NL-18-037, 2017 Annual Radiological Environmental Operating Report

2017 Annual Radiological Environmental Operating Report

ML18138A297
Person / Time
Site:	Indian Point
Issue date:	05/14/2018
From:	Vitale A Entergy Nuclear Operations
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
NL-18-037
Download: ML18138A297 (133)

Text

A

• -=--Entergy; NL-18-037 May 14, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6700 Anthony J. Vitale Site Vice President

Subject:

2017 Annual Radiological Environmental Operating Report Indian Point Unit Nos. 1, 2 and 3 Docket Nos.50-003, 50-247, and 50-286

Dear Sir or Madam:

Enclosed pleased find one copy of the Entergy Nuclear Operations, Inc. Indian Point Energy Center Annual Radiological Environmental Operating Report for the period January 1, 2017 to December 31, 2017.

This report is submitted in accordance with facility Technical Specification, Appendix A, Section 5.6.2 associated with license numbers DPR-5, DPR-26 and DPR-64 for Indian Point Unit Nos. 1, 2 and 3 respectively. There are no new regulatory commitments being made by Entergy in this correspondence.

Docket No.50-003, 50-247, 50-286 NL-18-037 Page 2 of 2 Should you or your staff have any questions regarding this matter, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.

Sin:~w AJV/trj

Enclosures:

2017 Annual Radiological Environmental Operating Report cc: Mr. David Lew, Acting Regional Administrator, NRC Region I Mr. Richard V. Guzman, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point Energy Center Ms. Kimberly Conway, IPEC NRC Unit 1 Project Manager Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Management, NYSDEC Ms. Bridget Frymire, New York State Public Service Commission Ms. Alicia Barton, President and CEO, NYSERDA

\\

ENCLOSURE TO NL-18-037 2017 Annual Radiological Environmental Operating Report Entergy Nuclear Operating, Inc.

Indian Point Unit Nos. 1, 2, and 3 Docket Nos.50-003, 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, 2017

TABLE OF CONTENTS EXECUTIVE

SUMMARY

Page vii

1.0 INTRODUCTION

1-1 1.1 Overview 1-1

2.0 BACKGROUND

2-1

• 2. t 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 A.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

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, 2007 to 2017 C-3 C-2 Radionuclides in Air - Gross Beta, 2007 to 2017 C-5 C-3 Radionuclides in Hudson River Water, Inlet & Discharge C-7 2007 to 2017 C-4 Radionuclides in Drinking Water, C-9 2007 to 2017 C-5 Radionuclides in Shoreline Soil, 2007 to 2017 C-11 C-6 Broad Leaf Vegetation, 2007 to 2017 C-13 C-7 Radionuclides in Fish & Invertebrates, C-15 2007 to 2017 C-9 Radionuclides in Bottom Sediment, 2007 to 2017 C-18 iii

LIST OF TABLES TABLE TITLE Page A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection Requirements for Environmental Sample Analysis A-8 A-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples

• A-10 B-1 Sampling Summary, 2017 B-2 B-1a 2017 Air Sampling Deviations B-3 B-1b 2017 Other Media Deviations B-3 B-2 Radiological Environmental Monitoring Program Summary B-4 Indian Point Energy Center-2017 B-3 Direct Radiation, Quarterly Data - 2017 B-10 B-4 Direct Radiation, 2007 through 2017 Data B-11 B-5 Direct Radiation, Inner and Outer Rings - 2017 B-12 I

B-6 Gross Beta Activity in Airborne Particulate Samples-2017 B-13 B-7 lodine-131 in Airborne Charcoal Samples - 2017 B-15 B-8 Gamma Emitters in Airborne Particulate Samples-2017 B-17 B-9 Radionuclides in Rainwater Samples - 2017 B-21 B-10 Radionuclides in Drinking Water Samples - 2017 B-22 B-11 Radionuclides in Groundwater Samples - 2017 B-26 B-12 Gamma Emitters in Soil Samples - 2017 B-27 B-13 Gamma Emitters in Broad leaf Vegetation Samples - 2017 B-28 B-14 Radionuclides in River Water Samples - 2017 B-37 B-15 Gamma Emitters in Bottom Sediment Samples - 2017 B-41 B-16 Radionuclides in Shoreline Soil Samples - 2017 B-43 B-17 Gamma Emitters in Aquatic Vegetation Samples - 2017 B-46

. B-18 Radionuclides in Fish / Invertebrates - 2017 B-49 B-19 Land Use Census, Residence & Milk Animal Results 2017 B-55 B-20 Land Use Census - 2017 - Unrestricted Area Boundary B-56 and Nearest Residences iv

LIST OF TABLES (Continued)

TABLE TITLE Page C-1 Direct Radiation Annual Summary, 2007 - 2017 C-2 C-2 Radionuclides in Air, 2007 - 2017 C-4 C-3 Radionuclides in Hudson River Water, Inlet & Discharge C-6 2007 to 2017 C-4 Radionuclides in Drinking Water C-8 2007 to 2017 C-5 Radionuclides in Shoreline Soil, 2007 to 2017 C-10 C-6 Radionuclides in Broad leaf Vegetation, 2007 to 2017 C-12 C-7 Radionuclides in Fish & Invertebrates, C-14 2007 to 2017 C-8 River Water Discharge Area Tritium, REMP vs Effluent C-16 C-9 Radionuclides in Bottom Sediment, 2007 to 2017 C-17 D-2.1 Ratio of Agreement D-2 D-3.1 Analytics lnterlaboratory Comparison Program D-3 and Ratio of Agreement D-3.2 DOE lnterlaboratory Comparison Program D-7 and Ratio of Agreement D-3.3 ERA lnterlaboratory Comparison Program D-8 and Ratio of Agreement D-4.1 Percent of Individual Dosimeters That Passed EDC D-9 Internal Criteria, 2017 D-4.2 Mean Dosimeter Analysis (N=6), 2017 D-10 D-4.3 Summary of Independent Dosimeter Testing, 2017 D-10 V

EXECUTIVE

SUMMARY

vi

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, 2017. The Indian Point site consists of Units 1, 2 and 3, which are operated by Entergy Nuclear Operations Inc. Unit 1 was retired as a generating facility in 1974, and its reactor is no longer operated.

The REMP has been established to monitor/measure the radiation and radioactivity detectable in the environment that may be attributable to the operation of I PEC. 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_.

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

During 2017 there were 1161 samples collected from the atmospheric, aquatic, and terrestrial environments. This includes 164 exposure measurements which were obtained using environmental thermoluminescent dosimeters (TLDs)..

A small number of inadvertent issues were encountered in 2017 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 1323 analyses performed on the environmental media samples. The analysis of the 2017 Indian Point environmental samples was performed by several laboratories.

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 2017. 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 whose milk is used for human consumption were identified within 5 miles of the Station 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. As allowed for in the ODCM, monthly broad leaf sampling may be used in lieu of a garden census.

vii

SUMMARY

OF RESULTS, Samples collected* as part of the IPEC REMP continued to contain detectable amounts of naturally-occurring and some man-made radioactive materials.

Offsite ambient radiation measurements using environmental. TLDs beyond the site boundary ranged between 46 and 81 milli-Roentgens (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 station indicated the presence of the following potential station related radioactivity, tritium and cesium-137. The tritium was found in river water at the downstream mixing zone of the discharge at levels that were expected from routine plant operation, or other sources such as fallout from past weapons testing. Low-levels of cesium-137 were detected in Hudson River bottom sediment samples downstream of the discharge as well as three soil samples. The levels detected were consistent with historical findings. No other plant related activity was detected in any offsite samples. The predominant radioactivity for an samples was from non-plant related sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.

CONCLUSIONS The 2017 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 2017 did not result in exposure to the public greater than environmental background levels.

viii

SECTION 1.0

• INTRODUCTION

1.0 INTRODUCTION

1. 1 Overview The Radiological Environmental Monitoring Program (REMP) for 2017 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, which is submitted to the NRC annually per Indian Point Technical Specifications, 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, 2017.

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.

This report contains a description of the REMP for IPEC and the conduct of that program in 2017 as required by the IPEC ODCM. Also included are summaries and discussions of the results of the 2017 program, trend analyses (where appropriate), comparison to historical results and evaluation of any potential impact on the environment.

Results of the annual land use census, as well as the inter-laboratory comparison program are included, per the ODCM requirements.

1-1

SECTION 2 BACKGROUND

2.0 BACKGROUND

2.1 Site Description The Indian Point site occupies 239 acres on the east barik 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. Indian Point Units 1 and 2 are owned by Entergy Nuclear Indian Point 2, LLC and Unit 3 is owned by Entergy Nuclear. Indian Point 3 LLC. All three units are 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. Thus, as used in this report, background levels consist of those resulting from both natural and anthropogenic sources of environmental radioactivity. Accumulation of this background data permits the detection and assessment of environmental activity attributable to plant operations.

2.3 Program Objectives The current environmental monitoring program is designed to meet two primary objectives:

1.

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

2.

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

To identify changes in activity, the environmental sampling schedule requires that analyses be conducted for specific environmental media on a regular basis.

The radioactivity profile of the environment is established and monitored through routine.

evaluation of the analytical results obtained.

The REMP designates sampling locations for the collection of environmental media for analysis.* These sample locations are divided into indicator and control locations.

Indicator locations are established 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.

2-1

Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is another objective of the REMP, which is met by meeting the two primary program objective described above. 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 2017 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 2017 REMP sample results confirms that environmental concentrations which could be attributed to 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 fish/invertebrate samples. Collection of fish and invertebrate samples is performed by a contracted environmental vendor, Normandeau Associates, Inc.

3.2 Sample Analysis The analysis of the 2017 Indian Point environmental samples was performed by several laboratories. 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 (AS) and seven indicator locations. These indicator locations are at sampling stations 4 (A1), 5 (A4), 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown on Figures A-1, A-2, and A-3. The air samples are collected continuously by means of fixed air particula~e 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 Wb1) and New Croton Reservoir (6.3 miles 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 are 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 (lc2) and 95 (lc1 ), and the control location is at sampling station 23 (lc3).

See Figures A-1 and A-2.

The samples are collected monthly, when available; and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.

3.3.8 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (sampling station 9, Wa1) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, Wa2); see Figure A.:.1.

An automatic composite sampler is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points.

These weekly river water samples are composited for monthly gamma spectroscopy analysis and quarterly for tritium analysis.

3-2

I

-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 (Wc1), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-1, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90.

I 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 (lb1), and a second sampling station 107 is located further downstream. The control location (upstream) is at sampling station 23 (lb2). See Figures A-1 and A-2. These samples are collected in season or semiannually if they are not seasonal. The fish and invertebrates sampleq 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 1,1se 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 are 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 is 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. con~_umption 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 Methodology 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):

Where:

LLD=

Ts=

Sb=

E=

V=

k=

Y=

,\\ =

t=

2.71 +3.29sb

• J1+(Tb)

LLD.= Ts Ts E

• V

• k

• Y

• e-A, The lower limit of detection as defined above (as picocurie per unit mass or volume)

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

The background count time in mim,ites The counting efficiency (as counts per transformation)

The sample size (in units of mass or volume)

A constant for the number of transformations per minute per unit of activity. (normally, 2.22E+6 dpm per uCi)

The fractional radiochemical yield (when applicable)

The radioactive decay constant for the particular radionuclide 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 2* and 3.

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 ttie 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 O'b * [(1 + (Tb/ Ts ))112] = 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 4). 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 for 2007 through 2017. The historical averages are calculated using only the positive values presented for 2007 through 2016.

The 2017 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 2017 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 Precipitation Groundwater Broad Leaf Vegetation Bottom Sediment Aquatic Vegetation Airborne Particulates and Radioiodine Drinking Water Soil Hudson River Water Shoreline Soil 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 2017 and assessed the significance of the findings.

A summary of the results of the 2017 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 plant operations, their presence is noted only in the data tables and will not be discussed further.

The second group of radionuclides detected in 2017 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 5). However, weapons testing in the 1950's an<;I 1960's 4-1

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 2017, the detected radionuclides 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 2017 REMP comprises those that may be attributable to current plant operations. During 2017, Cs-137 and Tritium 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. In 2017, very low levels of H-3 were detected in two river water samples.

Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2017, there were seven detections of Cs-137 in bottom sediment and shoreline soil at indicator locations. Cs-137 was also detected in all three soil samples obtained. In all cases, the Cs-137 concentrations, when detected, were consistent with historical values.

The fact that there was no Cs-134 present (recent plant releases would contain Cs-134) and that the levels detected were consistent with historical values indicates that the activity may be due to atmospheric weapons testing, with some contribution from plant releases from the past 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. No Sr-90 was detected in any of the fish, shoreline soil, or groundwater samples.

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as has been noted in previous years. 1~131 was not detected in 2017 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 environm!3ntal 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 2017 REMP, although they were observed in historical data.

In the following sections, a summary of the results of the 2017 REMP is presented by sample medium and the significance of any positive findings discussed. It should be noted that naturally occurring radionuclides are omitted from the summary table (Table 8-2) and further discussion.

4.1

• Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by Environmental Dosimetry Company. In 2017, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point St.ation. A summary of the annual TLD data is provided in Table 8-2 and all the TLD data are presented in Tables 8-3, 8-4 and 8-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table 8-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41.

Table 8-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 2007 through 2017. The 2017 means are also presented in Table 8-4.

Table 8-5 presents the 2017 TLD data for the inner ring and outer ring of TLDs. The table also provides the sector for each of the DR sample points.

The 2017 mean value for the indicator direct radiation sample points was 14.4 *mR per standard quarter - which is consistent with historical values. At those locations where the 2017 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 Df:s-16) is close to the site boundary.

The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The results of the annual averages for these two rings of TLDs are _provided in Table 8-5. The annual average for the inner ring was 14.3 mR per standard quarter and also average for the outer ring was 14.7 mR per standard quarter. The control location average for 2017 was 15.6 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 2017 averages are consistent with the historical data. The 2017 and previous years' data show that there is no measurable direct radiation in the environment due to the operation of the Indian Point site.

4-3

4.2 Airborne Particulates and Radioiodine An annual summary of the results of the 2017 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 0.013 pCi/m3 and the average for the control location was 0.012 pCi/m3. The

• activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location.

The results of the GSA of the quarterly composites of these samples are in Table 8-8.

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 2017 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 2017.

4.3 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table 8-9 contains the results of the precipitation samples for 2017. Only one naturally occurring radionuclide was detected in the precipitation samples.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2017 drinking water sample analysis results.

Results of the gross beta, tritium and gamma spectroscopy analyses of the monthly drinking water samples are in Table 8-10. Other than Gross Beta activity consistent with historical values, 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 2017 is contained in Table 8-2. Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, Ni-63 and Sr-90 are given in Table B-11. No plant related nuclides were noted in any acceptable 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 2017.

Other than naturally occurring radionuclides, very low levels of Cs-137 were detected in some soil samples consistent with historical results.

4.7 Broad Leaf Vegetation Table 8-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2017 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.

There were no plant related nuclides detected in the 2017 samples.

The detection of low levels of Cs-137 has occurred sporadically at indicator locations at relatively low concentrations for the past ten years, 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, and it was detected at low levels in two indicator samples. The levels are consistent with occasional historical detection of H-3.

Table C-3 shows historical H-3 concentrations at the plant inlet and discharge points. Table

. C-8 contains a comparison of H-3 detected at the plant discharge (Hudson River Water mixing point) versus calculated quarterly average effluents concentrations. The data in table C-8 provides assurance that the REMP is indeed providing verification of the calculation of radionuclide concentrations resulting from effluent releases attributable to the site.

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

Table B-15 contains the results of the analysis of bottom sediment samples for 2017..

Cesium-137 was detected in five of the indicator station samples, and none of the control location samples. Detection of positive levels of Cs-137 in river bottom sediment is not unusual. Cs-134 was not detected in any bottom sediment samples. The lack of Cs-134 points to the primary source of the Cs-137 in bottom sediment as being from prior historical plant releases over the years and from residual weapons test fallout.

Historical levels of Cs-137 in bottom sediment samples are shown in table C-9 and figure C-

8.

This data shows the continued detection of Cs-137 in bottom sediment samples at varying levels, and demonstrates that the levels observed during 2017 sampling are within the range of levels identified in historical samples.

4-5

4.1 O 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 two of the Hudson River shoreline soil samples in 2017.

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. Cesium-137 has been present in this media, both at indicator and occasionally at the control location, at a consistent level over the past ten years. Cesium-134 and Cs-137 are both discharged from the pl~nt in similar quantities. The lack of Cs-134 activity is an indication that the primary source of the Cs-137 in the shoreline soil is legacy contamination from weapons fallout.

Strontium-90 (Sr-90) was not detected in any of the 8 indicator location samples or any of the control location samples, 4.11 Aquatic Vegetation A summary of the aquatic sample analysis results is presented in Table B-2. Tabl~ B-17 contains the results of the analysis of aquatic vegetation samples for 2017. No plant related radionuclides were detected in any indicator $amples. This is consistent with historical findings.

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 2017.

No plant related radionuclides were detected. This is consistent with historical results which are shown in table and figure C-7.

4.13 Land Use Census A census was performed in the vicinity of Indian Point in 2017. 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 2017 census were generally same as the 2016 census results, in 2016 the presence of goats was noted on a property located less than 5.0 miles SSE of IPEC.

However, discussions with the owner for the 2017 land use surveys confirmed that the goats did not produce milk for human consumption and are therefore not milch animals.

The 2017 land use census indicated there were no new residences that were closer. in proximity to IPEC.

4-6

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 2017 REMP reveal that operations at the station did not result in an impact on the environment.

• The 2017 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 activity 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

5.0 REFERENCES

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

2. Currie, L.A., "Limits for Qualitative Detection of Quantitative Determination",

Analytical Chemistry, 40:586-593, 1968.

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

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

5. 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.

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

7. United States of America, Code of Federal Regulations, Title 10. *

8. United States of America, Code of Federal Regulations, Title 40.

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

10. U.S.

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

11. Entergy Nuclear Indian Point, Radiological Environmental Monitoring Chemistry Procedures.

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

13. Eisenbud; M., Environmental Radioactivity, Academic Press, New York, 1987.

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

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

16. 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.

17. 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.

5-1

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

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

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

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

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

1. 6~8. Philadelphia, PA, 1978.

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

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

1969.

25. 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.

26. National Council on Radiation Protection.

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

27. 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.

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

29. 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.

