NL-13-027, Submittal of 2012 Annual Radiological Environmental Operating Report

Submittal of 2012 Annual Radiological Environmental Operating Report

ML13144A133
Person / Time
Site:	Indian Point
Issue date:	05/15/2013
From:	Robert Walpole Entergy Nuclear Northeast
To:	Document Control Desk, NRC/FSME
References
NL-13-027
Download: ML13144A133 (129)

Text

EnteraE Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Licensing Manager NL-13-027 May 15, 2012 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555-0001

SUBJECT:

2012 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, 2012 to December 31, 2012.

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. Reid Tagliamonte, Radiation Protection Manager at 914-254-5790.

Sincerely, RW/mb/jd cc: next page

NL-13-027 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-13-027 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, 2012

TABLE OF CONTENTS Page EXECUTIVE

SUMMARY

vii

1.0 INTRODUCTION

1-1 1.1 Overview 1-1 1.2 Radiation and Radioactivity 1-1 1.3 Sources of Radiation 1-2

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 3-1 3.3.3 Precipitation 3-2 3.3.4 Drinking Water 3-2 3.3.5 Ground Water 3-2 3.3.6 Soil 3-2 3.3.7 Broad Leaf Vegetation 3-2 3.3.8 Hudson River Water 3-2 3.3.9 Hudson River Bottom Sediment 3-3 3.3.10 Hudson River Shoreline Soil 3-3 3.3.11 Hudson River Aquatic Vegetation 3-3 3.3.12 Fish and Invertebrates 3-3 3.3.13 Land Use Census 3-3 3.4 Statistical Methodology 3-4 3.4.1 Lower Limit of Detection and MDC 3-4 3.4.2 Table Statistics 3-5

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 Precipitation 4-4 4.4 Drinking Water 4-4 4.5 Ground Water 4-5 4.6 Soil 4-5 4.7 Broad Leaf Vegetation 4-5 4.8 Hudson River Water 4-5 4.9 Hudson River Bottom Sediment 4-5 4.10 Hudson River Shoreline Soil 4-6 4.11 Hudson River Aquatic Vegetation 4-6 4.12 Fish and Invertebrates 4-6 4.13 Land Use Census 4-6 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 Teledyne Environmental Laboratory

• TLD Dosimeter Testing 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, 2002 to 2012 C-3 C-2 Radionuclides in Air - Gross Beta, 2002 to 2012 C-5 C-3 Broad Leaf Vegetation - Cs-1 37, 2002 to 2012 C-7 C-4 Radionuclides in Hudson River Water, 2002 to 2012 C-9 C-5 River Water - Discharge Area - Tritium, 2002 to 2012 C-11 C-6 Radionuclides in Shoreline Soil, 2002 to 2012 C-13 iii

LIST OF TABLES TABLE TITLE Page 1.3 Radiation Sources and Corresponding Doses 1-2 A-i-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 Sampling Summary, 2012 B-2 B-ia 2012 Air Sampling Deviations B-3 B-lb 2012 Other Media Deviations B-3 B-ic Analysis Deviations B-3 B-2 Radiological Environmental Monitoring Program Summary Indian Point Energy Center-2012 B-4 B-3 Direct Radiation, Quarterly Data - 2012 B-13 B-4 Direct Radiation, 2002 through 2012 Data B-15 B-5 Direct Radiation, Inner and Outer Rings-2012 B-17 B-6 Gross Beta Activity in Airborne Particulate Samples - 2012 B-18 B-7 lodine-131 in Airborne Charcoal Samples - 2012 B-20 B-8 Gamma Emitters in Airborne Particulate Samples - 2012 B-22 B-9 Radionuclides in Rain Water Samples - 2012 B-26 B-10 Radionuclides in Drinking Water Samples - 2012 B-27 B-11 Radionuclides in Ground Water Samples - 2012 B-31 B-12 Gamma Emitters in Soil Samples - 2012 B-32 B-1 3 Gamma Emitters in Broad Leaf Vegetation Samples - 2012 B-33 B-14 Radionuclides in River Water Samples - 2012 B-42 B-15 Gamma Emitters in Bottom Sediment Samples - 2012 B-46 B-16 Radionuclides in Shoreline Soil Samples - 2012 B-47 B-17 Gamma Emitters in Aquatic Vegetation Samples - 2012 B-49 B-18 Radionuclides in Fish / Invertebrates - 2012 B-50 B-19 Land Use Census,Residence & Milch Animal Results, 2012 B-54 B-20 Land Use Census - 2012 - Unrestricted Area Boundary and Nearest Residences B-55 iv

LIST OF TABLES (Continued)

TABLE TITLE Page C-1 Direct Radiation Annual Summary, 2002 - 2012 C-2 C-2 Radionuclides in Air, 2002 - 2012 C-4 C-3 Broad Leaf Vegetation - Cs-137, 2002 - 2012 C-6 C-4 Radionuclides in Hudson River Water, 2002 - 2012 C-8 C-5 River Water - Discharge Area - Tritium C-10 C-6 Radionuclides in Shoreline Soil, 2002 - 2012 C-12 D-1 Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 Interlaboratory Comparison Program D-5 V

EXECUTIVE

SUMMARY

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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, 2012. 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 2012, there were 1001 samples collected from the atmospheric, aquatic, and terrestrial environments.

In addition, 163 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs).

A small number of inadvertent issues were encountered in 2012 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 1513 analyses performed on the environmental media samples. The analysis of the 2012 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.

Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the remaining analyses for 2012. 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. 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 2012, 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.

CONCLUSIONS The 2012 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 2012 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

1.0 INTRODUCTION

1.1 Overview The Radiological Environmental Monitoring Program (REMP) for 2012 performed by Entergy for the Indian Point Energy Center (IPEC) is discussed in this report. Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be established to monitor radiation and radioactivity in the environment (Reference 1). This report, published annually per Indian Point unit specific Technical Specifications (section 5.6.2 for Unit 1/2 and Section 5.6.2 for Unit 3), summarizes the results of measurements of radiation and radioactivity in the environment in the vicinity of the IPEC and at distant locations during the period January 1 to December 31, 2012.

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 and liquid material that might be released from the plant, cosmic radiation, and the naturally occurring radioactive materials in the ground.

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.

The ground water table is listed after the rain water and drinking water tables for ease of data comparison. However, ground water is not a dose pathway since it is not a drinking water pathway at IPEC.

These results are reviewed by IPEC's staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others for over 30 years.

In order to more fully understand how a nuclear power plant impacts humans and the environment, background information on radiation and radioactivity, natural and man-made sources of radiation, reactor operations, radioactive effluent controls, and radiological impact on humans is provided.

It is believed that this information is helpful in understanding the potential radiological impact on the environment and humans from the operation of IPEC.

1.2 Radiation and Radioactivity All matter is made of atoms. An atom is the smallest component into which matter can be broken down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particles that is given off from atoms in an excited state (e.g., unstable, radioactive atoms).

1-1

Radioactive materials exist naturally and have always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium.

Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are cesium-137 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium-90, and cobalt-60.

Radiation is measured in units of mrem, much like temperature is measured in degrees. A mrem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 600 mrem (References 2, 3, 4, and 5). The per capita dose has increased substantially since the mid 1980's because of the increased usage of medical procedures involving exposure to radiation (see Reference 3).

Radioactivity is measured in Curies.

Levels of radioactivity commonly seen in the environment are typically a small fraction of a Curie, therefore radioactivity in the environment is typically measured in picocuries.

One picocurie (pCi) is equal to 0.037 disintegrations per second (2.22 disintegrations per minute).

1.3 Sources of Radiation As mentioned previously, naturally occurring radioactivity has always been a part of our environment. Table 1.3 shows the sources and doses of radiation from natural and man-made sources.

Table 1.3 Radiation Sources and Corresponding Doses (1)

NATURAL MAN-MADE Radiation Dose Radiation Dose Source (millirem/year)

Source (millirem/year)

Internal, inhalation(2) 228 Medical(3) 300 External, space 33 Consumer(4) 13 Internal, ingestion 29 Industrial, security, (5) 0.3 External, terrestrial 21 Occupational 0.5 Weapons Fallout

< 1 Nuclear Power Plants

< 1 Approximate Total 311 Approximate Total 314 (1) information from References 3 and 4 (2) from radon and thoron (3) includes CT (147 millirem), nuclear medicine (77 mrem), interventional fluoroscopy (43 mrem) and conventional radiography and fluoroscopy (33 mrem)

(4) primarily from cigarette smoking (4.6 mrem), commercial air travel (3.4 mrem), building materials (3.5 mrem) and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational and research 1-2

Cosmic radiation (external, space) from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 30 mrem/year),

the ground we walk on (about 20 mrem/year) and the air we breathe (about 230 mrem/year).

The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, New Jersey and even Connecticut have a higher annual dose as a result of higher levels of radon/thoron gases in these areas. In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 310 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals.

The annual dose to an individual in the U.S. from medical and dental exposure is approximately 300 mrem.

Consumer products/uses, such cigarettes, building materials and commercial air travel contribute about 10 mrem/year. Much smaller doses result from weapons fallout (less than 1 mrem/year) and nuclear power plants (less than 1 mrem/year). Typically, the average person in the United States receives approximately 310 mrem per year from man-made sources.

1-3

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 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 atmospheric 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 Program 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.

2-1

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 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 2012 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 2012 REMP sample results confirms that radiological effluents were well below regulatory limits.

2-2

SECTION 3 PROGRAM DESCRIPTION

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

3.1 Sample Collection Entergy 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 2012 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.

Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the remaining analyses.

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. Additional TLD locations include a control location at Roseton (20.7 miles north) and eight locations of special interest.

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

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 filters and cartridges are changed on a weekly basis. The filters are analyzed for gross beta and the cartridge samples for radioiodine. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters.

3-1

3.3.3 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 gamma spectroscopy and for tritium.

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.

Monthly samples are composited quarterly and analyzed for tritium.

3.3.5 Groundwater Water Groundwater samples were obtained semi-annually at Lafarge (106.) Samples are analyzed for tritium, strontium-90, and nickel-63 and by gamma spectroscopy.

3.3.6 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.

3.3.7 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.

3.3.8 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 gamma spectroscopy analysis and quarterly for tritium analysis.

3-2

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 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-i, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90.

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

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

3.3.12 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 (Ib2). 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 strontium-90 and for nickel-63.

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.

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 New York State records or with 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.

3-3

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, since 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.

3.4 Statistical Methodoloqy There are several statistical calculation methodologies used in evaluating the data from the Indian Point REMP.

These methods include determination of Lower Limits of Detection (LLD) and the Minimum Detectable Concentration (MDC), and estimation of the mean and associated propagated error.

3.4.1 LOWER LIMIT OF DETECTION (LLD)

The LLD is the smallest concentration of radioactive material in a sample that will yield a net count above system background, and be detected with 95% probability, with a 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 + 3.29sb LLD= T, E*V*k*Y* e-Al where:

LLD =

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

Ts =

The sample counting time in minutes Sb =

The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

Tb =

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, 2.22E+6 dpm per uCi)

Y =

The fractional radiochemical yield (when applicable)

A =

The radioactive decay constant for the particular radionuclide t=

The elapsed time between midpoint of sample collection and time of counting 3-4

Note: The above LLD formula accounts for differing background and sample count times.

The Radiological Environmental Monitoring Program, REMP, may use an LLD formula that assumes equal background and sample count times, when appropriate.

The constants 2.71 and 3.29 and the general LLD equation were derived from References 6 and 7.

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 radionuclides 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 by a separate background count or in the case of gamma ray spectroscopy, from adjacent channels of the energy band of the gamma ray peak used for the quantitative analysis for that radionuclide.

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

To document the post priori (after the fact) measurement statistics, the MDC is calculated after the measurement using the same equation as above.

To handle the a posteriori problem, a decision level must be defined.

To minimize the number of false positives, a value is not considered positive unless it is greater than the MDC or 3 times the total standard deviation of the post priori measurement, where MDC is the post priori (after the fact) measurement statistic calculated similar to the LLD equation listed above (for Tb = Ts, the term 3.29 Ob" -/(1+(

Tb / T, )) = 4.66 Ob).

3.4.2 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 8). 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.

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 2002 through 2011. The 2012 average values are included in these historic tables for purposes of comparison.

3-5

SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2012 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 Precipitation Drinking Water Groundwater Soil Broad Leaf Vegetation Hudson River Water Bottom Sediment Shoreline Soil Aquatic Vegetation Fish and Invertebrates 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 2012 and assessed the significance of the findings.

A summary of the results of the 2012 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 indicator and control locations, and unrelated to piant operations, their presence is noted only in the data tables and will not be discussed further.

4-1

The second group of radionuclides detected in 2012 consists of those resulting from past weapons testing in the earth's atmosphere. The more recent contamination events resulting from the Chernobyl and Fukushima accidents only indicated detectable activity shortly after their occurrences (Reference 9). However, weapons testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, still contributes to the concentrations in the 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 2012, the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-137 in several media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years.

The final group of radionuclides detected by the 2012 REMP comprises those that may be attributable to current plant operations. During 2012, Cs-137 and tritium (H-3) were the only potentially plant-related radionuclides detected in any 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.

Natural occurrence is very low, on the order of approximately 5 pCi/liter (well below typical detectable levels). The major source of H-3 is typically from above ground nuclear weapons testing (in the range of 50 to 150 pCi/liter). Other sources include weapons production and industrial uses where levels are highly dependent on the release rates and distance from the source term.

One such industrial source is nuclear power plant operation.

Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2012, there were two detections of Cs-137 in shoreline soil (2 indicator samples). In bottom sediment there were five positive detections of Cs-137 (all at indicator stations or near the 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 be due to atmospheric weapons testing, with some contribution from plant releases from the past several years.

None of the fish samples indicated any detectable levels of these isotopes.

Strontium-90 (Sr-90) may also be present in the environment from atmospheric testing debris.

None of the fish samples, or any other media where Sr-90 was tested, 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 2012 in aquatic or terrestrial vegetation indicator and control locations.

4-2

Co-58 and Co-60 are activation/corrosion products also related to plant operations. They are produced by neutron activation in the reactor core. Co-58 has a much shorter half-life than Co-60. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is more likely the result of 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 2012 REMP, although they were observed in historical data.

In the following sections, a summary of the results of the 2012 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 2012, 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 2002 through 2011. The 2012 means are also presented in Table B-4. Table B-5 presents the 2012 TLD data for the inner ring and outer ring of TLDs.

The 2012 mean value for the indicator direct radiation sample points was 13.3 mR per standard quarter - which represents a small decrease from 2011. At those locations where the 2012 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.

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 13.2 mR per standard quarter and also average for the outer ring was 13.6 mR per standard quarter. The control location average for 2012 was 12.3 mR per standard quarter.

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDs. The 2012 averages are consistent with the historical data. The 2012 and previous years' data show that there is no measurable direct radiation in the environment due to the operation of the Indian Point site.

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4.2 Airborne Particulates and Radioiodine An annual summary of the results of the 2012 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 weekly charcoal cartridge analytical results are presented 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. All the charcoal cartridge results were less than MDC, consistent with historical trends when there were no episodes of fresh fallout from Weapons Testing or accidents The results of the GSA of the quarterly composites of these samples are in Table B-8.

These 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 2012 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.

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2012.

4.3 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table B-9 contains the results of the precipitation samples for 2012.

Only naturally occurring radionuclides were detected in the precipitation samples.

A review of historical data over the last 10 years indicates tritium had been detected in one indicator precipitation sample in 2010 and both indicator and control locations in 2010; however, there have been no instances of positive values in 2012.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2012 drinking water sample analysis results. Results of the tritium and gamma spectroscopy analyses of the monthly drinking water samples are in Table B-10. Other than naturally occurring radionuclides, no radioactivity was detected in drinking water samples. This has historically been the case for the radionuclide results for this media; operation of the Indian Point units had no detectable radiological impact on drinking water.

4-4

4.5 Ground Water A summary of the groundwater samples for 2012 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-1 1. No plant related nuclides were noted in these samples.

4.6 Soil A summary of the soil sample analysis results is presented in Table B-2.

Table B-12 contains the results of the soil samples for 2012.

Other than naturally occurring radionuclides, no activity was detected in any of the soil samples.

4.7 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2012 samples are presented in Table B-13.

Table C-3 contains an historical summary and Figure C-3 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.

Although Cs-1 37 was detected in one of the indicator samples in 2012, it is most likely the result of previous atmospheric weapons testing.

4.8 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 quarterly composites of H-3 are presented in Tables B-14.

The only plant related activity detected was H-3. The levels are consistent with occasional historical detection of H-3. Table C-4 and Figure C-4 show the recent historical trend of the H-3 levels. Table C-5 and Figure C-5 show a comparison to the amount measured in effluents. Because the REMP Discharge Area River Water sample is located in the mixing zone (per References 8 and 10), the REMP data is less than the calculated levels from the effluent data due to the effect of dilution in the nearby mixing zone.

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

Table B-15 contains the results of the analysis of bottom sediment samples for 2012. Cs-137 was detected at 5 of 6 indicator station samples. The control station (Cold Spring) samples did not indicate any Cs-137. This detection of positive levels 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 397 pCi/kg and 234 pCi/kg on samples taken 3 months apart (average = 251 pCi/kg.). The results are somewhat less than to the 2009, 2010, and 2011 results. The average of all indicator detections is 284 pCi/kg (321 pCi/kg in 2011, 553 pCi/kg in 2010 and 493 pCi/kg in 2009). This is consistent with historical annual average concentration for indicator locations.

4-5

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 approximately 300 pCi/kg. Cs-134 has not been detected in bottom sediment since 2002.

