Text

Annual Radioactive Effluent Release Report
	ML19122A390
Person / Time
Site:	Indian Point
Issue date:	04/23/2019
From:	Vitale A; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	NL-19-039
	Download: ML19122A390 (70)
	v • d • e

1 *... , Entergy Nuclear Northeast Indian Point Energy Center

~Entergx 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel 914-254-6700 Anthony J. Vitale Site Vice President 10 CFR 50.36a

. NL-19-039 April 23, 2019 ATTN: Do9ument Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

2018 Annual Radioactive Effluent Release Report Indian Point Nuclear Generating Units 1, 2, and 3 Docket Nos.50-003, 50-247, and 50-286 Facility Operating License No. DPR-5 Renewed Facility Operating License Nos. DPR-26 and DPR-64 The enclosure to this letter provides the Entergy Nuclear Operations, Inc. (Entergy) Annual Radioactive Effluent Release Report for 2018. This report is submitted in accordance with Technical Specification 5.6.3 and Regulatory Guide 1.21.

If you have any questions or require additional information, please contact Mr. Robert W.

Walpole, Regulatory Assurance Manager, at (914) 254-6710.

There are no new commitments being made in this letter.

Respectfully, Anthony J. Vitale AJV/cdm

Enclosure:

Radioactive Effluent Release Report: 2018 cc: See next page.

NL-19-039 Page 2 of 2 cc: . .,Mr. David Lew, Regional Administrator, NRC Region I

Mr, Richard V. Guzman, Senior Project Manager, NRC NRR DORL

/ Ms. Kimberly A. Conway, IPEC NRC Unit 1 Project Manager JNRC Resident Inspector's Office Ms. Alicia Barton, President and CEO, NYSERDA (w/o enclosure)

Ms. Bridget Frymire, New York State Public Service Commission (w/o enclosure)

~r. Timothy Rice, Bureau of Hazardous Waste & Radiation Mgmt. NYSDEC

...-Mr. Robert Snyder, NYS Department of Health Mr. Chuck Nieder, NYS Department of Environmental Conservation Engineering Department, American Nuclear Insurers

-Chief, Compliance Section, New York State DEC

- Division of Water Regional Water Engineer, New York State DEC

ENCLOSURE NL-19-039 Radioactive Effluent Release Report: 2018

Page 1 of 67 Facility: Indian Point Energy Center YEAR: 2018 Indian Point Units 1, 2 and 3 Docket Nos.: 50-3, 50-247, & 50-286 Entergy Nuclear Operations, Inc. (Entergy)

Annual Radioactive Effluent Release Report

Indian Point Units 1, 2 & 3 I Year: 2018 I Page 2 of 67 Annual Radioactive Effluent Release Report TABLE OF CONTENTS

1.0 INTRODUCTION

........................................................................................................................4 2.0 SUPPLEMENTAL INFORMATION ............................................................................................. .4 3.0 GASEOUS EFFLUENTS ........................................................................................................... 12 4.0 LIQUID EFFLUENTS ......... .' ...................................................................................................... 18 5.0 SOLID WASTE

SUMMARY

......................................................................................................23 6.0 RADIOLOGICAL IMPACT TO MAN ..........................................................................................42 7.0 METEOROLOGICAL DATA ......................................................................................................46 LIST OF TABLES ................................................................................................................................ 3 ATTACHMENTS Attachment 1 - Carbon 14 Discussion ...................................................................................................47 Attachment 2 - Groundwater Monitoring Program Results ................................................................... .48 Attachment 3 - 2018 Laboratory Analytical Results ............................................................................... 51

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 3 of 67 Annual Radioactive Effluent Release Report List of Tables Table 2.5-1 -Airborne Batch Releases Table 2.5 Liquid Batch Releases Table 3 Gaseous Effluents - Summation of All Releases - Units 1 and 2 Table 3 Gaseous Effluents - Batch Mode - Units 1 and 2 Table 3 Gaseous Effluents - Continuous Mode - Units 1 and 2 Table 3 Gaseous Effluents - Summation of All Releases - Unit 3 Table 3 Gaseous Effluents - Batch Mode - Unit 3 Table 3 Gaseous Effluents - Continuous Mode - Unit 3 Table 4 Liquid Effluents - Summation of All Releases - Units 1 and 2 Table 4 Liquid Effluents - Batch Mode - Units 1 and 2 Table 4 Liquid Effluents - Continuous Mode - Units 1 arid 2 Table 4 Liquid Effluents - Summation of All Releases - Unit 3 Table 4 Liquid Effluents - Batch and Continuous Modes - Unit 3 Table 6 Summary of Dose Assessments Table 6 Unit 2 Appendix I Dose Assessment Table 6 Unit 3 Appendix I Dose Assessment

l Indian Point Units 1, 2 & 3 YEAR: 2018 Page 4 of 67 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

This information is provided in accordance with the requirements of Regulatory Guide 1.21.

This report includes effluent information from Indian Point Units 1, 2, and 3. Units 1 and 2 share effluent processing equipment and Technical Specifications. In this site report, releases from Unit 1 are included with Unit 2, while Unit 3 releases are calculated and shqwn separately. Liquid and gaseous effluents are released in accordance with the Offsite Dose Calculation Manual (ODCM). This report is a summary of the effluent data in accordance with Unit 2 Technical Specification (TS) 5.6.3 and Unit 2 TS 5.6.3.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits Indian Point Energy Center is subject to limits on radioactive waste releases that are set forth in the Offsite Dose Calculation Manual (ODCM), Parts I and II, as defined in the Technical Specifications. ODCM Part I, also known as the Radiological Effluent Controls (or RECS) contains the specific requirements and controls, while ODCM Part II (calculation methodologies) contains the details* necessary to perform offsite dose calculations from the sampling and monitoring outlined in the RECS. The following are the limits required by the ODCM:

1. Fission and activation gases:

a. Noble gases dose rate due to radioactive materials released in gaseous effluents from the areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 500 mrem/year to the total body

Less than or equal to 3000 mrem/year to the skin

b. Noble gas air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

Quarterly: Less than or equal to 5 mrads gamma Less than or equal to 10 mrads beta

Yearly: Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta

2. Iodine, tritium, and all radionuclides in particulate form (with half-lives > 8 days).

a. The dose rate for lodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 1500 mrem/yr to any organ

b. The dose to a MEMBER OF THE PUBLIC from lodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Quarterly: Less thari or equal to 7.5 mrem to any organ

Yearly: Less than or equal to 15 mrem to any organ

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 5 of 67 Annual Radioactive Effluent Release Report

3. Liquid Effluents Dose The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

Quarterly: Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ

Yearly: Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ

4. Total Dose (40CFR190)

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:

Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.

Less than or equal to 75 mrem, Thyroid 2.2 Maximum Permissible Concentrations

1. Airborne Effluents Maximum concentrations and compliance with 10CFR20 release rate limits are controlled by the application of Radiation Monitor setpoints, preliminary grab sampling, and conservative procedural guidance for batch and continuous releases. These measures, in conjunction with plant design, preclude approaching release rate limits, per the ODCM.

2. Liquid Effluents Proximity to release rate and total release limits is controlled through the application of a calculated Allowed Diluted Concentration (ADC) and ALARA guidance with regard to dilution flow and maximum tank concentration. The ADC is used to determine a Radiation Monitor setpoint associated with an estimated amount of non-gamma activity (H-3, Ni-63, Fe-55, Sr-89/90 etc.), as well as the measured ga,mma activity. ADC is defined in the station ODCM as a means of assuring compliance with the release rate limits of 10CFR20, as defined by the application of ten times the Effluent Concentrations of the "n.ew 10CFR20.

Liquid effluents are further controlled by the application of proceduralized ALARA limits such as a MINIMUM dilution flow of 100,000 gpm required for batch discharges, a maximum gamma concentration of 5E-5 uCi/ml (without gas) for routine effluents, and procedural guidance for optimizing decay and treatment of liquid waste.

2.3 Average Energy This information is no longer used. It is available onsite if required.

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 6 of 67 Annual Radioactive Effluent Release Report 2.4 Measurements & Approximations of Total Radioactivity The following provides the methods used to measure or approximate the total radioactivity in effluents and how radionuclide composition is determined.

1. Fission & activation gases Analyses of effluent gases are* performed in compliance with the requirements of the RECS (ODCM Part I). In the case of isolated tanks (batch releases), the total activity discharged is based on an isotopic analysis of each batch with the volume of gas in the batch corrected to standard temperature and pressure.

Vapor containment purge and pressure relief (vent) discharges, which routinely total less than 150 hour0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months s/quarter in duration, have been treated as batch releases. However, both types of releases from the Vapor Containment are performed randomly with regard to time* of day and duration (release periods were not dependent solely on time of day or atmospheric condition).

Therefore, determination of doses due to Vapor Containment releases includes the use of annual average dispersion data, as defined in NUREG 0133, Section 3.3.

At least one complete isotopic concentration analysis of containment air is performed monthly and compared to a process monitor's reading. Pressure reliefs are quantified by scaling subsequent releases with the monitor's reading, applying the mixture from the grab sample. In this fashion, the base grab sample defines the mixture and the activity released. The monitor scales the release up or down and provides continuous indication of potential leaks.

Isotopic analyses for each vapor containment purge are taken prior to and during the purge.

This information is combined with the volume of air in each discharge to calculate the quantity of activity released from these discharges.

2. Iodines and Particulates Iodine and particulate releases are quantified by collecting a* continuous sample of ventilation air on a Triethylenediamine {TEDA) impregnated, activated charcoal cartridge and a glass-fiber filter paper. These samples are changed weekly as required in the RECS. The concentration of isotopes found by analysis of these samples is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged.

If no 1-131 is identified in weekly vent samples,"-" is entered in Table 1A. A ~ypical Minimum Detectable Activity (MDA) for weekly 1-131 analyses is 1.0E-13 uCi/cc, which is 100 times lower than ODCM requirements.

If 1-131 is identified in any routine weekly sample, it is added to the table and other iodine isotopic concentrations (1-133, 1-135) are then determined on a 24-hour sample at least once per month. The concentration of each isotope is analytically determined by ratioing the activities with weekly media for 1-131. This activity is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged. A compositing method of analyzing for gross alpha, Sr-89, and Sr-90 is used per the station ODCMs An absence of any positive ,activity is identified as"-".

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 7 of 67 Annual Radioactive Effluent Release Report

3. Tritium Tritium is collected by passing a known volume of the sample stream through a silica gel column. The collected samples are distilled and analyzed by liquid scintillation. The tritium released was calculated for each release point from the measured tritium concentration, the volume of the sample, the tritium collectiqn efficiency, and the respective ventilation exhaust flow rates. As a check on the silica gel sampling, Chemistry performs a comparison of total curies evaporated from the spent fuel pool (the major H-3 source term) and adjusts the silica gel measurements, as necessary.

