NL-11-068, Indian Point, Units 1, 2 and 3 - 2010 Annual Radioactive Effluent Release Report, Revision 1

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Indian Point, Units 1, 2 and 3 - 2010 Annual Radioactive Effluent Release Report, Revision 1
ML11172A042
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 06/10/2011
From: Robert Walpole
Entergy Nuclear Northeast
To:
Document Control Desk, NRC/FSME
References
NL-11-068
Download: ML11172A042 (52)
v • d • e


Text

SEntergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Licensing Manger NL-1 1-068 June 10, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

2010 Annual Radioactive Effluent Release Report, Revision 1 Indian Point Unit Nos. 1, 2 and 3 Docket Nos. 50-03, 50-247, 50-286 License Nos. DPR-5. DPR-26, DPR-64

REFERENCE:

1. Letter NL-1 1-039, '2010 Annual Radioactive Effluent Release Report', dated 4/22/2011.

Dear Sir or Madam:

The purpose of this letter is to correct an error that was discovered in the Radiological Effluent Release Report: 2010, on page 35 of the 40CFR1 90 Total Dose summary table in Reference 1.For the Groundwater component, percent limit values were erroneously given in place of the mrem dose values. The Groundwater dose section (Section H) is correct; it is only the summary table on page 35 that is being revised by this letter. This error was entered into Entergy Corrective Action Program as CR-IP3-2011-02991.

Enclosure 1 to this letter resubmits the entire Entergy Nuclear Operations, Inc.'s (ENO's) 2010 Radioactive Effluent Release Report. Page 35 of the report has been revised, as shown by revision markers in the right margin.There are no new commitments contained in this letter. If you have any questions or require additional information, please contact me at 914-734-6710.

Sincerely, RW/mb cc: next page NL-1 1-068 Docket Nos. 50-03, 50-247, 50-286 Page 2 of 2

Enclosure:

1. Radioactive Effluent Release Report: 2010.cc: Mr. William Dean, Regional Administrator, NRC Region 1 Mr. John Boska, Senior Project Manager, NRC NRR DORL IPEC NRC Resident Inspector's Office Mr. Stephen Giebel, IPEC NRC Unit 1 Project Manager Mr. Francis J. Murray, President and CEO, NYSERDA (w/o enclosure)

Mr. Paul Eddy, New York State Department of Public Service (w/o enclosure)

Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Mgmt, NYSDEC Mr. Robert Snyder, NYS Department of Health Mr. Chuck Nieder, NYS Department of Environmental Conservation Mr. Jason Martinez, American Nuclear Insurers Chief, Compliance Section, New York State DEC, Division of Water Regional Water Engineer, New York State DEC ENCLOSURE 1 TO NL-11-068 Radioactive Effluent Release Report: 2010 ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT UNIT 1,2, and 3 NUCLEAR POWER PLANTS DOCKET Nos. 50-03, 50-247, and 50-286 Docket No. 50-3, 50-247, & 50-286 Page 1 of 49 Radioactive Effluent Release Report: 2010 Facility Indian Point Enerqy Center (Indian Point Units 1, 2, and 3)Licensee Entergy Nuclear Operations, Inc (Enter qy)This information is provided in accordance with the requirements of Regulatory Guide 1.21. The numbered sections of this report reference corresponding sections of the subject Guide, pages 10 to 12.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 shown separately.

A. Supplemental Information

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 (calculational methodologies) contains the details necessary to perform offsite dose calculations from the sampling and monitoring outlined in the RECS.2. Maximum Permissible Concentration a) Airborne Releases 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.b) 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 Beta activity, as well as the measured gamma 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 new 1 OCFR20.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/mI (without gas or tritium) for routine effluents, and procedural guidance for optimizing decay and treatment of liquid waste.