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

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

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

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

5-2

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

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

36. ENN-Ll-102, Corrective Action Process

37. Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC"

38. National Council on Radiation Protection and Measurements, Report No. 169, "Design of Effective Radiological Effluent Monitoring and Environmental Surveillance Programs", December 2010.

39. Donald T. Oakley, "Natural Radiation Exposure in the United States."

U. S.

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

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

41. 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.

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

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

44. NYS Department of Environmental Conservation, "Measurement of Strontium and Other Radionuclides in Edible Tissue and Bone/carapace of Fish and Blue Crabs from the Lower Hudson River, New York", November 2009.

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-1, A-2, and A-3. The samples are analyzed according to criteria established in the ODCM.

These requirements include: methods of sample collection; types of sample analysis; minimum sample size required; lower limit of detection, which must be attained for each medium, sample, or analysis type, and environmental concentrations requiring special reports.

Table A-1 provides the sampling station number, location, sector, and distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2017 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-1, 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 3

DRS Service Center Building Onsite -

Direct Gamma 0.35 Mi (SSE) at 158° 4

A1 Algonquin Gas Line Onsite - 0.28 Mi (SW) at Air Particulate A1 234° Radioiodine A4 Air Particulate 5

A4 NYU Tower Onsite - 0.88 Mi (SSW)

Radioiodine at 208° DR10 Direct Gamma 7

Wb1 Camp Field Reservoir 3.4 Mi (NE at 51° Drinking Water 8

Croton Reservoir 6.3 Mi (SE) at 124° Drinking Water 9

Wa1 Plant Inlet (Hudson River Intake)*

Onsite -

HR Water 0.16 Mi (W) at 273° 10 Wa2 Discharge Canal (Mixing Zone)

Onsite -

HR Water 0.3 Mi (WSW) at 249° HR Bottom Sediment 14 DR?

Water Meter House Onsite -

0.3 Direct Gamma Mi (SE) at 133° HR Aquatic Vegetation 17 Off Verplanck 1.5 Mi (SSW) at 202.5° HR Shoreline Soil HR Bottom Sediment 20 DR38 Cortlandt Yacht Club 1.5 Mi (S) at 180° Direct Gamma (AKA Montrose Marina)

Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton*

20. 7 Mi (N) at 357° Direct Gamma lc3 Broad Leaf Vegetation Soil lb2 Fish & Invertebrates 25 lb1 Downstream Downstream Fish & Invertebrates Air Particulate 27 Croton Point 6.36 Mi (SSE) at 156° Radioiodine DR41 Direct Gamma HR Shoreline Soil 28 DR4 Lent's Cove 0.45 Mi (ENE) at 069° Direct Gamma HR Bottom Sediment HR Aquatic Vegetation Air Particulate 29 Grassy Point 3.37 Mi (SSW) at 196° Radioiodine DR39 Direct Gamma 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053° Direct Gamma 34 DR9 South East Corner of Site Onsite -

Direct Gamma 0.52 Mi (S) at 179° 35 DR5 Broadway & Bleakley Avenue Onsite -

Direct Gamma 0.37 Mi (E) at 092° 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 ° Direct Gamma

• = Control location

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

TABLEA-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS Precipitation 44 Peekskill Gas Holder Bldg 1.84 Mi (NE) at 052° Air Particulate Radioiodine 50 Wc2 Manitou Inlet*

4.48 Mi (NNW) at 347° HR Shoreline Soil 53 Wc1 White Beach 0.92 Mi (SW) at 226° HR Shoreline Soil DR11 Direct Gamma 56 DR37 Verplanck - Broadway & 6th Street 1.25 Mi (SSW) at 202° Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR17 Route 90 - Garrison 5.41 Mi (N) at 358° Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 032° Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 029° Direct Gamma Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 052° Direct Gamma 62 DR19 Westbrook Drive 5.03 Mi (NE) at 062° Direct Gamma (near the Community Center) 64 DR20 Lincoln Road - Cortlandt 4.6 Mi (ENE) at 067° Direct Gamma (School Parking Lot) 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 083° 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 127° Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 188° Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 203° Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 226° Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 252° 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 276° Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 272° Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 295° Direct Gamma 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 DR-28 Palisades Pkwy - lake Welch Exit 4.96 Mi (WSW) at 310° Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 334° 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 356° 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 025° Direct Gamma (near rock cut)

• = Control location

• • = Locations listed do not have sample designation locations specified in the ODCM A-3 HR= Hudson River R/S = Reuter Stokes

TABLEA-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 90 DR3 Charles Point 92 DR24 Warren Road - Cortlandt A2 94 A2 IPEC Training Center lc2 A3 95 A3 Meteorological Tower lc1 106 Lafarge Monitoring Well 107 Vicinity of Haverstraw Bay

• = Control location

• • = Locations listed do not have sample designation locations specified in the ODCM HR= Hudson River R/S = Reuter Stokes A-4 0.88 Mi (NE) at 047° 3.84 Mi (SSE) at 149° Onsite- 0.39 Mi (S) at 193° Onsite -

0.46 Mi (SSW) at 208° 0.63 mi SW 2.5 mi SS'f\\J (downstream)

Direct Gamma Direct Gamma Air Particulate Radioiodine Broad Leaf Vegetation Soil Air Particulate Radioiodine Broad Leaf Vegetation Soil Groundwater Fish & Invertebrates

Hudson Rive Slioreooe Soil Sampling Lo~tion Fish an$J Invertebrates (wher available)

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point downs Hudson River A-5

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

' ~ ~

Peekskill

{

J)

• I

• Indian Point Stdl !i3n

\\

Mo ttose

\\

1. 107 9

Fish and lnve:rfflb (where _availabl,e)'J tJpw ftfflll\\ llu~stJn,Riv1p A-6 Cortlan t Mano

- 1

\\351

\\

Yo *

. n

)

Amaw

~ vJktown

eitf, I

Rb cklan.d

,I County

• Ha.m.n Prec1p1tation

(;)Drinking Water Sample.,Locatiorr FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations Co A-7

""'s4:

~~

Cold Spring, 10.9 miles north Amaw ktown e* ht~

Cro1o ~en H d:so l

1, 1 =:;'

• Wcstdiester

(!l q Coun.ty /*

G ~ ~ Monitoring }Veil, SW of Siteffioundarv

'7 Aquatic v / getation.

Ossmm t

~

udson River

'.Bottom Sediment I

~

Ch pp.

Gross Beta H-3 Mn-54 Fe-59 Co-58 Co-60 Ni-63 (f)

Zn-65 Sr-90 (f)

Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 TABLEA-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES 4

0.01 2,000 (d) 15 130 30 260 15 130 15 130 30 100 30 260 1

5 30 15 1 (d) 0.07 60 15 0.05 130 15 60 18 0.06 150 18 80 60 60 15 15 A-8 5000 150 180

TABLEA-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 g priori (before the fact) limit representing the capability of a measurement system and not as an g 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

ii TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES i",,

RADIONUCLIDE

WATER, AIRBORNE, FISH MILK

("::,: o'~

FOOD PARTIUCLATE OR PRODUCTS ANALYSIS,/,.

(pCi/L)

C3ASES (pC:i/~3)

(pCi/kg! wet)

I, (pCi/L)

• *:,:'(pC:i/k:g, w~t).,.,;

\\

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 l

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B 8.1 2017 Annual Radiological Environmental Monitoring Program Summary The results of the 2017 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 2017. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8, and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 4). 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 2017, environmental sampling was performed for 12 unique media types addressed in the ODCM and for direct radiation. A total of 1161 samples of 1163 scheduled were obtained.

Of the scheduled samples, 99.8% were collected and analyzed for the program. Sampling deviations are summarized in Table B-1.

Discussions of the reasons for the deviations are provided in Table B-1 a for the air samples and Table B-1 b for other media.

8.4 Analytical Deviations No analytical deviations were found in 2017.

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

B-1

_J

TABLE B-1 Summary of Sampling Deviations - 2017 MEDIA TLD 164 0

100%

164 N/A PARTICULATES IN AIR 416 100%

447 See Table B-1a CHARCOAL FILTER 416 1

100%

415 See Table B-1 a PRECIPITATION 8

0 100%

16 N/A DRINKING WATER 24 0

100%

56 N/A GROUNDWATER 2

0 100%

8 N/A SAMPLES SOIL 3

0 100%

3 N/A BROAD LEAF 51 0

100%

51 N/A VEGETATION HUDSON RIVER WATER 24 0

100%

32 N/A SHORELINE SOIL 10 0

100%

20 N/A HUDSON RIVER BOTTOM 8

0 100°(<,

8 N/A SEDIMENT AQUATIC VEGETATION 4

0 100%

4 N/A FISH & INVERTEBRATES 33 0

100%

99 N/A TOTALS 1163 2

99.8%

1323 TOTAL NUMBER OF SAMPLES COLLECTED=

1161

• Samples not collected or unable to be analyzed.

• • Several sample types require more than one analysis 8-2

27 Croton Point 27 Croton Point 04 Algonquin 44 Peekskill Gas Holder 04 Algonquin 44 Peekskill Gas Holder 44 Peekskill Gas Holder 44 Peekskill Gas Hoider 44 Peekskill Gas Holder 29 Grassy Point 27 Croton Point "

94 IPEC Training Center 112312017 Delivered sample volume 1,300 ft3 vs. expected volume of >18,920 tt3 due to a tripped GFCI w/ 135.3 hrs outage time.

311312017 Delivered sample volume of 14,600 ft3 vs. expected volume of 20,104 tt3 due to a tripped GFCI w/ 45.7 hrs outage time.

312012017 Unable to collect sample since access was blocked by downed electrical wires,

causing a safety hazard.

4/24/2017 5/15/2017 Delivered sample volume of 7,900 ft3 vs. expected volume of 20,023 ft3 due to a tripped GFCI w/ 107.7 hrs outage time.

Delivered sample volume of 16,632 ft3 vs. expected volume of 18,641 ft3 w/ 18.6 hrs outage time.

9,2512017 Delivered sample volume of 6,000 ft3 vs. expected volume of 20,088 tt3 due to a tripped GFCI w/ 114.4 hrs outage time.

1111 312017 Delivered sample volume of 12,600 ft3 vs. expected volume of 18,815 tt3 due to a tripped GFCI w/ 54.8 hrs outage time.

11,2112017 Delivered sample volume of 200 ft3 vs. expected volume of 23,304 tt3 due to a tripped GFCI w/ 193.2 hrs outage time.

1211 112017 Delivered sample volume of 11,000 ft3 vs. expected volume of 18,648 tt3 due to a tripped GFCI w/ 69.0 hrs outage time.

1211 112017 Delivered sample volume of 18,600 ft3 vs. expected volume of 20,188 tt3 due to a tripped GFCI w/ 13.4 hrs outage time.

1211 112017 Delivered sample volume of 700 ft3 vs. expected volume of 19,602 ft3 due to a tripped GFCI w/162.4 hrs outage time.

12/26/2017 Air sampler hr meter stopped running. Replaced hr meter on 12/26/17 Note: All air particulate filters and Charcoal Cartridges were analyzed, except fo the air filter and air iodine from Sin 04 on 3/20/17.

09 Hudson River Intake 2/14/17 10 Hudson River Discharge 6/20/17 10 Hudson River Discharge 9/13/17 TABLE B-1b Composite sample not available due to samplerbeing found in 'Standby'. Grab sample obtained.

Composite sample not available due to sampler being found in 'Standby'. Grab sample obtained.

Hudson river discharge composite sample not available due to degraded sample suction tubing. Tubing replaced, as left pump operation SAT, and a grab sample was obtained.

B-3

Medium or Pathway Sampled (Units)

Direct Radiation (mR/Standard Quarter)

Air Particulate (pCi/m3)

Air Iodine (pCi/m3)

Air Particulate (10-3 pCi/m3)

Rainwater (pCi/L)

Rainwater (cont'd)

(pCi/L)

Drinking Water (pCi/L)

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2017 Dockets 50-03, 50-247 & 50-286 Indicator Analysis Total LLD*

Locations Location with Highest Mean Type Number Mean**

Location I Distance I Mean (Range)

Number Direction (Range) lid-Quarterly 164 NA 14.4 (160/160)

DR-28 4.96 Mi.

20.2 (4/4)

(10.8/20.5)

WSW (19.8/20.5)

Gr-B 415 0.01

.013 (361/363) 27 6.36 Mi.

.014 (51/52)

(.004/.073)

SSE

(.005/.073)

GAMMA 415 1-131 0.07

<LLD GAMMA 32 Be-7 NA 112.2 (28/28) 44 1.84 Mi.

118.7 (4/4)

(80. 7 /145. 5)

NE (91.1/131.9)

K-40 NA

<LLD Cs-134 0.05

<LLD Cs-137 0.06

<LLD Th-228 NA

<LLD H-3 8

3000

<LLD GAMMA 8

Co-60 15

<LLD Cs-134 15

<LLD Cs-137 18

<LLD Gr-B 24 4

3.26 (16/24) 7 3.4 Mi.

3.51 (7/12)

(2.24/5.27)

NE (2.55/5.27)

H-3 8

2000

<LLD GAMMA 24 Mn-54 15

<LLD Co-58 15

<LLD Fe-59 30

<LLD B-4 Control Locations Non-Routine Mean Reported (Range)

Measurements 15.6 (4/4) 0 (14.9/16.8)

.012 (52/52) 0

(.005/.020)

<LLD 0

111.9 (4/4) 0 (87.1/129.3)

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

NA 0

NA 0

NA 0

NA 0

NA 0

Medium or Pathway Sampled (Units)

Drinking Water (cont'd)

(pCi/L)

Groundwater (pCi/L)

TABLE 8-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2017 Dockets 50-03, 50-247 & 50-286 Indicator Analysis Total LLD*

Locations Location with Highest Mean Type Number Mean**

Location I Distance I Mean (Range)

Number Direction (Range)

Co-60 15

<LLD Zn-65 30

<LLD Nb-95 15

<LLD Zr-95 15

<LLD 1-131

<LLD Cs-134 15

<LLD Cs-137 18

<LLD Ba-140 60

<LLD La-140 15

<LLD H-3 2

3000

<LLD Ni-63 2

30

<LLD Sr-90 2

<LLD GAMMA 2

Mn-54 15

<LLD C0-58 15

<LLD Fe-59 30

<LLD Co-60 15

<LLD Zn-65 30

<LLD Nb-95 15

<LLD 8-5 Control Locations Non-Routine Mean Reported (Range)

Measurements NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

Medium or Pathway Sampled (Units)

Groundwater (cont'd)

(pCi/L)

Soil (pCi/kg dry)

Broadleaf Vegetation (pCi/kg wet)

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2017 Dockets 50-03, 50-247 & 50-286 Indicator Analysis Total LLD*

Locations Location with Highest Mean Type Number Mean**

Location I Distance I Mean (Range)

Number Direction (Range)

Zr-95 30

<LLD 1-131 15

<LLD Cs-134 18

<LLD Cs-137 60

<LLD Ba-140 15

<LLD La-140 15

<LLD GAMMA 3

Be-7 NA

<LLD K-40 NA 11635 (2/2) 23 20.7Mi.

19650 (1/1)

(8959/14310)

N Co-60 NA

<LLD Cs-134 150

<LLD Cs-137 180 206.8 (2/2) 23 20.7Mi.

249.2 (1/1)

(191.1/222.4}

N Ra-226 NA

<LLD 23 20.7Mi.

1687 (1/1)

N Th-228 NA 482.0 (2/2) 23 20.7 Mi.

947.7 (1/1)

(216.9/747.1)

N GAMMA 51 Be-7 NA 1574.3 (33/34) 94 0.39Mi.

1649.4 (16/17)

(183.9/4681) s (183.9/4681)

K-40 NA 5234.6 (34/34) 95 0.46 Mi.

5627.0 (17/17)

(2257/8693)

SSW

'(3153/8693)

Co-60 NA

<LLD 1-131 60

<LLD Cs-134 60

<LLD B-6 Control Locations Non-Routine Mean Reported (Range)

Measurements NA 0

NA 0

NA 0

NA 0

NA 0

NA 0

<LLD 0

19650 (1/1) 0

<LLD 0

<LLD 0

249.2 (1/1) 0 1687 (1/1) 0 947.7 (1/1) 0 1598.2 (16/17) 0 (389.4/4782) 4917.3 (17/17) 0 (2087/7776)

<LLD 0

<LLD 0

<LLD 0

Medium or Pathway Sampled (Units)

Broad leaf Vegetation ( cont'd)

(pCi/kg wet)

River Water (pCi/L)

Bottom Sediment (pCi/kg dry)

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2017 Dockets 50-03, 50-247 & 50-286 Indicator Analysis Total LLD*

Locations Location with Highest Mean Type Number Mean**

Location I Distance I Mean (Range)

Number Direction (Range)

Cs-137 80

<LLD Th-228 NA

<LLD 23 20.7Mi.

21.91 (1/17)

N H-3 8

3000 298.5 (2/4) 10 0.3Mi.

298.5 (2/4)

(216/381)

WSW (216/381)

GAMMA 24 Mn-54 15

<LLD Co-58 15

<LLD Fe-59 30

<LLD Co-60 15

<LLD Zn-65 30

<LLD Nb-95 15

<LLD Zr-95 15

<LLD 1-131 15

<LLD Cs-134 15

<LLD Cs-137 18

<LLD Ba-140 15

<LLD La-140 15

<LLD GAMMA 8

K-40 NA 15880 (6/6) 84 10.88 Mi.

20735 (2/2)

(9752/19880)

N (15200/26270)

Co-60 NA

<LLD Cs-134 150

<LLD 8-7 Control Locations Non-Routine Mean Reported (Range)

Measurements

<LLD 0

21.91 (1/17) 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

20735 (2/2) 0 (15200/26270)

<LLD 0

<LLD 0

Medium or Pathway Sampled (Units)

Bottom Sediment (cont'd)

(pCi/kg dry)

Shoreline Soil (pCi/kg dry)

Aquatic Vegetation (pCi/kg wet)

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2017 Dockets 50-03, 50-247 & 50-286 Indicator Analysis Total LLD*

Locations Location with Highest Mean Type Number Mean**

Location I Distance I Mean (Range)

Number Direction (Range)

Cs-137 180 350.3 (5/6) 10 0.3Mi.

570.0 (2/2)

(73/1067)

WSW (73/1067)

Ra-226 NA

<LLD 84 10.88 Mi.

2756 (1/2)

N Th-228 NA 805.7 (6/6) 84 10.88 Mi.

1061.8 (2/2)

(372.8/1157)

N (964. 5/1159)

Sr-90 10 5000

<LLD GAMMA 10 K-40 NA 12336 (6/6) 84 10.88 Mi.