4. Carbon-14 Carbon-14 release values were estimated using the methodology included in the EPRI Technical Report 1021106, using the normalized Carbon-14 production rate of 3.48 Ci/GWth-EFPyear for Unit 2 and 3.47 Ci/GWth-EFPyear for Unit 3, a gaseous release fraction of 100%,

a Carbon-14 carbon dioxide fraction of 26%, a reactor power rating 3216 MWth for Unit 2 and 3188 MWth for Unit 3 and equivalent full power (EFP) operation of 328.14 days for Unit 2 and 334.89 days for Unit 3 for calendar year 2018. See Section 6 and Attachment 1 for more details concerning the Carbon 14 calculations.

5. Liquid Effluents A sample of each batch discharge is taken and an isotopic analysis is performed in compliance with requirements specified in the ODCM. Proportional composit~ samples of continuous discharges are taken and analyzed per the ODCM, as well. Isotopic concentration data are combined With the information on volume discharged to determine the amount of each isotope discharged.

A compositing method of analyzing for non-gamma emitters is used per the station ODCM (Gross Alpha, Sr-89, Sr-90, Fe-55 and Ni-63). When there has been no positive activity, "-" is entered.

Liquid Effluent volumes of waste released on Tables 4-1 and 4-4 (Section 4) are differentiated between processed fluids (routine liquid waste and Unit 1's North Curtain Drain), and water discharged through monitored pathways identified in the ODCM, but NOT processed (SG Slowdown and Unit 1's Sphere Foundation Drain Sump). The unprocessed water may still contain trace levels of contamination (generally only tritium) and as such, is identified as liquid waste. Curie and dose data from unprocessed fluid is included in the following tables, along with all other liquid effluent, continuous or batch, processed or not. Processed and unprocessed water is differentiated only to prevent confusion with regard to measures undertaken to convert liquid to solid waste (resin cleanup). Therefore, volumes of processed and unprocessed liquid waste are reported separately on Tables 4-1 and 4-4.

6. Estimated Total Error Present Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:

Where: ET= total percent error E1 *** En = percent error due to calibration standards, Laboratory analysis, instruments, sample flow, etc.

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 8 of 67 Annual Radioactive Effluent Release Report 2.5 Batch Releases:

1. Airborne Table 2.5 Airborne Batch Releases

. Unit 1 and 2 Airborne Releases ***atr3 Qtr'1 Qtr2 Qtr4 2018 Number of Batch Releases 65 57 54 47 223 Total Time Period (min) 3220 2740 2400 2500 10900 Maximum Time Period (min) 123 136 87 84 136 Average Time Period (min) 49.6 48.1 44.5 53.2 48.7 Minimum Time Period (min) 5 2 5 2 2 Unit 3 Airborne Releases Qtr 1. Qtr2 Qtr3 Qtr.4 2018 Number of Batch Releases 17 18 19 17 71 Total Time Period (min) 1880 2380 2180 2030 8470 Maximum Time Period (min) 179 209 206 220 220 Average Time Period (min) 111 132 115 119 119 Minimum Time Period (min) 3 8 1 1 1

2. Liquid Table 2.5 Liquid Batch Releases Unit 1 and 2 Liquid Releases Qtr 1 Qtr2 Qtr3 Qtr4 2018 Number of Batch Releases 28 21 6 2 57 Total Time Period (min) 2430 1980 473 169 5052 Maximum Time Period (min) 108 107 100 92 107 Average Time Period (min) 86.9 94.1 78.8 84.5 88.6 Minimum Time Period (min) 45 85 32 77 32 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr3 Qtr4 2018 Number of Batch Releases 14 27 21 24 86 Total Time Period (min) 1480 2880 2420 2530 9310 Maximum Time Period (min) 132 118 200 117 200 Average Time Period (min) 106 107 115 106 108 Minimum Time Period (min) 58 44 108 49 44 Average Stream Flow:

Regulatory Guide 1.21 includes a section to report average stream flows. This data, for some plants, is used to 1

determine dilution volume. However, at IPEC, the Hudson River stream flow is not applied to dilution calculations, in favor of the more conservative method of using only the dilution in the discharge canal, running north to south, parallel to the river, and servicing the plant.

This conservative dilution volume is determined quarterly, applied to liquid offsite dose calculations (and all other determinations of diluted effluent), and reported on Tables 4-1 and 4-4, in Section 4 of this report. Hudson River flow information remains available, however, from the Department of the Interior, United States Geological Survey (USGS), or from web sites such as:

https://www.usgs.gov/centers/ny-water/data-tools

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 9 of 67 Annual Radioactive Effluent Release Report 2.6 Abnormal Releases

1. Liquid Two Abnormal Releases were noted in 2018.

On February 19, 2018, the Unit 1 Containment Spray Sump (U1-CSS) was discovered full and overflowing. Initial assessment indicated that a fire main had burst in the area which resulted in a large area near the U1-CSS of U-1 being flooded. Nearby floor drains likely channeled a small amount of this water to the river. Note that Unit 1 began operation in 1965, shut down in 1970 and retired permanently in 1980. The CSS was drained and isolated in 2006. Low levels of Cs-137, Sr-90 and H-3 have typically been detected in this sump. The following assumptions were made for performing the dose assessment for this potential liquid release:

r- -~----------*-- - -- -- -~-1-- * - -- -*1 --*- - l w-------------------- -----. - ------- -- - ----r- ---- -- - --1* *- - --

i~s_!_i!f!cl~~d _v_lt::>l_'::'_~_E:: _____ ,_____ _!~~\-gc1l_~~_ns!J~_t::>!1~~!_va_ti_ ~e_1::s_t_~_~_a_t~?---- --*-**. --1 _ _ __I __

1

!Cs-137: , 6.4E-07 1uCi/ml i(SN 664662) I I I l

[;'i ;~o:_==l:=~:;_::~:l!~~:;=l l

i

_-}:_-=:==J** :a;;t;~1~ie_as~:*:bE1~~~~;;},.;~ti I I uCi/year I Ci/year I fraction !

n~***

LActivity rel~ased: *_:~:Jcs-137: T~o.242Juci~:~:~:**-~--1._6.19E+04r~*o.0619~1:3.. 91E-061 . *_: __ -__ ~-:*~--

t**<< - !

- - - -"***** \ *"-"*-**-- *** - " **

iH-3:

--A,,-,-* ---*--*-*** '"'1!**** *1.136iuCi

- -*--*~*" ! *-**** *.-*n

! 7.75E+08:

- * * - - * * * - - { * * *** * ~--"'-*--~- -**

775 ) 1.47E-09 j

- - -*!*-*-*********** *****'"* * .-****s'*t-**, * *~ *******-*~~**-*~ ,-****,**:-n**~ -* *"**-*** '* - * ** *

!_ _ ....... __ **--* L__ .... _____J_~r::~CJ______ 3__ CJ_:~~.:4J~_C? __________j ___ ____ _________ L__ ...... _ __ .. L.*--*-*---***-** . ___ L ..... .

The above estimated release results in calculated doses of 1 e-7 mrem to the critical organ (bone) and 5 e-8 mrem to the total body (conservatively assuming a discharge directly to the Hudson River). Note that doses from routine liquid effluent releases are typically insignificant and the dose consequence from this event is even more insignificant.

The second Abnormal Release appears to be from an April 1, 2018 event where several thousand gallons of contaminated residual heat removal (RHR) water spilled onto the 15' of the Unit 2 Primary Auxiliary Building (PAS). This water was contained in a bermed area inside the RHR valve gallery and almost all of it was pumped into a nearby sump for transfer to waste processing. However, this spill seems to have contributed to a significant increase in H-3 levels at one of the down-gradient wells (MW-33). No other radioactive isotopes were detected in the groundwater samples from this postulated release. H-3 levels reached a peak level of 507,400 pCi/liter (onsite analysis) on June 11, 2018. Since that time the levels have significantly decreased. Attachment 2 provides a detailed list of all the Groundwater Monitoring Program results for 2018. As part of the detailed investigation of this event several methods were used to determine the likely amount of liquid released through the PAS floor/wall interface to the outside environment. The conclusion of this investigation was an estimated volume of 50 gallons may have reached groundwater. Based upon a conservative estimate of 100 gallons released, a conservative pathway of directly to the Hudson River and a known H-3 concentration of 0.035 uCi/ml in the RHR water, results in a calculated release of 13,300 uCi of H-3 and a dose of 1.5 e-7 mrem to both the critical organ and the whole body. As noted with the above event, the resulting doses are insignificant.

3.Gaseous None

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 10 of 67 Annual Radioactive Effluent Release Report 2.7 Non-routine, Planned Discharges Recovery Well - 1 (RW-1) was installed as a contingency for mitigation of spills in the affecting the area near the Unit 2 Fuel Storage Building. Due to the two abnormal releases that were discussed in the 2016 Radioactive Effluent Release Report it was determined necessary to actually operate this well to enhance the reduction of H-3 levels in groundwater.

This was determined to be necessary to reduce the H-3 to levels that would enable the Site to detect any new leaks or spills of contaminated waters. Operation of this well is a continuous monitored release pathway for liquid effluents from Unit 2. Therefore this well is sampled per procedure and monthly permits are performed for this liquid discharge pathway.

For ease of tracking, the releases from this pathway are documented as non-routine batch releases that are discharged from Unit 2. The batch totals listed in Section 2.5.2 do not include these in the totals since this discharge pathway is actually a continuous release pathway. Note that only H-3 has been detected in the RW-1.releases and the levels are very low compared to the typical batch releases. This does not present a problem with the dose calculations since the dose assessment modeling does not differentiate between continuous and batch releases.

Another non-routine release is one that occurs when routine ventilation is out of service (OOS). Typically this is only for very short of time per procedure, such that these releases are insignificant. Typically, the most significant of these releases occurs when the Fuel Storage Building (FSB) ventilation is OOS. The use of H-3 curie balance for the Spent Fuel Pool (SFP) can be used to account for these releases (also see Section 2.4 -Tritium) since the major airborne source term from the FSB is the evaporation of the SFP water. Another method is to evaluate the SFP H-3 airborne activity and.estimate the airborne release rate.

2. 7 Radioactive Waste Treatment System Changes There were no changes to the Radioactive.Waste Treatment System.

2.8 Land Use Census Changes No changes or modifications affecting receptors, receptor location or new (or changed) routes of exposure were identified as a result of the last Land Use Census.

2.9 Effluent Monitor Instrument lnoperability During this reporting period, the following ODCM required effluent monitoring equipment was out of service for greater than 30 consecutive days:

Effected Instrument .** interval Details The monitor was taken out of service for a 2 year calibration, which was completed on 1/24/18 2/1/2018. Subsequently, the background was too Unit 2 Liquid to high. The monitor was deconned on 02/12/2018 and Waste Effluent, 3/1/18 returned to Operations. Once again, high background R-54 36 days required another decontamination effort. This _second effort w~s completed on 02/28/2018. At that time, the monitor was returned to Operations.

I-------

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 11 of 67 Annual Ra.dioactive Effluent Release Report 2.10 Offsite Dose Calculation Manual Changes During this report period there were no ODCM changes.