Docket No. 50-3, 50-247, & 50-286 Page 2 of 49 3. Average Energy The average energies (l) of the radionuclide mixtures in releases of fission and activation gases were as follows: Units 1 and 2: 1st Quarter 1.60E-01 Mev/dis E 7 = 1.20E-01 Mev/dis 2nd Quarter = 2.49E-01 Mev/dis E 7 = 4.49E-01 Mev/dis 3rd Quarter I # = 2.58E-01 Mev/dis E 7= 4.70E-01 Mev/dis 4th Quarter = 3.13E-01 Mev/dis E 7 = 7.15E-01 Mev/dis Unit 3: 1st Quarter I = 4.34E-01 Mev/dis E 7 = 1.17E+00 Mev/dis 2nd Quarter F# = 4.31E-01 Mev/dis E 7 = 1.16E+00 Mev/dis 3rd Quarter F = 3.93E-01 Mev/dis E y = 9.40E-01 Mev/dis 4th Quarter = 4.21E-01 Mev/dis E 7 = 1.10E+00 Mev/dis 4. Measurements and Approximations of Total Radioactivity a) Fission and 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 <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />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 dependant 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.

The continuous building discharges are based on weekly samples of ventilation air analyzed for isotopic content. This information is combined with total air volume discharged and the process radiation monitor readings to determine the quantity of activity from continuous discharges.

Docket No. 50-3, 50-247, & 50-286 Page 3 of 49 b/c) lodines and Particulates Iodine-131 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 typical Minimum Detectable Activity (MDA) for weekly 1-131 analyses is 1.OE-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 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 is used per the station ODCMs. An absence of any positive Gross Alpha value for the quarter is identified on Table 1A as "-". A typical MDA for gross alpha is 8.OE-14 uCi/cc, which is over 100 times lower than ODCM requirements.

d) Carbon-14 C-14 release quantification details are discussed in Section E.e) 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 composite 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 gross alpha is used per the station ODCM. When there has been no positive Gross Alpha identified in a quarter,"-" is entered in Table 2A. A typical MDA value for Gross Alpha in liquids is 5E-8 uCi/mI, which is two times lower than ODCM requirements.

Liquid Effluent volumes of waste released on Table 2A are differentiated between processed fluids (routine liquid waste and Unit l's North Curtain Drain), and water discharged through monitored pathways identified in the ODCM, but NOT processed (SG Blowdown and Unit l'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 Table 2A.

Docket No. 50-3, 50-247, & 50-286 Page 4 of 49 5. Batch Releases Airborne: Unit I and 2 Airbome Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2010 Number of Batch Releases 60 45 54 45 204 Total Time Period (min) 4100 3200 2940 2670 12900 Maximum Time Period (min) 175 330 144 100 330 Average Time Period (mi) 68 71 55 59 63 Minimum Time Period (mn) 5 2 1 5 1 Unit 3 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2010 Number of Batch Releases 41 45 47 42 175 Total Time Period (min) 5780 6470 6200 6320 24800 Maximum Time Period (min) 213 250 236 199 250 Average Time Period (min) 141 144 132 151 142 Minimum Time Period (min) 4 8 7 4 4 Liquid: Unit I and 2 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2010 Number of Batch Releases 36 24 17 5 82 Total Time Period (min) 8530 2980 3320 469 15300 Maximum Time Period (min) 780 382 550 107 780 Average Time Period (min) 237 124 195 94 187 Minimum Time Period (min) 88 90 91 78 78 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2010 Number of Batch Releases 12 8 17 14 51 Total Time Period (min) 1350 874 1870 1540 5620 Maximum Time Period (min) 140 118 117 114 140 Average Time Period (min) 112 109 110 110 110 Minimum Time Period (min) 102 104 98 104 98 Average Stream Flow: Hudson River flow information is obtained from the Department of the Interior, United States Geological Survey (USGS). These data are received after review from the USGS, approximately 18 months after initial data collection.

This information is included in the effluents report as the data becomes available.

Estimated Average Stream Flows of the Hudson River at Indian Point: nl *-rf M~rA I- f.2008 2009 2009 2009 Fourth First Second Third 76,400 72,100 77,700 49,370 Docket No. 50-3, 50-247, & 50-286 Page 5 of 49 6. Abnormal Releases a) Liqu General Groundwater IPEC's groundwater monitoring program and the process (model) for quantification of effluent remained generally unchanged in 2010, from that of 2009 and earlier. The overall approach and formulation of the Precipitation Mass Balance Model remained unchanged.