4.10 Hudson River Shoreline Soil A summary of the radionuclide concentrations detected in the shoreline soil samples is contained in Table B-2. Table B-16 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 2012. Cs-137 was detected at the Verplanck location in both samples from that location, for a total of two positive values out of eight samples from indicator locations. Cs-137 was not detected at the control location (Manitou Inlet).

The average concentration for the indicator locations that had positive indication of Cs-137 was 141 pCi/kg (dry) with a maximum concentration of 167 pCi/kg (dry).

An historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table C-6 and Figure C-6. 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.

4.11 Aquatic Vegetation A summary of the aquatic sample analysis results is presented in Table B-2. Table B-17 contains the results of the analysis of aquatic vegetation samples for 2012. No plant related radionuclides were detected.

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

Table B-18 contains the results of the analysis of fish and invertebrate samples for 2012.

Similar to the past 10 years, no radionuclides other than naturally occurring ones were found in 2012. There were no plant related radionuclides detected.

4.13 Land Use Census A census was performed in the vicinity of Indian Point in 2012. 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 2012 census were generally same as the 2011 census results. The New York Agricultural Statistic Service showed there were no animals producing milk for human 4-6

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 2012 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 2012 REMP reveal that operations at the station did not result in an impact on the environment.

The 2012 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 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.

U.S.

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

6. Currie, L.A.,

"Limits for Qualitative Detection of Quantitative Determination",

Analytical Chemistry, 40:586-593, 1968.

7. Mayer, Dauer, "Application of Systematic Error Bounds to Detection Limits for Practical Counting"., Health Physics Journal, 65(1): 89-91, 1993.

8. U.S. Nuclear Regulatory Commission, Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

9. Wetherbee, Gregory A., et.al., Wet Deposition of Fission-Product Isotopes to North America from the Fukushima Dai-ichi Incident, March 2012, Environmental Science and Technology.

10. U.S. Nuclear Regulatory Commission, NUREG-1301, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors," April 1991.

5-1

5.2 BIBLIOGRAPHY

1. U.S. 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.

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

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

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

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

6. U.S.

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

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

8. U.S.

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

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

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

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

12.Glasstone, S., and W.

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

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

14.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.

15.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.

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

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

18.U.S. Nuclear Regulatory Commission, Branch Technical Position to Regulatory Guide 4.8, An Acceptable Radiological Environmental Monitoring

Program, November 1979.

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

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

1. 698, Philadelphia, PA, 1978.

5-2

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

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

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

1969.

24. 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.

25. National Council on Radiation Protection.

NCRP Report No. 62, Tritium in the Environment, March 1979.

26. 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.

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

28. 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.

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

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

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

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

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

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

35. ENN-LI-1 02, Corrective Action Process 36.Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC" 37.National Council on Radiation Protection and Measurements, Report No. 169, "Design of Effective Radiological Effluent Monitoring and Environmental Surveillance Programs", December 2010.

5-3

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

APPENDIX A Environmental media are sampled at the locations specified in Table A-1 and shown in Figures A-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 2012 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-19 and B-20 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING ASAMPLE STATION DE:,:1 ON iLOCATION DISTANCE SAMPLE TYPES 3

DR8 Service Center Building Onsite -

Direct Gamma 0.35 Mi (SSE) at 1580'iet am Al Algonquin Gas Line Onsite - 0.28 Mi (SW) at Air Particulate Al 2340 Radioiodine A4 Air Particulate 5A4 NYU Tower Onsite - 0.88 Mi (SSW)