34100 (2/2)

(7862/15880)

N (31950/36250)

Cs-134 150

<LLD Cs-137 180 151.0 (2/6) 17 1.5 Mi.

151.0 (2/2)

(85.9/216.1)

SSW (85. 9/216.1)

Ra-226 NA 3190 (1/6) 28 0.45 Mi.

3190 (1/2)

ENE Th-228 NA 697.8 (4/6) 28 0.45 Mi.

803.4 (2/2)

(472. 7/1134)

ENE (472.7/1134)

GAMMA 4

Be-7 NA

<LLD 84 10.88 Mi.

206.6 (1/2)

N K-40 NA 3579 (2/2) 28 0.45 Mi.

3695 (1/1)

(3462/3695)

ENE Co-60 NA

<LLD 1-131 60

<LLD Cs-134 60

<LLD Cs-137 80

<LLD Ra-226 NA

<LLD Ac-228 NA

<LLD Th-228 NA 106.4 (2/2) 28 0.45 Mi.

132.8 (1/1)

(80/132.8)

ENE B-8 Control Locations Non-Routine Mean Reported (Range)

Measurements

<LLD 0

2756 (1/2) 0

.1061.8 (2/2) 0 (964.5/1159)

<LLD 0

22576 (4/4) 0 (9658/36250)

<LLD 0

<LLD 0

2256 (1/4) 0 580.0 (4/4) 0 (446.4/694.5) 206.6 (1/2) 0 2295 (2/2) 0 (1654/2935)

<LLD 0

<LLD 0

<LLD 0

<LLD 0

• <LLD 0

<LLD 0

90.4 (2/2) 0 (85.8/95.1)

TABLE 8-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2017 Dockets 50-03, 50-247 & 50-286 Medium or Pathway Sampled (Units)

Fish (pCi/kg wet)

Analysis Total LLD*

Type Number Ni-63 33 100 Sr-90 33 5

GAMMA 33 K-40 NA Mn-54 130 Co-58 130 Fe-59 260 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Th-228 NA Environment Samples 1161 Analysis 1323

• LLD IS THE LOWER LIMIT OF DETECTION Indicator Locations Mean**

(Range)

<LLD

<LLD 2592 (23/23)

(1164/4715)

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

• • THE MEAN VALUES ARE CALCULATED USING THE POSITIVE VALUES

• • • MDC IS THE MIMINUM DETECTABLE CONCENTRATION B-9 Location with Highest Mean Location I Distance I Mean Number Direction (Range) 25 Downstream 2827 (12/12)

(1722/4715)

Control Locations Non-Routine Mean Reported (Range)

Measurements

<LLD 0

<LLD 0

2740 (10/10) 0 (2037/3971)

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

<LLD 0

INDIAN POINT ENERGY CENTER TABLE B-3 DIRECT RADIATION, QUARTERLY DATA-2017 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 16.3 +/- 0.7 16.0 +/- 1.0 17.1 +/- 0.5 16.3 +/- 0.7 16.4 +/- 0.5 65.6 DR-02 15.2 +/- 0.7 15.0 +/- 0.9 15.5 +/- 0.7 14.3 +/- 0.6 15.0 +/- 0.5 60.1 DR-03 12.7 +/- 1.0 12.0 +/- 1.0 13.5 +/- 0.5 12.5 +/- 0.6 12.7 +/- 0.6 50.8 DR-04 13.6 +/- 0.8 13.8 +/- 0.9 14.5 +/- 0.7 13.0 +/- 0.6 13.7 +/- 0.6 54.8 DR-05 14.1 +/- 0.7 14.8 +/- 1.0 15.1 +/- 0.5 14.3 +/- 1.3 14.5 +/- 0.5 58.2 DR-06 14.9 +/- 0.8 14.6 +/- 1.0 14.7 +/- 0.5 13.8 +/- 0.8 14.5 +/- 0.5 58.0 DR-07 15.9 +/- 0.9 16.3 +/- 1.2 16.7 +/- 0.5 15.6 +/- 0.7 16.1 +/- 0.5 64.6 DR-08 12.1 +/- 0.6 12.7 +/- 0.8 12.6 +/- 0.7 11.5 +/- 0.6 12.2 +/- 0.6 48.9 DR-09 13.7 +/- 0.9 14.3 +/- 1.0 14.4 +/- 1.2 13.4 +/- 0.8 13.9 +/- 0.5 55.8 DR-10 13.9 +/- 0.8 13.5 +/- 0.8 14.4 +/- 0.7 13.3 +/- 0.6 13.8 +/- 0.5 55.1 DR-11 11.0 +/- 0.9 10.9 +/- 0.8 11.7 +/- 0.5 10.8 +/- 0.7 11.1 +/- 0.4 44.5 DR-12 16.9 +/- 1.0 15.7 +/- 0.9 16.3 +/- 0.8 15.9 +/- 0.8 16.2 +/- 0.5 64.8 DR-13 17.5 +/- 0.8 16.1 +/- 0.9 17.3 +/- 0.9 16.7 +/- 0.8 16.9 +/- 0.6 67.6 DR-14 13.4 +/- 0.6 13.1 +/- 0.8 14.3 +/- 0.6 13.2 +/- 0.8 13.5 +/- 0.5 54.0 DR-15 13.8 +/- 0.8 13.0 +/- 0.8 13.6 +/- 0.7 13.3 +/- 0.6 13.4 +/- 0.4 53.8 DR-16 14.7 +/- 0.7 14.1 +/- 0.8 15.8 +/- 1.3 14.7 +/- 0.9 14.8 +/- 0.7 59.3 DR-17 14.7 +/- 0.9 14.2 +/- 0.9 15.8 +/- 0.8 14.6 +/- 0.8 14.8 +/- 0.7 59.3 DR-18 14.1 +/- 0.8 13.9 +/- 0.8 15.1 +/- 0.9 14.3 +/- 0.9 14.4 +/- 0.5 57.5 DR-19 15.1 +/- 0.7 14.3 +/- 0.9 16.3 +/- 0.6 14.7 +/- 0.9 15.1 +/- 0.8 60.4 DR-20 13.9 +/- 1.0 14.0 +/- 0.8 14.6 +/- 0.8 14.1 +/- 0.7 14.2 +/- 0.3 56.7 DR-21 14.3 +/- 1.0 13.7 +/- 0.9 14.8 +/- 0.6 14.5 +/- 0.6 14.3 +/- 0.5 57.3 DR-22 11.4 +/- 0.8 11.3 +/- 0.7 12.2 +/- 0.5 11.4 +/- 0.7 11.6 +/- 0.4 46.3 DR-23 14.2 +/- 0.7 13.8 +/- 0.8 15.3 +/- 0.6 14.1 +/- 1.0 14.3 +/- 0.7 57.4 DR-24 14.8 +/- 0.7 14.6 +/- 0.8 15.9 +/- 0.8 14.9 +/- 0.9 15.1 +/- 0.6 60.2 DR-25 12.5 +/- 0.6 11.9 +/- 0.8 12.7 +/- 0.6 12.9 +/- 0.7 12.5 +/- 0.4 50.0 DR-26 14.7 +/- 0.8 13.3 +/- 0.9 14.1 +/- 0.7 13.9 +/- 0.7 14.0 +/- 0.6 56.0 DR-27 14.1 +/- 1.0 13.2 +/- 0.8 14.6 +/- 0.5 14.6 +/- 1.1 14.1 +/- 0.6 56.5 DR-28 19.9 +/- 0.8 19.8 +/- 1.2 20.5 +/- 0.9 20.5 +/- 0.9 20.2 +/- 0.4 80.6 DR-29 14.3 +/- 0.6 14.2 +/- 0.9 15.2 +/- 0.7 14.7 +/- 0.7 14.6 +/- 0.5 58.3 DR-30 14.5 +/- 0.7 14.3 +/- 0.9 15.8 +/- 0.8 14.7 +/- 0.8 14.8 +/- 0.6 59.3 DR-31 16.1 +/- 1.0 16.7 +/- 1.0 17.8 +/- 0.8 16.8 +/- 0.8 16.9 +/- 0.7 67.4 DR-32 13.1 +/- 0.7 13.7 +/- 0.9 14.2 +/- 0.6 13.5 +/- 0.8 13.6 +/- 0.5 54.5 DR-33 13.6 +/- 0.9 14.0 +/- 1.0 13.8 +/- 0.6 13.7 +/- 0.9 13.8 +/- 0.2 55.0 DR-34 13.3 +/- 0.9 13.7 +/- 0.8 14.0 +/- 0.5 13.7 +/- 0.7 13.7 +/- 0.3 54.7 DR-35 13.3 +/- 0.6 14.2 +/- 1.2 15.2 +/- 0.9 13.7 +/- 1.0 14.1 +/- 0.8 56.3 DR-36 14.5 +/- 0.7 15.1 +/- 0.9 15.0 +/- 0.8 15.0 +/- 1.2 14.9 +/- 0.3 59.4 DR-37 14.0 +/- 0.8 14.2 +/- 1,0 14.7 +/- 0.7 13.9 +/- 1.0 14.2 +/- 0.4 56.8 DR-38 12.2 +/- 0.6 13.0 +/- 0.8 13.2 +/- 0.5 11.9 +/- 0.8 12.6 +/- 0.6 50.3 DR-39 14.5 +/- 0.7 14.9 +/- 1.2 15.5 +/- 0.7 13.9 +/- 0.8 14.7 +/- 0.7 58.8 DR-40*

14.9 +/- 0.8 15.6 +/- 1.0 16.8 +/- 1.0 15.0 +/- 0.9 15.6 +/- 0.9 62.4 DR-41 13.0 +/- 0.7 13.9 +/- 0.9 14.3 +/- 0.6 12.4 +/- 0.6 13.4 +/- 0.9 53.5 AVERAGE 14.2 +/- 1.6 14.1 +/- 1.5 14.9 +/- 1.6 14.1 +/- 1.7 14.4 +/- 1.6 57.5 (Indicator Locations)

• Control location B-10

INDIAN POINT ENERGY CENTER TABLE 8-4 DIRECT RADIATION, 2007 THROUGH 2017 DATA mR per Year Station Mean Standard Deviation Minimum Value Maximum Value 2017 Annual Number (2007-2016)

(2007-2016)

(2007-2016)

(2007-2016)

Total DR-01 61.1 2.8 55.6 64.5 65.6 DR-02 57.7 1.4 55.9 59.8 60:1 DR-03 45.8 4.1 35.0 49.8 50.8 DR-04 53.5 1.1 52.2 55.8 54.8 DR-05 54.8 1.3 53.3 56.7 58.2 DR-06 56.1 1.2 54.7 57.9 58.0 DR-07 63.3

• 1.9 60.7 66.6 64.6 DR-08 47.4 1.7 45.1 50.6 48.9 DR-09 52.7 1.8 50.0 55.1 55.8 DR-10 57.9 4.1 54.4 67.7 55.1 DR-11 43.2 1.1 41.4 45.5 44.5 DR-12 60.8 4.7 49.2 68.3 64.8 DR-13 70.0 7.7 62.3 82.1 67.6 DR-14 52.9 1.6 50.5 55.3 54.0 DR-15 52.6 1.5 50.3 54.9 53.8 DR-16 57.9 1.8 55.1 60.6 59.3 DR-17 56.6 5.2 42.6 61.4 59.3 DR-18 56.6 1.5 54.4 59.1 57.5 DR-19 58.8 1.6 55.9 60.7 60.4 DR-20 54.3 1.3 52.2 56.3 56.7 DR-21 54.7 2.0 51.9 57.5 57.3 DR-22 44.9 1.3 42.6 46.8 46.3 DR-23 55.7 1.3 53.6 58.1 57.4 DR-24 57.9 1.2 55.8 59.7 60.2 DR-25 49.1 1.8 45.7 52.6 50.0 DR-26 55.8 1.6 53.0 58.9 56.0 DR-27 54.0 1.4 51.5 56.6 56.5 DR-28 78.2 1.2 76.5 80.4 80.6 DR-29 56.7 1.2 54.8 58.8 58.3 DR-30 58.1 2.2 54.7 61.9 59.3 DR-31 65.0 1.8 61.5 67.4 67.4 DR-32 52.1 1.8 48.7 54.7 54.5 DR-33 54.0 1.0 52.3 55.6 55.0 DR-34 50.1 4.2 38.5 53.7 54.7 DR-35 52.0 1.9 49.9 55.2 56.3 DR-36 58.3 1.7 55.9 60.2 59.4 DR-37 55.0 1.6 53.3 58.0 56.8 DR-38 49.2 2.8 46.6 56.0 50.3 DR-39 58.8 2.6 54.8 61.7 58.8 DR-40*

59.3 7.9 49.3 75.2 62.4 DR-41 50.9 1.5 48.4 53.9 53.5 AVERAGE 55.6 57.5 (Indicator Locations)

• Control location B-11

Inner Ring ID DR-01 DR-02 DR-03 DR-04 DR-05 DR-06 DR-07 DR-08 DR-09 DR-10 DR-11 DR-12 DR-13 DR-14 DR-15 DR-16 INDIAN POINT ENERGY CENTER TABLE B-5 DIRECT RADIATION, INNER AND OUTER RINGS - 2017 (mR per Year)

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

65.60 DR-18 NNE 60.10 DR-19 NE 50.80 DR-20 ENE 54.80 DR-21 E

58.20 DR-22 ESE 58.00 DR-23 SE 64.60 DR-24 SSE 48.90 DR-25 s

55.80 DR-26 SSW 55.10 DR-27 SW 44.50 DR-28 WSW 64.80 DR-29 w

67.60 DR-30 WNW 54.00 DR-31 NW 53.80 DR-32 NNW 59.30 Average 57.24 B-12 Outer Ring Annual Average 59.30 57.50 60.40 56.70 57.30 46.30 57.40 60.20 50.00 56.00 56.50 80.60 58.30 59.30 67.40 54.50 58.61

INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2017 PERIOD Algonquin ENDING 4

01/03/17 0.011 +/- 0.002 01/09/17 0.011 +/- 0.002 01/17/17 0.014 +/- 0.002 01/23/17 0.011 +/- 0.002 01/30/17 0.009 +/- 0.002 02/06/17 0.012 +/- 0.002 02/13/17 0.011 +/- 0.002 02/21/17 0.013 +/- 0.002 02/27/17 0.011 +/- 0.002 03/06/17 0.014 +/- 0.002 03/13/17 0.015 +/- 0.002 03/20/17 (a) 03/27/17 (b) 0.012 +/- 0.001 04/03/17 0.005 +/- 0.002 04/10/17 0.009 +/- 0.002 04/17/17 0.016 +/- 0.002 04/24/17 0.006 +/- 0.002 05/01/17 0.008 +/- 0.002 05/08/17 0.008 +/- 0.002 05/15/17 0.007 +/- 0.002 05/22/17 0.013 +/- 0.002 05/30/17 0.005 +/- 0.002 06/05/17 0.007 +/- 0.002 06/12/17 0.013 +/- 0.002 06/19/17 0.012 +/- 0.002 06/26/17 0.014 +/- 0.002

• Control Location (a) Sample not able to be collected (b) Two week sample NYU Tower 5

0.012 +/- 0.002 0.011 +/- 0.003 0.015 +/- 0.002 0.010 +/- 0.002 0.008 +/- 0.002 0.011 +/- 0.002

\\

0.010 +/- 0.002 0.015 +/- 0.003 0.011 +/- 0.002

. 0.012 +/- 0.002 0.016 +/- 0.003 0.016 +/- 0.002 0.014 +/- 0.002 0.005 +/- 0.002 0.009 +/- 0.002 0.016 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.006 +/- 0.002 0.005 +/- 0.002 0.013 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 (c) Detection level unable to be met due to low air volume.

pCi/m3 +/- 2 Sigma Roseton Croton Point Grassy Point Peekskill 23*

27 29 44 0.013 + 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.003 0.011 +/- 0.002 0.014 +/- 0.003 0.011 +/- 0.003 0.017 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 (c) < 0.029 0.011 +/- 0.002 0.011 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.003 0.011 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.003 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.002 0.008 +/- 0.002 0.006 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 0.004 +/- 0.002 0.010 +/- 0.004 0.009 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.005 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.005 +/- 0.002 0.005 +/- 0.002 0.005 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.003 B-13 Training Building Met Tower 94 95 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.003 0.011 +/- 0.003 0.011 +/- 0.002 0.014 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.003 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.003 0.009 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.016 +/- 0.003 0.013 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.005 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.002 0.016 +/- 0.002 0.009 +/- 0.002 0.004 +/- 0.001 0.006 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.003

INDIAN POINT ENERGY CENTER TABLE 8-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES -2017 pCi/m3 +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower ENDING 4

5 23*

27 29 44 94 95 07/03/17 0.012 +/- 0.002 0.017 +/- 0.003 0.011 +/- 0.002 0.017 +/- 0.003 0.017 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.003 07/10/17 0.010 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 07/17/17 0.015 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.003 07/24/17 0.016 +/- 0.002 0.015 +/- 0.002 0.018 +/- 0.003 0.017 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.003 07/31/17 0.009 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.010 :f 0.002 0.010 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 08/07/17 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.003 08/14/17 0.019 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 0.018 +/- 0.003 0.015 +/- 0.002 0.019 +/- 0.003 08/21/17 0.013 +/- 0.002 0.017 +/- 0.003 0.015 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 08/28/17 0.017 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.016 +/- 0.003 09/05/17 0.012 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 09/11/17 0.011 +/- 0.002 0.013 +/- 0.003 0.012 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.003 0.010 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 09/18/17 0.017 +/- 0.002 0.018 +/- 0.003 0.016 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 09/25/17 0.019 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.006 0.021 +/- 0.003 0.021 +/- 0.003 10/02/17 0.014 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 10/10/17 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.015 +/- *0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 10/16/17 0.014 +/- 0.003 0.012 +/- 0.003 0.010 +/- 0.002 0.013 +/- 0.003 0.015 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.013 +/- 0.003 10/23/17 0.017 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.003 10/30/17 0.010 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 11/06/17 0.013 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 11/13/17 0.011 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.003 0.010 +/- 0.002 0.011 +/- 0.002 11/21/17 0.017 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002

{c) < 0.187 0.017 +/- 0.002 0.015 +/- 0.002 11/27/17 0.018 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 12/04/17 0.016 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.002 0.017 +/- 0.002 12/11/17 0.015 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0.073 +/- 0.037 0.014 +/- 0.002 0.018 +/- 0.004 0.017 +/- 0.003 0.014 +/- 0.002 12/18/17 0.011 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.004 0.012 +/- 0.002 0.011 +/- 0.002 12/26/17 0.014 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002

• Control Location

{c) Detection level unable to be met due to low air volume.

