 1.84E+02 +/- 1.98E+01 Mean = 1.75E+02 +/- 1.30E+01 9.86E+01 +/- 7.00E+00 Cs-134 8.86E+01 +/- 7.80E+00 1.02E+02 +/- 1.71 E+00 0.93 A 9.75E+01 +/- 6.70E+00 Mean = 9.49E+01 +/- 4.10E+00 9.10E+01 +/- 3.70E+00 Cs-137 9.41E+01 +/- 4.50E+00 9.07E+01 +/- 1.51E+00 1.00 A 8.80E+01 +/- 3.50E+00 Mean = 9.10E+01 +/- 4.10E+00 7.59E+01 +/- 3.60E+00 Co-58 8.37E+01 +/- 4.40E+00 7.77E+01 _ 1.30E+00 1.05 A 8.43E+01 _ 3.40E+00 Mean = 8.13E+01 +/- 2.20E+00 1.17E+02 +/- 4.30E+00 Mn-54 1.18E+02 4.90E+00 1.20E+02 +/- 2.01 E+00 1.01 A 09/15/2011 1 E8122-05 Water 1.28E+02 +/- 3.90E+00 Mean = 1.21 E+02 +/- 2.50E+00 5.17E+01 +/- 3.80E+00 Fe-59 4.44E+01 +/- 4.30E+00 4.37E+01 +/- 7.30E-01 1.09 A 4.73E+01 +/- 3.60E+00 Mean = 4.78E+01 +/- 2.30E+00 1.49E+02 +/- 7.90E+00 Zn-65 1.43E+02 +/- 8.90E+00 1.44E+02 +/- 2.40E+00 1.02 A 1.48E+02 +/- 7.00E+00 Mean = 1.47E+02 +/- 4.60E+00 1.24E+02 +/- 3,30E+00 Co-60 1.22E+02 +/- 3.80E+00 1.25E+02 +/- 2.09E+00 0.98 A 1.23E+02 +/- 3,00E+00 Mean = 1.23E+02 +/- 1,90E+00 8.59E+01 +/- 4.50E+00 1-131 8.20E+01 +/- 5.20E+00 7.99E+01 +/- 1.33E+00 1.03 A 7.91E+01 +/- 4.10E+00 Mean = 8.23E+01 +/- 2.70E+00 7.93E+01 +/- 1.OOE+00 7.61E+01 +/- 1.30E+00 1-131"* 7.99E+01 +/- 1.33E+00 0.84 A 7.63E+01 +/- 1.30E+00 Mean = 6.72E+01 +/- 7.OOE-01 (1) Ratio = Reported/Analytics. A=Acceptable Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

Page 16

Table D.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water DATE SAMPLE I MEDIUM ANALYSIS JAF ELAB RESULTS REFERENCE LAB* RATIO (1)

ID NO. pCi/liter +/- 1 sigma pCi/liter +/- 1 sigma 5.01E+02 +/- 4.08E+01 6.12E+02 +/- 3.81E+01 5.66E+02 +/- 3.61E+01 Cr-51 5.66E+02 +/- 9.45E+00 0.99 A 5.89E+02 +/- 3,49E+01 5&46E+02 +/- 3.77E+01 fean = 5.63E+02 +/- 2.55E+01 1.59E+02 +/- 1.34E+01 1.68E+02 +/- 1.17E+01 Cs-134 1.70E+02 +/- 9.30E+00 1.71E+02 +/- 2.86E+00 0.99 A 1.78E+02 +/- 1.08E+01 1.74E+02 +/- 1.07E+01 Mean = 1.70E+02 +/- 7.60E+00 2.16E+02 +/- 7.50E+00 2.13E+02 +/- 6.70E+00 2,09E+02 +/- 5.70E+00 Cs-137 2.10E+02 +/- 3.50E+00 1.03 A 2.12E+02 +/- 6.OOE+00 2.28E+02 +/- 6.50E+00 Mean = 2.16E+02 +/- 4.40E+00 2.29E+02 +/- 7.80E+00 2.36E+02 +/- 7.00E+00 Co-58 2.24E+02 +/- 5.70E+00 2.21E+02 +/- 3.69E+00 1.04 A 2.21E+02 +/- 6.30E+00 2.37E+02 +/- 6.50E+00 Mean = 2.29E+02 +/- 4.50E+00 2.49E+02 +/- 8.1OE+00 2.64E+02 +/- 7.20E+00 Mn-54 2.69E+02 6.20E+00 2.41 E+02 +/- 4.02E+00 1.08 A 2.61EE+02 +/- 6.60E+00 2.62E+02 +/- 6.90E+00 12/08/2011 E8183-09 Water Mean = 2.61E+02 +/- 4.80E+00 2.14E+02 +/- 8.50E+00 2.03E+02 +/- 7.73E+01 Fe-59 2.03E+02 6.40E+00 1.83E+02 +/- 3.06E+00 1.11 A 2.04E+02 +/- 7.OOE+00 1.88E+02 +/- 7.30E+00 Mean = 2.02E+02 +/- 4.90E+00 3.20E+02 +/- 1.44E+01 3.11E+02 +/- 1.27E+01 3.30E+02 +/- 1,03E+01 Zn-65 2.91E+02 +/- 4.87E+00 1.08 A 3.06E+02 +/- 1.13E+01 3.07E+02 +/- 1.22E+01 Mean = 3.15E+02 +/- 8.30E+00 2.86E+02 +/- 6.50E+00 2.87E+02 +/- 5.70E+00 Co-60 2.82E+02 t 4.80E+00 2,70E+02 +/- 4.51E+00 1.06 A 2.88E+02 +/- 5.20E+00 2.87E+02 +/- 5.50E+00 Mean = 2.86E+02 +/- 3.80E+00 9.25E+01 +/- 5.50E+00 1.OOE+02 +/- 5.30E+00 1-131 9.961+01 +/- 5.50E+00 8&87E+01 +/- 1.48E+00 1.05 A 8.49E+01 +/- 5.40E+00 8.66E+01 +/- 5.60E+00 Mean = 9.27E+01 +/- 3.60E+00 1.07Ej02 1.90E+00 I