2.11 Process Control Program (PCP) Changes There were no PCP changes during 2018.

2.12 Groundwater Monitoring and Program (NEI 07-07)

The Groundwater Monitoring Program is a voluntary program set up to assure timely effective management of situations involving inadvertent releases of licensed material to ground water.

A major part of the IPEC's program is a groundwater quantification model that involves verification/calibration such that the annual release to the environment remains a function of the annual precipitation and source term.

Although 2 abnormal releases were noted in 2018 (see Section 2.6) conservative assessments of these and legacy events have determined that the doses resulting from all these events were negligible. The groundwater monitoring program provides additional confirmation of these assessments. The groundwater monitoring program also includes a storm water monitoring program. Together these programs provide data for offsite dose evaluation. The subsurface water flow parameters of this assessment include direction and rate for use as a basis for estimating the dispersion of abnormal releases of liquid effluents into groundwater.

The offsite dose associated with the groundwater pathway remains extremely small. The 2018 effluent dose was approximately a factor of 2 higher than in 2017. This was primarily due to the increase in recorded rain in the area. The total routine liquid effluent dose inclusive of the groundwater pathway contributes < 0.2 % of the annual limit. Groundwater and storm water effluent flow rates an.d source term data are further described in Attachment 2 of this report. A breakdown of the total dose from the groundwater and storm water pathways and detailed results from the samples obtained as part of this program are also provided in Attachment 2.

Section 6 (Radiological Impact on Man) of this report provides a comparison of the groundwater and storm water doses to the other dose pathways.

2.13 Outside Tanks During this period there were no curie limits exceed in the outdoor tanks.

2.14 Errata/Corrections to Previous ARERRs There was no errata/corrections for previous ARERRs.

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 12 of 67 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS Table 3-1 Gaseous Effluents - Summation of All Releases - Units 1 and 2 Total A. Fission & Activation Gas, U *t Qtr 1 Qtr2 Qtr3 Year % Error rn s Qtr4 L

1. Total Release Ci 2.59E-01 3.83E-02 3.81E-02 2.82E-02 3.64E-01 +/-25

2. Average release rate uCi/sec 3.33E-02 4.87E-03 4.79E-03 3.55E-03 1.15E-02

8. Iodines

1. Total lodine-131 Ci - - - - O.OOE+OO +/-25

2. Average release rate uCi/sec - - - - O.OOE+OO C. Particulates

1. Total Release, with h:=ilf-JifA > 8 rl<=>\/e>

Ci - - - - O.OOE+OO +/-25

2. Average release rate uCi/sec - - - - O.OOE+OO

3. Gross Alpha Ci - - - - O.OOE+OO +/-25 D. Tritium

1. Total release Ci 9.28E-01 1.46E+OO 2.11E+OO 2.45E+OO 6.95E+OO +/-25

2. Average release rate uCi/sec 1.19E-01 1.86E-01 2.65E-01 3.08E-01 2.20E-01 E. Carbon-14

1. Total release Ci 2.53E+OO 2.53E+OO 2.53E+OO 2.53E+OO 1.01E+01

2. Average release rate uCi/sec 3.25E-01 3.21 E-01 3.18E-01 3.18E-01 3.20E-01

- Indicates < MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 13 of 67 Annual Radioactive Effluent Release Report Table 3-2 Gaseous Effluents - Batch Mode - Units 1 and 2 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 '

Qtr 3 Qtr4 Year Ar-41 Ci 4.40E-02 1.84E-02 1.67E-02 1.52E-02 9.43E-02 Kr-85 Ci - - - - O.OOE+OO Kr-85m Ci 1.36E-04 8.20E-05 1.11E-04 8.01E-07 3.30E-04 Kr-87 Ci 9.33E-05 6.56E-05 1.01E-04 6.43E-07 2.61E-04 Kr-88 Ci 2.46E-04 1.64E-04 2.06E-04 1.93E-06 6.18E-04 Xe-131m Ci 1.54E-04 - - - 1.54E-04 Xe-133 Ci 2.03E-01 1.83E-02 1.90E-02 1.30E-02 2.53E-01 Xe-133m Ci 2.81E-03 - - 3.77E-07 2.81E-03 Xe-135 Ci 9.06E-03 1.10E-03 1.BOE-03 1.10E-05 1.20E-02 Xe-135m Ci 5.?BE-05 1.24E-04 2.19E-04 1.48E-06 4.02E-04 Xe-138 Ci - - - -

I '., .,. ,. ,.. ., . *,. ,. '*r.

>: '*i::ot~l:tor Perfod: :,** . :Qi; << *~:~oE-of '* ,' :,*;,, ,:. *, ":,,>'<fl.,:

3.82Eso2. ,3:81E~02' , *2:s2E,02* *::f64E:.01 9.00E+OO

,; : / */', :,!, ,,, " * '" ',,.. ', _>i, s ' .,,;' ~ :',, ,,.:, , "'/ ',' ,1 ;'.: "'/, ," ~ , ,,,.,, .. ;,. ?,-,,:'. */;' ,:*;, :/' l

- indicates <MDA

2) Iodines Not Applicable for Batch Releases

3) Particulates Not Applicable for Batch Releases

India n Point Units 1, 2 & 3 I YEAR: 2018 Page 14 of 67 Annual Radioactive Effluent Release Report Ta ble 3-3 Gaseous Effluents - Continuous Mode - Units 1 and 2 Nuclides Released

1) Fissi on Gases Units Qtr 1 Qtr2 Qtr 3 Qtr4 Year Xe -133 Ci - - - - O.OOE+OO Total 1ior Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

2) lodin es I

1-1 31 Ci - - - - O.OOE+OO 1-1 33 Ci - - - - O.OOE+OO 1-1 35 Ci - - - - O.OOE+OO Total for Period - ,:--

CL Q,OOE+09, O.OOE:+-'00 -o.qoE+OO -, O, OOE +O_Cf O.OOE+OO

3) Parti culates I

Co-58 Ci - - - - O.OOE+OO Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indicates < M DA

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 15 of 67 Annual Radioactive Effluent Release Report Table 3-4 Gaseous Effluents - Summation of All Releases - Unit 3 A . Fission & Activation Gas1 Total Units Qtr 1 Qtr2 Qtr 3 Qtr4 Year % Error

1. Total Release Ci 8.18E-03 1.86E-02 2.58E-02 1.32E-02 6.58E-02 +/- 25

2. A\erage release rate uCi/sec 1.05E-03 2.37E-03 3.25E-03 1.66E-03 2.09E-03 B . Iodines

1. Total lodine-131 Ci O.OOE+OO +/- 25

2. A\erage release rate uCi/sec O.OOE+OO C . Particulates

1. Total Release, with Ci O.OOE+OO +/- 25 half-life> 8 da s

2. A\erage release rate uCi/sec O.OOE+OO

3. Gross Alpha Ci O.OOE+OO +/- 25 D. Tritium

1. Total release Ci 2.25E+OO 4.36E+OO 5.05E+OO 3.35E+OO 1.50E+01 +/- 25 2, A\erage release rate uCi/sec 2.89E-01 5.55E-01 6.35E-01 4.21 E-01 4.76E-01 E . Carbon-14

1. Total release Ci 2.53E+OO 2.53E+OO 2.53E+OO 2.53E+OO 1.01 E+01

2. A\erage release rate uCi/sec 3.25E-01 3.21 E-01 3.18E-01 3.18E-01 3.20E-01

- Indicates < MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 16 of 67 Annual Radioactive Effluent Release Report Table 3-5 Gaseous Effluents - Batch Mode - Unit 3 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Ar-41 Ci 7.82E-03 1.25E-02 8.90E-03 1.00E-02 3.92E-02 Kr-85 Ci - - - - O.OOE+OO Kr-85m Ci - - - - O.OOE+OO Kr-87 Ci - - - - O.OOE+OO Kr-88 Ci - - - - O.OOE+OO Xe-131m Ci - - - - O.OOE+OO Xe-133 Ci 3.57E-04 6.15E-03 1.67E-02 3.16E-03 2.64E-02 Xe-133m Ci - - - - O.OOE+OO Xe-135 Ci - - 1.63E-04 - 1.63E-04 Xe-135m Ci - - - - O.OOE+OO I Total for Period Ci 8.18E-03 1.87E-02 2.58E-02 1.32E-02 6.58E-02

- Indicates < MDA

2) Iodines Not Applicable for Batch Releases

3) Particulates Not Applicable for Batch Releases

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 17 of 67 Annual Radioactive Effluent Release Report Table 3-6 Gaseous Effluents - Continuous Mode - Unit 3 Nuclides Released

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year Ar-41 Ci - - - - O.OOE+OO Xe-133 Ci - - - - 0.00E+OO Xe-135 Ci - - - - O.OOE+OO I Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

2) Iodines 1-131 Ci - - - - O.OOE+OO 1-133 Ci - - - - O.OOE+OO 1-135 Ci - - - - O.OOE+OO I Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO

3) Particulates Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

- indicates< MDA

In dian Point Units 1, 2 & 3 YEAR: 2018 Page 18 of 67 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS Ta ble 4-1 Liquid Effluents - Sum*mation of All Releases - Units 1 and 2 Est. Total A. Fission & Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year % Error

1. Total Release (not including Ci 2.35E-02 1.56E-02 1.88E-02 2.25E-02 8.04E-02 +/- 25 Tritium, Gr Alpha, & Gases)

2. Averag e Diluted Cone uCi/ml 3.65E-11 2.19E-11 2.20E-11 2.79E-11 2.66E-11 B. Tritium I

1. Total Release Ci 3.33E+02 1.26E+02 2.31E+01 1.17E+01 4.94E+02 +/- 25

2. Averag e Diluted Cone uCi/ml 5.1 ?E-07 1. 77E-07 2. ?OE-08 1.45E-08 1.64E-07 C. Dissolved & Entrained Gases

1. Total Release Ci 2.82E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E-04 +/- 25

2. Averag eDiluted Cone uCi/ml 4.38E-13 O.OOE+OO O.OOE+OO O.OOE+OO 9.34E-14 D. Gross Alpha I 1. Total Release Ci IO.OOE+OO I +/- 25 E. Volume of Waste Released

1. Proces sed Fluids (rvbn Tanks) liters 4.03E+06 2.99E+06 2.48E+06 3.22E+06 1.27E+07 +/- 10

2. Unproc essed Fluids (SGs) liters 4.22E+07 4.85E+07 4.49E+07 4.75E+07 1.83E+08 +/- 10 F. Volume of Dilution Water liters 6.44E+11 7.11 E+11 8.56E+11 8.07E+11 3.02E+12 +/- 10