Radioiodine at 2080 DR10 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

~~~Onsite -

H ae 9

Wal Plant Inlet (Hudson River Intake)*

0.16 Mi (W) at 273Water Wa2 Onsi -WHR Water 10 Discharge Canal (Mixing Zone)

Onsite -

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 20 DR38 Cortlandt Yacht Club (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 DR4 Drc am 28 Lent's Cove 0.45 Mi (ENE) at 0690 Direct Gamma HR Bottom Sediment HR Aquatic Vegetation Air Particulate 29 Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine DR39 Direct Gamma

• = Control location 0* = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS i.....

........ L0 A. Tri N P.....

33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 0530 Direct Gamma 34 DR9 South East Corner of Site DinsitGamm 0.52 Mi (5) at 1790°iet am 35 DR5 Broadway & Bleakley Avenue Dinsiteamm 0.37 Mi (E) at 0920°iet am 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 1410 Direct Gamma Precipitation 44 Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate Radioiodine 50 Wc2 Manitou lnlet*

4.48 Mi (NNW) at 3470 HR Shoreline Soil WclHRSoeieSi 53 White Beach 0.92 Mi (SW) at 2260°RSoeieSi DR11_________

Direct Gamma 56 DR37 Verplanck - Broadway & 6th Street 1.25 Mi (SSW) at 2020 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 50 i(N)a 20Drc am Road 50 i(N)a 2°Drc am 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 0520 Direct Gamma Westbrook Drive 62__DR19___(near the Community Center) 5.03 Mi (NE) at 0620 iet am Lincoln Road - Cortlandt 46M EE t07 64 DR20

!(School Parking Lot) 4.6__Mi_(ENE)_at_067° Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 114° Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (5) at 1880 Direct Gamma 72 DR26 IRailroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR31 Palisades Parkway 4.65 Mi (NW) at 225° 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 0* = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAM P.,

,1111N

,T DIS'SIGE*,

,,E""

79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 296' Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 317' Direct Gamma 81 DR28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 3100 Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 3340 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 339' Direct Gamma 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 118' Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 2.89 Mi (NNE) at 0250 Direct Gamma 89________

DR35___________ (near rock cut) 2.89_Mi_(NNE)_at_025_

DirectGamma 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate A2 IPEC Onsite- 0.39 Mi (S) at Radioiodine 1c2 1930 Broad Leaf Vegetation Soil A3 Air Particulate A3 Onsite -

Radioiodine Icl 0.46 Mi (SSW) at 2080 Broad Leaf Vegetation

• I MSoil 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 F

,~

I Pee FAk w

(4 MEA2 Ibl K

Ib#

River e

j4 #

!4<

A-5

FIGURE A-2 SAMPLING LOCATIONS Greater than Two Miles from Indian Point

/

lami

,Roklanhl countyr Mb~ heg Hr T i~

F-a F XvrK i

'(0-n Peekskfll Corilandt Manor

• Ijidian Point f

MoItrose I....

I WAmaw We~tchester Story P1 Crup~r~

Cro!or~Oii t+jd~or

/

VVr4 Uw ftet výy I

= y County

• ,: 5 miles 0.'nng L~~J Soil Npi ft, A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations Af A

I "84:

I Cold Sprnig,10.9 miles north I I

Pu tnam,,*

Co unt 4

M ot'~e~an L aRe Ilk-y Y~k I rw Rocklandv "County Hi~r !man State Park*

Yorktown 106: GW 7o 7

• Fo se 14:

• 5 mille 85:

I S7ory Th1i

/P Precipitation Crolo'n On7, qý Hi I rr L

Westchester

County, h"'t v t*fA~

W

,,It vý I 27:13A]

Soi p

N G

Monitoring Well, W SW of SiteBoundarv yr Aquatic Vegetation

.qmlpIuBson ivir

dhapp, Bottoma Sidiment I;I t A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES AIRBORNE FISH FOOD SOIL or RADIONUCLIDE WATER PARTIUCLATE OR (pCi/kg, MILK PRODUCTS SEDIMENT GASES (pCi/m3) wet)

(pCi/L)

(pCi/kg, wet)

(pCi/kg, dry)

Gross Beta 4

0.01 H-3 2,000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Ni-63 (f) 30 100 Zn-65 30 260 Sr-90 (f) 1 5

5000 Zr-95 30 Nb-95 15 1-131 1 (d) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 A-8

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES Table Notation (a)

This list does not mean that only these nuclides 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 the ODCM.

(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 priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (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 the ODCM.

(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.

A-9

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNEFOOD RADIONUCLIDE WATER AIRBORNE FISH MILK PROD PARTIUCLATE 9R PRODUCTS ANALYSIS (pCi/L)

GASES (pCim)

(pC/kg, wet)

(pCi/L)

H-3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Ni-63 ***

300 1,000 Zn-65 300 20,000 Sr-90 ***

8*

40 Zr-95 400 Nb-95 400 1-131 2

• 0.9 3

100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCi/L (This is a 40 CFR 141 value)

Sr-90 12 pCi/L 1-131 20 pCi/L These reporting levels 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.

Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment.

A-10

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2012 Annual Radiological Environmental Monitoring Pro-gram Summary The results of the 2012 radiological environmental sampling program are presented in Tables B-2 through B-18. Table B-2 is a summary table of the sample results for 2012.

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 17). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-18.

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 H-3, Ni-63, Sr-90 and 1-131 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-19 and B-20, 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-13).

B.3 Sampling Deviations During 2012, environmental sampling was performed for 12 unique media types addressed in the ODCM and for direct radiation.

A total of 1164 samples of 1167 scheduled were obtained.

Of the scheduled samples, 99.7% 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-ia for the air samples and Table B-lb for other media.

B.4 Analytical Deviations There was one blue crab sample where there was insufficient sample for Sr-90 analysis. Several LLDs were not met due to the short half lives of the nuclides.

Table B-ic provides more details for the analytical deviations.

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

B-1

Summary of Sampling Deviations - 2012 TOB NFU M O

'SAMPLING.;",.

NUMBER 0.I,,RFASC MED.IA-

-IM LEs DEVIATIONS*

.EFFICIENCY

-ANALYSES**j :DEMII AMPLES.__

MEDIA TLD 164 1

99%

326 See Tat PARTICULATES IN AIR 416 0

100%

448 N,

CHARCOAL FILTER 416 0

100%

416 N,

PRECIPITATION 8

0 100%

16 N,

DRINKING WATER 24 0

100%

56 N,

GROUNDWATER 2

0 100%

8 N,

SAMPLES SOIL 3

0 100%

3 N,

BROAD LEAF VEGEAT 63 0

100%

108 N,

VEGETATION HUDSON RIVER WATER 24 0

100%

32 N,

SHORELINE SOIL 10 0

100%

20 N,

HUDSON RIVER BOTTOM 8

0 100%

8 N,

SEDIMENT AQUATIC VEGETATION 6

2 67%

4 See Tat FISH & INVERTEBRATES 23 0

100%

68 N,

TOTALS 1167 3

99.7%

1513 TOTAL NUMBER OF SAMPLES COLLECTED =

1164

• Samples not collected or unable to be analyzed.

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

I'UWt.

dil dili dI:LUIdLtW IIIWttl i dIlU UIt, uIIl.uUdl udllLIIUy"5 Vvtj1 dliddlyL/U TABLE B-lb 2012 Other Media Deviations LOCATION Week PROBLEM4I ACTIONS; TO&PREVENTRiEcU!R;REN Palasades Pky, Lake 15 TLD missing.

Welch exit Hudson River Intake 23 Failure of the water sampler peristaltic pump caused o 03790 Lents Cove 23 The attempt to collection aquatic vegetation in the spri was no vegetation to be found.

Water container full; automatic sampler collecting 2 sa normal). Trouble shooting revealed loose connections.

Hudson River Intake and 33 Water samples collected on 8/14 instead of 8/13 due t.

Discharge issues.

Automatic water sampler sensor not detecting water; a Hudson River Intake 37 samples per hour (twice normal). Next day follow-up r re-program sampler and replace sampler.

Lents Cove 38 Aquatic vegetation not available at this location.

Rain water sampler moved inside in preparation for HL 09:30 to 11/1 10:00).

Hudson River Intake 44 Sample station flooded by Hurricane Sandy, Grab sarr Note: The only samples not obtained were the Week 15 missing TLD and the Week 23 and 38 aqua TABLE B-Ic 2012 Analysis Deviations LOCATION Media' PROBLEM:I ACTIONS TO PREVENT REcURREN Croton Reservoir Drinking 1-131 result (<15.12) and La-140 result (<15.89) did nc Water pCi/liter) for 9/17/12 sample Roseton Rain 1-131 result (<15.57) did not meet required LLD (15 pC Water River 1-131 result (<20.22) and La-140 result (<18.64) did nc Water pCi/liter) for 11/26/12 sample River Hudson River Discharge Water 1-131 (<15.63) did not meet required LLD (15 pCi/liter)

Blue Downstream Crab Insufficient quantity to perform Sr-90 analysis The formulas for calculating the activity, uncertainty and MDC are contained in the software For the gamma system, when the new detector number 08 was added to the system in Janu 3.29 was used to calculated the MDCs on detector 08. The activity and uncertainty were nol been changed from 3.29 to the required 4.66. When the MDCs were recalculated using 4.6(

by 41.6%. This error has been corrected.

B-3

TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*

Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **

Location Distance Mean Mean Reported (Units)

(Range)

Number Direction (Range)

(Range)

Measurements Direct Radiation (mR/Standard Quarter)

TId-Quarterly 163 NA 13.3 (159/159)

(9.0- 19.9) 416 0.01 0.014 (364/364)

(0.003 - 0.025)

DR-28 95 4.96 Mi.

WSW 0.46 Mi.

SSW 19.3 (3/3) 12.3 (4/4)

(18.5-19.9)

(11.0 - 13.5) 0.014 (52/52) 0.014 (52/52)

(0.004 - 0.025)

(0.005 - 0.023) 0 0

Air Particulate (pCi/m')

Air Iodine (pCi/-* )

Air Particulate

( 10"t pCi/rn)

Gr-B GAMMA 1-131 GAMMA Be-7 416 0.07

<MDC***

<MDC 0

32 NA 63.9 (28/28)

(42.6 - 84.2) 23 20.7 Mi.

N 72.8 (4/4) 72.8 (4/4)

(58.5-111)

(58.5-111) 0 0

Cs-134 Cs-137 Th-228 0.05 0.06

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC Rainwater (pCi/liter)

H-3 GAMMA Co-60 NA 2.9 (2/28)

(2.0 - 3.8) 8 3000

<MDC 8

15

<MDC 15

<MDC 18

<MDC 0.88 Mi.

SSW 3.8 (1/4) 0 0

Cs-134 Cs-137

<MDC

<MDC

<MDC 0

B-4

TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*

Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **

Location Distance Mean Mean Reported (Units)

(Range)

Number Direction (Range)

(Range)

Measurements Drinking Water H-3 8

2000

<MDC NA 0

(pCi/liter)

Gr-B 24 4

3.23 (15/24) 08 6.3 Mi.

3.45 (8/12)

NA 0

(2.27 - 4.31)

SE (2.45 - 4.31)

GAMMA 24 Mn-54 15

<MDC NA 0

Co-58 15

<MDC NA 0

Fe-59 30

<MDC NA 0

Co-60 15

<MDC NA 0

Zn-65 30

<MDC NA Nb-95 15

<MDC NA 0

Zr-95 15

<MDC NA 0

1-131 15

<MDC NA 0

Cs-134 15

<MDC N A 0

B-5

TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*

Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units)

(Range)

Number Direction (Range)

(Range)

Measurements Drinking Water (coni'd)

Cs-137 18

<MDC NA 0

(pCi/liter)

Ba-140 15

<MDC NA 0

La-140 15

<MDC NA 0

Ground Water H-3 2000

<MDC NA 0

(pCi/liter)

Ni-63 30

<MDC NA 0

Sr-90 I

<MDC NA 0

GAMMA Mn-54 15

<MDC NA 0

Co-58 15

<MDC NA 0

Fe-59 30

<M DC NA 0

Co-60 15

<MDC NA 0

Zn-65 30

<MDC NA 0

Nb-95 15

<MDC NA 0

B-6

TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*

Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **

Location Distance Mean Mean Reported (Units)

(Range)

Number Direction (Range)

(Range)

Measurements Ground Water (cont'd)

(pCi/liter)

Zr-95 Cs-1 34 Cs-137 Ba-140 La-140 GAMMA Be-7 15 15 18 60 15 A

<MDC

<MDC

<MDC

<MDC

<MDC NA NA NA NA NA 0

0 0

0 0

Soil (pCi/kg dry) 3 NA

<MDC 23 23 20.7 Mi.

N 20.7 Mi.

N 900(1/I) 17400 (I/I)

K-40 Co-60 Cs-134 Cs-137 Ra-226 Th-228 NA 13620(2/2)

(13500- 13740) 900(1/I) 17400(1/I)

<MDC NA 150

<MDC

<MDC

<MDC 0

0 0

0 0

0 0

ISO 100(1/2)

NA

<MDC 95 23 23 0.46 Mi.

SSW 20.7 Mi.

N 20.7 Mi.

N 100(1/I) 1421(1/1/)

983 (1/1)

<MDC 1420(1/1) 983 (I/I)

NA 499 (2/2)

(396 - 602)

B-7

Medium or Pathway Sampled (Units)

Broadleaf Vcgetation (pCi/kg wet)

Broadleaf Vegetation (cont'd)

(pCi/kg wet)

River Water (pCi/liter)

Analysis Type 1-131 GAMMA BE-7 K-40 Co-60 1-131 Cs-134 Cs-137 Th-228 H-3 GAMMA Mn-54 Co-58 TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Indicator Total LLD*

Locations Location with Highest Mean Number Mean **

Location Distance (Range)

Number Direction (F

45 60

<MDC 63 NA 1462 (41/42) 94 0.39 Mi.

161 (198-4691)

S (19:

NA 5618 (42/42) 95 0.46 Mi.

589 (1271 - 10520)

SSW (3394 NA

<MDC 60

<MDC 60

<MDC 80 44.4 (1/42) 94 0.39 Mi.

44.

S NA

<MDC 23 20.7 Mi.

35.

N 8

3000 539(2/4) 10 0.3 Mi.

53 (460-617)

WSW (46 24 15

<MDC 15

<MDC Mean ange) 3 (21/21) 8 -4691) 6(21/21) 0- 10520)

Control Locations Mean (Range)

<MDC 1332 (21/21)

(278 - 3939) 5156(21/21)

(1169-7807)

<MDC

<MDC

<MDC

<MDC 35.8(I/21)

<MDC Non-Routine Reported Measurements Non-Routine Reported Measurements 0

0I 0

0 0

0 0

0 0

0 0

4 (1/21) 8 (1/21) 9 (2/4) 0-617)

<MDC

<MDC B-8

Medium or Pathway Sampled (Units)

River Water (cont'd)

(pCi/liter)

Bottom Sediment (pCi/kg dry)

Analysis Type Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 GAMMA K-40 TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Indicator Total LLD*

Locations Location with Highest Mean Number Mean Location Distance (Range)

Number Direction (F

30

<MDC 15

<MDC 30

<MDC 15

<MDC 15

<MDC 15

<MDC 15

<MDC 18

<MDC 15

<MDC 15

<MDC Mean lanqe) v Control Locations Mean (Range)

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC Non-Routine Reported Measurements Non-Routine Reported Measurements 0

0 0

0 0

0 0

0 0

0 0

S NA 18443 (6/6)

(14850 - 21240)

B-9 84 10.88 Mi.

32010 (2/2) 32010 (2/2)

N (30690 - 33330)

(30690 - 33330)

TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*

Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **

Location Distance Mean Mean Reported (Units)

(Range)

Number Direction (Range)

(Range)

Measurements Bottom Sediment (cont'd)

(pCi/kg dry)

Co-60 Cs-134 Cs-137 Ra-226 Th -2_2 8 NA 150

<MDC

<MDC

<MDC

<MDC

<MDC 180 284(5/6)

(234-397)

NA 2109(2/6)

(2100 - 2117)

NA 928(6/6)

(282-1213) 10 17 17 0.3 Mi.

WSW 1.5 Mi.

SSW 1.5 Mi.

SSW 315 (2/2)

(234-397) 2117 (1/2) 0 0

0 0

0 0

1888(1/2) 1162 (2/2) 655 (2/2)

(1111 -1213)

(593-716)

Shoreline Soil (pCi/kg dry)

Sr-90 10 5000

<MDC

<MDC GAMMA K-40 Cs-134 10 NA 12167 (8/8)