1.16E+02 +/-2.10E+00 1-131** 1.08E+02 +/-2.80E+00 8.87E+01 +/- 1.48E+00 1.25 A 1.11E+02 t 2-50E÷00 MAean = 1.11 E+02 +/- 1.30E+00 (1) Ratio = Reported/Analytics. A=Acceptable U=Unacceptable Sample provided by Analytics, Inc.

Result determined by Resin Extraction/Gamma Spectral Analysis.

Paqe 17

D.5 References D.5.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

D.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).

Paae 18

D.6 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES INTERCOMPARISON PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBEAnalytics March 2011 11 -MaW24 Water Am-241 Bq/L 0.418 0.529 0.370 - 0.688 W Ba-133 pCi/L 73.3 75.3 63.0 - 82.8 A E7463-396 AP Co-57 Bq/L 0.139 (1) A Co-58 pCi/L 121 113 1.07 A Co-60 pCi/L 186 172 1.08 A Cr-51 pCi 243 215 1.13 A Cs-134 pCi/L 130 130 1.00 A Cs-137 pCi/L 74.6 77.0 69.3 - 87.4 A E7464-396 Water Fe-55 pCi/L 2090 1940 1.08 A Fe-59 pCi/L .201 175 1.15 A Gr-A pCi/L 64.1 50.1 26.1 - 62.9 N (1)

Gr-B pCi/L 51.8 49.8 33.8 - 56.9 A H-3 pCi/L 10057 10200 8870-11200 A E7461-396 Milk 1-131 pCi/L 92.9 96.9 0.96 A K-40 Bq/kg 569 540 378 - 702 A Mn-54 pCi/L 289 266 1.09 A Ni-63 Bq/L 17.8 18.6 13.0 -24.2 A Pu-238 Bq/sample 0.095 0.096 0.067 - 0.125 A Pu-239/240 Bq/L 0.715 0.809 0.566 - 1.052 A March 2011 E7460-396 Milk Sr-89 pCi/L 98.8 97.4 1.01 A Sr-90 pCi/L 42.5 42.5 31.3 - 48.8 A Tc-99 Bq/kg -3.79 (1) A U-234/233 Bq/L 1.57 1.50 1.05-1.95 A U-238 Bq/sample 0.165 0.185 0.130 - 0.241 A U-Nat pCi/L 38.5 39.8 32.2 - 44.4 A Zn-65 pCi/L 287 261 1.10 A Ce-1 41 pCi/L 68.1 79.9 0.85 A (1) Calculationdid not allow for Y-90 ingrowth on the Sr-89 mount. NCR 09-14 (a) Teledyne Brown Engineeringreported result.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurementsmade during standardpreparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units ,Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2011 E7460-396 Milk Sr-89 pCi/L 98.8 97.4 1.01 A Sr-90 pCi/L 15.2 15.8 0.96 A E7461-396 Milk 1-131 pCi/L 92.9 96.9 0.96 A Ce-141 pCi/L NA Cr-51 pCi/L 398 298 1.34 N (1)

Cs-134 pCi/L 130 130 1.00 A Cs-137 pCi/L 232 205 1.13 A Co-58 pCi/L 121 113 1.07 A Mn-54 pCi/L 289 266 1.09 A Fe-59 pCi/L 201. 175 1.15 A Zn-65 pCi/L 287 261 1.10 A Co-60 pCi/L 186 172 1.08 A E7463-396 AP Ce-141 pCi NA Cr-51 pCi 243 215 1.13 A Cs-134 pCi 85.0 94.2 0.90 A Cs-137 pCi 168 148 1.14 A Co-58 pCi 89.2 81.8 1.09 A Mn-54 pCi 171 192 0.89 A Fe-59 pCi 129 126 1.02 A Zn-65 pCi 159 189 0.84 A Co-60 pCi 132 124 1.06 A E7462-396 Charcoal 1-131 pCi 96.5 96.3 1.00 A E7464-396 Water Fe-55 pCi/L 2090 1940 1.08 A June 2011 E7851-396 Milk Sr-89 pCi/L 96.7 103 0.94 A Sr-90 pCi/L 13.8 15.6 0.88 A E7852-396 Milk 1-131 pCi/L 110 103.0 1.07 A Ce-141 pCi/L 68.1 79.9 0.85 A Cr-51 pCi/L 186 206 0.90 A Cs-134 pCi/L 164 190 0.86 A Cs-137 pCi/L 140 138 1.01 A Co-58 pCi/L 141 152 0.93 A Mn-54 pCi/L 136 138 0.99 A Fe-59 pCi/L 128 123 1.04 A Zn-65 pCi/L 263 261 1.01 A Co-60 pCi/L 189 195 0.97 A E7854-396 AP Ce-141 pCi 49.9 42.9 1.16 A Cr-51 pCi 95.6 110 0.87 A Cs-134 pCi 104 102 1.02 A Cs-137 pCi 83.8 74.0 1.13 A Co-58 pCi 90.7 81.3 1.12 A Mn-54 pCi 74.5 73.9 1.01 A Fe-59 pci 62.0 66.1 0.94 A Zn-65 pCi 140 140 1.00 A Co-60 pCi 119 104 1.14 A E7853-396 Charcoal 1-131 pCi 76.2 86.1 0.89 A