- indicates < MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 19 of 67 Annual Radioactive Effluent Release Report Table 4-2 Liquid Effluents - Batch Mode - Units 1 and 2 Nuclides Released Units Qtr 1 Qtr2 Qtr3 Qtr4 Year Ag-110m Ci 1.09E-03 1.35E-05 - 1.12E-04 1.22E-03 Co-58 Ci 9.57E-03 1.12E-03 9.92E-05 2.29E-05 1.08E-02 Co-60 Ci 6.63E-04 2.02E-04 6.45E-05 5.40E-05 9.84E-04 Cr-51 Ci 8.24E-04 - - - 8.24E-04 Cs-137 Ci 7.76E-05 2.11E-04 9.14E-05 - 3.80E-04 Fe-55 Ci 1.19E-03 3.47E-04 1.67E-04 3.43E-04 2.0SE-03 Fe-59 4.71E-05 - - - 4. 71 E-05 Mn-54 Ci 1.23E-05 - - - 1.23E-05 Nb-95 Ci 8.47E-05 - - - 8.47E-05 Ni-63 Ci 1.04E-03 3.81E-04 1.67E-04 8.67E-05 1.67E-03 Sb-125 Ci 3.33E-05 - 2.35E-05 8.57E-04 9.14E-04 Te-123m Ci 2.31E-03 3.16E-05 6.65E-06 - 2.35E-03 Te-125m Ci - 1.18E-03 2.42E-03 - 3.60E-03 Total for Period 'Ci 1.69E-02 3.49E-03 3.04E-03 1.48E-03 2.49E-02

, I' Dissolved & Entrained Gas Ci - - - -

. O.OOE+OO Kr-85 *,

Xe-133 Ci 2.82E-04 - - - 2.82E-04 Total for Period Ci 2.82E-64 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E-04

- .Indicates < MDA

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 20 of 67 Annual Radioactive Effluent Release Report Table 4-3 Liquid Effluents - Continuous Mode - Units 1 and 2 Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year Cs-137 Ci 6.38E-03 1.21E-02 1.57E-02 2.0BE-02 5.50E-02 Ni-63 Ci - - - - O.OOE+OO Sr-89 Ci - - - - O.OOE+OO Sr-90 Ci 1.33E-04 1.58E-05 1.01E-04 1.94E-04 4.44E-04 I fotal for Period Ci 6.51E-03

1.21E-02 1.58E-02 2.10E-02 5.54E-02 H-3 (only) Ci 1.77E-02 1.92E-02 6.81E-02 9.24E-02 1.97E-01

- Indicates < MDA

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 21 of 67 Annual Radioactive Effluent Release Report Table 4-4 Liquid Effluents -Summation of All Releases - Unit 3 Est. Total A. Fission & Activation Products U .

rnts Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year % Error

1. Total Release (not including "

Ci 4.21E-03 2.08E-03 1.73E-03 1.55E-03 9.57E-03 +/-25 Tritium, Gr Alpha, & Gases)

2. Average Diluted Cone uCi/ml 6.53E-12 2.93E-12 2.02E-12 1.92E-12 3.17E-12 B. Tritium

1. Total Release \Ci 9.12E+01 1.86E+02 2.61E+02 3.26E+02 8.64E+02 +/-25

2. Average Diluted Cone uCi/ml 1.42E-07 2.62E-07 3.05E-07 4.04E-07 2.86E-07 C. Dissol\d & Entrained Gases

1. Total Release Ci 6.78E-06 - 6.42E-05 1.47E-04 2.18E-04 +/-25

2. AverageDiluted Cone uCi/ml 1.05E-14 - 7.50E-14 1.82E-13 7.22E-14 D. Gross Alpha

1. Total Release Ci IO.OOE+OO I +/-25 E. Volume of Waste Released

1. Processed Fluids (Mon Tanks) liters 3.34E+05 6.76E+05 5.35E+05 5.98E+05 2.14E+06 +/- 10

2. Unprocessed Fluids (SGs) liters 4.86E+06 1.82E+06 6.40E+06 3.15E+06 1.62E+07 +/- 10 F. Volume of Dilution Water liters 6.44E+11 7.11 E+11 8.56E+11 8.07E+11 3.02E+12 +/- 10

- indicates< MDA

% limit is located in Section 6, Tables 6-2 and 6-3

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 22 of 67 Annual Radioactive Effluent Release Report Table 4-5 Liquid Effluents - Batch and Continuous Modes - Unit 3 Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year Ag-110m Ci 1.38E-04 2.87E-04 1.51 E-04 1.75E-05 5.94E-04 Co-58 Ci 1.35E-04 9.41E-06 5.32E-05 3.66E-05 2.34E-04 Co-60 Ci 6.84E-04 1.08E-03 4.95E-04 9.23E-05 2.35E-03 Cr-51 Ci - - - - O.OOE+OO Cs-134 Ci - - - - O.OOE+OO Cs-137 Ci 9.22E-05 - - - 9.22E-05 Fe-55 Ci 1.29E-03 2.19E-04 4.00E-04 3.99E-04 2.31E-03 1-132 Ci - - - - O.OOE+OO Mn-54 Ci 1.99E-05 2.76E-05 6.72E-07 - 4.82E-05 Nb-95 Ci - - - - O.OOE+OO Ni-63 Ci 6.55E-04 2.42E-04 3.35E-04 1.25E-04 1.36E-03 Sb-124 Ci 1.43E-05 - - - 1.43E-05 Sb-125 Ci 1.17E-03 2.13E-04 2.95E-04 8.81E-04 2.56E-03 Tc-99m Ci - - - - O.OOE+OO Te-123m Ci 8.71E-06 - - - 8.71E-06 Te-125m Ci - - - - O.OOE+OO Te-132 Ci - - - - O.OOE+OO I Total for Period Ci 4.21E-03 2.08E-03 1.73E-03 1.55E-03 9.57E-03 Dissolved and Entrained Gas (Batch)

Xe-133 Ci 6.78E-06 - 6.42E-05 1.47E-04 2.18E-04 Xe-135 Ci - - - - O.OOE+OO I Total for Period Ci 6.78E-06 O.OOE+OO 6.42E-05 1.47E-04 2.18E-04 Continuous Releases (SG Blo'M:iown)

H-3 (only) Ci 1.50E-03 1.78E-03 4.33E-03 4.34E-04 8.04E-03

- indicates < mda

)

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 23 of 67 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Units 1 & 2 T~~es of Solid Waste - Summa~

Waste Stream: Resins, Filters, and Evap Bottoms Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 5.85E+02 1.66E+01 4.02E+01 +/- 25%

B 1.72E+02 4.86E+OO 2.89E+02 +/- 25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/- 25%

All 7.57E+02 2.14E+01 3.29E+02 +/- 25%

Waste Stream Dry Active Waste Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 2.80E+04 7.93E+02 1.21E+OO +/-25%

B O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All 2.80E+04 7.93E+02 1.21E+OO +/-25%

Waste Stream Irradiated Components Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

B O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

Waste Stream: Other Waste Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 1.50E+03 4.25E+01 7.46E-03 +/-25%

B O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All 1.50E+03 4.25E+01 7.46E-03 +/-25%

Waste Stream: Sum of All 4 Categories Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 3.01E+04 8.52E+02 4.14E+01 +/-25%

B 1.72E+02 4.t~?E+OO 2.89E+02 +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All 3.03E+04 8.57E+02 3.30E+02 +/-25%

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 24 of 67 Annual Radioactive Effluent Release Report 5.2 Units 1 & 2 Solid Waste - Destination by Carrier .

Number of Shipments Mode of Transportations Destination 1 H. W. Ferren Energy Solutions - Bear Creek 1 H. W. Ferren Energy Solutions - GRF 20 Hittman Transport Energy Solutions - Bear Creek 1 Hittman Transport Erwin Resin Solutions LLC 1 Hittman Transport Energy Solutions - Bear Creek 4 Horwith Trucks Erwin Resin Solutions GRF 1 Landstar Ranger Energy Solutions - Bear Creek

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 25 of 67 Annual Radioactive Effluent Release Report 5.3 Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Abundance Activity (Ci)

H-3 0.12% 4.79E-02 C-14 0.01% 5.31E-03 Cr-51 5.55% 2.23E+OO Mn-54 1.26% 5.0SE-01 Fe-55 11.65% 4.68E+OO Co-57 0.23% 9.29E-02 Co-58 8.94% 3.59E+OO Co-60 24.84% 9.98E+OO Ni-59 0.47% 1.88E-01 Ni-63 38.34% 1.54E+01 Zn-65 0.40% 1.59E-01 Sr-89 0.00% 1.27E-03 Sr-90 0.02% 7.53E-03 Nb-94 0.00% 5.32E-04 Nb-95 1.00% 4.00E-01 Tc-99 0.00% 4.08E-04 Ag-110m 0.38% 1.53E-01 Sn-113 2.38% 9.58E-01 Sb-125 1.08% 4.32E-01 Cs-134 0.05% 2.02E-02 Cs-137 3.24% 1.30E+OO Ce-144 0.03% 1.15E-02 Pu-238 0.00% 1.32E-04 Pu-239 0.00% 1.40E-05 Pu-241 0.02% 8.35E-03 Am-241 0.00% 9.48E-05 Cm-242 0.00% 1.12E-06 Cm-243 0.00% 5.18E-05 Total 100.00% 4.02E+01 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 26 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Percent Abundance Curies Be-7 0.04% 1.0SE-01 C-14 0.00% 5.91E-03 Cr-51 0.01% 3.22E-02 Mn-54 1.17% 3.38E+OO Fe-55 12.49% 3.61E+01 Co-57 0.27% 7.78E-01 Co-58 16.02% 4.63E+01 Co-60 23.57% 6.81E+01 Ni-59 0.47% 1.37E+OO Ni-63 42.91% 1.24E+02 Zn-65 1.90% 5.50E+OO Sr-90 0.00% 1.19E-02 Tc-99 0.00% 7.41 E-04 Ag-110m 0.07% 2.1 OE-01 Sn-113 0.00% 7.15E-03 Sb-125 0.65% 1.87E+OO Cs-134 0.00% 1.09E-02 Cs-137 0.41% 1.18E+OO Ce-144 0.00% 1.13E-02 Pu-238 0.00% 3.73E-04 Pu-239 0.00% 2.27E-05 Pu-241 0.00% 6.22E-04 Am-241 0.00% 4.72E-04 Cm-242 0.00% 1.38E-06 Cm-243 0.00% 2.00E-04 Total 100.00% 2.89E+02 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 27 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Total Combined Nuclide Name Percent Abundance Curies H-3 0.01% 4.79E-02 Be-7 0.03% 1.05E-01 C-14 0.00% 1.12E-02 Cr-51 0.69% 2.26E+OO Mn-54 1.18% 3.89E+OO Fe-55 12.35% 4.07E+01 Co-57 0.26% 8.71 E-01 Co-58 15.11% 4.98E+01 Co-60 23.69% 7.81E+01 Ni-59 0.47% 1.56E+OO Ni-63 42.47% 1.40E+02 Zn-65 1.72% 5.66E+OO Sr-89 0.00% 1.27E-03 I