(2785-19790) 84 10.88 Mi.

N 32300 (2/2)

(31530- 33070) 32300 (2/2)

(31530- 33070) 150

<MDC Cs-137 Ra-2 26 Th-22 8 180 141(2/8)

(115-167)

NA 3605 (4/8)

(1172-7724)

NA 529 (8/8)

(102 - 1230) 17 50 28 1.5 Mi.

SSW 4.48 Mi.

NNW 0.45 Mi.

ENE 141 (2/2)

(115-167) 4970(2/2)

(2216-7724)

<MDC

<MDC

<MDC 0

0 0

0 0

777 (2/2) 549 (2/2)

(324-1230)

(478-620)

B-10

Medium or Pathway Analysis Sampled Type (Units)

Aquatic Vegetation GAMMA (pCi/g wet)

Be-7 K-40 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Indicator Total LLD*

Locations Location with Highest Mean Number Mean **

Location Distance (Range)

Number Direction (F

4 NA 360 (2/2) 17 1.5 Mi.

36 (338 -383)

SSW (33 NA 2385 (2/2) 17 1.5 Mi.

23 (2069 - 2701)

SSW (206 NA

<MDC NA

<MDC NA

<MDC NA

<MDC NA

<MDC 84 10.88 Mi.

35 N

NA 102 (2/2) 17 1.5 Mi.

N (95 - 108)

SSW (9.

23 100

<MDC 21 5

<MDC Mean Range) 60 (2/2) 8 - 383) 85 (2/2) 9 - 2701)

Control Locations Mean (Range) 206(1/2) 1798 (2/2)

(1332 - 2264)

<MDC

<MDC

<MDC

<MDC 355 ((/2) 53.8 (1/2)

Non-Routine Reported Measurements 0

5 (/2)

)2 (2/2) 5-108)

Fish (pCi/kg wet)

Ni-63 Sr-90

<MDC

<MDC B-11

TABLE B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2012 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD*

Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean **

Location Distance Mean Mean Reported (Units)

(Range)

Number Direction (Range)

(Range)

Measurements Fish (cont'd)

(pCi/kg wet)

GAMMA K-40 23 NA 3320(11/11)

(2541 -4593) 25 Downstream 3320(11/11) 3183(12/12)

(2541 -4593)

(2285-4239)

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Th-228 130 130

<MDC

<MDC 260

<MDC 130 260 130

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC 0

0 0

0 0

0 0

0 0

150

<MDC NA

<MDC 23 20.7 Mi.

N 177(2/12) 177(2/12)

(168-186)

(168-186)

• LLD is the Lower Limit of Detection

• • The Mean Values are calculated only using the positive values: the fraction of positive values are listed in paraentheses

• • • MDC is the Minimum Detectable Concentration. Except as indicated in Table B-Ic, all MDCs are less than the required LLD.

B-12

INDIAN POINT ENERGY CENTER TABLE B-3 DIRECT RADIATION, QUARTERLY DATA - 2012 mR/Quarter +/- 1 sigma Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Annual Annual Nuclide Number 01/01-03/31 04/01-06/30 07/01-09/30 10/01-01/01 Average Total TLD DR-01 12.1 +/- 0.6 15.3 +/- 0.8 14.8 +/- 0.7 13.5 +/- 0.6 13.9 55.6 DR-02 12.6 +/- 0.7 15.2 +/- 0.9 14.0 +/- 0.5 14.2 +/- 0.7 14.0 55.9 DR-03 9.7 +/- 0.7 11.6 +/- 0.9 11.5 +/- 0.5 11.4 +/- 0.6 11.1 44.2 DR-04 11.7 +/- 0.6 13.7 +/- 0.7 13.6 +/- 0.5 13.1 +/- 0.6 13.0 52.2 DR-05 11.8 +/- 0.7 14.4 +/- 1.0 13.7 +/- 0.9 13.7 +/- 0.6 13.4 53.6 DR-06 12.4 +/- 0.8 14.5 +/- 0.8 13.9 +/- 0.6 13.9 +/- 0.7 13.7 54.8 DR-07 13.8 +/- 0.8 16.2 +/- 0.8 15.8 +/- 0.7 15.2 +/- 0.6 15.3 61.1 DR-08 9.7 +/- 0.8 12.2 +/- 0.6 11.8 +/- 0.5 11.3 +/- 0.5 11.3 45.1 DR-09 11.0 +/- 1.0 13.3 +/- 0.8 12.9 +/- 0.5 12.8 +/- 0.6 12.5 50.0 DR-10 12.1 +/- 0.7 14.8 +/- 0.9 14.0 +/- 0.7 13.9 +/- 0.7 13.7 54.9 DR-11 9.0 +/- 0.6 11.0 +/- 0.6 10.9 +/- 0.5 10.6 +/- 0.7 10.4 41.4 DR-12 13.6 +/- 0.8 15.8 +/- 1.0 15.7 +/- 0.8 14.5 +/- 0.8 14.9 59.5 DR-13 14.4 +/- 0.8 16.6 +/- 0.8 16.3 +/- 0.6 15.0 +/- 0.6 15.6 62.3 DR-14 11.4 +/- 0.5 13.6 +/- 0.7 13.3 +/- 0.6 12.2 +/- 0.8 12.6 50.5 DR-15 11.2 +/- 0.7 13.6 +/- 0.8 13.4 +/- 0.5 12.1 +/- 0.6 12.6 50.3 DR-16 12.1 +/- 0.6 14.9 +/- 0.9 15.0 +/- 0.6 13.1 +/- 0.6 13.8 55.1 DR-17 12.8 +/- 0.6 15.2 +/- 0.8 14.4 +/- 0.6 13.4 +/- 0.7 13.9 55.8 DR-18 12.4 +/- 0.7 15.1 +/- 1.0 14.6 +/- 0.9 14.1 +/- 0.8 14.1 56.3 DR-19 12.5 +/- 0.7 15.1 +/- 1.0 14.3 +/- 0.7 14.0 +/- 0.9 14.0 55.9 DR-20 11.7 +/- 0.6 14.2 +/- 0.7 13.8 +/- 0.6 13.7 +/- 0.6 13.3 53.4 DR-21 11.4 +/- 0.7 14.0 +/- 1.1 13.6 +/- 0.6 12.9 +/- 0.7 13.0 51.9 DR-22 9.3 +/- 0.6 11.5 +/- 0.7 11.0 +/- 0.7 10.8 +/- 0.5 10.6 42.6 DR-23 11.6 +/- 0.6 14.3 +/- 0.8 13.9 +/- 0.7 13.7 +/- 0.9 13.4 53.6 DR-24 11.9 +/- 0.7 15.0 +/- 0.9 14.1 +/- 0.5 14.8 +/- 0.8 14.0 55.8 DR-25 10.3 +/- 0.6 12.0 +/- 0.8 12.2 +/- 0.5 11.2 +/- 0.6 11.4 45.7 B-13

INDIAN POINT ENERGY CENTER TABLE B-3 DIRECT RADIATION, QUARTERLY DATA - 2012 mR/Quarter +/- 1 sigma Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Annual Annual Nuclide Number 01/01-03/31 04/01-06/30 07/01-09/30 10/01-01/01 Average Total TLD DR-26 DR-27 DR-28 DR-29 DR-30 DR-31 DR-32 DR-33 DR-34 DR-35 DR-36 DR-37 DR-38 DR-39 DR-40*

DR-41 AVERAGE (Indicator Locations) 12.0 +/- 0.6 11.9 +/- 0.6 12.1 +/- 0.7 12.2 +/- 0.7 14.0 +/- 0.6 10.6 +/- 0.5 11.6 +/- 0.8 10.7 +/- 0.8 10.3 +/- 0.6 12.7 +/- 0.8 11.7 +/- 0.7 10.2 +/- 0.7 12.2 +/- 0.6 11.0 +/- 0.7 11.0 +/- 0.7 14.0 13.4 (a) 19.5 14.4 14.4 16.2 13.1 14.5 13.1 13.5 14.7 14.6 12.5 14.4 13.5 13.2

+ 0.8

+/- 0.8

+/- 0.9

+/- 1.3

+ 0.7

+ 0.8

+ 0.6

+/- 1.0

+ 0.7

+ 0.9

+ 0.9

+ 1.4

+ 0.8

+ 0.8

+ 1.0

+ 0.7 13.8 13.6 19.9 15.0 14.7 16.1 13.1 13.9 13.4 13.6 15.0 13.4 12.3 14.6 13.0 13.0 13.9

+/- 0.6

+/- 0.7

+/- 0.7

+/- 0.8

+/- 0.8

+/- 0.6

+/- 0.9

+/- 0.6

+/- 0.6

+/- 0.7

+/- 0.6

+/- 0.6

+/- 0.9

+/- 0.6

+/- 0.6

+/- 0.7 13.2 12.6 18.5 13.7 13.4 15.2 11.9 13.3 13.1 12.8 14.4 13.6 11.7 13.5 11.8 13.0

+/- 0.5

+/- 0.8

+/- 0.7

+/- 0.8

+/- 0.6

+/- 0.6

+/- 0.7

+/- 0.7

+/- 0.7

+/- 0.7

+/- 0.7

+/- 0.8

+/- 0.6

+/- 0.7

+/- 0.6

+/- 0.9 13.2 12.9 19.3 13.8 13.7 15.4 12.2 13.3 12.6 12.5 14.2 13.3 11.7 13.7 12.3 12.5 13.3 53.0 51.5 77.1 55.2 54.7 61.5 48.7 53.4 50.2 50.2 56.7 53.3 46.7 54.8 49.3 50.2 53.4 11.7 14.2 13.3

• Control location (a) TLD missing, the annual total is based on using the 3 quarters average for the first quarter.

B-14

INDIAN POINT ENERGY CENTER TABLE B-4 DIRECT RADIATION, 2002 THROUGH 2012 DATA mR per Year Station Mean Standard Deviation Minimum Value Maximum Value 2012 Mean Number (2002-2011)

(2002-2011)

(2002-2011)

(2002-2011)

DR-01 61.3 2.3 58.3 66.0 55.6 DR-02 57.7 1.9 53.6 60.0 55.9 DR-03 47.3 1.7 44.0 50.0 44.2 DR-04 53.8 3.1 46.8 58.0 52.2 DR-05 54.3 2.3 48.4 56.8 53.6 DR-06 54.6 3.3 46.4 57.6 54.8 DR-07 63.2 3.2 55.6 66.4 61.1 DR-08 49.9 2.6 46.6 54.4 45.1 DR-09 52.7 2.3 47.2 55.2 50.0 DR-10 57.3 1.8 53.6 60.0 54.9 DR-11 43.9 1.7 40.8 46.4 41.4 DR-12 65.6 4.8 60.5 76.0 59.5 DR-13 74.8 5.3 65.6 82.0 62.3 DR-14 53.1 1.9 50.0 56.0 50.5 DR-15 52.2 2.4 46.4 54.8 50.3 DR-16 58.1 2.1 55.2 61.6 55.1 DR-17 DR-18 DR-19 DR-20 DR-21 DR-22 DR-23 DR-24 DR-25 DR-26 DR-27 DR-28 DR-29 DR-30 DR-31 DR-32 58.7 56.4 59.1 52.7 54.8 44.8 55.1 56.7 49.5 55.1 54.2 72.8 59.1 59.1 67.1 51.6 1.9 2.1 2.1 2.2 2.2 1.7 2.3 2.9 2.3 2.3 3.2 7.9 5.6 3.5 2.8 2.3 56.4 52.4 55.2 47.6 50.0 40.4 49.6 49.2 44.8 50.4 46.8 57.2 54.8 52.4 62.0 46.0 61.2 59.1 61.6 55.2 57.6 46.4 58.0 58.8 52.8 58.8 59.2 79.1 73.6 65.2 72.0 54.8 55.8 56.3 55.9 53.4 51.9 42.6 53.6 55.8 45.7 53.0 51.5 77.1 55.2 54.7 61.5 48.7 B-iS5

INDIAN POINT ENERGY CENTER TABLE B-4 DIRECT RADIATION, 2002 THROUGH 2012 DATA mR per Year Station Mean Standard Deviation Minimum Value Maximum Value 2012 Mean Number (2002-2011)

(2002-2011)

(2002-2011)

(2002-2011 )

DR-33 52.0 6.4 34.4 55.2 53.4 DR-34 50.8 3.0 43.2 54.8 50.2 DR-35 53.6 2.5 48.8 56.4 50.2 DR-36 58.7 2.4 52.4 60.8 56.7 DR-37 54.3 2.6 48.8 58.0 53.3 DR-38 50.8 2.4 48.0 56.0 46.7 DR-39 60.3 2.4 55.2 63.2 54.8 DR-40*

61.5 7.8 51.9 75.2 49.3 DR-41 50.7 2.6 44.4 53.6 50.2 AVERAGE (Indicator Locations)

• Control location 55.9 53.4 B-16

INDIAN POINT ENERGY CENTER TABLE B-5 DIRECT RADIATION, INNER AND OUTER RINGS - 2012 (mR per Year)

Inner Ring Outer Ring Sector Inner Ring Outer Ring ID ID Annual Average Annual Average DR-01 DR-17 N

55.6 55.8 DR-02 DR-18 NNE 55.9 56.3 DR-03 DR-19 NE 44.2 55.9 DR-04 DR-20 ENE 52.2 53.4 DR-05 DR-21 ENE 53.6 51.9 DR-06 DR-22 ESE 54.8 42.6 DR-07 DR-23 SE 61.1 53.6 DR-08 DR-24 SSE 45.1 55.8 DR-09 DR-25 S

50.0 45.7 DR-10 DR-26 SSW 54.9 53.0 DR-11 DR-27 SW 41.4 51.5 DR-12 DR-28 WSW 59.5 77.1 DR-13 DR-29 WSW 62.3 55.2 DR-14 DR-30 WNW 50.5 54.7 DR-15 DR-31 NW 50.3 61.5 DR-16 DR-32 NNW 55.1 48.7 Average 1

1 52.9 54.5 B-17

INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2012 pCi/M 3 +/- 2 Sigma PERIOD ENDING Algonquin 4

NYU Tower 5

Roseton 23*

Croton Point 27 Grassy Point 29 Peekskill Training Building Met Tower 44 94 95 ENDING 4

5 23*

01/09/12 0.016 +/- 0.003 01/17/12 0.011 +/- 0.002 01/23/12 0.012 +/- 0.002 01/30/12 0.012 +/- 0.003 02/06/12 0.015 +/- 0.002 02/13/12 0.012 +/- 0.002 02/21/12 0.014 +/- 0.002 02/27/12 0.014 +/- 0.003 03/05/12 0.011 +/- 0.002 03/12/12 0.015 +/- 0.002 03/19/12 0.014 +/- 0.002 03/26/12 0.016 +/- 0.003 04/02/12 0.011 +/- 0.002 04/09/12 0.015 +/- 0.003 04/16/12 0.013 +/- 0.002 04/23/12 0.012 +/- 0.002 04/30/12 0.013 +/- 0.002 05/07/12 0.008 +/- 0.002 05/14/12 0.016 +/- 0.003 05/21/12 0.012 +/- 0.002 05/29/12 0.008 +/- 0.002 06/04/12 0.010 +/- 0.003 06/11/12 0.013 +/- 0.002 06/18/12 0.010 +/- 0.002 06/25/12 0.014 +/- 0.002 07/02/12 0.018 +/- 0.003 0.016 +/- 0.003 0.010 +/- 0.002 0.012 +/- 0.003 0.011 +/- 0.003 0.016 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.016 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.007 +/- 0.002 0.015 +/- 0.003 0.013 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.002 0.015 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.003 0.012 +/- 0.003 0.017 +/- 0.003 0.013 +/- 0.002 0.016 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.003 0.012 +/- 0.002 0.015 +/- 0.003 0.015 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.009 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.003 0.018 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.015 +/- 0.003 0.012 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.017 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.003 0.015 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.007 +/- 0.002 0.015 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.007 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.003 0.008 +/- 0.002 0.013 +/- 0.003 0.011 +/- 0.003 0.016 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.003 0.011 +/- 0.003 0.012 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.003 0.015 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.003 0.011 +/- 0.002 0.008 +/- 0.002 0.013 +/- 0.003 0.009 +/- 0.002 0.008 +/- 0.002 0.012 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.002 0.016 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.003 0.011 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.003 0.012 +/- 0.002 0.013 +/- 0.002 0.016 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.007 +/- 0.002 0.015 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.003 0.010 +/- 0.002 0.015 +/- 0.003 0.011 +/- 0.002 0.017 +/- 0.002 0.011 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.003 0.014 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.008 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.003 0.011 +/- 0.002 0.008 +/- 0.002 0.018 +/- 0.003 0.016 +/- 0.002

• Control location B-18

INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2012 pCi/rn3 +/- 2 Sigma PERIOD ENDING Algonquin 4

NYU Tower 5

Roseton 23*

Croton Point 27 Grassy Point 29 Peekskill Training Building 44 94 Met Tower 95 07/09/12 07/16/12 07/23/12 07/30/12 08/06/12 08/13/12 08/20/12 08/27/12 09/04/12 09/10/12 09/17/12 09/24/12 10/01/12 10/09/12 10/15/12 10/22/12 10/29/12 11/05/12 11/13/12 11/19/12 11/26/12 12/03/12 12/10/12 12/18/12 12/26/12 01/02/13 0.015 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.003 0.017 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.020 +/- 0.003 0.017 +/- 0.002 0.014 +/- 0.003 0.011 +/- 0.002 0.012 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 0.018 +/- 0.003 0.004 +/- 0.002 0.017 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.014 +/- 0.002 0.0 14 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.002 0.012 +/- 0.003 0.014 +/- 0.003 0.011 +/- 0.002 0.012 +/- 0.002 0.019 +/- 0.003 0.017 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.002 0.011 +/- 0.003 0.0 14 +/- 0.002 0.018 +/- 0.003 0.004 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 0.0 16 +/- 0.003 0.013 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.003 0.016 +/- 0.003 0.012 +/- 0.003 0.018 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.018 +/- 0.003 0.019 +/- 0.002 0.013 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.002 0.014 +/- 0.003 0.011 +/- 0.002 0.022 +/- 0.003 0.005 +/- 0.003 0.016 +/- 0.002 0.017 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.003 0.0 16 +/- 0.002 0.015 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.016 +/- 0.003 0.011 +/- 0.002 0.014 +/- 0.002 0.020 +/- 0.003 0.019 +/- 0.002 0.012 +/- 0.003 0.015 +/- 0.002 0.012 +/- 0.002 0.0 14 +/- 0.003 0.018 +/- 0.003 0.013 +/- 0.003 0.010 +/- 0.002 0.017 +/- 0.003 0.005 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.003 0.025 +/- 0.003 0.022 +/- 0.003 0.0 14 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.018 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.017 +/- 0.002 0.003 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.003 0.021 +/- 0.002 0.021 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.002 0.0 14 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.012 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.020 +/- 0.003 0.017 +/- 0.002 0.014 +/- 0.003 0.015 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.017 +/- 0.002 0.012 +/- 0.003 0.014 +/- 0.002 0.018 +/- 0.003 0.004 +/- 0.002 0.016 +/- 0.002 0.019 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.002 0.016 +/- 0.002 0.011 +/- 0.002 0.015 +/- 0.002 0.0 16 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 0.017 +/- 0.003 0.010 +/- 0.002 0.014 +/- 0.002 0.020 +/- 0.003 0.020 +/- 0.002 0.014 +/- 0.003 0.014 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.003 0.015 +/- 0.002 0.012 +/- 0.003 0.012 +/- 0.002 0.017 +/- 0.003 0.003 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.003 0.025 +/- 0.003 0.022 +/- 0.003 0.015 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.019 +/- 0.003 0.011 +/- 0.002 0.015 +/- 0.002 0.02 1 +/- 0.003 0.018 +/- 0.002 0.015 +/- 0.003 0.011 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.003 0.015 +/- 0.002 0.011 +/- 0.003 0.012 +/- 0.002 0.019 +/- 0.003 0.004 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.003 0.02 1 +/- 0.003 0.025 +/- 0.003 0.015 +/- 0.002 0.017 +/- 0.002 0.010 +/- 0.002 0.015 +/- 0.002

• Control location B-i19

INDIAN POINT ENERGY CENTER TABLE B-7 IODINE-131 ACTIVITY IN AIRBORNE CHARCOAL SAMPLES - 2012 pCi/ma +/- 2 Sigma PERIOD Algonquin ENDING 4

NYU Tower 5

Roseton 23*