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

June 2011 E7855-396 Water Fe-55 pCi/L 1770 1970 0.90 A September 2011 E8070-396 Milk Sr-89 pCi/L 102 90.8 1.12 A Sr-90 pCi/L 13.2 14.7 0.90 A E8071-396 Milk 1-131 pCl/L 74.2 89.2 0.83 A Ce-141 pCilL 66.9 66.7 1.00 A Cr-51 pCi/L 249 226 1.10 A Cs-134 pCilL 116 128 0.91 A Cs-137 pCilL 106 114 0.93 A Co-58 pCi/L 95.4 97.5 0.98 A Mn-54 pCi/L 147 151 0.97 A Fe-59 pCi/L 53.1 54.8 0.97 A Zn-65 pCi/L 175 180 0.97 A Co-60 pCi/L 150 157 0.96 A E8073-396 AP Ce-141 pCi 66.6 67.5 0.99 A Cr-51 pCi 263 229 1.15 A Cs-134 pCi 139 130 1.07 A Cs-137 pCi 110 115 0.96 A Co-58 pCi / 108 98.6 1.10 A Mn-54 pCi 152 153 0.99 A Fe-59 pCi 57.5 55.5 1.04 A Zn-65 pCi 190 183 1.04 A Co-60 pCi 156 159 0.98 A E8072-396 Charcoal 1-131 pCi 77.6 80.6 0.96 A September 2011 E8074-396 Water Fe-55 pCi/L 1710 1790 0.96 A December, 2011 E8230-396 Milk Sr-89 pCi/L 93.3 93.1 1.00 A Sr-90 pCi/L 12.7 15.4 0.82 A E8231-396 Milk 1-131 pCi/L 82.5 90.2 0.91 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 465 566 0.82 A Cs-134 pCi/L 142 171 0.83 A Cs-137 pCi/L 185 210 0.88 A Co-58 pCi/L 177 221 0.80 A Mn-54 pCi/L 208 241 0.86 A Fe-59 pCi/L 164 183 0.90 A Zn-65 pCi/L 259 291 0.89 A Co-60 pCilL 224 270 0.83 A December, 2011 E8233-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 344 368 0.93 A Cs-134 pCi 105 ill 0.95 Cs-137 pCi 129 137 0.94 Co-58 pCi 145 144 1.01 A Mn-54 pCi 137 157 0.87 A Fe-59 pCi 119 119 1.00 A Zn-65 pCi 145 190 0.76 W Co-60 pCi 168 176 0.95 A

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2011 E8232-396 Charcoal 1-131 pCi 100 89.5 1.12 A (I) Sample appears to be biased high. Corrective Action evaluated after the 2nd QuarterAnalytics PE sample; no action required. NCR 11-13 (a) Teledyne Brown Engineering reported result.

(b) The Analytics known value is equal to 100% of the parameterpresentin the standardas determined by gravimetricand/or volumetric measurementsmade during standardpreparation.

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

(d) Analytics evaluation based on TBE internal OC limits: A= Acceptable. Reported result falls within ratiolimits of 0.80-1.20.

W-Acceptable with warning. Reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

March 2011 11 -MaW24 Water Am-241 Bq/L 0.418 0.529 0.370 - 0.688 W Cs-134 Bq/L 19.1 21.5 15.1 -28.0 A Cs-137 Bq/L 29.0 29.4 20.6 - 38.2 A Co-57 Bq/L 0.139 (1) A Co-60 Bq/L 23.9 24.6 17.2-32.0 A H-3 Bq/L 265 243 170-316 A Mn-54 Bq/L 31.8 31.6 22.1 -41.1 A Ni-63 Bq/L 17.8 18.6 13.0 - 24.2 A Pu-238 Bq/L 0.92 1.064 0.745 - 1.383 A Pu-239/240 Bq/L 0.715 0.809 0.566 - 1.052 A K-40 Bq/L 94.8 91 64- 118 A Sr-90 Bq/L 9.64 8.72 6.10- 11.34 A Tc-99 Bq/L 8.09 8.99 6.29- 11.69 A U-234/233 Bq/L 1.57 1.50 1.05-1.95 A U-238 Bq/L 1.57 1.54 1.08 - 2.00 A Zn-65 Bq/L -0.142 (1) A 11l-GrW24 Water Gr-A Bq/L 0.767 1.136 0.341 - 1.931 A Gr-B Bq/L 3.43 2.96 1.48- 4.44 A 11 -MaS24 Soil Am-241 Bq/kg 50.3 61.1 42.8 - 79.4 A Cs- 134 Bq/kg 612 680 476 - 884 A Cs- 137 Bq/kg 772 758 531 - 985 A Co-57 Bq/kg 910 927 649- 1205 A Co-60 Bq/kg 500 482 337 - 627 A Mn-54 Bq/kg 0.607 (1) A Ni-63 Bq/kg 511 582 407 - 757 A Pu-238 Bq/kg 0.375 0.48 (4) A Pu-239/240 Bq/kg NR 98.0 68.6- 127.4 N (2)