Sr-90 0.01% 1.95E-02 Nb-94 0.00% 5.32E-04 Nb-95 0.12% 4.00E-01 Tc-99 0.00% 1.15E-03 Ag-110m 0.11% 3.63E-01 Sn-113 0.29% 9.66E-01 Sb-125 0.70% 2.31E+OO Cs-134 0.01% 3.11E-02 Cs-137 0.75% 2.48E+OO Ce-144 0.01% 2.28E-02 Pu-238 0.00% 5.05E:*04 Pu-239 0.00% 3.67E-05 Pu-241 0.00% 8.98E-03 Am-241 0.00% 5.67E-04 Cm-242 0.00% 2.50E-06 Cm-243 0.00% 2.52E-04 Total 100.00% 3.30E+02 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 28 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.09% 1.14E-03 C-14 0.00% 4.84E-05 Mn-54 0.39% 4.78E-03 Fe-55 13.43% 1.63E-01 Co-57 0.35% 4.24E-03 Co-58 66.72% 8.10E-01 Co-60 5.94% 7.21E-02 Ni-59 0.11% 1.28E-03 Ni-63 8.48% 1.03E-01 Zn-65 0.14% 1.66E-03 Zr-95 1.08% 1.31 E-02 Nb-95 2.21% 2.68E-02 Tc-99 0.03% 3.38E-04 Ag-110m 0.31% 3.80E-03 Sn-113 0.14% 1.75E-03 Sb-125 0.41% 4.97E-03 Cs-137 0.16% 1.90E-03 Ce-144 0.00% 1.51 E-05 Pu-238 0.00% 2.38E-07 Pu-241 0.01% 8.91E-05 Am-241 0.00% 1.45E-07 Cm-243 0.00% 1.42E-07 Total 100.00% 1.21E+OO Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 29 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Dry Active Waste Total Combined Nuclide Name Percent Abundance Curies H-3 0.09% 1.14E-03 C-14 0.00% 4.84E-05 Mn-54 0.39% 4.78E-03 Fe-55 13.43% 1.63E-01 Co-57 0.35% 4.24E-03 Co-58 66.72% 8.10E-01 Co-60 5.94% 7.21E-02 Ni-59 0.11% 1.28E-03 Ni-63 8.48% 1.03E-01 Zn-65 0.14% 1.66E-03 Zr-95 1.08% 1.31 E-02 Nb-95 2.21% 2.68E-02 Tc-99 0.03% 3.38E-04 Ag-110m 0.31% 3.80E-03 Sn-113 0.14% 1.75E-03 Sb-125 0.41% 4.97E-03

(

Cs-137 0.16% 1.90E-03 Ce-144 0.00% 1.51 E-05 Pu-238 0.00% 2.38E-07 Pu-241 0.01% 8.91E-05 Am-241 0.00% 1.45E-07 Cm-243 0.00% 1.42E-07 Total 100.00% 1.21E+OO Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 \ Page 30 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.07% 5.29E-06 Mn-54 0.38% 2.82E-05 Fe-55 8.78% 6.55E-04 Co-57 0.37% 2.75E-05 Co-58 73.05% 5.45E-03 Co-60 4.52% 3.37E-04 Ni-59 0.10% 7.57E-06 Ni-63 7.96% 5.94E-04 Zn-65 0.14% 1.08E-05 Zr-95 1.18% 8.82E-05 Nb-95 2.48% 1.85E-04 Tc-99 0.03% 2.18E-06 Ag-110m 0.33% 2.48E-05 Sn-113 0.16% 1.16E-05 Sb-125 0.40% 2.99E-05 Cs-137 0.05% 3.92E-06 Total 100.00% 7.46E-03 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 I . YEAR: 2018 I Page 31 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Other Waste Total Nuclide Name Percent Abundance Curies H-3 0.07% 5.29E-06 Mn-54 0.38% 2.82E-05 Fe-55 8.78% 6.55E-04 Co-57 0.37% 2.75E-05 Co-58 73.05% 5.45E-03 Co-60 4.52% 3.37E-04 Ni-59 0.10% 7.57E-06 Ni-63 7.96% 5.94E-04 Zn-65 0.14% 1.08E-05 Zr-95 1.18% 8.82E-05 Nb-95 2.48% 1.85E-04 Tc-99 0.03% 2.18E-06 Ag-110m 0.33% 2.48E-05 Sn-113 0.16% 1.16E-05 Sb-125 0.40% 2.99E-05 Cs-137 0.05% 3.92E-06 Total 100;00% 7.46E-03 Note: For radionuclides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 32 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 0.12% 4.91E-02 C-14 0.01% 5.36E-03 Cr-51 5.39% 2.23E+OO Mn-54 1.23% 5.10E-01 Fe-55 11.73% 4.85E+OO Co-57 0.23% 9.71E-02 Co-58 10.64% 4.40E+OO Co-60 24.19% 1.00E+01 Ni-59 0.46% 1.89E-01 Ni-63 37.49% 1.55E+01 Zn-65 0.39% 1.60E-01 Sr-89 0.00% 1.27E-03 Sr-90 0.02% 7.53E-03 Zr-95 0.03% 1.32E-02 Nb-94 0.00% 5.32E-04 Nb-95 1.03% 4.27E-01 Tc-99 0.00% 7.48E-04 Ag-110m 0.38% 1.57E-01 Sn-113 2.32% 9.60E-01 Sb-125 1.06% 4.37E-01 Cs-134 0.05% 2.02E-02 Cs-137 3.17% 1.31E+OO Ce-144 r, 0.03% 1.15E-02 Pu-238 0.00% 1.32E-04 Pu-239 0.00% 1.40E-05 Pu-241 0.02% 8.44E-03 Am-241 0.00% 9:50E-05 Cm-242 0.00% 1.12E-06 Cm-243 0.00% 5.19E-05 Total 100.00% 4.13E+01 Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 33 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies Be-7 0.04% 1.05E-01 C-14 0.00% 5.91E-03 Cr-51 0.01% 3.22E-02 Mn-54 1.17% 3.38E+OO Fe-55 12.49% 3.61E+01 Co-57 0.27% 7.78E-01 Co-58 16.02% 4.63E+01 Co-60 23.57% \ 6.81E+01 Ni-59 0.47% 1.37E+OO Ni-63 42.91% 1.24E+02 Zn-65 1.90% - 5.50E+OO Sr-90 0.00% 1.19E-02 Tc-99 0.00% 7.41E-04 Ag-110m 0.07% 2.10E-01 Sn-113 0.00% 7.15E-03 Sb-125 0.65% 1.87E+OO Cs-134 0.00% 1.09E-02 Cs-137 0.41% 1.18E+OO Ce-144 0.00% 1.13E-02 Pu-238 0.00% 3.73E-04 Pu-239 0.00% 2.27E-05 Pu-241 0.00% 6.22E-04 Am-241 0.00% 4.72E-04 Cm-242 0.00% 1.38E-06 Cm-243 0.00% 2.00E-04 Total 100.00% 2.89+02 Note: For radionuc/ides H-3, C-14, Tc-99 and I-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 34 of 67 Annual Radioactive Effluent Release Report Units 1 & 2 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories All Waste Classes Nuclide Name Percent Abundance Curies H-3 0.01% 4.91 E-02 Be-7 0.03% 1.05E-01 C-14 0.00% 1.13E-02

. Cr-51 0.68% 2.26E+OO Mn-54 1.18% 3.89E+OO Fe-55 12.37% 4.09E+01 Co-57 0.26% 8.75E-01 Co-58 15.33% 5.07E+01 Co-60 23.61% 7.81E+01 Ni-59 0.47% 1.56E+OO Ni-63 42.33% 1.40E+02 Zn-65 1.71% 5.66E+OO Sr-89 0.00% 1.27E-03 Sr-90 0.01% 1.95E-02 Zr-95 0.00% 1.32E-02 Nb-94 0.00% 5.32E-04 Nb-95 0.13% 4.27E-01 Tc-99 0.00% 1.49E-03 Ag-110m 0.11% 3.67E-01 Sn-113 0.29% 9.67E-01 Sb-125 0.70% 2.31E+OO Cs-134 0.01% 3.11E-02 Cs-137 0.75% 2.48E+OO Ce-144 0.01% 2.28E-02 Pu-238 0.00% 5.06E-04 Pu-239 0.00% 3.67E-05 Pu-241 0.00% 9.0?E-03 Am-241 0.00% 5.67E-04 Cm-242 0.00% 2.50E-06 Cm-243 0.00% 2.52E-04 Total 100.00% 3.31 E+02 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 35 of 67 Annual Radioactive Effluent Release Report 5.4 Unit 3 T)l!;!es of Solid Waste - Summa!Y Waste Stream: Resins, Filters, and Evap Bottoms Waste Volume Curies % Error (Ci}

Class ft3 m3 Shipped A 1.80E+02 5.10E+OO 1.44E+OO +/- 25%

B 1.91 E+02 4.86E+OO 9.77E+01 +/- 25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/- 25%

All 3.71E+02 1.05E+01 9.91 E+01 +/- 25%

Waste Stream Dry Active Waste Waste Volume Curies % Error (Ci}

-Class ft3 m3 Shipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

B O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

Waste Stream Irradiated Components Waste Volume Curies % Error (Ci}

Class ft3 m3 Shipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

B O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

Waste Stream: Other Waste Waste Volume Curies % Error (Ci}

Class ft3 m3 Shipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

B O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

Waste Stream: Sum of All 4 Categories Waste Volume Curies % Error (Ci}

Class ft3 m3 Shipped A 1.80E+02 5.10E+OO 1.44E+OO +/-25%

B 1.91 E+02 5.41 E+OO 9.77E+01 +/-25%

C O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

All 3.71E+02 1.05E+01 9.91 E+01 +/-25%

- ------------ ---- ~~

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 36 of 67 Annual Radioactive Effluent Release Report 5.5 Unit 3 Solid Waste - Destination by Carrier Number of Mode of Transportations Destination Shipments 1 Hittman Transport Energy Solutions - Bear Creek 5.6 Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Abundance Activity (Ci)

H-3 0.08% 1.16E-03 C-14 2.83% 4.0BE-02 Cr-51 1.83% 2.63E-02 Mn-54 1.29% 1.86E-02 Fe-55 3.36% 4.84E-02 Co-57 0.21% 2.98E-03 Co-58 3.60% 5.18E-02 Co-60 12.01% 1.73E-01 Ni-59 0.85% 1.23E-02 Ni-63 60.61% 8.73E-01 Zn-65 0.27% 3.94E-03 Sr-90 0.00% 2.00E-05 Nb-95 0.03% 4.30E-04 Tc-99 0.01% 1.69E-04 Ag-110m 0.76% 1.10E-02 Sb-125 11.04% 1.59E-01 Cs-137 1.20% 1.73E-02 Ce-144 0.00% 9.03E-06 Pu-238 0.00% 8.92E-07 Pu-239 0.00% 1.70E-07 Pu-241 0.01% 1.01 E-04 Am-241 0.00% 4.23E-07 Cm-242 0.00% 8.46E-08 Cm-243 0.00% 5.57E-07 Total 100.00% 1.44E+OO Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 37 of 67 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Percent Abundance Curies H-3 0.00% 2.94E-03 C-14 0.17% 1.65E-01 Mn-54 1.45% 1.42E+OO Fe-55 11.57% 1.13E+01 Co-57 0.08% 7.55E-02 Co-58 0.59% 5.74E-01 Co-60 11.67% 1.14E+01 Ni-59 1.05% 1.03E+OO Ni-63 67.98% 6.64E+01 Sr-90 0.02% 2.09E-02 \

Tc-99 0.00% 1.75E-03 Sn-113 0.02% 2.03E-02 Sb-125 2.71% 2.65E+OO Cs-137 2.66% 2.60E+OO Ce-144 0.00% 3.58E-03 Pu-238 0.00% 9.25E-05 Pu-239 0.00% 4.40E-06 Pu-241 0.00% 4.53E-03 Am-241 0.00% 1.03E-04 Cm-242 0.00% 4.32E-06 Cm-243 0.00% 1.13E-04 Total 100.00% 9.77E+01 Note: For radionuclides H-3, C-14, Tc-99 and /-129 if value is <MDA then MDA is used to report Curies shipped.