Croton Point 27 Grassy Point 29 Peekskill Training Building 44 94 Met Tower 95 01/09/12 01/17/12 01/23/12 01/30/12 02/06/12 02/13/12 02/21/12 02/27/12 03/05/12 03/12/12 03/19/12 03/26/12 04/02/12 04/09/12 04/16/12 04/23/12 04/30/12 05/07/12 05/14/12 05/21/12 05/29/12 06/04/12 06/11/12 06/18/12 06/25/12 07/02/12

< 0.0246

< 0.0150

< 0.0180

< 0.0239

< 0.0172

< 0.0275

< 0.0107

< 0.0163

< 0.0261

< 0.0122

< 0.0140

< 0.0105

< 0.0130

< 0.0197

< 0.0160

< 0.0270

< 0.0313

< 0.0236

< 0.0198

< 0.0373

< 0.0217

< 0.0400

< 0.0395

< 0.0372

< 0.0532

< 0.0224

< 0.0242

< 0.0151

< 0.0219

< 0.0244

< 0.0170

< 0.0275

< 0.0107

< 0.0163

< 0.0268

< 0.0119

< 0.0140

< 0.0106

< 0.0129

< 0.0199

< 0.0160

< 0.0273

< 0.0314

< 0.0191

< 0.0197

< 0.0364

< 0.0221

< 0.0404

< 0.0396

< 0.0371

< 0.0534

< 0.0224

< 0.0196

< 0.0182

< 0.0194

< 0.0188

< 0.0203

< 0.0403

< 0.0169

< 0.0164

< 0.0229

< 0.0141

< 0.0234

< 0.0070

< 0.0222

< 0.0204

< 0.0155

< 0.0255

< 0.0243

< 0.0456

< 0.0263

< 0.0302

< 0.0272

< 0.0305

< 0.0285

< 0.0271

< 0.0597

< 0.0143 0.0239 0.0146 0.0216 0.0237 0.0163 0.0271 0.0104 0.0158 0.0260 0.0116 0.0136 0.0102 0.0127 0.0192 0.0154 0.0265 0.0305 0.0186 0.0190 0.0358 0.0211 0.0389 0.0382 0.0359 0.0513 0.0216

< 0.0152

< 0.0137

< 0.0148

< 0.0142

< 0.0204

< 0.0304

< 0.0128

< 0.0123

< 0.0172

< 0.0107

< 0.0178

< 0.0052

< 0.0166

< 0.0154

< 0.0117

< 0.0190

< 0.0179

< 0.0343

< 0.0201

< 0.0228

< 0.0204

< 0.0224

< 0.0220

< 0.0206

< 0.0450

< 0.0105

< 0.0211

< 0.0189

< 0.0210

< 0.0204

< 0.0223

< 0.0439

< 0.0182

< 0.0182

< 0.0250

< 0.0154

< 0.0254

< 0.0074

< 0.0233

< 0.0216

< 0.0168

< 0.0276

< 0.0264

< 0.0483

< 0.0278

< 0.0329

< 0.0293

< 0.0329

< 0.0310

< 0.0296

< 0.0646

< 0.0156

< 0.0227

< 0.0139

< 0.0202

< 0.0222

< 0.0160

< 0.0255

< 0.0100

< 0.0151

< 0.0244

< 0.0113

< 0.0129

< 0.0097

< 0.0121

< 0.0184

< 0.0148

< 0.0250

< 0.0291

< 0.0174

< 0.0184

< 0.0332

< 0.0203

< 0.0367

< 0.0364

< 0.0342

< 0.0489

< 0.0207

< 0.0186

< 0.0167

< 0.0176

< 0.0170

< 0.0192

< 0.0355

< 0.0158

< 0.0151

< 0.0210

< 0.0130

< 0.0218

< 0.0064

< 0.0207

< 0.0188

< 0.0144

< 0.0230

< 0.0229

< 0.0400

< 0.0249

< 0.0279

< 0.0249

< 0.0287

< 0.0258

< 0.0250

< 0.0561

< 0.0132

• Control location B-20

INDIAN POINT ENERGY CENTER TABLE B-7 IN AIRBORNE CHARCOAL SAMPLES - 2012 IODINE-131 ACTIVITY pCi/ma +/- 2 Sigma PERIOD Algonquin ENDING 4

NYU Tower 5

Roseton 23*

Croton Point 27 Grassy Point 29 Peekskill Training Building 44 94 Met Tower 95 07/09/12 07/16/12 07/23/12 07/30/12 08/06/12 08/13/12 08/20/12 08/27/12 09/04/12 09/10/12 09/17/12 09/24/12 10/01/12 10/09/12 10/15/12 10/22/12 10/29/12 11/05/12 11/13/12 11/19/12 11/26/12 12/03/12 12/10/12 12/18/12 12/26/12 01/02/13

< 0.0149

< 0.0207

< 0.0194

< 0.0178

< 0.0198

< 0.0157

< 0.0141

< 0.0285

< 0.0295

< 0.0172

< 0,0551

< 0.0236

< 0.0218

< 0.0301

< 0.0246

< 0.0254

< 0.0183

< 0.0143

< 0.0510

< 0.0458

< 0.0236

< 0.0236

< 0.0122

< 0.0145

< 0.0232

< 0.0173

< 0.0150

< 0.0210

< 0.0191

< 0.0237

< 0.0201

< 0.0157

< 0.0141

< 0.0283

< 0.0297

< 0.0175

< 0.0547

< 0.0236

< 0.0220

< 0.0305

< 0.0241

< 0.0259

< 0.0180

< 0.0142

< 0.0509

< 0.0457

< 0.0234

< 0.0236

< 0.0122

< 0.0144

< 0.0233

< 0.0172 0.0154 0.0230 0.0286 0.0137 0.0282 0.0202 0.0113 0.0225 0.0279 0.0168 0.0158 0.0177 0.0167 0.0291 0.0197 0.0359 0.0173 0.0404 0.0331 0.0576 0.0282 0.0125 0.0098 0.0133 0.0292 0.0172 0.0143 0.0205 0.0182 0.0172 0.0191 0.0150 0.0136 0.0271 0.0286 0.0168 0.0527 0.0224 0.0216 0.0301 0.0238 0.0255 0.0175 0.0138 0.0504 0.0451 0.0229 0.0233 0.0119 0.0141 0.0227 0.0169

< 0.0120

< 0.0167

< 0.0213

< 0.0106

< 0.0216

< 0.0152

< 0.0086

< 0.0170

< 0.0212

< 0.0127

< 0.0120

< 0.0132

< 0.0131

< 0.0222

< 0.0149

< 0.0266

< 0.0133

< 0.0262

< 0.0306

< 0.0360

< 0.0215

< 0.0095

< 0.0074

< 0.0103

< 0.0223

< 0.0128

< 0.0171

< 0.0246

< 0.0284

< 0.0134

< 0.0271

< 0.0190

< 0.0105

< 0.0206

< 0.0259

< 0.0160

< 0.0149

< 0.0159

< 0.0151

< 0.0261

< 0.0176

< 0.0319

< 0.0154

< 0.0215

< 0.0355

< 0.0419

< 0.0249

< 0.0112

< 0.0086

< 0.0120

< 0.0266

< 0.0154

< 0.0137

< 0.0192

< 0.0177

< 0.0165

< 0.0183

< 0.0145

< 0.0130

< 0.0264

< 0.0274

< 0.0160

< 0.0513

< 0.0220

< 0.0202

< 0.0280

< 0.0230

< 0.0238

< 0.0169

< 0.0133

< 0.0483

< 0.0430

< 0.0222

< 0.0224

< 0.0115

< 0.0137

< 0.0220

< 0.0164

< 0.0147

< 0.0207

< 0.0270

< 0.0127

< 0.0266

< 0.0185

< 0.0104

< 0.0208

< 0.0262

< 0.0155

< 0.0148

< 0.0165

< 0.0159

< 0.0278

< 0.0183

< 0.0324

< 0.0167

< 0.0268

< 0.0394

< 0.0424

< 0.0257

< 0.0115

< 0.0090

< 0.0123

< 0.0270

< 0.0156

• Control location B-21

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2012 10-3 pCi/m 3 + 2 Sigma Algonquin NYU Tower 4

5 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 50 +/- 13 80 +/- 14 64 +/- 16 66 +/- 19 58 +/- 12 71 +/- 20 62 +/- 16 84 +/- 22 K-40

< 18

< 18

< 23

< 14

< 14

< 14

< 29

< 21 Mn-54

< 1

< 1

< 1

< 1

< 1

<2

< 1

< 1 Co-58

<2

<2

< 1

<2

<2

<2

< 1

<3 Fe-59

<4

<3

<2

<8

<5

<6

<4

<9 Co-60

< 1

< 1

< 1

< 1

<2

<2

< 1

< 1 Zn-65

<2

<2

<2

<2

<3

<6

<2

<4 Nb-95

< 1

< 1

<2

<2

< 1

<3

<2

<3 Zr-95

<3

<2

<3

<4

<3

<4

<5

<4 Ru-103

<2

<2

< 1

<3

<2

<3

<2

<4 Ru-106

< 12

< 10

< 7

< 9

< 12

< 16

< 6

< 12 1-131

< 57

< 12

< 31

< 530

< 54

< 20

< 43

< 800 Cs-134

< 1

< 1

< 1

< 1

< 1

<2

< 1

< 1 Cs-137

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 1 Ba-140

< 38

< 15

< 34

< 178

< 44

< 29

< 43

< 209 La-140

< 22

< 8

< 13

< 68

< 16

< 13

< 14

< 120 Ce-141

<3

<2

<3

<5

<3

<3

<3

<6 Ce-144

<5

<5

<6

<5

<6

<6

<5

<6-Ra-226

< 19

< 20

< 21

< 16

< 20

< 29

< 19

< 22 Ac-228

< 3

<4

<4

<4

<4

< 7

<4

<4 Th-228

<2

<2

<2

< 1 4 +/-2

<3

<2

<2 B-22

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2012 10-3 pCi/m 3 +/- 2 Sigma Roseton 23*

Croton Point 27 DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1 st Quarter 2nd Quarter 3rd Quarter 60 +/- 22 25 1

2 4

1 3

2 4

3 14 82 1

1 60 25 3

7 22 4

2 63 + 16 20 2

2 6

2 5

2 4

2 17 22 2

1 27 9

3 6

28 7

2 58 +/- 17

< 15

<2

<2

<5

<2

<4

<3

<3

<3

< 14

< 52

<2

<2

< 48

< 12

<4

<6

< 26

<6

<2 111 +/- 29 30 2

3 8

1 4

3 6

5 16 854 2

1 237 126 8

9 28 6

2 58 +/- 16

< 20

<1

<2

<5

<1

<3

<2

<3

<3

< 10

< 75

<1

<1

< 45

< 16

<3

<5

< 23

<4

<2 65 +/- 13 9

1 1

4 1

3 2

3 2

12 13 1

1 19 8

2 6

23 4

2 59 +/- 22

< 15

<2

<2

<7

<1

<4

<3

<4

<3

< 14

< 70

<2

<1

< 58

< 13

<4

<7

< 27

<7

<3 4th Quarter 77 +/- 21

< 21

<1

<2

<8

<1

<2

<2

<4

<3

< 12

< 760

<1

<1

< 214

< 55

<6

<6

< 20

<5

<2

• Control location B-23

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2012 10-3 pCi/m 3 +/- 2 Sigma Grassy Point 29 Peekskill 44 DATE 1st Quarter Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 51.1 +/- 14.5

< 10.8

< 0.9

< 1.2

< 2.8

< 1.0

< 2.0

< 1.4

< 1.9

< 1.9

< 6.5

< 49.6

< 0.7

< 0.5

< 37.1

<9.1

< 2.4

< 3.8

< 13.0

< 2.9

< 1.1 2nd Quarter 58.8 +/- 11.2

< 15.5

< 1.0

< 1.1

< 2.2

< 0.9

< 2.3

< 1.3

< 2.0

< 1.3

< 8.8

< 9.9

< 0.9

< 1.0

< 14.3

< 5.2

< 1.9

< 3.8

< 15.4

< 3.7

< 1.3 3rd Quarter 51.4 +/- 20.4

< 22.9

< 1.2

< 1.7

< 4.9

< 1.2

<4.1

< 2.2

< 4.0

< 2.5

< 12.1

< 53.2

< 1.7

< 1.3

< 48.7

< 11.7

< 3.7

< 6.3

< 22.5

< 6.0

< 1.9 4th Quarter 78.2 +/- 29.6

< 25.7

< 2.0

< 2.4

< 9.6

< 1.7

< 4.4

< 2.6

< 5.6

< 5.3

< 15.7

< 976.5

< 1.6

< 1.8

< 283.2

< 116.1

< 5.6

< 6.0

< 21.9

< 6.5

< 2.2 1st Quarter 55.7 +/- 13.3

< 12.6

< 1.6

< 2.0

< 4.2

< 1.0

<4.1

< 1.6

< 2.8

< 2.7

< 11.8

< 72.7

< 1.4

< 1.2

< 59.9

< 17.5

< 3.9

< 6.4

< 23.4

< 3.6

< 2.0 2nd Quarter 70.7 +/- 14.5

< 21.1

< 1.1

< 1.5

<4.1

< 1.1

< 2.2

< 1.4

< 2.6

< 1.5

< 8.5

< 12.6

< 1.0

< 1.0

< 16.2

< 8.1

< 1.7

< 4.4

< 18.4

<4.1

< 1.6 3rd Quarter 65.8 +/- 15.6

< 19.6

< 0.8

< 1.5

< 3.0

< 1.0

< 2.8

< 1.3

< 2.8

< 2.0

< 10.3

< 32.4

< 1.0

< 0.8

< 34.1

< 7.5

< 2.4

< 4.7

< 17.8

< 4.0

< 1.6 4th Quarter 66.9 +/- 18.2

< 15.7

< 1.1

< 1.8

< 6.7

< 0.7

< 2.0

< 2.0

< 3.4

< 2.4

< 7.9

< 600.4

< 0.9

< 0.9

< 143.8

< 88.8

< 5.1

< 4.8

< 15.5

< 1.8

< 1.4 B-24

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2012 10-3 pCi/m 3 +/- 2 Sigma Training Building 94 Met Tower 95 DATE 1st Quarter Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-1.34 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 61.2 +/- 13.6

< 17.0

<1.1

• 1.5

< 3.5

< 1.4

< 3.1

< 1.7

< 2.8

< 1.7

< 8.7

< 56.0

< 1.1

< 0.9

< 33.9

< 18.0

< 2.8

< 4.5

< 16.0

< 3.7 2.0 +/- 1.1 2nd Quarter 61.9 +/- 17.0

< 22.0

< 1.3

< 1.9

< 3.8

< 1.4

< 4.3

< 1.8

< 3.4

< 2.0

< 11.0

< 18.4

< 1.5

< 1.5

< 23.0

< 7.2

< 2.7

<7.1

< 23.2

< 5.0

< 2.4 3rd Quarter 42.6 +/- 18.4

< 36.3

< 1.8

< 2.7

< 7.6

< 1.9

< 5.8

< 3.2

< 5.4

< 3.5

< 18.9

< 75.2

< 1.8

< 2.0

< 55.2

< 27.2

< 3.8

< 5.8

< 26.0

< 6.4

< 2.7 4th Quarter 1 st Quarter 2nd Quarter 62.4 + 14.9 20.5 1.1 2.1 6.1 1.1 2.9 2.3 3.9 3.7 9.4 614.0 1.3 0.8 190.0 72.2 5.1 4.8 15.6 4.7 1.7 46.8 + 18.4 28.8 1.9 2.5 7.6 1.6 5.3 3.0 5.0 3.8 16.0 85.4 1.7 1.5 81.3 25.2 4.3 6.1 24.5 7.0 2.5 65.7 +/- 12.9 18.5 1.2 1.1 3.1 0.7 2.0 1.5 1.8 1.0 10.4 10.9 1.1 1.1 16.8 5.7 1.7 4.3 18.5 2.9 1.5 3rd Quarter 72.8 +/- 18.0

< 22.1

< 1.2

<2.1

< 4.4

< 1.5

< 3.7

< 2.2

< 3.2

< 2.8

< 11.6

< 55.6

< 1.8

< 1.4

< 49.2

< 22.4

< 3.8

< 6.3

< 22.4

< 5.3

< 2.3 81.2 +

4th Quarter 22.1 11.5 1.4 1.6 7.5 1.2 2.8 2.0 5.1 3.9 13.2 678.9 1.5 1.2 212.7 98.2 5.6 6.1 18.9 5.2 1.7 B-25

INDIAN POINT ENERGY CENTER TABLE B-9 RADIONUCLIDES IN RAINWATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Roseton 23*

Peekskill 44 DATE 1st Quarter RADIOCHEMICAL 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter H-3

< 176 GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 53 41 5

5 11 4

11 5

9 6

49 11 5

7 28 9

9 40 114 21 9

< 180

< 63

< 147

<8

<7

< 16

<5

< 15

<9

< 14

<8

< 67

< 12

<7

<6

< 32

< 14

< 12

< 50

< 185

< 29

< 14

< 195

< 85

< 168

<9

<9

< 16

< 10

< 17

< 10

< 18

<9

< 73

< 16

<7

< 10

< 49

< 14

< 13

< 54

< 198

< 46

< 16

< 160 (a) 65 66 6

6 14 7

13 8

14 8

68 12 6

8 35 13 10 40 146 28 11

< 174

< 60

< 96

<6

<5

< 14

<5

<9

<5

< 11

<7

< 53

< 11

<5

<6

< 29

<8

< 11

< 45

< 137

< 18

< 11

< 180

< 58

< 68

<6

<6

< 12

<6

< 10

<5

< 11

<7

< 60

< 12

<6

<5

< 37

<9

< 11

< 47

< 158

< 22

< 12 67 59 7

7 15 6

15 8

10 8

59 14 6

7 37 14 13 51 186 21 12

< 192

< 160

< 56

< 60

<6

<6

< 12

<6

< 13

<6

< 10

<7

< 57

< 12

<5

<5

< 31

< 11

< 12

< 46

< 158

< 24

< 12

• Control location (a) See Table B-ic B-26

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Camp Field 7

DATE RADIOCHEMICAL 1/9/2012 2.4 +/- 1.4 2/13/2012 3/12/2012 3.2 +/- 1.6

< 180 4/9/2012 3.7 +/- 1.8 5/14/2012 6/11/2012 2.3 +/- 1.1

< 169 Gr-B H-3 (a)

GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-106 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228

< 2.5

< 2.2 39 83 6

4 9

4 8

4 8

5 48 6

5 5

17 6

10 38 156 20 11 37 60 4

4 8

5 7

4 8

4 31 9

4 4

22 7

8 30 109 18 9

< 46

< 45

<6

<5

< 13

<4

< 10

<6

<8

<5

< 39

<7

<4

<6

< 24

< 10

<8

< 36

< 129

< 22

<8

< 36

< 30

<4

<4

<8

<4

<9

<4

<7

<4

< 35

<7

<3

<4

< 20

<6

<8

< 30

< 107

< 14

<9

< 32

< 38

<4

<4

<7

<4

<7

<4

<7

<4

< 33

<8

<3

<4

< 18

<7

<7

< 30

< 93

< 17

<7

< 38

< 49

<4

<4

<6

<3

<9

<4

<6

<4

< 39

<8

<4

<4

<17

<6

<8

< 34

< 94

< 18

<7 (a) Quarterly composite B-27

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Camp Field 7

DATE RADIOCHEMICAL 7/9/2012 2.7 +/- 1.0 8/20/2012 9/17/2012 3.4 +/- 1.2

< 188 10/15/2012 3.2 +/- 2.0 11/19/2012 12/10/12 Gr-B H-3 (a)

GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 I1A31 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228

< 4.5

< 3.3

< 3.3

< 180

< 31.9

< 28.9

< 3.0

< 3.0

< 7.3

< 3.6

<8.1

< 4.2

< 5.8

< 3.9

< 32.7

< 7.0

< 3.8

< 3.9

< 16.7

< 4.3

< 6.8

< 26.0

< 77.7

< 14.0

< 7.7 48.9 68.9 4.2 4.1 10.1 3.3 9.8 5.9 8.2 5.5 38.7 9.0 4.6 4.0 28.1 9.5 10.3 39.2 144.0 14.6 10.7

< 57.6

< 44.5

< 5.2

< 5.3

< 12.4

< 5.4

< 9.4

< 6.0

< 10.2

< 5.3

< 51.2

< 11.5

< 5.6

< 6.2

< 28.8

< 5.5

< 11.1

< 41.3

< 140.6

< 23.5

< 11.7 28.8 53.2 3.1 3.2 5.6 3.2 6.2 4.1 6.3 3.8 31.8 8.0 3.2 3.2 20.1 5.1 7.0 26.5 97.8 14.4 5.7

< 35.5

< 57.2

< 3.6

< 4.0

< 9.8

< 3.7

<8.1

< 4.3

< 6.7

< 4.5

< 31.0

< 8.0

<4.1

< 3.7

< 24.7

< 5.9

< 7.8

< 31.9

< 90.3

< 16.2

<7.1 45.7 130.7 5.2 6.3 12.7 6.9 12.8 5.7 8.0 5.7 50.6 10.1 5.4 5.9 27.1 8.6 9.7 35.5 128.3 23.6 10.5 (a) Quarterly composite B-28

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Croton 8

DATE 1/9/2012 RADIOCHEMICAL 2/13/2012 3.3 +/- 1.5 3/12/2012 4.1 +/- 1.5

< 177 4/9/2012 4.3 + 1.8 5/14/2012 2.6 +/- 1.5 6/11/2012 3.6 +/- 1.2

< 168 Gr-B H-3 (a)

GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228

< 2.2

< 63.6

< 111.0

< 8.2

<6.1

< 13.5

<8.1

< 16.8

< 7.4

< 11.4

< 7.0

< 60.0

< 9.4

< 6.6

< 6.4

< 25.6

< 8.5

< 12.8

< 47.1

< 197.1

< 31.4

< 12.0

< 40.3

< 87.1

< 4.6

< 3.9

< 9.3

< 4.4

< 8.5

< 5.2

< 7.5

< 5.0

< 36.5

< 9.7

< 4.0

< 4.3

< 26.0

< 8.6

< 9.0

< 34.3

< 109.7

< 19.5

< 7.9

< 38.8

< 38.1

< 4.3

< 3.5

< 8.6

< 4.3

< 8.8

< 4.2

< 7.0

< 4.4

< 40.5

< 5.9

< 4.2

<4.1

< 19.8

<6.1

< 7.7

< 32.5

< 111.3

< 17.6

< 8.8

< 32.3

< 78.1

< 3.4

<4.1

< 7.7

< 3.8

< 7.0

<4.1

< 6.9

< 4.3

< 38.0

< 7.0

< 3.6

< 4.0

< 19.8

< 5.3

< 7.3

< 29.2

< 107.9

< 15.8

<6.1

< 36.4

< 78.9

< 3.9

< 3.9

< 8.6

< 4.6

< 7.2

< 4.3

< 8.6

< 4.5

< 41.7

< 8.6

< 4.5

< 4.6

< 25.2

< 8.4

< 8.7

< 34.3

< 118.2

< 19.1

< 9.3

< 43.2

< 62.3

< 4.8

<5.1

<8.2

< 4.0

<9.5

< 4.6

<8.1

< 5.6

< 45.9

<8.1

<4.1

< 5.4

< 21.5

< 9.0

< 8.9

< 34.7

< 125.2

< 18.7

< 9.8 (a) Quarterly composite B-29

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Croton 8

DATE 7/9/2012 8/20/2012 9/17/2012 10/15/2012 11/19/2012 12/10/12 RADIOCHEMICAL Gr-B 2.5 +/- 1.0

< 4.3 3.8 +/- 1.1 3.4 +/- 1.9

< 3.3

< 3.2 H-3 (a)

< 186

< 172 GAMMA Be-7

< 52.7

< 48.7

< 60.9

< 34.1

< 41.6

< 47.6 K-40

< 61.0

< 103.4

< 144.2

< 64.3

< 88.4

< 47.3 Mn-54

< 4.4

< 5.9

< 7.3

< 3.3

< 4.6

< 4.4 Co-58

< 4.9

< 5.3

< 7.2

< 3.2

< 4.0

< 5.3 Fe-59

< 12.8

< 11.2

< 17.3