K-40 Bq/kg 569 540 378 - 702 A Sr-90 Bq/kg NR 160 112 - 208 N (3)

Tc-99 Bq/kg -3.79 (1) A U-234/233 Bq/kg 148 176 123-229 A U-238 Bq/kg 134 184 129-239 W Zn-65 Bq/kg 1497 1359 951 - 1767 A 11-RdF24 AP Am-241 Bq/sample 0.0067 (1) A Cs-134 Bq/sample 3.26 3.49 2.44 - 4.54 A Cs-137 Bq/sample 2.36 2.28 1.60-2.96 A Co-57 Bq/sample 3.30 3.33 2.33 - 4.33 A Co-60 Bq/sample 0.0765 (1) A Mn-54 Bq/sample 2.84 2.64 1.85 - 3.43 A Pu-238 Bq/sample 0.095 0.096 0.067 - 0.125 A Pu-239/240 Bq/sample 0.0687 0.0765 0.0536 - 0.0995 A Sr-90 Bq/sample NR 1.36 0.95- 1.77 N (3)

U-234/233 Bq/sample 0.163 0.178 0.125 - 0.231 A U-238 Bq/sample 0.165 0.185 0.130 - 0.241 A Zn-65 Bq/sample 3.30 3.18 2.23- 4.13 A 11-GrF24 AP Gr-A Bqlsample 0.101 0.659 0.198 - 1.120 N (5)

Gr-B Bq/sample 1.23 1.323 0.662 - 1.985 A

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

March 2011 11 -RdV24 Vegetation Cs-134 Bq/sample 4.97 5.50 3.85 - 7.15 A Cs-137 Bq/sample 0.0356 (1) A Co-57 Bq/sample 10.8 9.94 6.96-12.92 A Co-60 Bq/sample 4.89 4.91 3.44 - 6.38 A Mn-54 Bq/sample 6.42 6.40 4.48 - 8.32 A Sr-90 Bq/sample NR 2.46 1.72-3.20 N (3)

Zn-65 Bq/sample 3.07 2.99 2.09 - 3.89 A September 2011 11-MaW25 Water Am-241 Bq/L 2.64 3.18 2,23-4.13 A Cs-134 Bq/L 16.0 19.1 13.4-24.8 A Cs-137 Bq/L 0.0043 (1) A Co-57 Bq/L 33.1 36.6 25.6 - 47.6 A Co-60 Bq/L 26.9 29.3 20.5 - 38.1 A H-3 Bq/L 1011 1014 710-1318 A Mn-54 Bq/L 23.2 25.0 17.5 - 32.5 A Ni-63 Bq/L 0.581 (1) A Pu-238 Bq/L 0.0264 0.016 (4) A Pu-239/240 Bq/L 1.74 2.40 1.66-3.12 W K-40 Bq/L 147 156 109-203 A Sr-90 Bq/L 15.8 14.2 9.9 - 18.5 A Tc-99 Bq/L -1.00 (1) A U-234/233 Bq/L 2.53 2.78 1.95-3.61 A U-238 Bq/L 2.60 2.89 2.02 - 3.76 A Zn-65 Bq/L 27.3 28.5 20.0 - 37.1 A 1 1-G rW25 Water Gr-A Bq/L 0.894 0.866 0.260 - 1.472 A Gr-B Bq/L 5.87 4.81 2.41 - 7.22 A 11 -MaS25 Soil Am-241 Bq/kg 0.270 0.259 (4) A Cs-134 Bq/kg -0.213 (1) A Cs-137 Bq/kg 1110 979 685-1273 A Co-57 Bq/kg 1290 1180 826-1534 A Co-60 Bq/kg 731 644 451 -837 A Mn-54 Bq/kg 987 848 594-1102 A Ni-63 Bq/kg 10.08 (1) A Pu-238 Bq/kg 93.1 93.6 65.5-121.7 A Pu-239/240 Bq/kg 74.6 77.4 54.2- 100.6 A K-40 Bq/kg 753 625 438 -813 W Sr-90 Bq/kg 276 320 224-416 A Tc-99 Bq/kg 133 182 127-237 W U-234/233 Bq/kg 275 263 184-342 A U-238 Bq/kg 281 274 192-356 A Zn-65 Bq/kg 1870 1560 1092-2028 A

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

September 2011 11-RdF25 AP Am-241 Bq/sample 0.124 0.147 0.103 - 0.191 A Cs-134 Bq/sample -0.043 (1) A Cs-137 Bqlsample 3.09 2.60 1.82 - 3.38 A Co-57 Bq/sample 5.36 5.09 3.56 - 6.62 A Co-60 Bq/sample 3.41 3.20 2.24-4.16 A Mn-54 Bq/sample 0.067 (1) A Pu-238 Bq/sample 0.138 0.1183 0.0828 - 0.1538 A Pu-239/240 Bq/sample 0.135 0.135 0.095 - 0.176 A Sr-90 Bq/sample 1.84 1.67 1.17-2.17 A U-234/233 Bq/sample 0.153 0.162 0.113 - 0.211 A U-238 Bq/sample 0.164 0.168 0.118-0.218 A Zn-65 Bq/sample 5.17 4.11 2.88-5.34 W 11 -GrF25 AP Gr-A Bq/sample 0.0058 (1) A Gr-B Bq/sample -0.01 (1) A 11-RdV25 Vegetation Cs-134 Bq/sample 0.0081 (1) A Cs-137 Bq/sample 4.94 4.71 3.30 -6.12 A Co-57 Bq/sample 0.0639 (1) A Co-60 Bq/sample 3.36 3.38 2.37 - 4.39 A Mn-54 Bq/sample 5.89 5.71 4.00 - 7.42 A Sr-90 Bq/sample 1.31 1.26 0.88-1.64 A Zn-65 Bq/sample 6.54 6.39 4.47 - 8.31 A (1) False positive test.