B-14

PERIOD Algonquin ENDING 4

01/03/17

< 0.026 01/09/17

< 0.040 01/17/17

< 0.027 01/23/17

< 0.032 01/30/17

< 0.019 02/06/17

< 0.028 02/13/17

< 0.046 02/21/17

< 0.027 02/27/17

< 0.029 03/06/17

< 0.022 03/13/17

< 0.040 03/20/17 (a) 03/27/17 (b)

< 0.013 04/03/17

< 0.025 04/10/17

< 0.019 04/17/17

< 0.029 04/24/17

< 0.031 05/01/17

< 0.038 05/08/17

< 0.029 05/15/17

< 0.052 05/22/17

< 0.039 05/30/17

< 0.033 06/05/17

< 0.019 06/12/17

< 0.022 06/19/17

< 0.028 06/26/17

< 0.024

• Control Location (a) Sample not able to be collected (b) Two week sample INDIAN POINT ENERGY CENTER TABLE 8-7 IODINE-131 ACTIVITY IN AIRBORNE CHARCOAL SAMPLES -2017 pCi/m 3 +/- 2 Sigma NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower 5

23*

27 29 44 94 95

< 0.027

< 0.024

< 0.026

< 0.024

< 0.026

< 0.025

< 0.025

< 0.041

< 0.041

< 0.040

< 0.043

< 0.045

< 0.043

< 0.046

< 0.028

< 0.012

< 0.027

< 0.023

< 0.025

< 0.026

< 0.025

< 0.033

< 0.024

< 0.420

< 0.025

< 0.027

< 0.031

< 0.028

< 0.020

< 0.018

< 0.018

< 0.019

< 0.020

< 0.018

< 0.020

< 0.029

< 0.011

< 0.027

< 0.026

< 0.028

< 0.027

< 0.030

< 0.038

< 0.034

< 0.045

< 0.033

< 0.036

< 0.044

< 0.037

< 0.031

< 0.012

< 0.026

< 0.022

< 0.024

< 0.026

< 0.025

< 0.029

< 0.034

< 0.028

< 0.035

< 0.039

< 0.028

< 0.038

< 0.022

< 0.022

< 0.021

< 0.023

< 0.025

< 0.021

< 0.025

< 0.043

< 0.014

< 0.055

< 0.036

< 0.040

< 0.042

< 0.040

< 0.028

< 0.031

< 0.027

< 0.031

< 0.035

< 0.028

< 0.029

< 0.040

< 0.027

< 0.037

< 0.029

< 0.031

< 0.038

< 0.029

< 0.025

< 0.028

< 0.024

< 0.031

< 0.030

< 0.008

< 0.033

< 0.019

< 0.014

< 0.019

< 0.015

< 0.014

< 0.017

< 0.015

< 0.029

< 0.024

< 0.030

< 0.026

< 0.025

< 0.011

< 0.026

< 0.028

< 0.026

< 0.029

< 0.028

< 0.068

< 0.029

< 0.027

< 0.035

< 0.025

< 0.036

< 0.052

< 0.050

< 0.035

< 0.051

< 0.026

< 0.027

< 0.027

< 0.030

< 0.029

< 0.026

< 0.029

< 0.042

< 0.023

< 0.045

< 0.026

< 0.025

< 0.041

< 0.025

< 0.037

< 0.038

< 0.040

< 0.041

< 0.040

< 0.038

< 0.039

< 0.032

< 0.039

< 0.033

< 0.036

< 0.040

< 0.032

< 0.040

< 0.020

< 0.031

< 0.021

< 0.030

< 0.032

< 0.008

< 0.030

< 0.021

< 0.026

< 0,022

< 0.024

< 0.026

< 0.022

< 0.027

< 0.029

< 0.023

< 0.030

< 0.022

< 0.024

< 0.028

< 0.023

< 0.023

< 0.015

< 0.022

< 0.032

< 0.033

< 0.023

< 0.033 B-15

INDIAN POINT ENERGY CENTER TABLE 8-7 IODINE-131 ACTIVITY IN AIRBORNE CHARCOAL SAMPLES -2017 pCi/m3 +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower ENDING 4

5 23*

27 29 44 94 95 07/03/17

< 0.031

< 0.031

< 0.018

< 0.029

< 0.036

< 0.036

< 0.031

< 0.037 07/10/17

< 0.028

< 0.027

< 0.024

< 0.026

< 0.026

< 0.027

< 0.027

< 0.027 07/17/17

< 0.030

< 0.030

< 0.026

< 0.029

< 0.028

< 0.029

< 0.029

< 0.028 07/24/17

< 0.029

< 0.030

< 0.029

< 0.029

< 0.030

< 0.031

< 0.031

< 0.031 07/31/17

< 0.027

< 0.029

< 0.013

< 0.027

< 0.025

< 0.026

< 0.030

< 0.026 08/07/17

< 0.023

< 0.024

< 0.022

< 0.023

< 0.023

< 0.024

< 0.025

< 0.024 08/14/17

< 0.012

< 0.032

< 0.032

< 0.030

< 0.033

< 0.035

< 0.032

< 0.034 08/21/17

< 0.019

< 0.024

< 0.026

< 0.023

< 0.028

< 0.029

< 0.024

< 0.030 08/28/17

< 0.040

< 0.035

< 0.020

< 0.032

< 0.021

< 0.022

< 0.035

< 0.022 09/05/17

< 0.012

< 0.036

< 0.033

< 0.035

< 0.036

< 0.037

< 0.038

< 0.037 09/11/17

< 0.030

< 0.033

< 0.034

< 0.030

< 0.036

< 0.037

< 0.033

< 0.036 09/18/17

< 0.021

< 0.023

< 0.037

< 0.022

< 0.040

< 0.041

< 0.023

< 0.041 09/25/17

< 0.020

< 0.022

< 0.019

< 0.020

< 0.020

< 0.064

< 0.022

< 0.020 10/02/17

< 0.036

< 0.038

< 0.024

< 0.036

< 0.026

< 0.027

< 0.040

< 0.027 10/10/17

< 0.031

< 0,034

< 0.025

< 0.031

< 0.028

< 0.028

< 0.034

< 0.029 10/16/17

< 0.037

< 0.039

< 0.033

< 0.037

< 0.036

< 0.037

< 0.041

< 0.038 10/23/17

< 0.021

< 0.022

< 0.015

< 0.020

< 0.016

< 0.016

< 0.023

< 0.016 10/30/17

< 0.028

< 0.030

< 0.023

< 0.028

< 0.025

< 0.026

< 0.031

< 0.027 11/06/17

< 0.020

< 0.022

< 0.020

< 0.020

< 0.022

< 0.022

< 0.023

< 0.021 11/13/17

< 0.029

< 0.030

< 0.010

< 0.016

< 0.033

< 0.051

< 0.032

< 0.030 11/21/17

< 0.035

< 0.037

< 0.021

< 0.034

< 0.023

< 2.525,

< 0.039

< 0.021 11/27/17

< 0.030

< 0.031

< 0.017

< 0.030

< 0.020

< 0.020

< 0.034

< 0.018 12/04/17

< 0.024

< 0.024

< 0.029

< 0.024

< 0.032

< 0.033

< 0.027

< 0.028 12/11/17

< 0.023

< 0.023

< 0.035

< 0.711

< 0.040

< 0.068

< 0.027

< 0.035 12/18/17

< 0.025

< 0.025

< 0.014

< 0.029

< 0.019

< 0.047

< 0.029

< 0.017 12/26/17

< 0.046

< 0.045

< 0.034

< 0.052

< 0.038

< 0.039

< 0.054

< 0.035

• Control Location B-16

INDIAN POINT ENERGY CENTER TABLE 8-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES-2017 10-3 pCi/m3 +/- 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-7 115 +/- 19 92 +/- 24 146 +/- 26 94 +/- 18 117 + 24 119 +/- 19 102 +/- 21 98 +/- 26 K-40

< 12

< 26

< 19

< 14

< 21

< 26

< 8

< 31 Mn-54

< 1

<2

< 1

< 1

< 1

< 2

< 1

<2 Co-58

< 1

< 2

<2

< 1

< 2

< 2

<2

< 3 Fe-59

< 5

< 6

<7

<4

< 6

< 8

< 6

< 9 Co-60

< 1

< 2

< 1

< 1

< 1

< 1

< 1

< 3 Zn-65

< 3

<4

< 2

< 2

< 3

<4

< 5

< 4 Nb-95

< 2

< 2

< 2

< 2

<2

< 3

< 3

< 3 Zr-95

< 3

<4

<4

< 3

< 3

< 5

<4

< 7 Ru-103

< 2

<3

< 3

< 2

< 3

< 3

< 3

<4 Ru-106

< 10

< 10

< 11

< 8

< 12

< 16

< 11

< 16 1-131

< 152

< 144

< 487

< 244

< 216

< 226

< 526

< 436 Cs-134

< 1

< 1

< 1

< 1

< 1

< 2

< 1

< 2 Cs-137

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 2 Ba-140

< 77

< 76

< 143

< 85

< 119

< 112

< 212

< 186 La-140

< 23

< 40

< 62

< 23

< 34

< 42

< 87

< 87 Ce-141

<4

<4

< 5

<4

< 5

<6

< 5

< 7 Ce-144

< 5

<6

<6

< 5

< 7

< 9

< 6

< 7 Ra-226

< 15

< 23

< 21

< 15

< 24

< 28

< 19

< 29 Ac-228

<4

< 5

< 5

< 3

< 3

< 6

<4

< 6 Th-228

< 2

<2

<2

< 1

< 2

< 2

< 2

< 2 B-17

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2017 10-3 pCi/m3 +/- 2 Sigma Roseton Croton Point 23*

27 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 115 +/- 27 129 +/- 37 117 +/- 27 87 +/- 25 121 +/- 25 127 +/- 19 110 +/- 30 81 +/- 23 K-40

< 22

< 33

< 16

< 27

< 22

< 14

< 30

< 22 Mn-54

< 1

< 2

<2

< 1

< 1

< 1

< 2

< 1 Co-58

< 2

< 3

< 3

< 2

< 2

< 2

<4

< 1 Fe-59

< 5

< 10

< 11

<6

< 6

< 5

< 11

< 8 Co-60

< 1

<2

< 1

< 1

< 2

< 1

< 2

< 1 Zn-65

<4

< 6

<4

< 3

< 3

< 3

< 5

< 3 Nb-95

< 3

< 3

<4

<2

< 2

< 2

< 3

< 2 Zr-95

< 5

< 5

< 5

<4

< 3

< 3

<6

<4 Ru-103

<4

< 5

< 5

<4

<4

<2

< 5

< 3 Ru-106

< 15

< 19

< 20

, < 11

< 12

< 10

< 15

< 12 1-131

< 307

< 255

< 770

< 347

< 223

< 132

< 707

< 300 Cs-134

< 2

<2

< 2

< 1

< 1

< 1

< 2

< 1 Cs-137

< 1

< 2

< 2

< 1

< 1

< 1

< 2

< 1 Ba-140

< 146

< 138

< 282

< 140

< 123

< 80

< 316

< 106 La-140

< 45

< 42

< 104

< 64

< 36

< 20

< 143

< 40 Ce-141

< 6

< 5

< 9

< 5

< 5

<4

<7

< 5 Ce-144

< 8

<7

< 10

< 7

<7

<5

<7

< 5 Ra-226

< 26

< 25

< 28

< 24

< 25

< 16

< 25

< 18 Ac-228

< 6

<8

< 7

< 5

< 3

<4

<6

< 4 Th-228

< 2

<2

< 3

< 2

<2

<2

<2

< 2

• Control Location B-18

INDIAN POINT ENERGY CENTER TABLE.B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES -2017 10-3 pCi/m3 +/- 2 Sigma Grassy Point Peekskill 29 44 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 94 +/- 24 120 +/- 24 132 +/- 24 91 +/- 18 125 +/- 27 91 +/- 20 132 +/- 25 127 +/- 31 K-40

< 19

< 16

< 21

< 15

< 26

< 30

< 18

< 20 Mn-54

< 1

< 1

< 1

< 1

< 1

< 1

< 2

< 2 Co-58

< 2

<2

<3

< 2

< 2

< 2

< 1

< 2 Fe-59

< 6

< 6

< 8

<4

<4

<8

< 9

< 10 Co-60

< 1

< 1

<2

< 1

< 1

< 2

< 1

< 2 Zn-65

< 3

<4

<4

< 3

< 3

<4

<4

< 4 Nb-95

< 2

< 2

< 3

<2

< 3

< 2

< 2

. < 3 Zr-95

<4

< 3

< 5

< 3

< 3

<4

< 3

< 6 Ru-103

< 2

< 3

< 5

< 3

<4

< 3

< 3

< 5 Ru-106

< 9

< 10

< 15

< 8

< 15

< 10

< 12

< 19 1-131

< 176

< 140

< 709

< 245

< 251

< 158

< 497

< 492 Cs-134

< 1

< 1

<2

< 1

< 2

< 1

< 1

< 2 Cs-137

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 2 Ba-140

< 88

< 59

< 222

< 119

< 135

< 74

< 210

< 193 La-140

< 41

< 42

< 82

< 44

< 20

< 37

< 58

< 90 Ce-141

<4

<4

< 9

< 5

< 5

<4

<5

< 8 Ce-144

< 5

< 5

< 9

< 5

<7

<6

< 6

< 10 Ra-226

< 17

< 18

< 30

< 19

< 23

< 22

< 20

< 34 Ac-228

< 5

<4

< 6

<4

<6

< 6

<4

< 8 Th-228

< 2

<2

<2

< 1

<2

<2

< 2

< 3 B-19 L_

INDIAN POINT ENERGY CENTER TABLE 8-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES-2017 10-a pCi/m3 +/- 2 Sigma Training Building Met Tower 94 95 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 133 +/- 21 134 +/- 24 125 +/- 25 81 +/- 22 122 +/- 23 101 +/- 20 118 +/- 30 93 +/- 21 K-40

< 12

< 13

< 8

< 16

< 27

< 21

< 11

< 11 Mn-54

< 1

<2

< 1

< 1

< 1

<2

< 1

< 1 Co-58

< 2

<2

<2

< 3

<2

< 2

< 2

< 2 Fe-59

< 5

< 5

< 5

< 5

<6

< 5

< 8

< 8 Co-60

< 1

< 1

<2

< 1

<2

< 1

<2

< 1 Zn-65

< 3

<4

< 3

< 3

< 3

<3

< 5

< 3 Nb-95

<2

< 2

< 2

< 2

< 2

<2

< 2

< 2 Zr-95

<4

<4

< 5

< *3

<3

<4

< 3

< 3 Ru-103

<2

<2

< 3

< 3

< 3

< 3

<4

< 3 Ru-106

< 9

< 11

< 12

< 12

< 13

< 11

< 8

< 9 1-131

< 219

< 150

< 444

< 361

< 216

< 174

< 540

< 303 Cs-134

< 2

< 1

< 1

< 2

< 2

< 1

< 1

< 1 Cs-137

< 1

< 1

< 1

< 2

< 1

< 1

< 1

< 1 Ba-140

< 91

< 91

< 143

< 154

< 130

< 95

< 191

< 123 La-140

< 18

< 24

< 79

< 39

< 35

< 37

< 87

< 64 Ce-141

< 3

<4

< 6

< 5

< 5

<4

<6

<4 Ce-144

< 5

< 5

< 6

<6

<6

<7

< 6

< 6' Ra-226

< 18

< 21

< 21

< 20

< 23

< 21

< 20

< 19 Ac-228

<4

< 5

< 5

<4

<6

< 5

< 6

< 5 Th-228

< 2

< 2

<2

< 2

<2

< 2

< 2

< 1 B-20

INDIAN POINT !ENERGY CENTER TABLE B-9 RADIONUCLIDES IN RAINWATER SAMPLES -2017 pCi/L +/- 2 Sigma Roseton Peekskill 23*

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

< 172

< 191

< 178

< 175

< 173

< 186

< 173

< 177 GAMMA Be-7

< 9

< 10

< 8

< 11

< 12

< 10

< 11

< 18 K-40

< 5

< 14

< 14

< 21

< 6

< 24

< 7

< 11 Mn-54

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 1 Co-58

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 2 Fe-59

< 2

< 2

< 2

< 3

< 3

< 2

< 3

<4 Co-60

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 1 Zn-65

< 1

< 1

< 1

< 2

< 1

< 2

< 2

<3 Nb-95

< 1

< 1

< 1

< 1

< 1

< 1

< 1

<2 Zr-95

< 1

< 1

< 1

< 2

< 2

< 2

< 2

< 3 Ru-103

< 1

< 1

< 1

< 2

< 1

< 1

< 2

<2 Ru-106

< 5

< 6

< 6

< 6

< 7

< 7

< 7

< 8 1-131

< 55

< 39

< 36

< 72

< 69

< 44

< 47

< 113 Cs-134

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 1 Cs-137

< 1

< 1

< 1

< 1

< 1

< 1

< 1

< 1 Ba-140

< 32

< 34

< 29

< 45

< 43

< 31

< 31

< 66 La-140

< 9

< 9

< 9

< 16

< 12

< 9

< 9

< 23 Ce-141

< 3

< 3

< 3

< 3

< 3

< 3

< 3

< 5 Ce-144

< 5

< 6

< 6

< 5

< 6

< 5

< 6

< 7 Ra-226

< 17

< 15

< 16

< 17

< 15

< 20

< 21

< 27 Ac-228

<2

< 3

< 3

< 3

< 3

<4

<4

< 5 Th-228

< 1 10 +/- 3

< 2

< 2

< 2 5 +/- 3

< 1

<2

• Control Location B-21

INDIAN POINT ENERGY CENTER TABLE 8-10 RADIONUCLIDES IN DRINKING WATER SAMPLES -2017 pCi/L +/- 2 Sigma Camp Field 7

DATE 01/10/17 02/14/17 03/20/17 04/12/17 05/08/17 06/13/17 RADIOCHEMICAL Gr-B 4 +/- 2

< 3

< 2 3 +/- 1

< 2

< 2 H-3 (a)