< 7.1

< 7.9

< 10.2 Co-60

< 5.6

< 5.4

< 8.5

< 2.9

< 3.8

< 4.4 Zn-65

< 12.0

< 10.1

< 15.3

< 7.2

< 6.6

< 10.1 Nb-95

< 5.8

< 5.4

< 9.0

< 4.1

< 3.9

< 5.3 Zr-95

< 9.9

< 8.9

< 12.7

< 6.0

< 8.0

< 8.4 Ru-103

< 6.5

< 6.2

< 8.0

< 4.0

< 4.8

< 5.8 Ru-106

< 46.9

< 54.4

< 73.0

< 31.9

< 45.0

< 45.8 1-131

< 9.8

< 10.8

< 15.1 (b)

< 8.6

< 9.3

< 9.3 Cs-134

< 5.6

< 5.7

< 7.3

< 3.6

< 3.4

< 5.0 Cs-137

< 5.2

< 6.0

< 9.0

< 3.8

< 4.2

< 5.1 Ba-140

< 26.1

< 29.4

< 40.0

< 20.6

< 25.4

< 27.1 La-140

< 10.4

< 8.7

< 15.9 (b)

< 6.0

< 4.4

< 7.3 Ce-141

< 8.0

< 10.7

< 12.0

< 7.8

< 8.6

< 10.7 Ce-144

< 31.0

< 42.3

< 41.6

< 30.2

< 38.0

< 43.4 Ra-226

< 116.2

< 129.5

< 163.3

< 102.4

< 118.1

< 137.7 Ac-228

< 21.8

< 20.6

< 29.4

< 13.1

< 20.1

< 20.2 Th-228

< 9.6

< 11.4

< 12.5

< 8.3

< 7.5

< 10.8 (a) Quarterly composite (b) See Table B-ic B-30

INDIAN POINT ENERGY CENTER TABLE B-11 RADIONUCLIDES IN GROUNDWATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Lafarge Monitoring Well 106 DATE 5/29/2012 11/19/2012 RADIOCHEMICAL H-3 Ni-63 Sr-90 GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-106 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ac-228

< 463

< 21.2

< 1.99

< 102

< 134

< 10

< 10

< 33

< 11

< 22

< 12

< 22

< 81

< 12

< 11

< 40

< 40

< 23

< 51

< 47

< 219

< 17.1

< 1.94

< 166

< 76

< 11

< 14

< 52

<8

< 21

< 21

< 30

< 98

<9

<9

< 590

< 590

< 51

< 50

< 45 (a)

(a)

(a)

(a) LLD not met due to age of sample B-31

INDIAN POINT ENERGY CENTER TABLE B-12 GAMMA EMITTERS IN SOIL SAMPLES, 2012 pCi/kg dry +/- 2 Sigma Roseton 23*

11/13/2012 Training Building 94 11/13/2012 Met Tower 95 11/13/2012 DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 900 +/- 365 17400 +/- 1270

< 51

< 47

< 116

< 66

< 113

< 64

< 111

< 54

< 381

< 159

< 45

< 49

< 349

< 99

< 86

< 277 1420 +/- 914 983 +/- 81

< 455 13740+/- 1156

< 46

< 46

< 114

< 40

< 88

< 58

< 85

< 51

< 348

< 154

< 36

< 57

< 313

< 70

< 90

< 286

< 1046 602 +/- 70

< 362 13500 +/- 1018

< 40

< 44

< 116

< 48

< 108

< 52

< 70

< 42

< 323

< 139

< 31 100 +/- 37

< 285

< 75

< 62

< 206

< 729 396 +/- 52

• Control location B-32

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 4/30/2012 Burdock 4/30/2012 Common Mullein 4/30/2012 Ragweed 5/21/2012 Burdock 5/21/2012 Common Mullein 5/21/2012 Ragweed 6/18/2012 Burdock RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 23 458 +/- 119 3189 +/- 311

< 19

< 20

< 47

< 25

< 52

< 19

< 34

< 21

< 183

< 38

< 20

< 20

< 102

< 29

< 35

< 135

< 459

< 33 564 +/-

4260 +/-

36+/-

139 378 21 22 50 30 58 24 42 22 183 42 22 23 107 35 35 131 417 24 424 +/-

7030 +/-

108 345 16 17 42 23 44 16 31 17 147 29 16 17 85 20 28 108 357 27 1642 +/- 177 6245 +/- 380

< 11

< 12

< 29

< 17

< 30

< 13

< 24

< 12

< 109

< 28

< 11

< 12

< 58

< 13

< 23

< 86

< 280

< 22 1181 +/-

4106 +/-

326 593 18 23 62 23 49 26 37 27 198 53 987 +/- 214 6825 +/- 646

< 22

< 25

< 56

< 29

< 48

< 25

< 43

< 22

< 208

< 49

< 21

< 24

< 133

< 24

< 41

< 153

< 537

< 45 898 +/- 133 4523 +/- 342

< 11

< 12

< 30

< 16

< 30

< 14

< 19

< 12

< 99

< 25

< 10

< 13

< 60

< 11

< 22

< 80

< 231

< 21

< 24

< 23

< 132

< 36

< 47

< 165

< 637

< 41

• Control location (a) lodine-131 by low level analysis B-33

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 6/18/2012 Common Mullein 6/18/2012 Ragweed 7/17/2012 Catalpa 7/17/2012 Burdock 7/17/2012 Common Mullein 8/13/2012 Catalpa 8/13/2012 Burdock RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 20

< 32

< 44

< 40

< 55

< 57

< 45 574 +/- 307 5743 +/- 738

< 27

< 26

< 69

< 38

< 67

< 30

< 34

< 23

< 271

< 60

< 23

< 26

< 112

<41

< 45

< 173

< 655

< 56 2132 +/- 320 7455 +/- 765

< 27

< 24

< 70

< 40

< 65

< 33

< 46

< 24

< 239

< 50

< 25

< 26

< 165

< 16

< 49

< 178

< 591

< 46 278 +/- 96 1169 +/- 173

<8

<8

< 20

<9

< 20

<9

< 13

< 10

< 65

< 18

<9

<9

< 43

< 10

< 14

< 53

< 194

< 19 992 +/-

7807 +/-

172 519 16 16 44 23 35 17 31 17 119 31 14 2166 +/- 328 5206 +/- 608

< 23

< 28

< 65

< 35

< 68

< 29

< 54

< 29

< 242

< 57

< 23

< 31

< 133

< 45

< 50

< 181

< 651

< 49 788 + 227 3746 + 444

< 21

< 19

< 49

< 23

< 50

< 22

< 32

< 20

< 203

< 37

< 22

< 23

< 109

• 29

< 33

< 127

< 460

< 42 769 +/- 234 7450 +/- 607

< 20

< 24

< 47

< 26

< 48

< 23

< 39

< 21

< 193

< 43

< 20

< 22

< 110

< 25

< 40

< 148

< 526

< 40

< 18

< 84

<21

< 30

< 109

< 416

< 32

• Control location (a) Iodine-131 by low level analysis B-34

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 8/13/2012 Common Mullein 9/10/2012 Ragweed 9/10/2012 Catalpa 9/10/2012 Common Mullein 10/9/2012 Ragweed 10/9/2012 Catalpa 10/9/2012 Common Mullein RADIOCHEMICAL 1-131 (a)

GAMMA

< 45

< 38

< 34

< 36

< 51

< 54

< 47 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-1 34 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 517 +/- 162 5529 +/- 450

< 17

< 17

<41

<21

< 38

< 17

< 29

< 18

< 156

< 38

< 15

< 17

< 85

< 29

< 29

< 112

< 389

< 28 3712 +/-

5339 +/-

196 317 11 11 27 15 29 13 21 12 109 26 11 12 68 18 24 89 347 23 1347 +/-

3326 +/-

146 301 13 14 30 17 29 14 22 11 101 28 13 13 68 19 24 86 333 23 645 +/-

5215 +/-

143 382 13 16 36 19 35 16 26 15 127 32 15 3939 +/- 528 4850 +/- 744

< 38

< 42

< 90

< 40

< 73

< 40

< 70

< 36

< 301

< 66

< 36

< 34

< 201

< 52

< 45

< 187

< 764

< 53 1785 +/- 382 4066 +/- 581

< 31

< 31

< 64

< 34

< 69

< 29

< 54

< 30

< 245

< 62

< 30

< 30

< 176

< 47

< 49

< 192

< 640

< 53 2168 +/- 347 5204 +/- 650

< 30

< 24

< 56

< 35

< 72

< 30

< 44

< 29

< 242

< 64

< 24

< 30

< 169

< 43

< 49

< 166

< 596

< 59

< 14

< 74

<21

< 25

< 90

< 335

< 26

• Control location (a) lodine-131 by low level analysis B-35

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 4/30/2012 Motherswort 4/30/2012 Ragweed 4/30/2012 Common Mullein 5/21/2012 Wild Grape 5/21/2012 Ragweed 5/21/2012 Cottonwood 6/18/2012 Burdock RADIOCHEMICAL 1-131 (a)

GAMMA

< 36 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 198 +/-

5147 +/-

121 395 22 22 54 27 54 23 41 24 202 44 24 24 121 30 38 151 468 36 680 +/- 191 8637 +/- 531

< 27

< 28

< 65

< 35

< 66

< 29

< 51

< 28

< 237

< 54

< 29

< 30

< 138

< 33

< 49

< 201

< 621

< 49 608 +/- 162 5291 +/- 446

< 23

< 25

< 59

< 33

< 62

< 24

< 43

< 24

< 186

< 44

< 23

< 24

< 114

< 30

< 39

< 143

< 497

< 39 826 +/- 190 3307 +/- 397

< 19

< 17

< 46

< 25

< 47

< 18

< 34

< 21

< 166

< 38

< 17

< 19

< 98

< 26

< 32

< 119

< 416

< 30 1088 +/- 220 7667 +/- 561

< 19

< 23

< 49

< 26

< 47

< 24

<41

< 23

< 199

< 45

<21

< 20

< 122

< 27

< 37

< 133

< 478

< 39 552 +/- 205 5068 +/- 581

< 23

< 23

< 67

< 35

< 64

< 28

< 40

< 21

< 242

< 51

< 26

< 27

< 156

< 39

< 32

< 113

< 464

< 37 1602 +/-

9207 +/-

348 824 22 27 78 47 65 32 60 31 283 59 27 30 152 50 47 181 693 40 (a) lodine-131 by low level analysis B-36

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 6/18/2012 Ragweed 6/18/2012 Catalpa 7/16/2012 Wild Rasberry 7/16/2012 Ragweed 7/16/2012 Catalpa 8/13/2012 Burdock 8/13/2012 Ragweed RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 34

< 29

< 58

< 55

< 51

< 43

< 56 1007 +/- 243 6408 +/- 717

< 25

<31

< 58

<41

< 67

< 26

< 49

< 24

< 171

< 49

< 23

< 30

< 129

< 36

< 38

< 157

< 525

< 41 568 +/-

3056 +/-

183 468 20 23 45 24 53 25 36 23 211 52 22 20 119 27 40 157 564 44 1394 +/- 304 4428 +/- 550

< 28

< 30

< 54

< 33

< 61

< 29

< 51

< 26

< 236

< 61

< 28

< 26

< 159

< 39

< 51

< 175

< 530

< 52 1612 +/- 207 7673 +/- 455

< 15

< 17

<41

< 22

<41

< 15

< 30

< 16

< 137

< 35

< 16

< 17

< 95

< 20

< 33

< 119

< 375

< 34 815 +/- 189 2603 +/- 490

< 22

< 25

< 56

< 24

< 56

< 27

< 42

< 25

< 205

< 42

< 22

< 23

< 140

< 37

< 30

< 99

< 401

< 32 1586 +/- 231 7560 +/- 525

< 17

< 18

< 40

< 26

< 39

< 17

< 31

< 16

< 148

< 35

< 13

< 16

< 84

< 26

< 27

< 108

< 361

< 32 2378 +/- 246 6199 +/- 464

< 18

< 18

< 48

< 23

<41

< 21

< 31

< 21

< 164

< 40

< 17

< 19

< 100

< 29

< 35

< 123

< 462

< 36 (a) lodine-131 by low level analysis B-37

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 8/13/2012 9/10/2012 Bittersweet Common Mullein 9/10/2012 Ragweed 9/10/2012 Catalpa 10/9/2012 Common Mullein 10/9/2012 Ragweed 10/9/2012 Catapalpa RADIOCHEMICAL 1-131 (a)

GAMMA

< 49

< 26

< 29

< 40

< 52

< 37

< 55 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 1494 +/- 296 4670 +/- 590

< 24

< 23

< 62

< 28

< 57

< 31

< 46

< 31

< 223

< 47

<21

< 24

< 155

< 34

< 45

< 163

< 619

< 44 2221 +/- 184 4172 +/- 316

< 13

< 13

< 32

< 18

< 31

< 15

< 23

< 14

< 121

< 31

< 12 44 +/- 17

< 67

< 21

< 23

< 88

< 288

< 23 2175 +/- 249 5079 +/- 469

< 22

< 22

< 46

< 27

< 49

< 22

<41

< 24

< 194

< 47

< 18

< 22

< 115

< 40

< 38

< 133

< 501

< 39 2122 +/- 167 2763 +/- 240

< 11

< 13

< 24

< 13

< 25

< 13

< 22

< 13

< 104

< 26

< 11

< 13

< 63

< 20

< 22

< 79

< 285

< 26 2226 +/-

5901 +/-

404 739 32 31 72 28 71 29 50 34 250 64 29 35 185 58 53 208 741 68 4024 +/- 383 6038 +/- 698

< 29

< 25

< 62

< 36

< 59

< 25

< 39

< 30

< 271

< 60

< 25

< 28

< 154

< 35

< 48

< 195

< 513

< 51 4691 +/- 424 1271 +/- 418

< 23

< 25

< 46

< 31

< 48

< 27

< 37

< 27

< 217

< 62

< 21

< 26

< 127

< 31

< 47

< 190

< 667

< 55 (a) lodine-131 by low level analysis B-38

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 4/30/2012 Motherwort 4/30/2012 Ragweed 4/30/2012 Common Mullein 5/21/2012 Wild Grape 5/21/2012 Ragweed 5/21/2012 Bittersweet 6/18/2012 Burdock RADIOCHEMICAL 1-131 (a)

GAMMA

< 30 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 261 6298 +/- 552

< 31

< 33

< 68

< 39

< 78

< 34

< 52

< 32

< 303

< 60

< 27

< 27

< 158

< 40

< 53

< 209

< 639

< 52 354 +/- 159 7830 +/- 512

< 17

< 18

< 44

< 24

< 45

< 18

< 26

< 19

< 163

< 33

< 15

< 17

< 86

< 21

< 30

< 105

< 378

< 30 306 +/- 125 4125 +/- 354

< 20

< 20

< 46

< 24

< 46

< 20

< 38

< 23

< 179

< 41

< 21

< 22

< 100

< 25

< 37

< 147

< 469

< 35 895 +/- 203 3540 +/- 409

< 22

<21

< 55

< 27

< 48

< 25

< 39

< 23

< 195

< 47

< 21

< 20

< 108

< 22

< 40

< 143

< 430

< 41 1034 +/- 215 7336 +/- 607

<21

< 23

< 58

< 25

< 50

< 25

< 43

< 24

< 173

< 54

<21

< 25

< 134

< 30

< 43

< 159

< 561

< 47 477 +/- 170 3390 +/- 466

< 15

< 19

< 47

< 21

< 44

< 20

< 33

< 21

< 164

< 36

< 18

< 19

< 101

< 21

< 33

< 121

< 438

< 37 936 +/- 325 8266 +/- 947

< 44

< 33

< 110

< 47

< 87

< 33

< 57

< 36

< 308

< 60

< 30

< 28

< 188

< 30

< 43

< 157

< 633

< 61 (a) lodine-131 by low level analysis B-39

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 6/18/2012 Ragweed 6/18/2012 Common Mullein 7/16/2012 Burdock 7/16/2012 Wild Mustard 7/16/2012 Common Mullein 8/13/2012 Ragweed 8/13/2012 Wild Grape RADIOCHEMICAL 1-131 (a)

GAMMA

< 34

< 38

< 60

< 52

< 54

< 41

< 37 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-1 34 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 1513 +/- 262 6510 +/- 586

< 23

< 22

< 57

< 35

< 53

< 27

< 43

< 24

< 197

< 54

< 23

< 24

< 130

< 33

< 39

< 151

< 512

< 35 353 +/- 206 5363 +/- 735

< 22

< 24

< 59

< 25

< 65

< 25

< 40

< 27

< 212

< 56

< 21

< 29

< 113

< 47

< 40

< 150

< 615

< 51 1602 +/- 198 8627 +/- 486

< 17

< 15

< 42

< 22

< 40

< 17

< 27

< 17

< 140

< 32

< 15

< 18

< 84

< 23

< 26

< 100

< 320

< 25 556 +/-

8788 +/-

185 584 22 23 55 27 47 24 43 25 205 51 21 20 124 24 45 164 508 40 1131 +

4271 +

258 475 18 18 36 24 41 15 34 21 153 38 17 18 104 27 29 127 428 30 2698 +/- 298 6373 +/- 523

< 21

< 20

< 56

< 27

< 49

< 25

< 42

< 23

< 174

< 45

< 21

< 22

< 119

< 27

< 35

< 149

< 448

< 37 775 +/- 248 3550 +/- 465

< 25

< 24

< 55

< 25

< 53

< 29

<41

< 26

< 190

< 47

< 23

< 26

< 129

< 39

< 48

< 179

< 622

< 44 (a) Iodine-131 by low level analysis B-40

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 8/13/2012 Bittersweet 9/10/2012 Ragweed 9/10/2012 Cottonwood 9/10/2012 Burdock 10/9/2012 Ragweed 10/9/2012 Cottonwood 10/9/2012 Common Mullein RADIOCHEMICAL 1-131 (a)

GAMMA

< 46

< 37

< 44

<41

< 53

< 51

< 42 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 1224 +/- 219 3893 +/- 500

< 23

< 27

< 54

< 27

< 50

< 24

< 38

< 22

< 198

< 51

<21

< 27

< 121

< 29

< 37

< 139

< 536

<41 1965 +/- 269 4703 +/- 467

< 26

< 24

< 63

< 27

< 50

< 26

< 45

< 24

< 210

< 43

< 21

< 25

< 125

< 39

< 30

< 108

< 408

< 36 1482 +/- 261 5284 +/- 475

<19

< 20

< 46

< 24

< 39

< 19

< 35

<21

< 180

< 44

< 17

< 20

< 112

< 21

< 37

< 129

< 446

< 34 2202 +/-

10520 +/-

191 459 15 16 37 20 35 16 27 16 125 32 15 16 84 19 27 105 368 26 3724 +/-

5632 +/-

470 683 32 29 73 38 57 28 54 31 260 65 29 32 174 57 48 202 637 65 1471 +/- 350 5022 +/- 755

< 28

< 30

< 73

< 33

< 77

< 25

< 59

< 30

< 241

< 59

< 25

< 27

< 162

< 53

< 45

< 170

< 664

< 48 1367 +/- 293 4490 +/- 567

< 20

< 22

< 54

< 33

< 56

< 21

< 36

< 21

< 183

< 44

< 18

< 22

< 135

< 24

< 34

< 134

< 497

< 44 (a) lodine-131 by low level analysis B-41

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Plant Inlet Hudson River Intake 9*

DATE 1/30/2012 2/27/2012 3/26/2012 5/1/2012 5/29/2012 6/25/2012 RADIOCHEMICAL H-3 (a)

< 174 GAMMA K-40 Mn-54 Co-58 Fe-59

.Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 165 6

6 15 6

14 7

10 6

64 9

6 7

26 6

11 48 165 31 11 102 5

5 9

4 9

5 8

5 39 7

5 5

21 7

8 39 119 18 10

< 68

<7

<7

< 16

<7

< 13

<7

< 12

<7

< 64

< 14

<6

<8

< 38

.< 11

< 10

< 39

< 133

< 23

<11 81 7

8 18 9

19 9

16 9

72 14 9

10 39 15 12 48 163 35 13

< 71

<5

<5

< 12

<8

< 10

<8

< 11

<7

< 55

<9

<6

<7

< 29

<12

<9

< 40

< 140

< 29

< 10

< 180

< 99

<5

<6

< 11

<4

<9

<5

<11

<6

< 52

< 12

<5

<6

< 24

<9

< 12

< 43

< 148

<21

< 12

• Control location (a) Quarterly composite B-42

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Plant Inlet Hudson River Intake 9*

DATE 7/30/2012 8/27/2012 9/24/2012 10/30/12 11/26/12 1/2/2013 RADIOCHEMICAL H-3 (a)

< 193

< 187 GAMMA K-40

< 48

< 73

< 51

< 80

< 85

< 33 Mn-54

<6

<3

<6

<3

<9

<4 Co-58

<5

<3

<7

<4

< 10

<4 Fe-59

< 10

<7

< 15

<8

<20

<7 Co-60

<6

<4

<7

<4

< 10

<4 Zn-65

< 10

<6

< 14

<6