(2) Evaluated as failed, with a note of false negative due to reportingonly one of the plutonium isotopes. NCR 11-11 (3) Evaluated as failed due to not reporting a previously reportedanalyte. NCR 11-11 (4) Sensitivity evaluation (5) The filter for Gross Alpha was counted on the wrong side. Recounted on the correctside resulted in acceptable results. NCR 11-11 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determinedby gravimetricand/or volumetric measurements made during standardpreparation.

(c) DOEIMAPEP evaluation:A=acceptable, W=acceptable with warning,N=not acceptable.

ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)

May 2011 RAD-85 Water Sr-89 pCi/L 59.8 63.2 51.1 -71.2 A Sr-90 pCi/L 42.5 42.5 31.3-48.8 A Ba-133 pCi/L 73.3 75.3 63.0- 82.8 A Cs-134 pCi/L 64.9 72.9 59.5 - 80.2 A Cs-137 pCi/L 74.6 77.0 69.3 - 87.4 A Co-60 pCl/L 87.8 88.8 79.9- 100 A Zn-65 pCi/L 103 98.9 89.0- 118 A Gr-A pCi/L 64.1 50.1 26.1 -62.9 N (1)

Gr-B pCi/L 51.8 49.8 33.8 - 56.9 A 1-131 pCi/L 27.4 27.5 22.9 - 32.3 A U-Nat pCi/L 38.5 39.8 32.2 - 44.4 A H-3 pCi/L 10057 10200 8870- 11200 A MRAD-1 4 Filter Gr-A pCi/filter 79.7 74.3 38.5-112 A November 2011 RAD-87 Water Sr-89 pCi/L 81.0 69.7 56.9 - 77.9 N (2)

Sr-90 pCi/L 35.5 41.4 30.2 - 47.2 A Ba- 133 pCi/L 90.7 96.9 81.8 - 106 A Cs-134 pCi/L 36.6 33.4 26.3 - 36.7 A Cs-137 pCi/L 44.7 44.3 39.4- 51.7 A Co-60 pCi/L 118.7 119 107- 133 A Zn-65 pCi/L 80.2 76.8 68.9 - 92.5 A Gr-A pCi/L 34.2 53.2 27.8 - 66.6 A Gr-B pCi/L 39.3 45.9 30.9 - 53.1 A.

1-131 pCi/L 22.9 27.5 22.9 - 32.3 A U-Nat pCi/L 46.8 48.6 39.4- 54.0 A H-3 pCi/L 15733 17400 15200- 19100 A MRAD-15 Filter Gr-A pCi/filter 44.6 58.4 30.3 - 87.8 A (1) The solids on the planchetexceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio of 1.16 fell within acceptable rangeof +/- 20%. No action required.NCR 11-16 (a) Teledyne Brown Engineeringreportedresult.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determinedby gravimetricand/or volumetric measurements made during standardpreparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE-check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

D.7 Environmental TLD Quality Assurance Environmental dosimetry services for the reporting period of January - December, 2011 were provided by the Environmental Dosimetry Company (EDC), Sterling, Massachusetts. The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in-house performance testing and independent performance testing by EDC clients.

The purpose of the dosimetry quality assurance program is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes. Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in-house testing program conducted by the EDC QA Officer and (2) independent test perform by EDC clients.

Excluded from this report are instrumentation checks. Although instrumentation checks represent an important aspect of the quality assurance program, they are not included as process checks in this report. Instrumentation checks represent between 5-10% of the TLDs processed.

Table D.7-1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons (Cs-137) only. The internal acceptance (tolerance) criteria for the Panasonic Environmental dosimeters are: +/- 15% for bias and +/- 12.8%

for precision. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (72/72) met the criterion for precision.

Table D.7-2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall, 100% (12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria.

Table D.7-3 presents the independent blind spike results for irradiated dosimeters provided by client utilities during this annual period. All results passed the performance acceptance criterion.

TABLE D.7-1 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2011(1), (2)

Number P d Bi Cite % Passed Precision Dosimeter Type Tested asse ias rera Criteria Panasonic Environmental 72 100 100 1

( )This table summarizes results of tests conducted by EDC.

(2)Environmental dosimeter results are free in air.

TABLE D.7-2 MEAN DOSIMETER ANALYSES (N=6)

JANUARY - DECEMBER 2011(1)' (2)

Standard Tolerance Process Date Mean Bias % Deviation % Limit +1-15%

04/22/2011 3.0 1.9 Pass 05/02/2011 8.0 1.4 Pass 05/18/2011 0.2 1.4 Pass 07/21/2011 6.2 0.6 Pass 08/05/2011 5.4 0.6 Pass 08/16/2011 7.0 1.1 Pass 10/14/2011 -1.6 1.7 Pass 11/07/2011 0.4 0.8 Pass 01/19/2012 -1.0 1.3 Pass 01/22/2012 -3.1 1.8 Pass 01/29/2012 4.9 1.2 Pass 02/09/2012 -1.6 1.5 Pass (1)This table summarizes results of tests conducted by EDC for TLDs issued in 2011.