< 190

< 180 GAMMA Be-7

< 48

< 48

< 46

< 41

< 45

< 60 K-40

< 102

< 111

< 43

< 54

< 48

< 145 Mn-54

<4

<4

< 6

< 5

< 6

< 9 Co-58

< 5

< 5

< 3

< 5

< 6

< 7 Fe-59

< 10

< 11

< 10

< 8

< 11

< 15 Co-60

< 7

<4

< 6

<2

< 7

<4 Zn-65

< 9

< 12

< 7

< 13

< 11

< 17 Nb-95

< 5

< 7

< 5

<6

< 6

< 7 Zr-95

< 9

< 8

< 10

<7

< 10

< 11 Ru-103

< 5

< 5

< 6

< 6

< 6

< 8 Ru-106

< 53

< 51

< 47

< 53

< 53

< 56 1-131

< 9

< 10

< 7

< 8

< 8

< 9 Cs-134

< 5

<6

< 5

< 6

< 6

<7 Cs-137

. < 6

<6

< 6

< 6

< 6

< 8 Ba-140

< 24

< 20

< 17

< 24

< 25

< 31 La-140

< 6

<7

< 7

< 8

< 7

< 10 Ce-141

< 10

< 11

< 9

< 8

< 11

< 13 Ce-144

< 41

< 41

< 44

< 39

< 48

< 56 Ra-226

< 126

< 134

< 126

< 154

< 160

< 191 Ac-228

< 24

< 23

< 13

< 20

< 29

< 36 Th-228

< 11

< 11

< 9

< 11

< 13

< 15 (a) Quarterly Composite B-22 J

INDIAN POINT ENERGY CENTER TABLE 8-10 RADIONUCLIDES IN DRINKING WATER SAMPLES -2017 pCi/L +/- 2 Sigma Camp Field 7

DATE 07/11/17 08/15/17 09/12/17 10/06/17 11/28/17 12/11/17 RADIOCHEMICAL Gr-B 3 +/- 2

<2 4 +/- 2 3 +/- 2 5 +/- 2 3 +/- 2 H-3 (a)

< 178

< 184 GAMMA Be-7

< 49

< 37

< 47

< 54

< 84

< 68 K-40

< 139

< 41

< 104

< 87

< 144

< 101 Mn-54

< 6

< 5

< 5

< 4

< 8

< 9 Co-58

< 6

<4

< 5

< 6

< 9

< 11 Fe-59

< 12

< 10

< 11

< 16

< 12

< 16 Co-60

< 5

<4

<4

< 7

< 8

< 11 Zn-65

< 13

< 8

< 10

< 14

< 21

< 19 Nb-95

< 6

< 5

< 5

<7

< 9

< 8 Zr-95

< 10

< 8

< 9

< 11

< 15

< 14 Ru-103

< 6

<4

< 6

< 7

< 10

< 8 Ru-106

< 53

< 35

< 47

< 60

< 80

< 77 1-131

< 11

< 6

< 15

< 14

< 12

< 12 Cs-134

< 8

< 5

< 6

< 6

< 10

< 9 Cs-137

< 7

< 5

< 5

.< 5

< 9

< 9 Ba-140

< 31

< 20

< 39

< 30

< 38

< 35 La-140

<7

< 5

< 11

< 8

< 10

< 9 Ce-141

< 11

< 8

< 11

< 13

< 20

< 12 Ce-144

< 43

< 35

< 36

< 43

< 86

< 49 Ra-226

< 125

< 137

< 133

< 159

< 285

< 191 Ac-228

< 25

< 15

< 22

< 22

< 38

< 31 Th-228

< 12

< 10

< 9

< 11

< 20

< 14 (a) Quarterly Composite 8-23

INDIAN POINT ENERGY CENTER TABLE 8-10 RADIONUCLIDES IN DRINKING WATER SAMPLES -2017 pCi/L +/- 2 Sigma Croton 8

DATE 01/10/17 02/14/17 03/20/17 04/12/17 05/08/17 06/13/17 RADIOCHEMICAL Gr-B 3 +/- 2

<2 3 +/- 2 3 +/- 2 3 +/- 2 2 +/- 1 H-3 (a)

< 190

< 182 GAMMA Be-7

< 66

< 59

< 56

< 70

< 86

< 55 K-40

< 95

< 147

< 146

< 101

< 144

< 119 Mn-54

< 8

< 6

< 7

< 9

< 9

< 7 Co-58

< 6

< 7

< 6

< 12

< 9

< 7 Fe-59

< 17

< 13

< 12

< 21

< 16

< 15 Co-60

< 9

< 8

< 7

< 8

< 9

< 9 Zn-65

< 11

< 13

< 14

< 16

< 20

< 13 Nb-95

< 9

< 6

< 6

< 10

< 9

< 8 Zr-95

< 13

< 14

< 11

< 14

< 14

< 13 Ru-103

< 8

< 8

< 6

< 9

< 9

< 8 Ru-106

< 69

< 50

< 54

< 86

< 77

< 63 1-131

< 13

< 12

< 9

< 12

< 11

< 9 Cs-134

< 8

< 6

< 8

< 9

< 8

< 9 Cs-137

<6

< 8

< 8

< 11

< 12

< 7 Ba-140

< 33

< 33

< 23

< 40

< 39

< 28 La-140

< 12

< 9

< 8

< 14

< 11

< 8 Ce-141

< 14

< 13

< 11

< 13

< 14

< 12 Ce-144

< 60

< 49

< 48

< 50

< 58

< 50 Ra-226

< 194

< 188

< 152

< 186

< 215

< 191 Ac-228

< 29

< 24

< 31

< 32

< 40

< 25 Th-228

< 15

< 13

< 14

< 15

< 17.

< 16 (a) Quarterly Composite B-24

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES -2017 pCi/L +/- 2 Sigma Croton 8

DATE 07/11/17 08/15/17 09/12/17 10/06/17 11/28/17 12/11/17 RADIOCHEMICAL Gr-B 3 +/- 2

< 2 3 +/- 2 3 +/- 2 4 +/- 2

<2 H-3 (a)

< 179

< 185 GAMMA Be-7

< 69

< 55

< 37

< 48

< 69

< 56 K-40

< 116

< 72

< 61

< 110

< 172

< 145 Mn-54

< 8

< 5

< 3

< 5

< 8

< 7 Co-58

< 8

<6

< 5

< 5

< 8

< 5 Fe-59

< 15

< 11

< 9

< 12

< 13

< 10 Co-60

< 8

< 6

< 3

< 6

< 7

< 8 Zn-65

< 15

< 13

< 8

< 8

< 18

< 14 Nb-95

< 8

< 5

<4

<6

< 8

< 8 Zr-95

< 12

< 9

< 7

< 9

< 14

< 13 Ru-103

< 9

< 6

<4

<7

< 8

<7 Ru-106

< 66

< 49

< 36

< 51

< 73

< 71 1-131

< 12

< 8

< 13

< 13

< 10

< 10 Cs-134

< 9

< 7

<4

< 6

< 10

< 7 Cs-137

< 8

< 6

<4

< 6

< 8

< 7 Ba-140

< 31

< 24

< 31

< 31

< 36

< 30 La-140

< 14

< 7

< 8

< 10

< 8

< 11 Ce-141

< 13

< 10

< 8

< 12

< 11

< 13 Ce-144

< 46

< 45

< 27

< 46

< 49

< 55 Ra-226

< 179

< 146

< 107

< 141

< 167

< 180 Ac-228

< 30

< 25

< 15

< 19

< 31

< 25 Th-228

< 13

< 13

< 8

< 11

< 13

< 16 (a) Quarterly Composite B-25

DATE 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-103 Ru-106 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ac-228 INDIAN POINT ENERGY CENTER TABLE B-11 RADIONUCLIDES IN GROUNDWATER SAMPLES-2017 04/18/17

< 194

< 14

< 1

< 89

< 138

< 11

< 9

< 16

< 11

< 25

< 13

< 17

< 10

< 87

< 10

< 12

< 38

< 13

< 19

< 80

< 48 pCi/L +/- 2 Sigma Lafarge Monitoring Well 106 B-26 11/16/17

< 177

< 13

< 0

< 33

< 27

< 3

< 3

< 6

< 3

< 7

<4

< 6

<4

< 30

< 3

<4

< 24

< 7

< 9

< 32

< 11

INDIAN POINT ENERGY CENTER TABLE 8-12 GAMMA EMITTERS IN SOIL SAMPLES, 2017 pCi/kg dry+/- 2 Sigma Roseton Training Building Met Tower 23*

94 95 DATE 09/25/17 09/25/17 09/25/17 Be-7

< 501

< 698

< 446 K-40 19650 +/- 1750 14310 +/- 1473 8959 +/- 966 Mn-54

< 59

< 69

< 46 Co-58

< 66

< 74

< 46 Fe-59

< 128

< 160

< 85 Co-60

< 61

< 69

< 41 Zn-65

< 164

< 158

< 107 Nb-95

< 72

< 79

< 53 Zr-95

< 122

< 129

< 77 Ru-103

< 51

< 73

< 50 Ru-106

< 455

< 616

< 436 1-131

< 102

< 149

< 83 Cs-134

< 74

< 88

< 62 Cs-137 249 +/- 63 191 +/- 68 222 +/- 68 Ba-140

< 293

< 386

< 228 La-140

< 105

< 93

< 66 Ce-141

< 91

< 134

< 78 Ce-144

< 320

< 478

< 304 Ra-226 1687 +/- 932

< 1617

< 1229 Th-228 948 +/- 100 747 +/- 121 217 +/- 80

• Control Location

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 05/17/17 05/17/17 05/17/17 06/21/17 06/21/17 06/21/17 GAMMA Be-7 450 +/- 224 389 +/- 207 891 +/- 248 616 +/- 102

< 155 2186 +/- 152 K-40 4282 +/- 545 4563 +/- 526 6909 +/- 555 4956 +/- 214 4627 +/- 234 7776 +/- 316 Mn-54

< 23

< 23

< 23

< 9

< 10

< 10 Co-58

< 26

< 25

< 22

< 10

< 11

< 11 Fe-59

< 53

< 46

< 49

< 22

< 30

< 32 Co-60

< 25

< 20

< 25

< 9

< 10

< 11 Zn-65

< 58

< 46

< 53

< 22

< 21

< 26 Nb-95

< 24

< 26

< 22

< 10

< 12

< 12 Zr-95

< 39

< 43

< 41

< 17

< 21

< 19 Ru-103

< 25

< 25

< 23

< 12

< 12

< 12 Ru-106

< 189

< 197

< 212

< 72

< 86

< 93 1-131

< 34

< 30

< 30

< 50

< 53

< 54 Cs-134

< 23

< 30

< 25

< 9

< 10

< 11 Cs-137

< 25

< 29

< 21

< 9

< 10

< 10 Ba-140

< 98

< 115

< 97

< 87

< 93

< 97 La-140

< 27

< 26

< 20

< 24

< 25

< 23 Ce-141

< 39

< 37

< 34

< 20

< 17

< 21 Ce-144

< 163

< 155

< 141

< 60

< 49

< 63 Ra-226

< 544

< 540

<_482

< 203

< 173

< 197 Th-228

< 41

< 43

< 40

< 17

< 15 22 +/- 12

• Control Location 8-28

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 07/26/17 07/26/17 07/26/17 08/23/17 08/23/17 08/23/17 GAMMA Be-7 2141 +/- 401 2248 +/- 442 1245 +/- 401 2056 +/- 394 1216 +/- 317 1811 +/- 321 K-40 5973 +/- 674 4664 +/- 693 3614 +/- 623 3086 +/- 583 4882 +/- 649 7461 +/- 842 Mn-54

< 39

< 27

< 32

< 36

< 38

< 25 Co-58

< 37

< 28

< 28

< 29

< 33

< 30 Fe-59

< 79

< 62

< 64

< 58

< 81

< 60 Co-60

< 42

< 19

< 30

< 35 0

37

< 39 Zn-65

< 93

< 67

< 65

< 69

< 86

< 79 Nb-95

< 39

< 35

< 44

< 41

< 32

< 29 Zr-95

< 60

< 46

< 64

< 52

< 57

< 59 Ru-103

< 36

< 33

< 40

< 33

< 37

< 30 Ru-106

< 348

< 254

< 306

< 322

< 363

< 269 1-131

< 59

< 53

< 58

< 45

< 54

< 41 Cs-134

< 37

< 38

< 40

< 39

< 40

< 37 Cs-137

< 35

< 33

< 30

< 32

< 42

< 27 Ba-140

< 176

< 135

< 164

< 146

< 165

< 110 La-140

< 46

< 46

< 45

<.42

< 46

< 41 Ce-141

< 57

< 44

< 61

< 56

< 55

< 45 Ce-144

< 211

< 195

< 205

< 263

< 235

< 191 Ra-226

< 814

< 603

< 935

< 912

< 814

< 699 Th-228

< 70

< 46

< 69

< 68

< 63

< 56

• Control Location B-29

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 09/25/17 09/25/17 09/25/17 10/06/17 10/06/17 GAMMA Be-7 1667 +/- 509 521 +/- 310 1464 +/- 423 1887 +/- 334 4782 +/- 337 K-40 2087 +/- 609 6558 +/- 853 3780 +/- 817 2940 +/- 619 5436 +/- 464 Mn-54

< 44

< 40

< 44

< 20

< 20 Co-58

< 37

< 36

< 36

< 32

< 17 Fe-59

< 56

< 88

< 88

< 58

< 48 Co-60

< 29

< 41

< 29

< 23

< 20 Zn-65

< 70

< 111

< 93

< 53

< 48 Nb-95

< 34

< 36

< 41

< 28

< 21 Zr-95

< 57

< 63

< 80

< 49

< 33 Ru-103

< 43

< 45

< 35

< 28

< 21 Ru-106

< 362

< 366

< 332

< 235

< 200 1-131

< 54

< 56

< 50

< 57

< 46 Cs-134

< 37

< 48

< 48

< 27

< 23 Cs-137

< 35

< 42

< 48

< 26

< 21 Ba-140

< 154

< 151

< 186

< 134

< 118 La-140

< 31

< 35

< 62

< 50

< 22 Ce-141

< 61

< 65

< 67

< 43

< 37 Ce-144

< 246

< 271

< 239

< 159

< 135 Ra-226

< 1056

< 983

< 1035

< 691

< 469 Th-228

< 66

< 78

< 91

< 54

< 34

• Control Location B-30

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 05/17/17 05/17/17 05/17/17 06/21/17 06/21/17 06/21/17 GAMMA Be-7 404 +/- 161 855 +/- 177

< 178 1315 +/- 111 524 +/- 84 184 +/- 75 K-40 4154 +/- 442 8048 +/- 650 3345 +/- 473 7222 +/- 263 2672 +/- 169 5707 +/- 220 Mn-54

< 15

< 17

< 23

< 8

< 8

< 8 Co-58

< 19

< 19

< 18

< 9

< 9

< 9 Fe-59

< 42

< 46

< 47

< 26

< 21

< 23 Co-60

< 19

< 26

< 18

< 9

< 9

< 8 Zn-65

< 43

< 59

< 47

< 20

< 19

< 19 Nb-95

< 18

< 21

< 22

< 10

< 10

< 9 Zr-95

< 30

< 38

< 35

< 16

< 16

< 16 Ru-103

< 19

< 20

< 21

< 11

< 11

< 10 Ru-106

< 142

< 206

< 188

< 71

< 77

< 71 1-131

< 28

< 29

< 29

< 47

< 48

< 41 Cs-134

< 16

< 23

< 20

< 9

< 9

< 8 Cs-137

< 19

< 22

< 23

< 8

< 9

< 8 Ba-140

< 78

< 71

< 92

< 81

< 85

< 77 La-140

< 20.

< 23

< 27

< 23

< 23

< 19 Ce-141

< 29

< 33

< 33

< 16

< 18

< 16 Ce-144

< 124

< 128

< 141

< 49

< 54

< 48 Ra-226

< 498

< 451

< 528

< 192

< 167

< 143 Th-228

< 32

< 38

< 37

< 14

< 14

< 12 8-31

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 07/26/17 07/26/17 07/26/17 08/23/17 08/23/17 08/23/17 GAMMA Be-7 2564 +/- 349 1217 +/- 284 2059 +/- 398 2259 +/- 437 1604 +/- 412 1204 +/- 342 K-40 6938 +/- 697 2257 +/- 532 7014 +/- 829 6448 +/- 810 2695 +/- 596 4094 +/- 712 Mn-54

< 29

< 29

< 32

< 33

< 35

< 23 Co-58

< 26

< 20

< 35

< 35

< 33

< 31 Fe-59

< 58

< 65

< 74

< 67

< 61

< 62 Co-60

< 28

< 38

< 33

< 35

< 39

< 35 Zn-65

< 69

< 57

< 84

< 68

< 59

< 75 Nb-95

< 29

< 34

< 35

< 32

< 34

< 38 Zr-95

< 45

< 62

< 54

< 57

< 55

< 54 Ru-103

< 28

< 30

< 30

< 30

< 37

< 38 Ru-106

< 257

< 255

< 255

< 278

< 352

< 401 1-131

< 45

< 51

< 52

< 39

< 56

< 58 Cs-134

< 29

< 38

< 31

< 36

< 45

< 36 Cs-137

< 29

< 37

< 41

< 33

< 37

< 34 Ba-140

< 119

< 177

< 146

< 146

< 141

< 157 La-140

< 27

< 42

< 40

< 15

< 43

< 24 Ce-141

< 48

< 51

< 47

< 53

< 60

< 53 Ce-144

< 191

< 201

< 205

< 202

< 246

< 202 Ra-226

< 695

< 802

< 813

< 859

< 937

< 955 Th-228

< 54

< 64

< 59

< 66

< 80

< 70 B-32

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 09/25/17 09/25/17 09/25/17 10/06/17 10/06/17 GAMMA Be-7 2294 +/- 477 4681 +/- 608 1657 +/- 475 1098 +/- 365 2471 +/- 358 K-40 2447 +/- 618 5960 +/- 960 4497 +/- 829 2616 +/- 507 6202 +/- 654 Mn-54