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 38 of 67 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Resins, Filters and Evaporator Bottoms Total Combined Nuclide Name Percent Abundance Curies H-3 0.00% 4.10E-03 C-14 0.21% 2.06E-01 Cr-51 0.03% 2.63E-02 Mn-54 1.44% 1.43E+OO Fe-55 11.41% 1.13E+01 Co-57 0.08% 7.85E-02 Co-58 0.63% 6.26E-01 Co-60 11.62% 1.15E+01 Ni-59 1.05% 1.04E+OO Ni-63 67.98% 6.73E+01 Zn-65 0.00% 3.94E-03 Sr-90 0.02% 2.09E-02 Nb-95 0.00% 4.30E-04 Tc-99 0.00% 1.92E-03 Ag-110m 0.01% 1.10E-02 Sn-113 0.02% 2.03E-02 Sb-125 2.83% 2.80E+OO Cs-137 2.65% 2.62E+OO Ce-144 0.00% 3.59E-03 Pu-238 0.00% 9.34E-05 Pu-239 0.00% 4.57E-06 Pu-241 0.00% 4.63E-03 Am-241 0.00% 1.03E-04 Cm-242 0.00% 4.41 E-06 Cm-243 0.00% 1.13E-04

'Total 100.00% 9.90E+01 Note: For radionuc/ides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 39 of 67 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 0.08% 1.16E-03 C-14 2.83% 4.0BE-02 Cr-51 1.83% 2.63E-02 Mn-54 1.29% 1.86E-02 Fe-55 3.36% 4.84E-02 Co-57 0.21% 2.98E-03 Co-58 3.60% 5.18E-02 Co-60 12.01% 1.73E-01 Ni-59 0.85% 1.23E-02 Ni-63 60.61% 8.73E-01 Zn-65 0.27% 3.94E-03 Sr-90 0.00% 2.00E-05 Nb-95 0.03% 4.30E-04 Tc-99 0.01% I 1.69E-04 Ag-110m 0.76% 1.10E-02 Sb-125 11.04% 1.59E-01 Cs-137 1.20% 1.73E-02 Ce-144 0.00% 9.03E-06 Pu-238 0.00% 8.92E-07 I

Pu-239 0.00% 1.?0E-07 Pu-241 0.01% 1.01 E-04 Am-241 0.00% 4.23E-07 Cm-242 0.00% ', 8.46E-08 Cm-243 0.00% 5.57E-07 Total 100.00% 1.44+00 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 40 of 67 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - - Major Nuclides by Waste Class and Stream Sum All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.00% 2.94E-03 C-14 0.17% 1.65E-01 Mn-54 1.45% 1.42E+OO Fe-55 11.57% 1.13E+01 Co-57 0.08% 7.55E-02 Co-58 0.59% 5.74E-01 Co-60 11.67% 1.14E+01 Ni-59 1.05% 1.03E+OO Ni-63 67.98% 6.64E+01 Sr-90 0.02% 2.09E-02 Tc-99 0.00% 1.75E-03 Sn-113 0.02% 2.03E-02 Sb-125 2.71% 2.65E+OO Cs-137 2.66% 2.60E+OO Ce-144 0.00% 3.58E-03 Pu-238 0.00% 9.25E-05 Pu-239 0.00% 4.40E-06 Pu-241 0.00% 4.53E-03 Am-241 0.00% 1.03E-04 Cm-242 0.00% ' 4.32E-06 Cm-243 0.00% 1.13E-04 Total 100.00% 9.77+01 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 41 of 67 Annual Radioactive Effluent Release Report Unit 3 Solid Waste - Major Nuclides by Waste Class and Stream Sum All 4 Categories All Waste Classes Nuclide Name Percent Abund.ance Curies H-3 O.OOJa 4.10E-03 C-14 0.21% 2.06E-01 Cr-51 0.03% 2.63E-02 Mn-54 1.44% 1.43E+OO Fe-55 11.41% 1.13E+01 Co-57 0.08% 7.85E-02 Co-58 0.63% 6.26E-01 Co-60 11.62% _,I 1.15E+01 Ni-59 1.05% 1.04E+OO Ni-63 67.98% 6.73E+01 Zn-65 0.00% 3.94E-03 Sr-90 0.02% 2.09E-02 Nb-95 0.00% 4.30E-04 Tc-99 0.00% 1.92E-03 Ag-110m 0.01% 1.10E-02 Sn-113 0.02% .2.03E-02 Sb-125 2.83% 2.80E+OO Cs-137 2.65% 2.62E+OO Ce-144 0.00% 3.59E-03 Pu-238 0.00% 9.34E-05 Pu-239 0.00% 4.57E-06 Pu-241 0.00% 4.63E-03 Am-241 0.00% 1.03E-04 Cm-242 0.00% 4.41 E-06 Cm-243 0.00% 1.13E-04 Total 100.00% 9.90E+01 Note: For radionuclides H-3, C-14, Tc-99 and 1-129 if value is <MDA then MDA is used to report Curies shipped

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 42 of 67 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN The Radiological Impact on Man due to radioactive effluent from the site is determined from NRC approved modeling, per Regulatory Guide 1.109 and NUREG 0133. Calculations are divided into 3 categories: Noble Gases, Particulates and Iodine, and Liquid Releases (fish and invertebrate consumption). This modeling involves conservative dose calculations to Adult, Teen, Child, and Infant age groups. Furthermore, dose modeling is performed for six separate organs as well as the total body dose. This well-established industry model provides doses (as a result of plant effluent) to a hypothetical maximally exposed individual offsite. While ALL age groups and organs are considered, it is this maximum value that is provided in the tables that follow.

An approved computer code is used to perform liquid and gaseous dose calculations according to the models and parameters presented in the Indian Point Offsite Dose Calculation Manual (ODCM). This information is stored in a database on site to enhance dose tracking and information management. Site airborne effluent dose calculations include annual average dispersion and deposition factors, averaged from data collected over approximately ten year periods. When new data is averaged (approximately every ten years) the modeling is updated and used in subsequent airborne effluent calculations. Liquid offsite dose calculations involve fish and invertebrate consumption pathways only, as determined appropriate in the ODCM.

While the ODCM identified some site-specific dose factors, the bulk of this information is obtained directly from Regulatory Guide 1.109 and NU REG 0133. Details of the calculations, site-specific data, and their bases are presented in the ODCM. See the tables at the end of this section for the 10CFR50 Appendix I Dose Assessments.

6.1 Dose to Members of the Public Inside the Site Boundary Members of the public visiting the site receive minimal dose as a result of onsite releases because of the relatively insignificant total amount of time they are on site, as well as the immeasurably low levels of dose at the critical receptors. Their doses can be calculated from standard ODCM methodology, with typical occupancy factors employed. These factors are determined by comparing a conservative assumption for their expected hours on site, to 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months (the number of hours in a year, used in calculations in the ODCM).

Example 1: Several students visit the site for 8-hour tour.

Their occupancy factor is: 8 / 8760 or 0.0009 Example 2: A man drives his wife to work and drops her off at the security gate each morning, with a stay time of 2 minutes per day. His occupancy factor is calculated as follows:

2 min/day

250 days/year/ 60 min/hr/ 8760 hr/year= 0.0010 6.2 Dose to a Member of the Public due to Release of Radioactive Material in Groundwater Curies and dose contribution from activity discovered in onsite groundwater and storm drain pathways during the year are discussed in more detail in Attachment 2. The offsite dose calculation involves multiple source term measurements, as well as computations for release and dilution flow. A summary of the quantification methodology, and the resulting calculated doses, is also provided at Attachment 2. The Summation of Dose Assessments (Table 6-1) below provides a means to compare ground water doses with those of other components making up the total offsite dose.

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 43 of 67 Annual Radioactive Effluent Release Report 6.3 40CFR Part 190 Dose to Individual in the Unrestricted Area Unit and pathway-specific dose data can be found on the Radiological Impact on Man tables following this discussion. For simplicity and to demonstrate compliance with 40CFR190, the following table indicates the maximum hypothetical Total Dose to an individual from operation of the facility, including any measured direct shine component from the site property.

Table 6-1 Summation of Dose Assessments Year: 2018 Total Body Max Organ 40 CFR 19.0 limit===+ IPEC .. 25 mrem /

75 mrem 1

Routine Airborne Effluents Units 1 and 2 1.21E-03 1.21E-03 Routine Liquid Effluents Units 1 and 2 1.64E-03 1.48E-03 14 Liquid Releases of C Units 1 and 2 1.17E-03 5.83E-03 14 Airborne Releases of C Units 1 and 2 6.21 E-02 3.11 E-01 1

Routine Airborne Effluents Unit 3 2.49E-03 2.49E-03 Routine Liquid Effluents Unit 3 3.07E-04 6.07E-04 14 Liquid Releases of C Unit 3 1.17E-03 5.83E-03 14 Airborne Releases of C Unit 3 6.19E-02 3.10E-01 2

Ground Water & Storm Drain Totals IPEC 9.0SE-05 3.67E-04 Direct Shine from areas such as dry 3

cask storage, radwaste storage, SG IPEC 2.SOE-01 2.SOE-01 Mausoleum, etc.

Indian Point Energy Center IPEC 3.82E-01 8.89E-01 Total Dose, per 40 CFR 190

Note 1: Routine airborne dose' in this table is conservatively represented as a sum of Iodine, Particulate, and Tritium dose (excluding C-14, in mrem) with a mrem term added from noble gas gamma air energy (mrad, expressed as mrem). This 'addition' does not represent a real dose and is listed here solely to help demonstrate compliance with 40CFR190. (Doses by type of release and comparison to the specific limits of 10CFR50 Appendix I are summarized on the following pages.)

Note 2: Groundwater curie and dose calculations ~re provided in Section H.

Note 3: 40CFR190 requires the reporting of total dose, including that of direct shine. Direct shine dose from sources other than dry cask are indistinguishable from background. Direct shine dose is determined from TLDs near the dry cask area and site boundary, compared with REMP TLDs and historical values, and corrected with occupancy factors to determine a bounding, worst case assessment of direct shine dose to a real individual. Details of each year's dose evaluation are available on site.