(2) Environmental dosimeter results are free in air.

TABLE D.7-3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2011 (1) (2)

Standard Pass I Fail Issuance Period Client Mean Bias % Deviation %

1s'Qtr.2011 Millstone 1.9 2.9 Pass 2na Qtr.2011 Millstone 1.4 3.0 Pass 2nd Qtr.201 I Seabrook 2.0 1.8 Pass 3rd Qtr. 2011 Millstone -2.1 2.9 Pass 4th Qtr.2011 Millstone 7.8 2.8 Pass 4th Qtr.2011 Seabrook 1.7 2.0 Pass

( 1)Performance criteria are +/- 30%.

(2) Blind spike irradiations using Cs-1 37

APPENDIX E ADDENDA E-1

APPENDIX E ADDENDA The following pages are corrections to the 2010 AREOR.

E-1

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2010 Radiological Environmental Monitoring Program (REMP) for the Indian Point site. The Indian Point site consists of Units 1, 2 and 3. Units 1, 2 and 3 are owned and operated by Entergy Nuclear Operations, Inc. Unit 1 was retired as a generating facility in 1974 and, as such, its reactor is no longer operated.

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

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

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

This report contains a description of the REMP and the conduct of that program as required by the IPEC Offsite Dose Calculation Manual, herein referred to as ODCM. This 2010 AREOR also contains summaries and discussions of the results of the 2010 program, trend analyses, and potential impact on the environment, land use census, and inter-laboratory comparisons.

During 2010, a total of 1156 samples were obtained out of a planned load of 1168 samples. Table B-1 presents a summary of the collected sampling results.

An investigation of groundwater contamination with tritium and other radionuclides has been ongoing since 2005 and continued throughout 2010.

This investigation of potential onsite sources of contamination is not the focus of this Annual Radiological Environmental Operating Report; however, in 2006, Entergy agreed to several changes in the REMP to assure that all pathways were being evaluated. Specifically, two new groundwater wells (non-drinking water) were 1-1

TABLE B-1 Summary of Sampling Deviations - 2010 MEDIA~ TOTAL NUMBER OF SAMPLING REASON FOR MEDIA SCHEDULED SAMPLES DEVIATIONS* EFFICIENCY % DEVIATION MEDIA PARTICULATES IN AIR 416 98.8% See Table B-la CHARCOAL FILTER 416 98.8% See Table B-la TLD 164 99% See Table B-lb HUDSON RIVER WATER 24 96% See Table B-lc DRINKING WATER 24 100% N/A SHORELINE SOIL 10 100% N/A BROAD LEAF 63 100% N/A VEGETATION FISH & INVERTEBRATES 24 100% N/A AQUATIC VEG.ETATION 6 100% N/A HUDSON RIVER BOTTOM SEDIMENT 100% N/A SOIL 3 100% N/A PRECIPITATION 8 100% N/A GROUNDWATER 2 SAMPLES 100% N/A TOTALS 1168 99.0%

TOTAL NUMBER OF SAMPLES COLLECTED =

Samples not collected or unable to be analyzed.

B-3

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2010 1-131 ACTIVITY pCi/ m3 +/- 1 Sigma SAMPLE STATION #

Week Week End 4 5 94 95 23** 27 29 44 Number Date 27 07/06/10 < 0.027 < 0.017 < 0.025 < 0.032 < 0.030 < 0.015 < 0.025 < 0.030 28 07/12/10 < 0.044 < 0.039 < 0.033 < 0.026 < 0.032 < 0.037 < 0.025 < 0.033 29 07/19/10 < 0.029 < 0.016 < 0.020 < 0.024 < 0.037 < 0.018 < 0.017 < 0.023 30 07/26/10 < 0.021 < 0.018 < 0.029 < 0.026 < 0.021 < 0.028 < 0.017 < 0.020 31 08/02/10 < 0.016 < 0.024 < 0.034 < 0.026 < 0.023 < 0.017 < 0.010 < 0.024 32 08/09/10 < 0.013 < 0.022 < 0.027 < 0.023 < 0.016 < 0.020 < 0.015 < 0.022 33 08/16/10 < 0.045 < 0.031 < 0.020 < 0.033 < 0.039 < 0.035 < 0.244 < 0.021 34 08/23/10 < 0.021 < 0.014 < 0.021 < 0.017 < 0.036 < 0.029 < 0.034 35 08/30/10 < 0.020 < 0.019 < 0.027 < 0.021 < 0.021 < 0,026 < 0.018 < 0.025 36 09/07/10 < 0.019 < 0.016 < 0.031 < 0.023 < 0.025 < 0.013 < 0.014 < 0.018 37 09/13/10 < 0.034 < 0.019 < 0.024 < 0.030 < 0.018 < 0.031 < 0.024 < 0.032 38 09/20/10 < 0.026 < 0.025 < 0.025 < 0.031 < 0.024 < 0.017 < 0.017 < 0.022 39 09/27/10 < 0.025 < 0.018 < 0.026 < 0.019 < 0.023 < 0.020 < 0.016 < 0.019 40 10/04/10 < 0.026 < 0.025 < 0.021 < 0.017 < 0.029 < 0.024 < 0.018 < 0.029 41 10/12/10 < 0.020 < 0.017 < 0.018 < 0.018 < 0.025 < 0.017 < 0.023 < 0.021 42 10/18/10 < 0.032 < 0.020 < 0.027 < 0.025 < 0.026 < 0.017 < 0.014 < 0.030 43 10/25/10 < 0.019 < 0.021 < 0.024 < 0.020 < 0.022 < 0.019 < 0.047 < 0.020 44 11/01/10 < 0.022 < 0.015 < 0.023 < 0.018 < 0.024 < 0.014 < 0.011 < 0.019 45 11/08/10 < 0.024 < 0.021 < 0.025 < 0.021 < 0.021 < 0.020 < 0.010 < 0.035 46 11/15/10 < 0,026 < 0.017 < 0.028 < 0.018 < 0.020 < 0.013 < 0.014 < 0.034 47 11/22/10 < 0.022 < 0.022 < 0.015 < 0.024 < 0.021 < 0.013 < 0.015 < 0.025 48 11/29/10 < 0.021 < 0.029 < 0.017 < 0.019 < 0.014 < 0.023 < 0.016 < 0.027 49 12/06/10 < 0.020 < 0.016 < 0.018 < 0.022 < 0.013 < 0.018 < 0.018 50 12/13/10 < 0.004 < 0.018 < 0.013 < 0.021 < 0.017 < 0.024 < 0.016 < 0.021 51 12/20/10 < 0.037 < 0.036 < 0.026 < 0.032 < 0.033 < 0.022 < 0.024 < 0.031 52 12/27/10 < 0.034 < 0.027 < 0.025 < 0.022 < 0.028 < 0.025 < 0.020 < 0.024