<20

<7 Nb-95

<6

<3

<8

<4

< 10

<4 Zr-95

< 10

< 6

< 13

< 7

< 18

< 6 Ru-103

<6

<4

<7

<5

<8

<4 Ru-106

< 48

< 33

< 65

< 37

< 63

< 33 1-131

< 10

< 7

< 10

< 7

< 20 (b)

< 7 Cs-134

<5

<3

<6

<4

< 10

<3 Cs-137

<6

<3

<7

<4

< 11

<4 Ba-140

< 28

< 19

< 30

< 19

< 55

< 18 La-140

< 9

< 7

< 11

< 6

< 19 (b)

< 6 Ce-141

< 9

< 6

< 11

< 8

< 16

< 8 Ce-144

< 37

< 24

< 40

< 31

< 59

< 30 Ra-226

< 125

< 81

< 153

< 103

< 221

< 98 Ac-228

< 22

< 13

< 34

< 15

< 34

< 14 Th-228

< 10

<7

< 12

<8

< 17

<6

• Control location (a) Quarterly composite (b) See Table B-ic B-43

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Discharge Canal 10 DATE 1/30/2012 2/27/2012 RADIOCHEMICAL 3/26/2012 617 +/- 138 5/1/2012 5/29/2012 6/25/2012 H-3 (a)

GAMMA K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228

< 191

< 10

<8

< 16

<8

< 13

<6

< 12

<7

< 84

< 12

<8

<9

< 35

< 10

< 12

< 48

< 177

< 33

< 15

< 55

<5

<4

<8

<5

<9

<5

<9

<6

< 47

<7

<4

<6

< 22

<6

<9

< 37

< 148

< 23

< 11

< 55

<5

<5

<9

<6

< 11

<5

< 10

<5

< 48

< 11

<5

<5

< 28

<8

< 11

< 45

< 147

< 16

< 13

< 46

<6

<6

< 11

<6

< 12

<6

< 10

<7

< 54

<9

<7

<6

< 30

< 10

< 11

< 45

< 131

< 22

< 10

< 143

<7

<9

< 12

<8

< 13

<7

< 13

<8

< 63

< 12

<7

<7

< 28

< 11

< 13

< 51

< 185

< 27

< 14

< 178

< 85

<6

<8

< 15

<9

< 15

<8

< 14

<8

< 61

< 12

<7

<6

< 39

< 10

< 12

<41

< 171

< 30

< 13 (a) Quarterly composite B-44

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2012 pCi/liter +/- 2 Sigma Discharge Canal 10 DATE 7/30/2012 8/27/2012 9/24/2012 10/30/12 11/26/12 1/2/2013 RADIOCHEMICAL H-3 (a)

< 193 460 +/- 150 GAMMA K-40

< 41

< 42

< 121

< 110

< 65

< 46 Mn-54

<4

<4

<5

< 5

<9

<2 Co-58

<4

<5

<5

<6

<8

<2 Fe-59

< 9

< 10

< 14

< 11

< 21

< 5 Co-60

< 4

< 5

< 6

< 6

< 8

< 2 Zn-65

< 8

< 10

< 14

< 11

< 22

< 4 Nb-95

<4

<6

<6

<6

<7

<2 Zr-95

<7

<8

<8

< 12

< 13

<4 Ru-103

<5

<5

<5

<6

<9

<2 Ru-106

< 42

< 42

< 58

< 45

< 73 (b)

< 14 1-131

<8

<9

< 11

<9

< 16

<3 Cs-134

<4

<5

<5

<5

<8

<2 Cs-137

<4

<5

<5

<6

<7

<2 Ba-140

< 21

< 26

< 31

< 27

< 59

< 10 La-140

<8

<9

< 12

<8

<9

<2 Ce-141

< 8

< 7

< 10

< 8

< 15

< 3 Ce-144

< 27

< 27

< 41

< 32

< 53

< 13 Ra-226

< 106

< 85

< 157

< 122

< 181

< 52 Ac-228

< 18

< 19

<24

<23

<27

<9 Th-228

< 9

< 8

< 10

< 10

< 14

< 5 (a) Quarterly composite (b) See Table B-ic B-45

INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2012 pCi/kg dry +/- 2 Sigma Discharge Canal 10 Off Verplanck 17 Lent's Cove 28 Cold Spring 84*

DATE 6/12/2012 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 Ce-141 Ce-144 Ra-226 Th-228

< 554 18320 +/- 1480

< 63

< 55

< 142

< 73

< 141

< 67

< 110

< 66

< 557

< 133

< 55 397 +/- 74

< 327

< 86

< 345

< 1141 853 +/- 90 9/20/2012

< 358 14850 +/- 950

< 38

< 35

< 93

< 47

< 97

< 48

< 62

< 46

< 328

< 186

< 34 234 +/- 45

< 330

< 64

< 208

< 640 282 +/- 56 6/12/2012 9/20/2012 6/8/2012 9/20/2012 6/8/2012 9/19/2012

< 762 18790 +/- 1872

< 88

< 73

< 186

< 108

< 188

< 104

< 152

< 87

< 845

< 196

< 82 269 +/- 118

< 485

< 168

< 627

< 2043 1111 +/- 133

< 740 21240 +/- 1783

< 79

< 82

< 181

< 66

< 185

< 106

< 166

< 102

< 665

< 403

< 68 270 +/- 83

< 800

< 180

< 553 2117 +/- 1292 1213 +/- 121

< 845 19520 +/- 2135

< 85

< 79

< 203

< 114

< 169

< 74

< 155

< 86

< 638

< 207

< 64

< 80

< 519

< 146

< 453

< 1676 1118 +/- 178

< 558 17940 +/- 1632

<61

< 65

< 171

< 84

< 134

< 75

< 137

< 77

< 479

< 284

< 62 250 +/- 68

< 533

< 104

< 331 2100 +/- 1082 994 +/- 97

< 501 30690 +/- 2424

< 60

< 62

< 182

< 94

< 160

< 69

< 131

< 63

< 546

< 195

< 49

< 70

< 379

< 118

< 389

< 1340 593 +/- 143

< 545 33330 +/- 1573

< 54

< 57

< 170

< 73

< 129

< 67

< 111

<71

< 476

< 302

< 51

< 59

< 592

< 121

< 355 1888 +/- 886 716 +/- 125

• Control location B-46

INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN SHORELINE SEDIMENT SAMPLES - 2012 pCi/kg dry +/- 2 Sigma Off Verplanck 17 Lent's Cove 28 Manitou Inlet 50 DATE 6/12/2012 9/18/2012 06/08/12 09/18/12 6/8/2012 9/18/2012 RADIOCHEMICAL Sr-90 GAMMA

< 36

< 46

<41

< 45

< 39

< 48 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228

< 308 14060 +/- 1062

< 37

< 35

< 70

< 43

<81

< 28

< 68

< 33

< 276

< 62

< 30 115 +/- 48

< 192

< 47

< 54

< 221

< 652

< 121 437 +/- 76

< 459 19790 +/- 1330

< 54

< 54

< 129

< 54

< 127

< 63

< 100

< 61

< 417

< 313

< 44 167 +/- 50

< 557

< 157

< 89

< 269

< 917

< 340 840 +/- 81 13070 +

588 1593 61 63 160 91 161 69 131 81 572 190 68 75 365 80 12960 +/-

324 625 1296 51 63 129 59 104 65 97 67 363 318 43 66 635 130 109 327 1222 161 77

< 307 2785 +/- 438

< 31

< 30

< 62

< 30

< 67

< 47

< 51

< 32

< 253

< 103

< 31

< 32

< 212

< 69

< 69

< 238 2216 +/- 847

< 106 382 +/- 47

< 580 14540 +/- 1127

< 54

< 63

< 137

< 68

< 140

< 95

< 117

< 76

< 460

< 349

< 50

< 58

< 612

< 220

< 130

< 355 7724 +/- 1336

< 199 784 +/- 77

< 131

< 440 3306 +/- 1665

< 189 1230 +/- 137 B-47

INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN SHORELINE SEDIMENT SAMPLES - 2012 pCi/kg dry +/- 2 Sigma White Beach 53 Cold Spring 84*

DATE 6/12/2012 9/18/2012 6/8/2012 9/18/2012 RADIOCHEMICAL Sr-90

<41

< 49

< 40

< 47 GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-106 1-131 Cs-134 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228

< 270 11310 +/- 1005

< 34

< 30

< 83

< 46

< 89

< 33

< 57

< 32

< 326

< 61

< 32

< 37

< 160

< 49

< 55

< 180

< 800

< 180 138 +/- 47

< 397 8817 +/- 825

< 37

<41

< 121

< 52

< 99

< 52

< 82

< 49

< 322

< 280

< 34

< 38

< 419

< 117

< 81

< 224 1172 +/- 765

< 181 102 +/- 49

< 463 31530 +/- 1598

< 48

< 54

< 143

< 69

< 131

< 58

< 89

< 50

< 407

< 136

< 45

< 52

< 324

< 76

< 88

< 277

< 885

< 173 620 +/- 89

< 401 33070 +/- 1582

< 47

< 45

< 137

< 64

< 107

< 47

< 94

< 52

< 340

< 235

< 39

<41

< 444

< 140

< 73

< 218

< 820

< 259 478 +/- 56

• Control location B-48

INDIAN POINT ENERGY CENTER TABLE B-17 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2012 pCi/kg wet +/- 2 Sigma Off Verplanck 17 Cold Spring 84*

DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-1 06 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Ac-228 Th-228 6/12/2012 Myrophyllium 383 +/- 92 2701 +/- 236

< 11

< 11

< 25

< 12

< 25

< 12

< 20

< 11

< 91

< 24

< 10

< 12

< 58

< 18

< 20

< 76

< 238

< 61 108 +/- 24 9/20/2012 Myrophyllium 338 +/- 123 2069 +/- 218

< 12

< 14

< 29

< 14

< 27

< 14

< 26

< 14

< 110

< 48

< 13

< 15

< 103

< 24

< 28

< 97

< 303

< 67 95 +/- 18 6/8/2012 Myrophyllium

< 100 2264 + 309

< 13

< 13

< 31

< 13

< 32

< 16

< 22

< 13

< 111

< 36

< 11

< 17

< 91

< 17

< 20

< 74

< 274

< 46 54 + 26 9/19/2012 Myrophyllium 206 + 117 1332 + 218

<9

< 11

< 29

• 16

< 26

< 12

< 25

< 13

< 99

< 44

< 10

< 13

< 95

< 28

< 19

< 65 355 + 196

< 44

< 19

• Control location B-49

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH IINVERTEBRATES - 2012 pCi/kg wet +/-2 Sigma Roseton 23*

DATE 5/1/2012 American Eel 05/11/12 Sunfish 5/17/2012 White Perch 5/17/2012 Catfish 5/24/2012 Blue Crab 6/15/2012 Striped Bass RADIOCHEMICAL Ni-63 Sr-90 GAMMA

< 39

< 3.4

< 43

< 3.0

< 47

< 3.2

< 36

< 3.3

< 53

< 3.2

< 48 a

Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zrz95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 875 3207 +/- 715

< 45

< 58

< 234

< 55

< 97

< 94

< 151

< 130

< 425

< 28030

< 36

< 38

< 8208

< 1937

< 239

< 275

< 927

< 81

< 945 3782 +/- 793

< 66

< 88

< 225

< 55

< 123

< 100

< 142

< 154

< 471

< 12820

< 48

< 55

< 6173

< 2161

< 285

< 287

< 1232

< 85 2285 +

806 925 45 60 205 52 85 96 151 110 380 7090 48 45 3497 1092 228 345 1064 87 4239 +/-

186+/-

882 937 56 94 257 63 121 111 139 116 466 8920 45 62 4327 1166 196 294 1111 118

< 654 2624 +/- 679

< 44

< 67

< 189

< 36

< 127

< 71

< 123

< 78

< 335

< 3440

< 40

< 45

< 2285

< 942

< 141

< 215

< 857

< 81

< 359 3327 +/- 911

< 37

< 35

< 88

< 36

< 61

< 46

< 72

< 49

< 318

< 420

< 34

< 33

< 596

< 140

< 79

< 201

< 645 168 +/- 83 a Not enough sample for Sr-90 analysis B-50

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH /INVERTEBRATES

- 2012 pCi/kg wet +/-2 Sigma Roseton 23*

DATE 7/25/2012 Striped Bass 8/3/2012 American Eel 8/8/2012 Blue Crab 8/8/2012 Catfish 8/8/2012 White Perch 08/15/12 Sunfish RADIOCHEMICAL Ni-63 Sr-90 GAMMA

<41

< 4.4

< 35

< 4.6

< 74

<2.1

< 35

< 2.0

< 43

< 3.9

< 44

< 2.5 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-1 06 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 758 4108 +/- 1187

< 69

< 81

< 238

< 64

< 135

< 103

< 178

< 142

< 431

< 3706

< 57

< 53

< 2494

< 869

< 223

< 369

< 1523

< 150

< 800 2408 +/- 914

< 53

< 61

< 120

< 50

< 115

< 79

< 129

< 104

< 557

< 1510

< 53

< 53

< 1351

< 440

< 154

< 316

< 1257

< 77

< 507 2339 +/- 565

< 46

< 60

< 91

< 42

< 65

< 68

< 95

< 77

< 376

< 845

< 37

< 46

< 942

< 218

< 182

< 409

< 1285

< 110

< 689 2788 +/- 924

< 61

< 69

< 122

< 65

< 126

< 89

< 123

< 97

< 499

< 1260

< 44

< 68

< 1112

< 284

< 200

< 494

< 1748

< 137

< 937 2968 +/- 1072

< 74

< 93

< 241

< 83

< 156

< 109

< 195

< 140

< 850

< 1632

< 77

< 88

< 1609

< 599

< 227

< 563

< 1863

< 134

< 575 4123 +/- 860

< 51

< 63

< 139

< 50

< 129

< 71

< 84

< 71

< 459

< 580

< 46

< 58

< 735

< 189

< 107

< 283

< 1009

< 98 B-51

INDIAN POINT ENERGY CENTER TABLE 8-18 RADIONUCLIDES IN FISH /INVERTEBRATES

- 2012 pCi/kg wet +/-2 Sigma Downstream 25 DATE 4/30/2012 Striped Bass 5/3/2012 American Eel 5/3/2012 Catfish 5/3/2012 White Perch 5/3/2012 Sunfish 6/13/2012 Blue Crab RADIOCHEMICAL Ni-63 Sr-90 GAMMA

< 35

< 3.9

< 42

< 3.9

< 35

< 3.2

< 54

< 3.7

< 45

< 3.4

< 64 a

Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228

< 854 4593 +/- 1028

<41

< 83

< 187

< 30

< 122

< 54

< 148

< 121

< 451

< 27100

< 45

< 46

< 8424

< 1278

< 264

< 304

< 1059

< 89

< 1125 2609 +/- 980

< 49

< 79

< 199

< 64

< 168

< 100

< 147

< 175

< 454

< 26620

< 46

< 43

< 9292

< 2346

< 251

< 308

< 1111

< 93 2714 +/-

622 780 38 59 232 35 99 58 114 103 322 18500 32 38 7632 1333 207 231 769 67 3679 +/-

882 841 50 79 232 50 106 99 145 149 474 27370 48 53 7838 1649 311 327 1130 100

< 910 2844 +/- 932

< 43

< 75

< 200

< 44

< 75

< 65

< 129

< 145

< 342

< 18690

< 40

< 54

< 6751

< 2351

< 269

< 315

< 982

< 79

< 815 4511 +/- 1925

< 72

< 90

< 198

< 70

< 149

< 96

< 169

< 114

< 645

< 1082

< 73

< 71

< 1371

< 366

< 168

< 436

< 1811

< 166 a Not enough sample for Sr-90 analysis B-52

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH /INVERTEBRATES

- 2012 pCi/kg wet +/-2 Sigma Downstream 25 DATE 8/1/2012 American Eel 8/14/2012 White Perch 8/14/2012 Catfish 8/15/2012 Blue Crab 8/16/2012 Sunfish RADIOCHEMICAL Ni-63 Sr-90

< 34

< 5.0

< 44

< 5.0

< 36

< 4.9

< 70

< 3.6

< 38

< 4.6 GAMMA Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 1-131 Cs-134 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 Th-228 2541 +/-

555 650 38 58 133 40 96 65 93 73 376 1520 37 44 1260 319 124 260 861 72

< 822 3373 +/- 919

< 76

< 73

< 182

< 73

< 129

< 83

< 137

< 91

< 590

< 775

< 68

< 58

< 1077

< 233

< 182

< 502

< 1567

< 119

< 434 3597 +/- 739

< 46

< 57

< 145

< 52

< 96

< 59

< 108

< 63

< 370

< 438

< 44

< 45

< 620

< 199

< 87

< 216

< 824

< 72

< 399 2740 +/- 682

< 46

< 61

< 107

< 45

< 70

< 60

< 85

< 59

< 338

< 423

< 40

< 46

< 559

< 142

< 84

< 238

< 920

< 77

< 667 3318 +/- 1011

< 62

< 75

< 173

< 49

< 138

< 80

< 140

< 87

< 537

< 548

< 62

< 71

< 816

< 308

< 125

< 324

< 1311

< 105 B-53

Table B-19 LAND USE CENSUS - RESIDENCE and MILCH ANIMAL RESULTS 2012 The 2012 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-54

TABLE B-20 LAND USE CENSUS 2012 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES 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 Sector Compass Point (meters)

(meters)

(meters)

Census 1

N RIVER RIVER 1788 41 River Road Tomkins Cove 2

NNE RIVER RIVER 3111 Chateau Rive Apts. John St. Peekskill 3

NE 550 636 1907 211 Viewpoint Terrace, Peekskill 4

ENE 600 775 1478 1018 Lower South St. Peekskill 5

E 662 785 1371 1103 Lower South St. Peekskill 6

ESE 569 622 715 461 Broadway Buchanan 7

SE 553 564 1168 223 First St. Buchanan 8

SSE 569 551 1240 5 Pheasant's Run Buchanan 9

S 700 566 1133 320 Broadway Verplanck 10 SSW 755 480 1574 240 Eleventh St. Verplanck 11 SW 544 350 3016 8 Spring St. Tomkins Cove 12 WSW RIVER RIVER 2170 9 West Shore Dr. Tomkins Cove 13 W

RIVER RIVER 1919 712 Rt. 9W Tomkins Cove 14 WNW RIVER RIVER 1752 770 Rt. 9W Tomkins Cove 15 NW RIVER RIVER 1693 807 Rt. 9W Tomkins Cove 16 NNW RIVER RIVER 1609 4 River Rd. Tomkins Cove B-55

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 2012 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

2002-2012 Average Quarterly Dose (mR/Quarter)

Control Year Inner Ring Outer Ring Location 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 2012 13.2 13.6 12.3 Historical Average 14.1 14.2 15.6 2002-2011 C-2

FIGURE C-1 DIRECT RADIATION, ANNUAL

SUMMARY

2002-2012 40.0 35.0 30.0 25.0 t

E 20.0 15.0 10.0 5.0 0.0 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 C-3

TABLE C-2 RADIONUCLIDES IN AIR 2002-2012 (pCi/m 3)

Gross Beta Cs-1 37 All Indicator Control All Indicator Control Locations Location Locations Location 2002 0.02 0.02

< MDC

<MDC 2003 0.01 0.01

< MDC

<MDC 2004 0.01 0.01

< MDC

<MDC 2005 0.02 0.02

< MDC

<MDC 2006 0.01 0.01

< MDC

<MDC 2007 0.01 0.01

< MDC

<MDC 2008 0.01 0.01

< MDC

<MDC 2009 0.01 0.01

< MDC

<MDC 2010 0.01 0.01

< MDC

<MDC 2011 0.014 0.014

< MDC

<MDC 2012 0.014 0.014

< MDC

<MDC Hist09. iclaili, Average isorca A.erag 0.01 0.01

< MDC

<MDC 2002-2011 The Minimum Detectable Concentration (MDC) is less than the ODCM required LLD.

<MDC indicates no positive values were detected C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 2002-2012 0.05 WAII Indicator Locations

-Control Location 0.04 0.03 CL 0.02 0.01 0.00

ý,00, 00ý I

% 10 01ý0/0 01 OF zX/

iZ-i i r i

f 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012

• Includes ODCM and non-ODCM indicator locations.

Gross Beta ODCM required LLD = 0.01 pCi/m 3 C-5