< 46

< 43

< 47

< 27

< 24 Co-58

< 43

< 37

< 44

< 30

< 26 Fe-59

< 40

< 86

< 83

< 71

< 51 Co-60

< 48

< 37

< 34

< 30

< 25 Zn-65

< 97

< 91

< 89

< 68

< 55 Nb-95

< 49

< 47

< 42

< 25

< 23 Zr-95

< 72

< 59

< 57

< 54

< 44 Ru-103

< 38

< 42

< 40

< 39

< 25 Ru-106

< 371

< 388

< 323

< 288

< 193 1-131

< 57

< 56

< 49

< 56

< 60 Cs-134

< 49

< 52

< 41

< 22

< 24 Cs-137

< 41

< 47

< 49

< 27

< 28 Ba-140

< 168

< 153

< 164

< 181

< 116 La-140

< 39

< 48

< 56

< 57

< 29 Ce-141

< 73

< 66

< 64

< 51

< 42 Ce-144

< 313

< 258

< 255

< 212

< 147 Ra-226

< 1035

< 834

< 1119

_< 637

< 621 Th-228

< 74

< 82

< 75

< 49

< 44 B-33

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 05/17/17 05/17/17 05/17/17 06/21/17 06/21/17 06/21/17 GAMMA Be-7 905 +/- 221 852 +/- 228 608 +/- 186 1551 +/- 105 1302 +/- 130 1427 +/- 120 K-40 3514 +/- 507 8693 +/- 646 6645 +/- 499 7516 +/- 237 3344 +/- 209 4304 +/- 176 Mn-54

< 23

< 23

< 21

< 9

< 9

< 9 Co-58

< 25

< 20

< 19

< 9

< 11

< 10 Fe-59

< 56

< 47

< 36

< 24

< 23

< 22 Co-60

< 23

< 19

< 18

< 8

< 9

<8 Zn-65

< 52

< 47

< 48

< 21

< 21

< 21 Nb-95

< 25

< 21

< 18

< 9

< 11

< 10 Zr-95

< 47

< 39

< 38

< 17

< 19

< 18 Ru-103

< 22

< 19

< 18

< 11

< 12

< 12 Ru-106

< 201

< 171

< 170

< 75

< 84

< 80 1-131

< 32

< 29

< 26

< 45

< 54

< 54 Cs-134

< 27

< 23

< 20

< 9

< 10

< 10 Cs-137

< 25

< 23

< 20

< 8

< 9

< 9 Ba-140

< 107

< 85

< 77

< 82

< 92

< 90 La-140

< 33

< 21

< 19

< 21

< 25

< 22 Ce-141

< 30

< 31

< 29

< 17

< 18

< 23 Ce-144

< 114

< 132

< 131

< 51

< 49

< 68 Ra-226

< 466

< 477

< 439

< 171

< 199

< 217 Th-228

< 38

< 35

< 32

< 13

< 16

< 18 8-34

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 07/26/17 07/26/17 07/26/17 08/23/17 08/23/17 08/23/17 GAMMA Be-7 2582 +/- 319 708 +/- 399 1671 +/- 378 1039 +/- 364 1115 +/- 324 2423 +/- 442 K-40 6697 +/- 743 5236 +/- 854 4168 +/- 597 6054 +/- 960 5997 +/- 694 6693 +/- 1024 Mn-54

< 27

< 27

< 29

< 38

< 41

< 38 Co-58

< 32

< 32

< 24

< 38

< 36

< 42 Fe-59

< 69

< 73

< 54

< 97

< 70

< 78 Co-60

< 29

< 26

< 23

< 32

< 41

< 47 Zn-65

< 75

< 74

< 52

< 111

< 95

< 94 Nb-95

< 32

< 29

< 29

< 39

< 40

< 37 Zr-95

< 50

< 66

< 42

< 79

< 64

< 50 Ru-103

< 24

< 32

< 30

< 32

< 35

< 40 Ru-106

< 259

< 277

< 254

< 329

< 328

< 235 1-131

< 51

< 58

< 51

< 58

< 52

< 55 Cs-134

< 37

< 43

< 30

< 37

< 42

< 38 Cs-137

< 29

< 32

< 32

< 41

< 36

< 45 Ba-140

< 133

< 154

< 124

< 182

< 152

< 136 La-140

< 40

< 32

< 27

< 54

< 45

< 45 Ce-141

< 47

< 58

< 45

< 57

< 50

< 54 Ce-144

< 184

< 210

< 185

< 245

< 199

< 245 Ra-226

< 65.9

< 822

< 661

< 987

< 742

< 888 Th-228

< 59

< 66

< 54

< 77

< 58

< 69 8-35

INDIAN POINT ENERGY CENTER TABLE 8-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 09/25/17 09/25/17 09/25/17 10/06/17 10/06/17 GAMMA Be-7 2784 +/- 452 801 +/- 440 978 +/- 313 2656 +/- 290 2160 +/- 286 K-40 6597 +/- 1018 4889 +/- 912 5233 +/- 904 6926 +/- 541 3153 +/- 429 Mn-54

< 38

< 43

< 37

< 21

< 23 Co-58

< 36

< 29

< 28

< 21

< 22 Fe-59

< 90

< 93

< 79

< 53

< 58 Co-60

< 34

< 44

< 50

< 24

< 24 Zn-65

< 78

< 96

< 82

< 53

< 51 Nb-95

< 41

< 47

< 43

< 23

< 27 Zr-95

< 69

< 77

< 64

< 39

< 40 Ru-103

< 37

< 41

< 36

< 23

< 24 Ru-106

< 360

< 384

< 347

< 177

< 185 1-131

< 43

< 54

< 46

< 52

< 57 Cs-134

< 29

< 53

< 50

< 26

< 27 Cs-137

< 36

< 41

< 45

< 23

< 22 Ba-140

< 143

< 150

< 141

< 128

< 137 La-140

< 44

< 66

< 46

< 39

< 43 Ce-141

< 53

< 62

< 53

< 37

< 41 Ce-144

< 219

< 256

< 211

< 138

< 154 Ra-226

< 875

< 832

< 710

< 539

< 571 Th-228

< 70

< 74

< 64

< 36

< 39 B-36

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES-2017 pCi/L +/- 2 Sigma Plant Inlet Hudson River Intake 9*

DATE 01/31/17 02/28/17 03/29/17 04/25/17 05/31/17 06/27/17 RADIOCHEMICAL H-3 (a)

< 189

< 195 GAMMA K-40

< 32 152 +/- 42

< 19

< 14

< 21

< 65 Mn-54

< 2

< 3

< 2

< 2

< 1

< 3 Co-58

< 2

< 3

<2

< 2

< 1

< 3 Fe-59

<4

< 7

< 5

<4

< 3

< 8 Co-60

< 2

< 3

< 2

< 2

< 1

< 3 Zn-65

< 3

< 7

<4

<4

< 2

< 7 Nb-95

< 2

<4

< 2

< 2

< 1

<4 Zr-95

< 3

< 6

<4

< 3

< 3

<6 Ru-103

< 2

<4

< 2

< 2

<2

<4 Ru-106

< 15

< 26

< 15

< 15

< 11

< 30 1-131

< 9

< 12

< 10

< 9

< 15

< 11 Cs-134

<2

< 3

<2

<2

< 1

<4 Cs-137

<2

< 3

< 2

< 2

< 1

< 3 Ba-140

< 15

< 24

< 18

< 16

< 19

< 25 La-140

< 5

< 9

<6

< 6

<6

< 8 Ce-141

<4

< 6

<4

<4

< 4

< 6 Ce-144

< 13

< 17

< 13

< 12

< 9

< 18 Ra-226

< 42

< 65

< 40

< 36

< 26

< 67 Ac-228

< 6

< 12

< 7

< 8

< 5

< 12 Th-228 7 +/- 3

< 5

< 3

< 3

< 2

< 5

• Control Location (a) Quarterly Composite 8-37

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES-2017 pCi/L +/- 2 Sigma Plant Inlet Hudson River Intake 9*

DATE 07/25/17 08/29/17 09/27/17.

10/31/17 11/28/17 12/27/17 RADIOCHEMICAL H-3 (a)

< 193

< 196 GAMMA K-40

< 17

< 16

< 13 74 +/- 31

< 44

< 16 Mn-54

< 2

<2

< 1

< 2

<2

< 2 Co-58

<2

< 2

< 2

< 2

< 3

< 2 Fe-59

< 5

< 5

<4

< 5

< 6

< 5 Co-60

<2

< 2

< 1

< 2

< 2

< 2 Zn-65

<4

<4

<*3

<4

< 5

<4 Nb-95

< 3

<2

< 2

<2

< 3

<2 Zr-95

< 4

<4

< 3

<4

< 5

< 3 Ru-103

< 3

< 3

~ 2

< 3

< 3

<2 Ru-106

< 18

< 17

< 12

< 17

< 21

< 16 1-131

< 14

< 14

< 15

< 15

< 9

< 11 Cs-134

<2

< 2

< 1

< 2

<3

< 2 Cs-137

<2

<2

< 1

< 2

< 2

< 2 Ba-140

< 24

< 24

< 20

< 22

< 19

< 17 La-140

<7

< 7

< 7

< 7

< 6

<6 Ce-141

< 5

<4

<4

< 5

< 5

<4 Ce-144

< 16

< 11

< 10

< 15

< 17

< 11 Ra-226

< 58

< 35

< 37

< 47

< 62

< 37 Ac-228

< 9

< 8

< 5

<6

< 8

< 7 Th-228

< 3

< 3

< 2

< 3

< 5

< 3

• Control Location (a) Quarterly Composite 8-38

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES -2017 pCi/L +/- 2 Sigma Discharge Canal 10 DATE 01/31/17 02/28/17 03/29/17 04/25/17 05/31/17 06/27/17 RADIOCHEMICAL H-3 (a) 216 +/- 128

< 191 GAMMA K-40

< 13

< 47

< 21

< 19

< 27

< 51 Mn-54

< 2

< 3

< 2

< 2

< 1

< 3 Co-58

< 2

< 3

< 2

< 2

< 1

< 3 Fe-59

<4

<6

< 5

< 5

< 3

<7 Co-60

<2

< 3

< 2

< 2

< 1

< 3 Zn-65

< 3

< 5

<4

<4

< 2

<6 Nb-95

< 2

< 3

< 2

< 2

< 1

<3 Zr-95

< 3

< 5

< 4

<4

<2

< 6 Ru-103

< 2

< 3

< 3

< 3

<2

<4 Ru-106

< 14

< 22

< 18

< 19

< 10

< 31 1-131

< 8

< 10

< 12

< 12

< 1---4

< 13 Cs-134

< 1

< 3

<2

< 2

< 1

< 3 Cs-137

<2

< 3

< 2

< 2

< 1

< 3 Ba-140

< 15

< 22

< 22

< 21

< 18

< 26 La-140

<4

< 6

< 7

<6

< 5

< 7 Ce-141

<4

<6

< 5

< 5

< 3

< 9 Ce-144

< 12

< 21

< 15

< 16

< 8

< 31 Ra-226

< 44

< 68

< 56

< 46

< 30

< 93 Ac-228

< 6

< 7

< 9

< 8

< 5

< 12 Th-228

< 3

< 5

<4

<4

< 2

< 7 (a) Quarterly Composite B-39

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES -2017 pCi/L +/- 2 Sigma Discharge Canal 10 DATE 07/25/17 08/29/17 09/27/17 10/31/17 11/28/17 12/27/17 RADIOCHEMICAL H-3 (a)

< 179 381 +/- 136 GAMMA K-40

< 42 47 +/- 27

< 10 62 +/- 37

< 46

< 48 Mn-54

< 2

< 2

< 1

< 2

<2

< 2 Co-58

< 2

< 2

< 2

< 2

< 3

< 2 Fe-59

< 5

< 5

<4

< 5

<6

< 5 Co-60

< 2

<2

< 1

< 2

< 3

< 2 Zn-65

< 5

<4

< 2

<4

< 5

<4 Nb-95

< 3

<2

< 2

< 2

< 3

< 2 Zr-95

<4

<4

< 3

< 3

< 5

<4 Ru-103

< 3

< 3

< 2

< 3

< 3

< 3 Ru-106

< 20

< 17

< 12

< 18

< 22

< 18 1-131

< 15

< 15

< 15

< 15

< 9

< 14 Cs-134

<2

< 2

< 1

< 2

< 3

< 2 Cs-137

< 2

< 2

< 1

< 2

< 2

< 2 Ba-140

< 25

< 24

< 20

< 23

< 19

< 23 La-140

< 8

<_8

< 6

< 7

<6

< 7 Ce-141

< 5

< 5

< 3

< 5

< 4

< 5 Ce-144

< 15

< 12

< 9

< 13

< 14

< 14 Ra-226

< 51

< 45

< 37

< 49

< 47

< 41 Ac-228

< 8

< 7

< 6

< 8

< 9

< 8 Th-228

<4

< 3

< 2

<4

<4

<4 (a) Quarterly Composite B-40

DATE 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 Ce-141 Ce-144 Ra-226 Th-228 INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2017 06/15/17

< 611 Discharge Canal 10 pCi/kg dry+/- 2 Sigma 09/21/17

< 309 19560 +/- 1845 12920 +/- 813

< 77

< 34

< 65

< 34

< 144

< 83

< 86

< 30

< 181

< 78

< 75

< 40

< 123

< 61

< 69

< 37

< 516

< 305

< 114

< 94

< 89

< 38 1067+/- 131 73 +/- 39

< 323

< 238

< 102

< 60

< 357

< 186

< 1719

< 787 979 +/- 113 373 +/- 50 B-41 06/15/17

< 527 15490 +/- 1714

< 58

< 74

< 127

< 64

< 136

< 62

< 111

< 64

< 574

< 107

< 106

< 76

< 320

< 93

< 373

< 1199 877 +/- 134 Off Verplanck 17 09/21/17

< 772 19880 +/- 1851

< 94

< 86

< 200

< 88

< 189

< 98

< 178

< 95

< 742

< 237

< 104 288 +/- 88

< 546

< 116

< 411

< 1516 1157 +/- 122

INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2017 pCi/kg dry +/- 2 Sigma Lent's Cove Cold Spring 28 84*

DATE 06/15/17 09/21/17 06/16/17 09/22/17 GAMMA Be-7

< 462

< 732

< 647

< 700 K-40 9752 +/- 1173 17680 +/- 1589 15200 +/- 1739 26270 +/- 1458 Mn-54

< 60

< 82

< 85

< 78 Co-58

< 53

< 80

< 78

< 76 Fe-59

< 139

< 214

< 199

< 195 Co-60

< 62

< 92

< 90

< 75 Zn-65

< 152

< 206

< 226

< 227 Nb-95

< 62

< 95

< 89

< 91 Zr-95

< 113

< 146

< 159

< 151 Ru-103

< 61

< 89

< 83

< 86 Ru-106

< 534

< 757

< 711

< 694 1-131

< 99

< 260

< 129

< 204 Cs-134

< 68

< 96

< 115

< 86 Cs-137 150 +/- 55 174 +/- 87

< 94

< 79 Ba-140

< 312

< 567

< 419

< 473 Ce-141

< 96

< 150

< 141

< 142 Ce-144

< 384

< 519

< 579

< 496 Ra-226

< 1141

< 1640 2756 +/- 1672

< 1551 Th-228 382 +/- 124 1067 +/- 127 965 +/- 141 1159 +/- 134

• Control Location B-42

DATE RADIOCHEMICAL Sr-90 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 INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2017 pCi/kg dry +/- 2 Sigma Off Verplanck 17 06/02/17 09/13/17 06/02/17

< 39

< 37

< 29

< 515

< 744

< 619 14040 +/- 1421 15880 +/- 1629 14930 +/- 1693

< 66

< 70

< 81

< 57

< 72

< 76

< 121

< 206

< 140

< 58

< 67

< 77

< 154

< 158

< 150

< 62

< 89

< 86

< 112

< 149

< 150

< 61

< 84

< 83

< 578

< 593

< 642

< 97

< 264

< 137

< 71

< 81

< 108 86 +/- 53 216 +/- 74

< 81

< 265

< 644

< 339

< 95

< 136

< 86

< 104

< 150

< 135

< 393

< 488

< 497

< 1479

< 1523 3190 +/- 1661

< 385

< 232

< 585 501 +/- 141 683 +/- 112 1134 +/- 172 B-43 Lent's Cove 28 09/13/17

< 37

< 689 12670 +/- 1802

< 82

< 78

< 178

< 83

< 120

< 78

< 135

< 96

< 608

< 246

< 93

< 93

< 633

< 159

< 132

< 393

< 1444

< 465 473 +/- 103

INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN SHORELINE SOIL SAMPLES -2017 pCi/kg dry+/- 2 Sigma Manitou Inlet White Beach 50*

53 DATE 06/02/17 09/13/17 06/02/17 09/13/17 RADIOCHEMICAL Sr-90

< 30

< 47

< 35

< 29 GAMMA Be-7

< 598

< 491

< 383

< 385 K-40 9658 +/- 875 12440 +/- 1177 7862 +/- 1058 8635 +/- 870 Mn-54

< 66

< 51

< 52

< 35 Co-58

< 64

< 47

< 53

< 43 Fe-59

< 111

< 115

< 95

< 72 Co-60

< 58

< 49

< 46

< 45 Zn-65

< 191

< 107

< 108

< 95 Nb-95

< 73

< 65

< 60

< 50 Zr-95

< 116

< 99

< 98

< 69 Ru-103

< 65

< 56

< 49

< 43 Ru-106

< 538

< 359

< 420

< 340 1-131

< 108

< 144

< 81

< 131 Cs-134

< 68

< 63

< 59

< 43 Cs-137

< 72

< 56

< 56

< 40 Ba-140

< 313

< 357

< 216

< 300 La-140

< 84

< 128

< 55

< 87 Ce-141

< 127

< 95

< 62

< 70 Ce-144

< 497

< 327

< 224

< 237 Ra-226

< 1608 2256 +/- 993

< 902

< 684 Ac-228

< 291

< 192

< 220

< 180 Th-228 695 +/- 122 551 +/- 72

< 72

< 66

• Control Location B-44

DATE RADIOCHEMICAL Sr-90 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

• Control Location INDIAN POINT ENERGY CENTER TABLE 8-16 RADIONUCLIDES IN SHORELINE SOIL SAMPLES -2017 pCi/kg dry+/- 2 Sigma Cold Spring 84*

06/02/17 09/13/17

< 24

< 35

< 486

< 476 36250 +/- 2112 31950 +/- 1955

< 55

< 60

< 63

< 58

< 150

< 182

< 68

< 66

< 174

< 158

< 61

< 65

< 119

< 114

< 59

< 50

< 572

< 480

< 91

< 177.