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma

95 Meteorological Tower

,*am ple Location MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER Date 4/26/2010 4/26/2010 4/26/2010 5/17/2010 5/17/2010 5/17/2010 Client ID IBV951710S1 IBV951710S2 IBV951710S3 IBV952010S1 IBV952010S2 lBV952010S3 Req. CL RAGWEED MULLEIN BURDOCK RAGWEED MULLEIN ALLROOT adionuclidc (pCi) _ I I I _II Be-7 774.9 +/- 71.0 1813.0 +/- 116.7 1316.0 +/- 118.7 831.2 +/- 69.6 649.6 +/- 66.3 562.9 +/- 72.6 1-131 50 < 9.01 < 10.25 < 13.11 < 10.44 < 9.02 < 10.45 Cs-134 50 < 6.17 < 8.07 < 14.48 < 6.32 < 6.71 < 7.29 Cs-137 50 < 8.22 < 10.51 < 12.49 < 7.20 < 8.87 < 8.35 Zr-95 < 10.44 < 14.52 < 18.17 < 12.78 < 14.27 < 15.45 Nb-95 < 7.68 < 10.69 < 12.66 < 8.62 < 7.64 < 10.89 Co-58 < 7.23 < 7.49 < 10.31 < 7.46 < 6.88 < 9.48 Mn-54 < 6.82 < 9.16 < 10.96 < 8.67 < 8.62 < 7.94 Zn-65 < 19.13 < 25.70 < 31.43 < 21.82 < 20.25 < 28.02 Fe-59 < 18.73 < 29.61 < 33.04 < 22.67 < 19.71 < 27.62 Co-60 < 7.02 < 10.67 < 10.67 < 9.90 < 7.56 < 9.81 BalLa-140 < 6.11 < 10.03 < 12.37 < 7.84 < 8.77 < 8.69 Ru-103 < 6.33 < 10.35 < 13.15 < 8.40 < 6.79 < 7.12 Ru-106 < 76.47 < 117.8 < 120.7 < 85.7 < 89.20 < 108.9 Ce-141 < 9.63 < .13.11 < 13.51 < 10.98 < 9.56 < 11.14 Ce-144 < 40.17 < 48.79 < 59.36 < 48.96 < 37.66 < 49.68 AcTh-228 < 23.75 < 27.19 < 45.00 < 30.50 < 32.31 < 36.49 Ra-226 < 151.8 < 180.0 < 212.7 285.6 +/- 111.2 291.5 +/- 103.1 411.9 +/- 122.6 K-40 4522.0 +/- 191.1 3846.0 +/- 226.2 4071.0 +/- 282.4 734.6.0 +/- 247.3 7108.0 +/- 262.2 7286.0 +/- 306.8

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- I Sigma

95 Meteorological Tower Sample MET TOWER MET TOWER MET TOWER Location Date 6/14/2010 6/14/2010 6/14/2010 Client ID IBV952410S1 1BV952410S2 IBV952410S3 Req. CL RAGWEED MULLEIN BURDOCK adionuclide (pCi) I Be-7 749.6 +/- 75.2 531.1 +/- 69.5 1642.0 +/- 112.0 1-131 50 < 9.27 < 9.07 < 10.75 Cs-134 50 < 12.71 < 5.81 < 11.39 Cs-137 50 < 8.42 < 7.09 < 11.12 Zr-95 < 15.10 < 12.15 < 21.32 Nb-95 < 8.55 < 8.29 < 11.56 Co-58 < 7.81 < 7.93 < 10.47 Mn-54 < 7.95 < 8.63 < 8.81 Zn-65 < 25.63 < 20.05 < 28.20 Fe-59 < 26.13 < 20.29 < 32.75 Co-60 < 8.69 < 8.59 < 12.94 Ba/La-140 < 6.58 < 8.51 < 15.22 Ru-103 < 6.70 < 6.78 < 11.57 Ru-106 < 87.83 < 90.44 < 111.9 Ce-141 < 10.40 < 10.34 < 14.39 Ce-144 < 37.62 < 47.73 < 64.94 AcTh-228 < 33.66 < 31.39 < 42.00 Ra-226 < 142.2 447.8 +/- 119.2 439.9 +/- 167.3_