TABLE C-3 BROAD LEAF VEGETATION - Cs-1 37 2002-2012 (pCi/Kg, wet)

Cs-1 37 Year Indicator Control 2002 14 16 2003 14

< MDC 2004 10

< MDC 2005

< MDC

< MDC 2006

< MDC

< MDC 2007

< MDC

< MDC 2008

< MDC

< MDC 2009

< MDC

< MDC 2010 31

< MDC 2011

< MDC

< MDC 2012 44

< MDC Historical Average 17 16 2002-2011 The Minimum Detectable Concentration (MDC) is less than the ODCM required LLD.

<MDC indicates no positive values were detected C-6

FIGURE C-3 BROAD LEAF VEGETATION - Cs-137 2002 -2012 100 80 60 C.,

40 20 0

2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 ODCM required LLD = 80 pCi/Kg, wet C-7

TABLE C-4 RADIONUCLIDES IN HUDSON RIVER WATER 2002-2012 (pCi/L)

Tritium (H-3)

Cs-1 37 Year Inlet Discharge Inlet Discharge 2002 432 562

< MDC

< MDC 2003

< MDC

< MDC

< MDC

< MDC 2004

< MDC 553

< MDC

< MDC 2005

< MDC 618

< MDC

< MDC 2006

< MDC 386

< MDC

< MDC 2007

< MDC

< MDC

< MDC

< MDC 2008

< MDC

< MDC

< MDC

< MDC 2009

< MDC

< MDC

< MDC

< MDC 2010 428

< MDC

< MDC

< MDC 2011

< MDC 661

< MDC

< MDC 2012

< MDC 539

< MDC

< MDC Historical Average 430 556

< MDC

< MDC

.2002-2011 The Minimum Detectable Concentration (MDC) is less than the ODCM required LLD.

<MDC indicates no positive values were detected C-8

FIGURE C-4 RADIONUCLIDES IN HUDSON RIVER WATER 2002-2012 2000 U Inlet (H-3) 1800

• Discharge (H-3) 1600 1400 1200 1000 800 600 400 200 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Tritium ODCM required LLD = 3000 pCi/L C-9

TABLE C-5 RIVER WATER - Discharge Area - Tritium REMP vs. EFFLUENT (pCi/liter)

Year REMP*

EFFLUENT **

1Q 2010

< 403 959 2Q 2010

< 397 239 3Q 2010

< 409 261 4Q 2010

< 408 796 1Q 2911 661 2192 2Q 2011

< 424 400 3Q 2011

< 412 493 4Q 2011

< 182 389 1Q 2102 617 2186 2Q 2012

< 178 394 3Q 2012

< 193 489 4Q 2012 460 860 Three Year Average 639 800 2010-2012

• Sample from mixing zone, expected to be less than average activity in the discharge canal

• • Based upon Effluent Report data, average activity in the discharge canal calculated from the total H-3 discharged/total dilution flow C-10

FIGURE C-5 REVER WATER - DISCHARGE AREA - TRITIUM REMP vs. EFFLUENT (pCi/liter) 2200 2000 1800 1600 1400 1200 c3 1000 0.

800 600 400 200 0

• REMP (H-3)

N EFFLUENT (H-3) 1Q2010 2Q2010 3Q2010 4Q2010 1Q2911 2Q2011 3Q2011 4Q2011 1Q2102 202012 3Q2012 4Q2012 C-1l

TABLE C-6 RADIONUCLIDES IN SHORELINE SOIL 2002 -2012 (pCi/kg, dry)

Cs-1 34 Cs-1 37 Year Indicator Control Indicator Control 2002

< MDC

< MDC 221 238 2003

< MDC

< MDC 124 73.

2004

< MDC

< MDC 104 138 2005

< MDC

< MDC 156 36 2006

< MDC

< MDC 120

< MDC 2007

< MDC

< MDC 190

< MDC 2008

< MDC

< MDC 187

< MDC 2009

< MDC

< MDC 149

< MDC 2010

< MDC

< MDC 154 63 2011

< MDC

< MDC 108

< MDC 2012

< MDC

< MDC 141

< MDC Historical Average

< MDC

< MDC 150 110 2002-2011 The Minimum Detectable Concentration (MDC) is less than the ODCM required LLD.

<MDC indicates no positive values were detected C-12

FIGURE C-6 RADIONUCLIDES IN SHORELINE SOIL 2002 to 2012 750 650 550 450 350 C.

250 150 50 2002 2003 2004

-50 Cs-1 34 ODCM required LLD = 150 pCi/Kg, dry Cs-1 37 ODCM required LLD = 175 pCi/Kg, dry C-13

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX D INTERLABORATORY COMPARISON PROGRAM This section presents the results of the interlaboratory comparison program for the 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 Pro-gram Description Teledyne Brown Engineering Environmental Services Comparison Programs The Teledyne Brown Engineering Environmental Services participates in several interlaboratory comparison programs.

These programs include sample media for which samples are routinely collected and for which comparison samples are commercially available.

Participation in these interlaboratory comparison programs ensure 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, Teledyne Brown Engineering Environmental Services has engaged the following programs:

" Eckert & Ziegler Analytics Environmental Radioactivity Cross Check Program

" Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP)

" Environmental Resource Associates (ERA) Cross Check Program These programs supply sample media as blind samples (typically spikes), which contain certified levels of radioactivity unknown to the analysis laboratory.

These samples are prepared and analyzed by the Teledyne Brown Engineering Environmental Services using standard laboratory procedures. Each program issues a statistical summary report of the results.

Teledyne Brown Engineering Environmental Services uses predetermined acceptance criteria methodology for evaluating its laboratory performance.

Teledyne Brown Engineering Environmental Services 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 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.2.1 Analytics 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 OR E!INRATI

-RATIO OF AGRiEEMENT.

< 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 QAIQC program report when results are unacceptable.

D.2.2 ERA and MAPEP Sample Result Evaluation Both these programs supply an acceptance range for evaluating the results.

D.3 Program Results Summary The Interlaboratory Comparison Program numerical results are summarized in the following tables.

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

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

March 2012 E10066 E10067 E1 0069 E10068 E10070 June 2012 E10198 Milk Sr-89 Sr-90 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 Milk Sr-89 Sr-90 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 101 94.8 pCi/L 11.7 13.5 1.07 A

0.87 A

pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 87.5 92.5 247 260 435 436 133 149 156 159 127 132 F

190 195 179 168 327 333 274 279 F

167 164 310 276 107 94.5 109 101 87.6 83.5 133 123 113 106 226 210 185 176 pCi 92.8 94.2 pCi/L 1800 1570 pCi/L 86.1 99.8 pCi/L 9.2 12.7 0.95 0.95 1.00 0.89 0.98 0.96 0.97 1.07 0.98 0.98 1.02 1.12 1.13 1.08 1.05 1.08 1.07 1.08 1.05 0.99 1.15 0.86 0.72 0.89 0.89 0.98 0.91 0.97 0.97 0.98 1.01 0.97 0.96 0.97 1.00 1.04 1.06 1.01 0.98 1.07 0.99 1.04 F

F F

F F

F p.

F 7

F A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A W

E10199 E10201 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 88.9 99.7 72.8 82.2 394 402 159 174 206 212 89.5 92.3 129 132 129 128 193 199 342 355 73.2 75.1 367 366 165 159 205 193 84.7 84.2 118 121 125 117 181 182 338 324 E10200 Charcoal 1-131 pCi 101 96.6 1.05 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 Eveluation (d)

June 2012 E10202 September 2012 E10296 E10297 E10299 E10298 E 10300 December2012 E10334 Water Fe-55 Milk Sr-89 Sr-90 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 Milk Sr-89 Sr-90 Milk 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 1890 1580 pCi/L 106 99.6 pCi/L 13.6 16.0 1.20 A

1.06 A

0.85 A

pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 89.8 99.6 r

160 164 230 248 101 108 174 174 97.2 100 188 196 159 152 195 192 155 152 145 135 219 205 94.1 89.4 140 144 88.3 83.0 173 162 136 125 165 159 133 125 pCi 95.5 97.2 pCi/L 1630 1900 pCi/L 101 96.6 pCi/L 11.3 13.8 0.90 0.98 0.93 0.94 1.00 0.97 0.96 1.05 1.02 1.02 1.07 1.07 1.05 0.97 1.06 1.07 1.09 1.04 1.06 0.98 0.86 1.05 0.82 1.03 1.03 1.07 0.95 0.97 0.96 1.00 1.07 1.02 1.01 1.04 1.10 1.02 0.99 1.01 1.05 0.94 0.92 1.08 r

F F

F r

r A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A E 10335 E 10337A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 93.1 90.0 52.5 51.0 373 348 157 165 113 117 94.1 98.5 116 116 124 116 190 186 172 170 51.8 49.6 372 338 165 161 113 114 96.5 95.8 118 112 105 112 166 181 179 165

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 Eveluation (d)

December2012 E10336 Charcoal 1-131 pCi 73.1 72.7 1.01 A

E10333 Water Fe-55 pCi/L 1550 1750 0.89 A

(a) Teledyne Brown Engineering reported result.

(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation based on TBE intemal QC limits:

A= Acceptable. Reported result falls within ratio limits 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 2)

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

Range Evaluation (c)

March 2012 12-MaW26 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 12-GrW26 Water Gr-A Gr-B 12-MaS26 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/L

-0.0045 (1)

Bq/L 37.5 39.9 27.9-51.9 Bq/L 30.8 32.9 23.0 -42.8 Bq/L 22.4 23.72 16.60 - 30.84 Bq/L 456 437 306 - 568 Bq/L 31.0 31.8 22.3-41.3 Bq/L 144 142 99-185 Bq/L

-0.0084 (1)

Bq/L

-0.369 (1)

Bq/L 2.06 2.14 0.64 - 3.64 Bq/L 7.48 6.36 3.18-9.54 Bq/kg 831 828 580- 1076 Bq/kg 0.145 (1)

Bq/kg 1270 1179 825-1533 Bq/kg 7.61 1.56 (2)

Bq/kg 634 558 391 - 725 Bq/kg 1690 1491 1044-1938 Bq/kg 328 392 274 - 540 Bqlkg 753 642 449 - 835 Bq/sample 2.31 2.38 1.67-3.09 Bq/sample 2.15 1.79 1.25-2.33 Bq/sample -0.0701 (1)

Bq/sample 2.62 2.182 1.527 - 2.837 Bq/sample 4.13 3.24 2.27-4.21 Bq/sample 0.0185 (1)

Bq/sample 4.19 2.99 2.09 -3.89 12-RdF26 12-GrF26 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 A

A A

A A

A A

A A

A A

A A

A N (3)

A A

A A

A W

A W

W A

N (3)

A A

A A

W A

A A

A A

A A

A A

A A

N (4)

A AP Gr-A Bq/sample 0.365 1.2 Gr-B Bq/sample 2.31 2.4 0.4-2.0 1.2-3.6 12-RdV26 Vegetation Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 September 2012 12-MaW27 Water Cs-134 Cs-137 Co-57 CO-60 H-3 Mn-54 K-40 Sr-90 Zn-65 12-GrW27 Water Gr-A Gr-B Bq/sample 8.72 8.43 5.90 - 10.96 Bq/sample 0.0424 (1)

Bq/sample 15.5 12.0 8.4 - 15.6 Bq/sample 6.80 6.05 4.24 - 7.87 Bq/sample 0.0057 (1)

Bq/sample 2.24 2.11 1.48 -2.74 Bq/sample 10.5 8.90 6.23-11.57 Bq/L 21.4 23.2 16.2 - 30.2 Bq/L 17.0 16.7 11.7-21.7 Bq/L 28.7 29.3 20.5 -38.1 Bq/L 0.179 (1)

Bq/L 387 334 234 -434 Bq/L 18.1 17.8 12.5-23.1 Bq/L 139 134 94-174 Bq/L 19.6 12.2 8.5-15.9 Bq/L 27.2 25.9 18.1 -33.7 Bq/L 0.966 1.79 0.54-3.04 Bq/L 10.0 9.1 4.6-13.7 A

A

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)

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

Range Evaluation (c)

September 2012 12-MaS27 Soil Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg 880 939 657-1221 Bq/kg 1220 1150 805-1495 Bq/kg 1330 1316 921-1711 Bq/kg 552 531 372 - 690 Bq/kg 1000 920 644-1196 Bq/kg 674 632 442 - 822 Bq/kg 528 508 356 - 660 Bq/kg 665 606 424 - 788 12-RdF27 12-GrF27 12-RdV27 AP Cs-134 Bq/sample 2.760 2.74 1.92-3.56 Cs-137 Bq/sample 0.0415 (1)

Co-57 Bq/sample 2.00 191.00 1.34-2.48 Co-60 Bq/sample 1.78 1.728 1.210 - 2.246 Mn-54 Bq/sample 2.40 2.36 1.65-3.07 Sr-90 Bq/sample 0.931 1.03 0.72-1.34 Zn-65 Bq/sample -0.688 (1)

AP Gr-A Bq/sample 0.434 0.97 0.29-1.65 Gr-B Bq/sample 1.927 1.92 0.96-2.88 Vegetation Cs-134 Bq/sample 6.28 6.51 4.56-8.46 Cs-1 37 Bq/sample 4.62 4.38 3.07-569 Co-57 Bq/sample 6.51 5.66 3.96-7.36 Co-60 Bq/sample 5.32 5.12 3.58 -6.66 Mn-54 Bq/sample 3.59 3.27 2.29 - 4.25 Sr-90 Bq/sample 0.0012 (1)

Zn-65 Bq/sample

-0.046 (1)

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

(1) False positive test.

(2) Sensitivity evaluation (3) No cause was found for the failed high soil Co-60 sensitivity test or the high Zn-65 in AR Which TBE considers an anomaly. NCR 12-08 (4) Sr-90 in water high due to incorrect aliquot entered in LIMS. 12-11 (a) Teledyne Brow, Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by graeimetric and/or volumetric measurements made during standard preparation.

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

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

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

Limits Evaluation (c)

May 2012 RAD-89 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 MRAD-16 Filter Gr-A pCi/L 63.4 58.5 46.9-66.3 pCi/L 33.5 37.4 27.4-43.1 pCi/L 89.2 82.3 69.1 - 90.5 pCi/L 66.5 74.2 60.6-81.6 pCi/L 152 155 140-172 pCi/L 73.3 72.9 65.6-82.6 pCi/L 109 105 94.5-125 pCi/L 82.4 62.9 33.0 - 78.0 pCi/L 43.6 44.2 29.6-51.5 pCi/L 25.9 27.1 22.5-31.9 pCi/L 15433 15800 13800- 17400 pCi/filter 39.5 77.8 26.1 - 121 pCi/L 46.5 39.1 29.7 -46.1 pCi/L 16.6 20.1 14.4 -23.8 pCi/L 85.2 84.8 71.3-93.3 pCi/L 76.9 76.6 62.6-84.3 pCi/L 177 183 165-203 pCi/L 77.4 78.3 70.5 - 88.5 pCi/L 209 204 184 - 240 pCilL 50.6 58.6 30.6 - 72.9 pCi/L 59.3 39.2 26.0- 46.7 pCi/L 22.9 24.8 20.6-29.4 pCi/L 5020 4890 4190-5380 pCilfilter 59.6 87.5 29.3 - 136 A

A A

A A

A A

N(1)

A A

A A

November, 2012 RAD-91 MRAD-17 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Filter Gr-A N (2)

A A

A A

A A

A N (2)

A A

A (1) Detector G I is slightly biased high for Th-230 based measurements used only for ERA Gross Alpha samples. NCR 12-05 (2) The Sr-89 found to known ratio was 1.19, Mhich TBE considers acceptable. It appears the aliquot was entered incorrectly for the Gross Beta NCR 12-13 (a) Teledyne Bromw Engineering reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravrmetric and/or volumetric measurements made during standard preparation.

(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.4 Environmental TLD Quality Assurance Environmental dosimetry services for the reporting period of January - December, 2012 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.4-1 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.4-2 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.4-3 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.4-1 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2012(')' (2)

-W F'"

Numbe

ý,

j~

4 Iso Bosime.e" T

.PassedB n.ieten-se, I

aasni Evrnet e

Panasonic Environmental 72 100 100 (1)rhis table summarizes results of tests conducted by EDC.

(2)Environmental dosimeter results are free in air.

TABLE D.4-2 MEAN DOSIMETER ANALYSES (N=6)

JANUARY - DECEMBER 2012(1)' (2)

POl sDA~te Mean B~

Sadr IE~

it.i*:,l5 D& ~ i d

4/18/2012 7.7 1.7 Pass 4/21/2012 11.6 1.4 Pass 5/1/2012 1.1 1.4 Pass 6/5/2012

-0.5 1.3 Pass 7/19/2012 2.3 1.6 Pass 7/23/2012

-4.0 0.8 Pass 11/1/2012 2.5 2.2 Pass 11/4/2012 1.5 0.9 Pass 11/26/2012

-2.3 2.6 Pass 1/23/2013

-3.2 1.1 Pass 1/28/2013 4.4 1.3 Pass 2/2/2013

-0.1 1.2 Pass (1 This table summarizes results of tests conducted by EDC for TLDs issued in 2012.

(2)Environmental dosimeter results are free in air.

TABLE D.4-3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2012(1)' (2)

.~~~~~~~

~Cennis%

Stnd'a rd.

1 st Qtr.2012 Millstone

-10.4 2.6 Pass 2nd Qtr.2012 Millstone

-4.7 1.6 Pass 2nd Qtr.2012 Seabrook

-0.8 1.5 Pass 3rd Qtr. 2012 Millstone

-13.9 2.6 Pass 4th Qtr.2012 Millstone 4.3 1.5 Pass 4th Qtr.2012 Seabrook

-5.2 1.3 Pass

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

(2)Blind spike irradiations using Cs-137