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 44 of 67 Annual Radioactive Effluent Release Report Table 6-2 Unit 2 Appendix I Dose Assessment A. LIQUID DOSES Qtr'1 Qtr2**

Qtr 3 ' Qtr4 ANNUAL Organ Dose mrem 4.55E-04 5.91 E-04 6.23E-04 8.81E-04 1.48E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit % 9.09E-03 1.18E-02 1.25E-02 1.76E-02 1.48E-02 Age Group Child Teen Child Child Child Critical Organ Bone Liver Bone Bone Bone Adult Total Body 3.00E-04 3.83E-04 3.98E-04 5.60E-04 1.64E-03 Applicable Limit 1.5 1.5 1.5 1.5 3.0 Percent of Limit % 2.00E-02 2.55E-02 2.66E-02 3.73E-02 5.47E-02 B. AIRBORNE NOBLE GAS DOSES Otr 1 <::itr 2 Otr 3 Qtr4 ANNUAL Gamma Air 2.26E-05 7.75E-06 7.21 E-06 6.15E-06 4.37E-05 Applicable Limit 5 5 5 5 10 Percent of Limit % 4.52E-04 1.55E-04 1.44E-04 1.23E-04 4.37E-04 Beta Air 2.71 E-05 5.89E-06 5.70E-06 4.47E-06 4.32E-05 Applicable Limit 10 10 10 10 20 Percent of Limit 2.71E-04 5.89E-05 5.70E-05 4.47E-05 2.16E-04 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES excluding C-14, for info only)

Qtr 1*

Qtr2 Qtr 3 *** Qtr4 ANNUAL Iodine/Part (mrem 1.56E-04 2.45E-04 3.53E-04 4.11E-04 1.17E-03 Applicable Limit mrem 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 2.08E-03 3.27E-03 4.71E-03 5.48E-03 7.77E-03 Age Group Child Child Child Child Child Critical Organ Liver Liver Liver Liver Liver D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Child TB Dose (mrem) 1.57E-02 1.58E-02 1.59E-02 1.59E-02 6.33E-02 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit %) 2.09E-01 2.10E-01 2.12E-01 2.12E-01 4.22E-01 Qtr 1 *atr2 Qtr 3 Qtr4 ANNUAL Child Bone Dose 7.78E-02 7.78E-02 7.78E-02 7.78E-02 3.11E-01 Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.04E+OO 1.04E+OO 1.04E+OO 1.04E+OO 2.07E+OO

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 45 of 67 Annual Radioactive Effluent Release Report Table 6-3 Unit 3 Appendix I Dose Assessment A LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr*4 ANNUAL Organ Dose (mrem) 7.44E-05 8.37E-05 6.21E-05 5.80E-05 6.07E-04 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 1.49E-03 1.67E-03 1.24E-03 1.16E-03 6.07E-03 Aoe Group Child Adult Adult Adult Adult Critical Organ Bone GI-LU GI-LLI GI-LU GI-LU Adult Total Body (mrem) 2.71E-05 3.54E-05 4.03E-05 5.18E-05 1.55E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 1.81 E-03 2.36E-03 2.69E-03 3.45E-03 5.15E-03 B. AIRBORNE NOBLE GAS DOSES Qtr1 Qtr 2 Qtr 3 Qtr4 ANNUAL Gamma Air (mrad) 3.33E-06 5.46E-06 4.28E-06 4.35E-06 1.74E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 6.66E-05 1.09E-04 8.56E-05 8.70E-05 1.74E-04 Beta Air (mrad) 3.69E-06 6.71E-06 6.69E-06 5.14E-06 2.22E-05 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 3.69E-05 6.71E-05 6.69E-05 5.14E-05 1.11 E-04 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excluding C-14, for info only)

Qtr 1 Qtr 2 . Qtr3 Qtr4 ANNUAL Iodine/Part (mrem) 3.73E-04 7.20E-04 8.34E-04 5.54E-04 2.48E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 4.97E-03 9.60E-03 1.11 E-02 7.39E-03 1.65E-02 Age Group Child Child Child Child Child Critical Organ Lh.er Liver Liver Liver Liver D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Child TB Dose (mrem) 1.58E-02 1.62E-02 1.63E-02 1.60E-02 6.44E-02 Applicable Limit. (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 2.11E-01 2.16E-01 2.17E-01 2.14E-01 4.29E-01 Qtr 1 Qtr 2 Qtr3 Qtr4 ANNUAL Child Bone Dose (mrem) 7.75E-02 7.75E-02 7.75E-02 7.75E-02 3.10E-01 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 1.03E+OO 1.03E+OO 1.03E+OO 1.03E+OO 2.07E+OO

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 46 of 67 Annual Radioactive Effluent Release Report 7.0 METEOROLOGICAL DATA The site meteorological data is maintained on-site and available for review.

Indian Point Units 1, 2 & 3 YEAR: 2018 I Page 47 of 67 Annual Radioactive Effluent Release Report - Carbon-14 Discussion Concentrations and offsite dose from C-14 were determined from sampling at Indian Point #3 from August 1980 to June 1982, during a study conducted by the NY State Department of Health (C.

Kunz, later published and incorporated into NCRP 81). The annual C-14 curies released, as determined from this study, were consistent with NUREG 0017, Rev. 1. Data was then normalized to a maximum expected annual total, based on rated electrical capacity, (approximately 1000 MW(e) maintained for the entire year). Once the curies released were established, dose calculations were performed per the station ODCM, which uses all C-14 released to determine inhalation doses, and 26% of the total (determined to be Carbon Dioxide form), to determine the ingestion doses, in accordance with Regulatory Guide 1.109.

In 2010, IPEC and other facilities combined historical data with the application of an EPRI model designed to estimate C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc.). The estimates from this model, for IPEC, closely match the measured observations of 1982.

The maximum annual C-14 release information is as follows:

Maximum (Bounding) Annual C-14 releases from IPEC Unit2 Un it 3 Liquid Effluent C Released Curies 0.07 0.07 Total Airborne C 14 Released Curies 11.19 11 .05 14 Airborne C as CO2 Curies 2.91 2 ~87 Airborne Effluent Child TB Dose, C 14 mrem 0.0690 0.0 675 14 Airborne Effluent Child Bone Dose, C mrem 0.346 0. 338 Liquid Effluent Child TB Dose, C14 mrem 0.00117 0.0 0116 Liquid Effluent Child Bone Dose, C14 mrem 0.00583 0.0 0577 The bounding values were then normalized with actual effective full power days (EFFD) to yield more accurate year to year annual airborne curies and mrem for each unit. A small liquid effluent component is maintained at IPEC as a result of data accumulated in the 1983 study (Kunz). Tables 3-1 and 3-4 (shown earlier) include the airborne curie data for the current year. Section 6.0 (Radiological Impact on Man) includes the dose information.

C-14 doses are grouped with "Iodine and Particulate" and reported in Section D of Tables 6-2 and 6-

3. Section C of these tables provides doses from this category excluding C-14, to facilitate historical comparisons. However, since C-14 is grouped as a particulate, the total dose for this isotope needs to be added to the doses from iodine, particulate and H-3 doses for comparison to the singular* dose limit for this category. Therefore, Tables 6-2 and 6-3 include dose from all categories of this group (Iodine, Particulate, Tritium, and Carbon-14), fo~ appropriate comparison of the dose limits. C-14 doses (alone) for the current year are provided (for information) in the following table:

Calculated Annual C-14 releases from IPEC, 2018 Unit2 Unit3 14 Airborne Effluent Child TB Dose, C mrem 0.0621 .0619 1----------------+- 14

+-----+---

A ir borne Effluent Child Bone Dose, C mrem 0.311 0.310 The airborne effluent dose from C-14 is distributed evenly over the year and applied to a total Iodine and Particulate dose in Tables 6-1, 6-2 and 6-3.

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 48 of 67 1-------

Annual Radioactive Effluent Release Report Attachment 2 - Groundwater Monitoring Program Results Summary of IPEC Groundwater and Storm Water Activity, 2018 The .precipitation mass balance model applied in previous 'years was applied for offsite dose caJculations in 2018, with some minor calibration updates performed by the contractor with regard to the distribution of groundwater flow through the site. Groundwater elevation readings continued to validate the model throughout the year.

As defined in the ODCM, a conservative method of source term selection is used for determining offsite dose from Groundwater and Storm Water. If a result is below MDC (whether positive or negative) it is not included in the computed average. This computed average is therefore biased high (more conservative from a dose computation perspective) relative to an average computed using all of the data (many of which indicate no activity). In cases where all the sampling locations assigned to a given stream tube provided results below the MDC, then an average activity value of zero was assigned to the effected portion of the stream tube. (This mathematically allows the calculation to proceed in the absence of positive detections).

Historical average precipitation at IPEC has been approximately 3 feet per year. In 2011, precipitation was unusually high (over 6 feet). In 2018, precipitation was measured at 5.99 feet per year (or inches per month, as an average). Doses from Groundwater/Storm water are dependent on two factors: source term and precipitation during the effected year.

Results of 2018 Groundwater and Storm water offsite dose evaluation The results of the assessment are shown below. These dose values are a small portion of the annual limits (<0.1%), and were added to the Total Dose table in the opening summary of the Radiological Impact to Man section of this report (Section 6).

Groundwater (GW) and storm water tritium released from IPEC in 2018 totaled approximately 0.30 curies, resulting in a total body dose of significantly less than 0.1 mrem. It is evident that tritium alone, whether from ground water or routine effluents, does not arithmetically contribute to integrated offsite dose.

Sampling near the effluent points identified only trace levels of Tritium and Strontium-90. These data, as part of the Monitored Natural Attenuation analyses, show a continuation of the decreasing trends established with the termination of the identified Unit 2 SFP leaks (tritium plume) and the defueling and draining of Unit 1 SFPs (strontium plume). Strontium-90, a legacy isotope from Unit 1, contributed approximately 0.000061 curies to site effluent from the groundwater pathway.

Combined GW releases from IPEC in 2018 (all radionuclides) resulted in a calculated annual dose of less than 0.004 % of the annual limits for*whole body and critical organ:

IPEC Groundwater and Storm Water Effluent Dose, 2018 0.0000908 mrem to the total body (0.0030% limit) 0.000367 mrem to the critical organ, adult bone (0.0037% limit)

The annual dose from combined groundwater and storm water pathways remains well below applicable limits. When combined with routine liquid effluents (Section E), the total dose also remains significantly below ALARA limits of 3 mrem total body, and 10 mrem to the critical organ.