K-40 7903.0 +/- 286.2 4656.0 +/- 206.9 8229.0 +/- 321.41

TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2010 Results in Units of pCi/kg I- 1 Sigma Sample COLD SPRING COLD SPRING LENTS COVE LENTS COVE Location VERPLANCK VERPLANCK Date 7/1/2010 9/13/2010 7/1/2010 9/13/2010 6/3/2010 7/1/2010 Client ID IAV842610 IAV843710 IAV282610 IAV283710 1AV172210 1AV172610 MYRO MYRO MYRO MYRO MYRO MYRO Req. CL Radionuclide (pCi)

Be-7 118.8 +/- 35.0 < 50.2 90.3 +/- 37.9 < 53.5 445.0 +/- 69.2 < 52.6 1-131 30 < 8.7 26.2 +/- 6.0 < 9.8 < 10.4 < 16.6 < 10.6 Cs-134 30 < 6.0 < 7.4 < 3.7 < 7.6 < 5.1 < 6.9 Cs-137 40 16.8 +/- 3.1 < 6.5 17.6 +/- 3.4 < 5.1 < 7.6 < 6.5 Zr-95 < 10.4 < 8.8 < 8.2 < 10.1 < 14.6 < 10.1 Nb-95 < 6:1 < 6.6 < 6.0 < 6.9 < 9.0 < 8.0 Co-58 < 5.7 < 6.8 < 5.0 < 6.4 < 10.3 < 6.4 Mn-54 < 4.6 < 5.8 < 5.4 < 6.5 < 9.8 < 5.1 Zn-65 < 11.2 < 16.9 < 13.0 < 9.5 < 30.9 < 19.4 Fe-59 < 14.4 < 16.1 < 14.4 < 13.7 < 35.7 < 19.4 Co-60 < 5.3 < 5.9 < 4.8 < 4.9 < 12.3 < 6.0 Ba/La-140 < 7.3 < 9.2 < 7.6 < 11.5 < 17.1 < 8.0 Ru-103 < 5.2 < 6.1 < 4.8 < 6.1 < 8.5 < 7.2 Ru-106 < 40.5 < 53.3 < 60.2 < 61.5 < 87.6 < 61.9 Ce-141 < 8.0 < 9.7 < 8.6 < 8.4 < 12.4 < 8.9 Ce-144 < 31.5 < 33.0 < 38.2 < 32.8 < 49.0 < 31.0 AcTh-228 131.6 +/- 19.0 109.8 +/- 19.9 250.5 +/- 22.0 180.0 +/- 22.2 134.7 +/- 29.4 109.4 +/- 21.1 Ra-226 273.3 +/- 67.0 239.7 +/- 87.1 575.9 +/- 96.6 315.6 +/- 84.4 363.8 +/- 146.3 245.6 +/- 89.0 K-40 14573.0 +/- 145.9 1728.0 +/- 126.1 3162.0 +/- 126.7 1555.0 +/- 108.3 4782.0 +/- 238.9 2551.0 +/- 148.2

TABLE B-20 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L + 3 sigma Monitoring Well MW-LAF MW-LAF Sample Name MW-LAF-002-013 MW-LAF-002-014 Sample Date 5/11/2010 11/22/2010 Radionuclide Req. MDC H-3 < 163 < 121 Cs-137 18 < 7.6 < 6.8 Co-60 < 7 < 6.2 Sr-90 1 < 0.78 < 0.54 Ni-63 < 25.4 < 20.5 Note 1: Less than values "<"are Minimum Detectable Concentration (MDC) values.

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

B-49

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 2000 to 2010 (pCi/Kg, dry)

&Cs- 134 C-3

><Year ,Indicator Control Indicator Control 2000 58 < Lc 179 231 2001 45 < Lc 230 427

< Lc < Lc 2002 221 238

< Lc < Lc 2003 124 73

< Lc < Lc 2004 104 138

< Lc < Lc 2005 156 36

< Lc < Lc 2006 120 < Lc

< Lc < Lc < Lc 2007 190

< Lc < Lc < Lc 2008 187

< Lc < Lc < Lc 2009 149 2010 < Lc < LC 154 63 52 < Lc 166 191 Critical Level (Lj)is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 750 . 2000 to 2010 M Indicator (Cs-134) 650 =Control (Cs-134)

M Indicator (Cs-137) 550

-Control (Cs-137) 450 350 C,

250 150 50-2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010

-50 Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry C-11

NL-12-009, Transmittal of 2011 Annual Radiological Environmental Operating Report

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NL-12-009, Transmittal of 2011 Annual Radiological Environmental Operating Report

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SUBJECT:

Dear Sir or Madam:

Enclosure:

SUMMARY

2.0 BACKGROUND

5.0 REFERENCES

SUMMARY

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5.1 REFERENCES

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