< 80

< 74

< 71

< 65

< 292

< 367

< 63

< 124

< 91

< 87

< 369

< 287

< 1323

< 1006

< 180

< 383 446 +/- 108 628 +/- 99 8-45

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 INDIAN POINT ENERGY CENTER TABLE B-17 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2017 06/15/17 Myrophyllium (a) pCi/kg wet +/- 2 Sigma Lent's Cove 28 09/21/17 Myrophyllium

< 227 3695 +/- 404

< 21

< 19

< 41

< 22

< 54

< 25

< 41

< 24

< 193

< 58

< 24

< 25

< 123

< 40

< 43

< 150

< 566

< 72 133 +/- 34 (a) Unable to locate and collect samples at this location B-46

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 INDIAN POINT ENERGY CENTER TABLE 8-17 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2017 06/15/17 Myrophyllium (a) pCi/kg wet +/- 2 Sigma Off Verplanck 17 09/21/17 Myrophyllium

< 163 3462 +/- 342

< 16

< 16

< 40

< 15

< 33

< 18

< 30

< 18

< 152

< 46

< 21

< 18

< 103

< 31

< 32

< 104

< 339

< 55 80 +/- 28 (a) Unable to locate and collect samples at this location B-47

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

• Control Location INDIAN POINT ENERGY CENTER TABLE B-17 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2017 pCi/kg wet +/- 2 Sigma Cold Spring 84*

06/16/17 09/22/17 Myrophyllium Myrophyllium

< 134 207 +/- 105 1654 +/- 273 2935 +/- 206

< 21

< 9

< 15

< 10

< 25

< 21

< 16

< 8

< 36

< 21

< 14

< 10

< 30

< 17

< 18

< 10

< 134

< 87

< 25

< 25

< 21

< 12

< 17

< 11

< 68

< 59

< 19

< 16

< 24

< 18

< 111

< 71

< 373

< 213

< 50

< 35 86 +/- 23 95 +/- 21 B-48

INDIAN POINT ENERGY CENTER TABLE 8-18 RADIONUCLIDES IN FISH/ INVERTEBRATES - 2017 pCi/kg wet +/- 2 Sigma Downstream 107 DATE 05/01/17 05/01/17 05/25/17 05/31/17 05/31/17 06/16/17 White Perch Catfish Sunfish American Eel Striped Bass Blue Crab RADIOCHEMICAL Ni-63

< 69

< 55

< 97

< 70

< 56

< 75 Sr-90

<4

< 2

<4

<4

< 3

< 5 GAMMA Be-7

< 735

< 809

< 508

< 595

< 840

< 579 K-40 2650 +/- 487 2530 +/- 770 2092 +/- 741 1164 +/- 755 1775 +/- 1108 2714 +/- 842 Mn-54

< 51

< 38

< 44

< 53

< 82

< 56 Co-58

< 76

< 71

< 54

< 78

< 91

< 70 Fe-59

< 241

< 158

< 149

< 147

< 236

< 169 Co-60

< 43

< 51

< 25

< 57

< 73

< 62 Zn-65

< 116

< 115

< 98

< 107

< 105

< 147 Nb-95

< 78

< 83

< 67

< 73

< 107

< 64 Zr-95

< 131

< 135

< 135

< 131

< 219

< 136 Ru-103

< 126

< 115

< 79

< 117

< 116

< 88 Ru-106

< 452

< 463

< 422

< 476

< 677

< 580 1-131

< 13010

< 9386

< 1525

< 1175

< 1625

< 404 Cs-134

< 48

< 49

< 60

< 66

< _79

< 71 Cs-137

< 45

< 41

< 41

< 62

< 74

< 70 Ba-140

< 5479

< 6201

< 1038

< 1156

< 1949

< 609 La-140

< 1536 (a)

< 432

< 470

< 430

< 134 Ce-141

< 249

< 197

< 136

< 119

< 151

< 120 Ce-144

< 306

< 204

< 248

< 296

< 339

< 397 Ra-226

< 982

< 778

< 795

< 1089

< 1347

< 1330 Th-228

< 77

< 77

< 77

< 92

< 94

< 122 (a) MDA could no be calculated due to the age of the sample at the time of analysis.

B-49

INDIAN POINT ENERGY CENTER TABLE 8-18 RADIONUCLIDES IN FISH/ INVERTEBRATES~ 2017 pCi/kg wet +/- 2 Sigma Downstream 107 DATE 08/01/17 08/07/17 08/31/17 08/31/17 09/11/17 Blue Crab Catfish Sunfish White Perch American Eel RADIOCHEMICAL Ni-63

< 27

< 23

< 26

< 23

< 24 Sr-90

< 3

< 2

< 2

< 2

<2 GAMMA Be-7

< 698

< 664

< 585

< 759

< 256 K-40 2392 +/- 653 3161 +/- 536 2431 +/- 814 2919 +/- 749 1870 +/- 457 Mn-54

< 37

< 52

.< 55

< 65

< 33 Co-58

< 64

< 67

< 59

< 61

< 32 Fe-59

< 173

< 178

< 157

< 171

< 67 Co-60

< 43

< 38

< 40

< 65

< 26 Zn-65

< 85

< 119

< 112

< 117

< 71 Nb-95

< 78

< 78

< 76

< 80

< 38 Zr-95

< 123

< 121

< 136

< 136

< 67 Ru-103

< 101

< 105

< 75

< 95

< 37 Ru-106

< 336

< 469

< 468

< 594

< 263 1-131

< 6506

< 4941

< 621

< 874

< 181 Cs-134

< 45

< 49

< 51

< 65

< 31 Cs-137

< 40

< 44

< 52

< 60

< 31 Ba-140

< 2936

< 3007

< 905

< 1174

< 268 La-140

< 993

< 970

< 311

< 310

< 105 Ce-141

< 148

< 196

< 102

< 164

< 56 Ce-144

< 238

< 308

< 255

< 399

< 153 Ra-226

< 795

< 977

< 948

< 1276

< 487 Th-228

< 67

< 76

< 82

< 107

< 45 B-50

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH/ INVERTEBRATES-2017 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 05/09/17 05/16/17 05/23/17 05/23/17 05/24/17 08/01/17 White perch Catfish American Eel Stripped Bass Sunfish White Perch RADIOCHEMICAL Ni-63

< 69 *

< 50

< 67

< 51

< 80

< 36 Sr-90

< 4

<4

< 3

< 4

< 3

<4 GAMMA Be-7

< 676

< 1013

< 891

< 850

< 639

< 966 K-40 2548 +/- 795 2778 +/- 988 2037 +/- 756 2579 +/- 683 2397 +/- 875 2488 +/- 899 Mn-54

< 56

< 63

< 67

< 58

< 73

< 60 Co-58

< 63

< 82

< 93

< 79

< 102

< 80 Fe-59

< 214

< 240

< 205

< 211

< 203

< 250 Co-60

< 39

< 60

< 60

< 65

< 46

< 56 Zn-65

< 103

< 114

< 142

< 130

< 124

< 110 Nb-95

< 71

< 101

< 112

< 100

< 91

< 108 Zr-95

< 121

< 141

< 143

< 159

< 120

< 175 Ru-103

< 132

< 122

< 131

< 126

< 123

< 155 Ru-106

< 357

< 547

< 583

< 557

< 541

< 488 1-131

< 4635

< 4263

< 4518

< 2670

< 1923

< 11940 Cs-134

< 41

< 65

< 56

< 66

< 72

< 53 Cs-137

< 45

< 64

< 59

< 60

< 49

< 57 Ba-140

< 2118

< 3099

< 3044

< 2103

< 2239

< 5064 La-140

< 937

< 919

< 1076

< 717

< 320

< 1500 Ce-141

< 179

< 213

< 223

< 211

< 159

< 287 Ce-144

< 256

< 307

< 369

< 425

< 328

< 382 Ra-226

< 801

< 1158

< 1242

< 1363

< 1173

< 1311 Th-228

< 64

< 104

< 107

< 103

< 75

< 106

• Control Location 8-51

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH/ INVERTEBRATES -2017 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 08/28/17 08/28/17 09/01/17 09/07/17 American Eel Blue Crab Sunfish Catfish RADIOCHEMICAL Ni-63

< 25

< 25

< 44

< 25 Sr-90

< 3

< 5

< 5

< 2 GAMMA Be-7

< 384

< 537

< 461

< 641 K-40 2774 +/- 613 2205 +/- 523 3971 +/- 884 3623 +/- 931 Mn-54

< 40

< 45

< 48

< 63 Co-58

< 47

< 58

< 67

< 73 Fe-59

< 93

< 153

< 143

< 138 Co-60

< 45

< 44

< 58

< 56 Zn-65

< 84

< 114

< 102

< 121 Nb-95

< 49

< 71

< 77

< 81 Zr-95

< 83

< 112

< 100

< 124 Ru-103

< 56

< 74

< 69

< 84 Ru-106

< 328

< 419

< 424

< 500 1-131

< 648

< 906

< 685

< 493 Cs-134

< 34

< 52

< 56

< 68 Cs-137

< 33

< 50

< 46

< 55 Ba-140

< 853

< 1036

< 931

< 680 La-140

<*305

< 311

< 258

< 243 Ce-141

< 84

< 132

< 103

< 104 Ce-144

< 210

< 294

< 276

< 262 Ra-226

< 726

< 1080

< 940

< 1094 Th-228

< 60

< 81

< 78

< 91

• Control Location B-52

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH/ INVERTEBRATES - 2017 pCi/kg wet +/- 2 Sigma Downstream 25 DATE 05/01/17 05/01/17 05/24/17 05/31/17 05/31/17 06/16/17 White Perch Catfish Sunfish American Eel Stripped bass Blue Crab RADIOCHEMICAL Ni-63

< 74

< 50

< 67

< 54

< 63

< 75 Sr-90

<4

< 4

< 2

<4

< 2

< 5 GAMMA Be-7

< 788

< 752

< 1092

< 730

< 678

< 580 K-40 2984 +/- 756 2652 +/- 755 2047 +/- 846 1847 +/- 986 3157 +/- 952 2454 +/- 633 Mn-54

< 47

< 46

< 71

< 59

< 64

< 53 Co-58

< 73

< 85

< 95

< 95

< 83

< 63 Fe-59

< 238

< 232

< 245

< 185

< 196

< 150 Co-60

< 52

< 60

< 60

< 63

< 53

< 63 Zn-65

< 104

< 93

< 168

< 180

< 135

< 159 Nb-95

< 74

< 80

< 116

< 94

< 81

< 71 Zr-95

< 163

< 124

< 153

< 149

< 151

< 128 Ru-103

< 110

< 116

< 137

< 122

< 98

< 80 Ru-106

< 424

< 455

< 666

< 539

< 543

< 649 1-131

< 11580

< 12210

< 2760

< 1300

< 1243

< 322 Cs-134

< 45

< 48

< 80

< 58

< 79

< 78 Cs-137

< 39

< 38

< 72

< 63

< 70

< 60 Ba-140

< 5198

< 5837

< 1984

< 1807

< 1489

< 606 La-140

< 1439

< 1723

< 671

< 433

< 384

< 142 Ce-141

< 199

< 196

< 218

< 201

< 153

< 133 Ce-144

< 234

< 221

< 393

< 407

< 321

< 397 Ra-226

< 862

< 910

< 1535

< 1450

< 1202

< 1335 Th-228

< 78

< 75

< 120

< 105

< 109

< 109 B-53

INDIAN POINT ENERGY CENTER TABLE 8-18 RADIONUCLIDES IN FISH/ INVERTEBRATES -2017 pCi/kg wet +/- 2 Sigma Downstream 25 DATE 08/03/17 08/23/17 08/23/17 08/23/17 09/01/17 09/11/17 Stripped Bass White Perch Blue Crab American Eel Sunfish Catfish RADIOCHEMICAL Ni-63

< 91

< 44

< 28

< 27

< 40

< 26 Sr-90

<4

< 4

< 1

< 3

< 5

<2 GAMMA Be-7

< 944

< 577

< 470

< 969

< 718

< 538 K-40 4715 +/- 1184 3224 +/- 906 2530 +/- 541 3307 +/- 1005 3279 +/- 709 1722 +/- 868 Mn-54

< 65

< 51

< 34

< 75

< 72

< 64 Co-58

< 98,

< 67

< 45

< 92

< 82

< 85 Fe-59

< 250

< 163

• < 120

< 247

< 183

< 146 Co-60

< 66

< 55

< 35

< 53

< 55

< 62 Zn-65

< 136

< 94

< 75

< 150

< 163

< 140 Nb-95

< 103

< 70

< 51

< 101

< 85

< 71 Zr-95

< 169

< 130

< 91

< 166

< 124

< 122 Ru-103

< 149

< 95

< 70

< 135

< 101

< 72 Ru-106

< 571

< 498

< 346

< 693

< 640

< 344 1-131

< 9621

< 1313

< 1088

< 2162

< 890

< 330 Cs-134

< 68

< 49

< 34

< 75

< 67

< 66 Cs-137

< 61

< 50

< 42

< 71

< 68

< 62 Ba-140

< 5105

< 1290

< 898

< 1940

< 1210

< 529 La-140

< 1398

< 487

< 327

< 430

< 384

< 170 Ce-141

< 218

< 127

< 112

< 218

< 158

< 106 Ce-144

< 287

< 275

< 225

< 521

< 423

< 263 Ra-226

< 959

< 1062

< 774

< 1480

< 1354

< 1149 Th-228

< 83

< 74

< 65

< 121

< 113

< 93 B-54

INDIAN POINT ENERGY CENTER TABLE B-19 LAND USE CENSUS - RESIDENCE AND MILCH ANIMAL RES UL TS 2017 The 2017 land use census indicated there were no new residences that were closer in proximity to IPEC. IPEC 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-55

N RIVER NNE RIVER NE 550 ENE 600 E

662 ESE 569 SE 553 SSE 569 s

700 SSW 755 SW 544 WSW RIVER w

RIVER WNW RIVER NW RIVER NNW RIVER INDIAN POINT ENERGY CENTER TABLE 8-20 LAND USE CENSUS 2017 UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES RIVER 1788 RIVER 3111 636 1907 775 1478 785 1371 622 715 564 1168 551 1240 566 1133 480 1574 350 3016 RIVER 2170 RIVER 1919 RIVER 1752 RIVER 1693 RIVER 1609 B-56 41 River Road Tomkins Cove Chateau Rive Apts. John St. Peekskill 211 Viewpoint Terrace, Peekskill 1018 Lower South St. Peekskill 1103 Lower South St. Peekskill 461 Broadway Buchanan 223 First St. Buchanan 5 Pheasant's Run Buchanan 320 Broadway Verplanck 240 Eleventh St. Verplanck 8 Spring St. Tomkins Cove 9 West Shore Dr. Tomkins Cove 712 Rt. 9W Tomkins Cove 770 Rt. 9W Tomkins Cove 807 Rt. 9W Tomkins Cove 4 River Rd. Tomkins Cove

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 2017 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

2007-2017 2007 14.4 14.6 2008 14.5 14.2 2009 14.5 14.2 2010 14.0 14.3 2011 13.6 14.4 2012 13.2 13.5 2013 13.4 13.8 2014 13.7 13.6 2015 13.8 14 2016 14.3 14.2 2017 14.3 14.7 14.0 14.1 C-2 18.8 17.3 17.3 13.0 13.4 12.5 14.2 14.2 14.3 15.6 15.6 15.1

FIGURE C-1 DIRECT RADIATION, ANNUAL

SUMMARY

2007 to 2017 40.0....----'----------------------.,..,,,,,-------=

~

ca :, a -

0:::

35.0 30.0 25.0 E 20.0 C m

E -

15.0 10.0 5.0 0.0 2007 2008 2009 2010 2011 C-3

~Inner Ring i::;:;::::;:JQuter Ring

-Control Location 2012 2013 2014 2015 2016 2017

2007 2008 2009 2010 201.1 2012 2013 2014 2015 2016 2017 TABLE C-2 RADIONUCLIDES IN AIR 2007 to 2017 (pCi/m3) 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.014 0.014 0.014 0.014 0.014 0.014 0.013 0.013 0.016 0.015 0.015 0.015 0.013 0.012 0.01 0.01 Critical Level (Le) is less than the ODCM required LLD.

<Le indicates no positive values above sample critical level.

C-4

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

< Le

<Le.

< Le

< Le

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 2007 to 2017 0.05....--------------------------------~

-All Indicator Locations

-Control Location 0.04 0.03 0.02 0.01 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017

• Includes ODCM and non-ODCM indicator locations.

Gross Beta ODCM required LLD = 0.01 pCi/m3 C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER-TRITIUM 2007 to 2017 (pCi/L) 2007

< Le

< Le

< Le

< Le 2008

< Le

< Le

< Le

< Le 2009

< Le

< Le

< Le

< Le 2010 428

< Le

< Le

< Le 2011

< Le 661

< Le

< Le 2012

< Le 539

< Le

< Le 2013 241 462

< Le

< Le 2014 224 253

< Le

< Le 2015 188 341

< Le

< Le 2016

< Le 415

< Le

< Le 2017

< Le 299

< Le

< Le 270 424

< Le

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

<Le indicates no positive values above sample critical level.

C-6

1800 1600 1400 1200

...J

~1000 C.

800 600 FIGURE C-3 RADIONUCLIDES IN HUDSON RIVER WATER-TRITIUM 2007 to 2017 mi Inlet (H-3)

!:I Discharge (H-3) 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 Tritium ODCM required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 2007 to 2017 (pCi/L) 2007

< Le

< Le 2008

< Le

<Le 2009

< Le

< Le 2010

< Le

< Le 2011

< Le

< Le 2012

< Le

< Le 2013

< Le

< Le 2014

< Le

< Le 2015

< Le

< Le 2016

< Le

< Le 2017

< Le

< Le

< Le

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

<Le indicates no positive values above sample critical level.

C-8

1800 1600 1400 1200

...J i31000 Q.

800 600 400 200 FIGURE C-4 RADIONUCLIDES IN DRINKING WATER 2007 to 2017 NO IDENTIFiED NUCLIDES IN PREVIOUS TEN YEARS HISTORY 0 +-------.---.....---~----.---....----,----,---~-----,-----,---

2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 Tritium ODCM required LLD = 2000 pCi/L C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 2007 to 2017 (pCi/Kg, dry) 2007

< Le

< Le 190 2008

< Le

< Le 187 2009

< Le

< Le 149 2010

< Le

< Le 154 2011

< Le

< Le 108 2012

< Le

< Le 141 2013

< Le

< Le*

133 2014

< Le

< Le 327 2015

< Le

< Le 110 2016

< Le

< Le

< Le 2017

< Le

< Le 151

<Le

< Le 165 Critical Level (Le) is less than the RETS required LLD.

<Le indicates no positive values above sample critical level.

C-10

< Le

< Le

< Le 63

< Le

< Le

< Le

< Le

< Le

< Le

< Le 63

750 650 550 450

~

't,

~

iJ 350 C.