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 49 of 67 Annual Radioactive Effluent Release Report IPEC Summary for Storm & Ground Water Releases 2018 Northern Clean Zone Adult Doses, in mrem ISOTPP~ BONE LIVER TOT BODY J:HYROID KlpNEY LUNG Gl'-LLI .. uCi H-3 O.OOE+OO 7.88E-09 7.88E-09 7.88E-09 7.88E-09 7.88E-09 7.88E-09 7.04E+02 Co-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO totals O.OOE+OO 7.88E-09 7.88E-09 7.88E-09 7.88E-09 7.88E-09 7.88E-09 7.0,4E+02 Unit 2 North ISOTOPE *'BONE . Ll'vER * ,TOT BODY :THYROID "* KIDNEY'"' L0NG;** . 'GI-LL( . ,. uCi H-3 O.OOE+OO 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.54E+05 Co-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-J37 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO totals O.OOE+OO 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.54E+05 Unit 1/2 J~OTQPE. J30N~ . :UVEJ~ . TOTBODY. THYRQID Klpt>]FY,* . .* . ;*

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H-3 O.OOE+OO 4.63E-07 4.63E-07 4.63E-07 4.63E-07 4.63E-07 4.63E-07 1.00E+05 Co-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 3.67E-04 O.OOE+OO 8.99E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.06E-05 6.11E+01 Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO totals 3.67E-04 4.63E-07 9.04E-05 4.63E-07 4.63E-07 4.63E-07 1.10E-05 1.00E+05 Unit 3 North BONE' * * *uvER "for BODY l'HYROID KIDNEY

LUNG GI-LU **uc; H-3 O.OOE+OO 2.59E-07 . 2.59E-07 2.59E-07 2.59E-07 2.59E-07 2.59E-07 2.71E+04 Co-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO totals O.OOE+OO 2.59E-07 2.59E-07 2.59E-07 2.59E-07 2.59E-07 2.59E-07 2.71E+04 Unit 3 South

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H-3 O.OOE+OO 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 1.92E+04 Co-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO totals O.OOE+OO 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 4.31E-08 1.92E+04

Indian Point Units 1, 2 & 3 I YEAR: 2018 I Page 50 of 67 Annual Radioactive Effluent Release Report Southern Clean Zone

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H-3 0.00E+OO O.OOE+OO O.OOE+OO O'.OOE:tOO O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO Co-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE:t-00 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE:t-00 O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+.00 O.OOE+OO O.OOE+OO O:OOE:t-00

O.OOE+OO O.OOE+Off O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO totals O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO o:ooE+OO Totals: Adult Doses, in mrem H-3 only O.OOE+OO 8.83E-07 8.83E-07 8.83E-07 8.83E-07 8.83E-07 8.83E-07

. . . ,BON!;.,. *, .'LIVER :, "T:OT;BQQY ,.JHYBQID.. ,. KIONE;Y:" .....*L.IJNG.,:..,. . , .z,Gl.sL~L , : 3.01E+05 H3 all isotopes 3.67E-04 8.83E-07 9.0SE-05 8.83E-07 8.83E-07 8.83E-07 1.14E-05 O.OOE+OO Co O.OOE+OO Ni Adult Doses 6.11E+01 Sr

% Annual Limit 0,00367 I 0. 000 I 0.00303 I 0. 000 j

0.000 I 0'.000 I 0. 000 I 0. OOE+OO Cs O.OOE+OO Sb

Indian Point Units 1, 2 & 3 YEAR: 2018 Page 51 of 67 1----------

Annual Radioactive Effluent Release Report Attachment 3 - Laboratory Analytical Results The following pages list the results of the 2018 groundwater samples. Not that the positive results are shown in bold print.

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1-2 5/8/18 -2.43E+02 3.87E+02 0.55 1.44 -0.3 5.5 8.0 15,9 MH-5VCFD 1/19/18 1.53E+03 4.56E+02 -0.11 1.06 1.1 7.1 -0.5 17.1 MH-5VCFD 1/31/18 2.01E+03 4.98E+02 0.05 1.29 0.8 3.9 -0.l 10.6 MH-5 VCFD 2/13/18 2.SOE+04 1.29E+03 -0.87 1.26 0.7 5.1 4.3 13.8 MH-5VCFD 2/26/18 1.98E+04 1.20E+03 0,16 1.62 4.3 5.7 14.1 14.7 MH-5 VCFD 3/12/18 9.90E+03 MH-5 VCFD 3/27/18 6.00E+OZ 1

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MW-111 9/4/18 2.80E+04 1.50E+03 -0.67 1.27 1.5 5.1 3.8 14.6 MW-111 9/17/18 7.6SE+04 MW-111 10/1/18 1.60E+03 MW-111 10/4/18 3.4SE+03 6.30E+02 0.32 1.53 1.4 5.4 2.0 12.9 MW-111 10/15/18 1.32E+04 MW-111 10/29/18 3.53E+04 l.60E+03 0.10 1.50 -0.2 6.6 -3.2 16.3 MW-111 11/12/18 1.23E+04 l.06E+03 -0.05 0.89 0.3 5.2 7.6 16.2 MW-111 11/26/18 5.80E+03 MW-111 12/10/18 3.90E+03 MW-111 12/17/18 2.54E+04 MW-111 12/27/18 1.59E+04 MW-30-69 1/30/18 4.48E+OS MW-30-69 2/12/18 1.65E+OS MW-30-69 2/26/18 1.0SE+OS MW-30-69 3/12/18 8.56E+04 MW-30-69 3/26/18 8.BOE+04 MW-30-69 4/9/18 9.40E+04 MW-30-69 4/23/18 8.91E+04 MW-30-69 5/8/18 8.31E+04 2.24E+03 0.69 1.13 2.8 5.3 -1.8 17.9 MW-30-69 6/4/18 9.21E+04 MW-30-69 8/16/18 6.76E+04 3.78E+03 0.10 1.39 2.8 6.1 2.3 15.8 MW-30-69 9/10/18 9.77E+04 MW-30-69 11/21/18 1.41E+05 4.35E+03 -0.05 1.35 3.6 6.3 5.4 15.8 MW-30-71 1/15/18 1.44E+05 MW-30-71 12/18/18 1.19E+05 3.33E+03 -0.28 1.31 -0.7 5.3 9.8 12.3 MW-30-84 1/15/18 1.35E+05 MW-30-84 5/8/18 1.31E+OS 3.87E+03 0.17 1.09 0.5 6.4 -2.5 18.4 MW-30-84 8/16/18 1.24E+OS 5.10E+03. 0.42 1.22 -2.9 7.4 5.2 13.0 MW-30-84 9/10/18 1.14E+OS MW-30-84 10/30/18 9.66E+04 2.72E+03 *0.01 1.44 0.6 8.4 -4.2 15.3 MW-30-84 11/21/18 1.04E+OS 3.18E+03 -0.83 1.11 -2.7 5.9 0.4 16.4 MW-31-49 1/8/18 3.21E+04 1.50E+03 0.11 1.37 2.2 4.7 2.3 11.8 MW-31-49 1/15/18 1.72E+04 1.10E+03 0.63 1.56 2.4 4.2 17.1 20.2 MW-31-49 1/30/18 4.7SE+03 6.00E+02 -0.16 1.35 0.0 12.8 9.9 16.0 MW-31-49 2/12/18 7.44E+03 5.07E+02 0.01 1.31 -0.3 4.6 0.3 10.7 MW-31-49 2/26/18 2.17E+03 4.89E+02 -1.02 1.57 1.1 6.5 0.8 13.5 MW-31-49 3/12/18 3.24E+02 3.48E+02 1.50 1.57 0.6 5.0 -3.5 15.0 MW-31-49 3/27/18 3.31E+04 MW-31-49 4/9/18 1.85E+04 MW-31-49 4/23/18 8.00E+02 MW-31-49 5/9/18 3.71E+03 5.67E+02 0.75 1.17 0.9 12.1 7.5 11.8 Page 53 of 67

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MW-67-276 5/14/18 7.SOE+OZ 4.26E+02 0.75 1.37 3.8 5.9 12.3 15.7 -3.5 13.3 MW-67-276 6/5/18 1.10E+03 MW-67-276 8/2/18 8.89E+02 5.19E+02 -0.05 1.19 -3.9 4.9 *3.4 18.5 0.1 14.4 MW-67-276 9/5/18 8.00E+OZ MW-67-276 10/19/18 3.00E+OZ MW-67-276 11/19/18 1.02E+03 4.65E+02 -0.29 *1.50 -1.7 6.1 4.3 22.6 -2.2 15.9 1----1----11----+---11--_.,1----11-----1----111------1---1 MW-67-276 12/20/18 1.00E+03 MW-67-340 1/23/18 1.43E+02 3.09E+02 -0.88 1.48 1.6 4.9 2.7 17.1 *0.2 12.9 MW-67-340 5/14/18 2.42E+02 3.81E+02 0.18 1.01 3.1 7.2 14.5 7.8 11.4 MW-67-340 8/2/18 3.12E+02 4.50E+02 0.73 1.45 0.0 6.6 2.8 13.8 -5.8 18.6 MW-/57-340 11/19/18 7.67E+02 3.51E+02 0.10 1.45 -0.3 4.7 -8.4 12.0 2.4 13.7 MW-67-39 1/23/18 8.46E+03 7.77E+02 6.04 2.30 3.1 5.9 -3.4 19.9 2.4 13.4 MW-67-39 2/13/18 7.70E+03 MW-67-39 5/14/18 7.23E+03 7.14E+02 2.88 2.02 0.7 6.0 -3.5 15.5 1.6 14.8 MW-67-39 6/5/18 8.ZOE+03 MW-67-39 8/2/18 8.05E+03 9.66E+02 5.10 2.08 -0.8 6.8 3.0 17.0 -3.2 15.2 MW-67-39 9/5/18 6.80E+03 MW-67-39 10/19/18 6.70E+03 MW-67-39 11/19/18 6.79E+03 7.38E+02 5.04 2.39 -2.6 5.3 2.7 23.6 1.4 14.4 MW-67-39 12/20/18 7.00E+03 MW-68-103 1/25/18 5.90E+02 3.48E+02 -0.67 1.39 -0.3 5.2 -3.7 14.6 MW-68-103 5/24/18 7.64E+02 3.66E+02 0.27 0.47 2.2 5.4 -2.2 14.1 MW-68-103 8/8/18 5.30E+02 3.96E+02 0.51 0.77 -3.6 7.8 -3.2 15.7 MW-68-103 11/5/18 5.90E+02 4.41E+02 -0.44 1.31 5.3 7.0 0.1 16.3 MW-68-132 1/25/18 4.27E+02 3.48E+02 0.07 1.60 1.0 4.5 -2.0 11.2 MW-68-132 5/24/18 7.25E+02 3.39E+02 0.36 1.11 1.6 5.6 -3.2 13.3 MW-68-132 8/8/18 5.76E+02 3.96E+02 0.74 1.01 -4.4 9.2 0.9 16.5 MW-68-132 11/5/18 6.33E+02 3.96E+02 0.40 1.62 -1.9 7.6 1.8 16.3 Page 66 of 67

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NL-19-039, Annual Radioactive Effluent Release Report

Contents

Text

SUBJECT:

Enclosure:

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

SUMMARY

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NL-19-039, Annual Radioactive Effluent Release Report

Text

SUBJECT:

Enclosure:

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

SUMMARY

Navigation menu

Search