250 150 50 I-------

2007 2008

-50 FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 2007 to 2017 E=ilndicator (Cs-134) e-**9Control (Cs-134) l!!!!i!iil Indicator (Cs-137)

-Control (Cs-137)

/ '

2009 2010 2011 2012 2013 2014 2015 2016 2017 Cs-134 ODCM required LLD= 150 pCi/Kg, dry Cs-137 ODCM required LLD= 175 pCi/Kg, dry C-11

TABLE C-6 RADIONUCLIDES IN BROADLEAF VEGETATION 2007 to 2017 (pCi/Kg~ wet) 2007

< Le

< Le 2008

< Le

< Le 2009

< Le

< Le 2010

< Le

< Le 2011 31

< Le 2012

< Le

< Le 2013 44

< Le 2014

< Le

< Le 2015

< Le

< Le 2016

< Le

< Le 2017

< Le

< Le 38

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

<Le indicates no positive values above sample critical level.

C-12

+o Q) 3:

C)

s:::: -

0 C.

FIGURE C-6 RADIONUCLIDES IN BROADLEAF VEGETATION 2007 to 2017 100 --.------------------------,--------~------,

• Indicator (Cs-137)

Eteontrol (Cs-137) 80 60 40 20 0 --1------,----,-----,----.--

2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 ODCM required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 2007 to 2017 (pCi/Kg, dry) 2007

< Le

< Le 2008

< Le

< Le 2009

< Le

< Le 2010

< Le

< Le 2011

< Le

< Le 2012

< Le

< Le 2013

< Le

< Le 2014

< Le

< Le 2015

< Le

< Le 2016

< Le

< Le 2017

< Le

< Le

< Le

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

<Le indicates no positive values above sample critical level.

C-14

180 160 140 120 80 60 40 20 FIGURE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES -

2007 to 2017 E:ttndicator (Cs-137) 1::1-ontrol (Cs-137)

NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEARS HISTORY 0 +----,-----,.-----,,----.-----.-----.----,----,-----,----.,..-----l 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 Cs-137 ODCM required LLD= 150 pCi/Kg, wet C-15

TABLE C-8 RIVER WATER - Discharge Area - Tritium REMP vs. EFFLUENT (pCi/liter) 1Q 2103 357 1813 2Q 2013

< 170 223 3Q 2013

< 186 428 4Q 2013 306 896 1Q 2104

<195 952 2Q 2014 253 82 3Q 2014

<189 26 4Q 2014

<157 218 1Q 2015 959 1940 2Q 2015

,274 241 3Q 2015

<186 350 4Q 2015 341 536 1Q 2016 572 830 2Q 2016 257 762 3Q 2016 177 55 4Q 2016 195 253 1Q 2017 216 912 2Q 2017

<191 372 3Q 2017

<179 51 4Q 2017 381 665 Four Year Average, by 357 600 Quarter, 2013 - 2017

• 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 divided by the total dilution volume for the quarter.

C-16

TABLE C-9 RADIONUCLIDES IN BOTTOM SEDIMENT 2007 to 2017 (pCi/Kg, dry) 2007 221 254 2008 239

< Le 2009 493 225 2010 552

< Le 2011 287 238 2012 284

< Le 2013 -

2738 264 2014 327

< Le 2015 876

< Le 2016 224

< Le 2017 350

< Le 599 245 Critical Level (Le) is less than the RETS required LLD.

<Le indicates no positive values above sample critical level.

C-17

~

"C C)

~ -

0 Q.

FIGURE C-9 RADIONUCLIDES IN BOTTOM SEDIMENT 2800...--~~~~~~~~2~0~0~7~t~o~2~0~1~7~~~~~~,---~~~~~

l!i!!'E Indicator 2600

-Control 2400 2200 2000 1800 1600 1400 1200 1000 800 600 400 200 0

2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 Cs-137 ODCM required LLD= 175 pCi/Kg, dry C-18

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.

D.1 Program 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 lnterlaboratory 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-1

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 Tables D-3.1, D-3.2, and D-3.3, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

Ratio of agreement

=

QC Result Reference Result If the value falls within the agreement interval, the result is acceptable.

TABLE D-2.1 Ratio of Agreement

<4 No Comparison 4to 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 lnterlaboratory Comparison Program.

This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

D.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 lnterlaboratory Comparison Program numerical results are summarized in the following tables.

D-2

TABLE D-3.1 Analytics Environmental Radioactivity Cross Check Program Teled~ne Brown Ensineerin§! Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value (a)

Analytics Result Evaluation (bJ Value March 2017 E11811 Milk Sr-89 pCi/L 87 97.7 0.89 A

Sr-90 pCi/L 12.4 16.2 0.77 w

E11812 Milk Ce-141 pCi/L 135 145 0.93 A

Co-58 pCi/L 153 150 1.02 A

Co-60 pCi/L 182 183 1.00 A

Cr-51 pCi/L 258 290 0.89 A

Cs-134 pCi/L 104 120 0.87 A

Cs-137 pCi/L 142 140 1.02 A

Fe-59 pCi/L 135 129 1.05 A

1-131 pCi/L 92.6 97.9 0.95 A

Mn-54 pCi/L 173 164 1.05 A

Zn-65 pCi/L 208 199 1.04 A

E11813 Charcoal 1-131 pCi 92 93.9 0.98 A

E11814 AP Ce-141 pCi 99.9 101 0.99 A

Co-58 pCi 95.4 104 0.92 A

Co-60 pCi 140 127 1.10 A

Cr-51 pCi 211 201 1.05 A

Cs-134 pCi 82.1 83.2 0.99 A

Cs-137 pCi 92.8 97.0 0.96 A

Fe-59 pCi 107 89.3 1.20 A

Mn-54 pCi 106 114 0.93 A

Zn-65 pCi 137 138 0.99 A

E11816 Soil Ce-141 pCi/g 0.258 0.250 1.03 A

Co-58 pCi/g 0.241 0.258 0.93 A

Co-60 pCi/g 0.312 0.315 0.99 A

Cr-51 pCi/g 0.439 0.500 0.88 A

Cs-134 pCi/g 0.176 0.207 0.85 A

Cs-137 pCi/g 0.304 0.317 0.96 A

Fe-59 pCi/g 0.210 0.222 0.95 A

Mn-54 pCi/g 0.292 0.283 1.03 A

Zn-65 pCi/g 0.353 0.344 1.03 A

E11815 Water Fe-55 pCi/L 1600 1890 0.85 A

(a) 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 (b) Analytics evaluation based on TBE internal 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 D-3

TABLE D-3.1 Analytics Environmental Radioactivity Cross Check Program Teled~ne Brown En9ineerin9 Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value (a)

Analytics Result Value June 2017 E11844 Milk Sr-89 pCi/L 81.3 92.6 0.88 Sr-90 pCi/L 12.1 13.5 0.90 E11846 Milk Ce-141 pCi/L 142 151 0.94 Co-58 pCi/L 147 155 0.95 Go-60 pCi/L 185 191 0.97 Cr-51 pCi/L 321 315 1.02 Cs-134 pCi/L 168 188 0.89 Cs-137 pCi/L 148 150 0.99 Fe-59 pCi/L 116 115 1.01 1-131 pCi/L 102 93.6 1.09 Mn-54 pCi/L 168 172 0.98 Zn-65 pCi/L 195 204 0.96 E11847 Charcoal 1-131 pCi 87.9 84.8 1.04 E11845 AP Sr-89 pCi 70.8 79.1 0.90 Sr-90 pCi 9.10 11.5 0.79 E11848 AP Ce-141 pCi 112 116 0.96 Co-58 pCi 119 119 1.00 Co-60 pCi 171 146 1.17 Cr-51 pCi 270 241 1.12 Cs-134 pCi 152 144 1.05 Cs-137 pCi 114 115 0.99 Fe-59 pCi 94.1 88.3 1.07 Mn-54 pCi 139 132 1.06 Zn-65 pCi 141 156 0.90 E11849 Water Fe-55 pCi/L 1840 1890 0.97 July 2017 E11901 AP GR-A pCi 50.1 44.2 1.13 GR-8 pCi 218.

233 0.93 (a) 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 (b) Analytics evaluation based on TBE internal 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 D-4 Evaluation (bl A

A A

A A

A A

A A

A A

A A

A w

A A

A A

A A

A A

A A

A A

TABLE D-3.1 Analytics Environmental Radioactivity Cross Check Program Teledlne Brown Engineerinfi! Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value (a)

Analytics Result Evaluation (bl Value September 2017 E11914 Milk Sr-89 pCi/L 84.3 82.7 1.02 A

Sr-90 pCi/L 12.6 12.1 1.04 A

E11915 Milk Ce-141 pCi/L 93.9 87.0 1.08 A

Co-58 pCi/L 115 117 0.98 A

Co-60 pCi/L 265 262 1.01 A

Cr-51 pCi/L 273 217 1.26 w

Cs-134 pCi/L 186 201 0.93 A

Cs-137 pCi/L 175 172 1.02 A

Fe-59 pCi/L 137 125 1.09 A

1-131 pCi/L 78.0 71.0 1.10 A

Mn-54 pCi/L 128 123 1.04 A

Zn-65 pCi/L 206 184 1.12 A

E11916 Charcoal 1-131 pCi 71.9 64.4 1.12 A

E11917 AP Ce-141 pCi 80.1 86.3 0.93 A

Co-58 pCi 110 116 0.95 A

Co-60 pCi 277 260 1.07 A

Cr-51 pCi 275 215 1.28 w

Cs-134 pCi 192 199 0.96 A

Cs-137 pCi 165 170 0.97

• A Fe-59 pCi 122 124 0.98 A

Mn-54 pCi 120 122 0.99 A

Zn-65 pCi 175 183 0.96 A

E11918 Water Fe-55 pCi/L 1630 1630 1.00 A

E11919 Soil Ce-141 pCi/g 0.136 0.142 0.96 A

Co-58 pCi/g 0.179 0.191 0.94 A

Co-60 pCi/g 0.405 0.429 0.94 A

Cr-51 pCi/g 0.230 0.355 0.65 N(1l Cs-134 pCi/g 0.272 0.328 0.83 A

Cs-137 pCi/g 0.336 0.356 0.94 A

Fe-59 pCi/g 0.210 0.205 1.02 A

Mn-54 pCi/g 0.210 0.201 1.05 A

Zn-65 pCi/g 0.301 0.301 1.00 A

(a) 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 (b) Analytics evaluation based on TBE internal 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 (1) See NCR 17-16 D-5

TABLE D-3.1 Analytics Environmental Radioactivity Cross Check Program Teledlne Brown En§Jineering Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value (al Analytics Result Value December 2017 E12054 Milk Sr-89 pCi/L 92.1 92.3 1.00

• Sr-90 pCi/L 18.3 16.9 1.09 E12055 Milk Ce-141 pCi/L 97.8 98.3 0.99 Co-58 pCi/L 92.3 89.9 1.03 Co-60 pCi/L 176 173 1.02 Cr-51 pCi/L 226 242 0.93 Cs-134 pCi/L 118 125 0.95 Cs-137 pCi/L 148 141 1.05 Fe-59 pCi/L 123 113 1.08 1-131 pCi/L 66.0 57.8 1.14 Mn-54 pCi/L 173 161 1.08 Zn-65 pCi/L 233 211 1.10 E12056 Charcoal 1-131 pCi 48.1 47.5 1.01 E12057A AP Ce-141 pCi 108 111 0.97 Co-58 pCi 89.5 102 0.88 Co-60 pCi 223 196 1.14 Cr-51 pCi 311 274 1.13 Cs-134 pCi 141 142 1.00 Cs-137 pCi 162 160 1.01 Fe-59 pCi 121 129 0.94 Mn-54 pCi 177 182 0.97 Zn-65 pCi 203 239 0.85 E12058 Water Fe-55 pCi/L 1970 1740 1.13 E12059 AP Sr-89 pCi 71.2 87.4 0.81 Sr-90 pCi 12.9 16,0 0.81 (a). 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 (b) Analytics evaluation based on TBE internal 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 D-6 Evaluation (bl 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

TABLE D-3.2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledlne Brown Engineering Environmental Services Identification TBE Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value Value (a)

Range February 2017 17-MaS36 Soil Ni-63 Sq/kg

-5.512 (1)

A Sr-90 Sq/kg 571 624 437 - 811 A

17-MaW36 Water Am-241 Sq/L 0.693 0.846 0.592 - 1.100 A

Ni-63 Sq/L 13.4 12.2 8.5 -15.9 A

Pu-238 Sq/L 0.7217 0.703 0.492 - 0.914 A

Pu-239/240 Sq/L 0.9277 0.934 0.654-1.214 A

17-RdF36 AP U-234/233 Sq/sample 0.0911 0.104 0.073 - 0.135 A

U-238 Sq/sample 0.0967 0.107 0.075- 0.139 A

17-RdV36 Vegetation Cs-134 Sq/sample 6.44 6.95 4.87 - 9.04 A

Cs-137 Sq/sample 4.61 4.60 3.22 - 5.98 A

Co-57 Sq/sample

-0.0229 (1)

A Co-60 Sq/sample 8.52 8.75 6.13 - 11.38 A

Mn-54 Sq/sample 3.30 3.28 2.30-4.26 A

Sr-90 Sq/sample 1.30 1.75 1.23 - 2.28 w

Zn-65 Sq/sample 5.45 5.39 3.77 - 7.01 A

August 2017 17-MaS37 Soil Ni-63 Sq/kg 1130 1220 854 - 1586 A

Sr-90 Sq/kg 296 289 202-376 A

17-MaW37 Water Am-241 Sq/L 0.838 0.892 0.624-1.160 A

Ni-63 Sq/L

-0.096 (1)

A Pu-238 Sq/L 0.572 0.603 0.422 - 0. 784 A

Pu-239/240 Sq/L 0.863 0.781 0.547 - 1.015 A

17-RdF37 AP U-234/233 Sq/sample 0.103 0.084 0.059 - 0.109 w

U-238 Sq/sample 0.115 0.087 0.061 -0.113 N (2) 17-RdV37 Vegetation Cs-134 Sq/sample 2.34 2.32 1.62 - 3.02 A

Cs-137 Sq/sample 0.05 (1)

A Co-57 Sq/sample 3.32 2.8 2.0- 3.6 A

Co-60 Sq/sample 2.09 2.07 1.45 -2.69 A

Mn-54 Sq/sample 2.90 2.62

• 1.83 - 3.41 A

Sr-90 Sq/sample 1.17 1.23 0.86 -1.60 A

Zn-65 Sq/sample 6.07 5.37 3.76-6.98 A

(a) The MAPEP 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 (b) DOEIMAPEP evaluation:

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 (1) False positive test (2) See NCR 17-15 D-7

TABLE D-3.3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services ldentrification TBE Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value Value(*>

Limits March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 - 133 A

April 2017 RAD-109 Water Ba-133 pCi/L 49.2 49.7 40.8-55.1 A

Cs-134 pCi/L 83.2 90.1 74.0- 99.1 A

Cs-137 pCi/L 202 206 185-228 A

Co-60 pCi/L.

51.2 54.7 49.2 - 62.7 A

Zn-65 pCi/L 39.3 53.8 47.2-65.9 N(1>

GR-A pCi/L 53.6 75.0 39.5-92.3 A

GR-8 pCi/L 42.7 38.5 25.5 -46.0 A

U-Nat pCi/L 50.1 55.6 45.2-61.7 A

H-3 pCi/L 7080 6850 5920- 7540 A

Sr-89 pCi/L 40.7 66.2 53.8 - 74.3 N(1l Sr-90 pCi/L 26.9 26.7 19.3-31.1 A

1-131 pCi/L 26.7 29.9 24.9-34.9 A

September 2017 MRAD-27 AP GR-A pCi/sample 40.9 50.1 16.8 - 77.8 A

AP GR-8 pCi/sample 58.0 61.8 39.1 - 90.1 A

October 2017 RAD-111 Water Ba-133 pCi/L 71.3 73.7 61.7-81.1 A

Cs-134 pCi/L 43.0 53.0 42.8 - 58.3 A

Cs-137 pCi/L 48.2 52.9 47.6-61.1 A

Co-60 pCi/L 69:0 69.5 62.6 - 78.9 A

Zn-65 pCi/L 335 348 313 - 406 A

GR-A pCi/L 32.5 35.6 18.3 -45.8 A

GR-8 pCi/L 24.3 25.6 16.0 - 33.6 A

U-Nat pCi/L 36.6 37.0 30.0 -40.9 A

H-3 pCi/L 6270 6250 5390 - 6880 A

1-131 pCi/L 26.4 24.2 20.1 -28.7 A

November 2017 1113170 Water Sr-89 pCi/L 57.1 50.0 39.4 - 57.5 A

Sr-90 pCi/L 27.1 41.8 30.8 -48.0 N (2)

(a) The ERA known value is equal to 100% of the parameter present in the standard as detem1ined by gravimetric and/or volumetric measurements made during standard preparation.

(b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 17-09 (2) See NCR 17-19 D-8

D.4 Environmental TLD Quality Assurance Environmental dosimetry services for the reporting period of January - December, 2017 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 2017 (1l, (2l (1lThis table summarizes results oftests conducted by EDC.

(ZlEnvironmental dosimeter results are free in air.

D-9

TABLE D-4.2 MEAN DOSIMETER ANALYSES (N=6)

JANUARY - DECEMBER 2017 <1l, <2l 5/01/2017 1.0 0.9 5/08/2017

-0.4 1.0 5/08/2017 0.8 2.4 7/25/2017

-2.5 1.7 7/29/2017 5.5 1.0 8/8/2017

-3.8 0.9 10/23/2017 3.8 2.8 10/31/2017 1.7 1.2 11/12/2017 0.5 1.0 2/01/2018 2.6 1.4 2/06/2018 3.0 0.6 2/08/2018 0.5 2.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass (llThis table summarizes results of tests conducted by EDC for TLDs issued in 2017.

!2lEnvironmental dosimeter results are free in air.

TABLE D-4.3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2017 <1l, <2l.

ist Qtr. 2017 Millstone 2.9 1.5 2nd Qtr.2017 Millstone 2.8 1.2 3rd Qtr. 2017 Millstone 1.1 2.7 4th Qtr.2017 Millstone

-3.5 2.4 4th Qtr.2017 Seabrook 8.6 1.6 (llPerformance criteria are+/- 30%.

!2lBlind spike irradiations using Cs-137 D-10 Pass Pass Pass Pass Pass