Additional groundwater elevation data, collected since the initiation of the Long Term Monitoring Program in 2007, was applied to enhance the accuracy of the model through further calibrations to the larger data set. Details of these refinements are included in second quarter 2009 Long Term Monitoring Report, GZA, September 22, 2010.The resulting offsite dose as a result of the station's continuing natural attenuation was very small, similar to 2009's totals. Groundwater doses are included in the total dose table of Section E, the Dose-To-Man section of this report. Details of the IPEC Radiological Groundwater Monitoring Program are provided in Section H of this report, and include the following:

1) an update on the current condition of IPEC's GW natural attenuation, 2) a discussion of the removal of fuel (source term) from Unit 1, and 3) per the ODCM and NEI 07-07, a summary table of all groundwater radio-analyses results in 2010.Storm Drain Contamination Events, January 2010 and April 2010 In January, 2010, a small increase in routine levels of tritium and trace gamma was discovered in a storm drain outside Unit 2's Primary Building, near the interface with the Fuel Storage Building (MH-9). Investigation identified that the contamination had originated in late November 2009, from leaking hoses during an operation involving RWST cleanup to remove silica prior to Unit 2's outage. Silica removal in the RWST is required to improve clarity in the pool, transfer canal, and reactor cavity. The silica is a product of boraflex grid support plates in the unit 2 pool. During the cleanup event, some hose leakage accumulated in a burm under the skid, and was inadvertently released to the local concrete driveway area, some of which entered MH-9. The investigation led to several corrective actions for future improvements, including operation of the skid indoors, where sumps and hoses can be more closely monitored, and where these leaks do not become "spills".

Contamination discovered from this event was evaluated for release impact and found to be arithmetically insignificant with regard to effluent release (< 1 E-6 mrem).In April, Storm Drain A-2 outside Unit 3 Fuel Storage Building (FSB) was identified with increased tritium. After a long investigation, the increase was attributed to a lack of ventilation in the nearby FSB. The building's exhaust fan was moved to Unit 2 to replace a failed fan, leaving no operable exhaust fan for Unit 3. While attempts were made to repair, replace, or build a new fan from parts, a ground-level airborne effluent term was understood to be unavoidable from small openings such as the ventilation inlet plenum on the roof. Airborne effluent was monitored, calculated, and reported, based on measurements of FSB atmosphere (for tritium and other contaminants), pool level, temperature and barometric pressure, etc. These parameters were used to complete a mass balance for the lost tritium.

Docket No. 50-3, 50-247, & 50-286 Page 6 of 49 While the airborne effluent was being monitored and reported, it became evident that in addition to the airborne effluent, the released vapor was condensing (particularly on the FSB roof) and traveling (via a direct pipe roof drain) into a local storm drain a few feet from the south-east corner of the spent fuel building (identified as storm drain A-2). The direct contribution from the FSB roof was verified by collecting a sample directly from the roof drain pipe going into the basin of drain A-2. This drain system continued to indicate elevated H-3 throughout the year, as the FSB ventilation remained out of service.During this interval, tritium and other monitoring occurred at various levels in the FSB, to ensure an accurate representation of potential effluent out the door. All airborne effluent was quantified at ground level. While the tritium leaving the building was determined to be approximately the same as routine operation, the effluent airborne dose calculations indicated increased mrem over this interval, due to the ground level release of this tritium, versus routine releases up the Plant Vent (where the release point is atop the containment building).

Despite exceeding department goals, the effluent airborne dose from this tritium release remained a very small portion of the ODCM limit.An assessment was also performed to determine a bounding offsite dose calculation for the liquid pathway from the storm drain system. The curies and dose from this pathways were insignificant with regard to total site effluent, but for completeness, added to the monthly reports. No attempt was made to subtract the liquid curies as already quantified, as these totals were insignificant with respect to routine releases.Operating Experience was distributed to the industry covering lessons learned from this event and its associated challenges to radiological effluents.

b) Gaseous See the discussion above, regarding the Unit 3 Fuel Storage Building ground level release of tritium, while the exhaust fan remained inoperable.

Docket No. 50-3, 50-247, & 50-286 Page 7 of 49 7. ODCM Reporting Requirements ODCM Part I requires reporting of prolonged outages of effluent monitoring equipment.

Also required in this report is notification of any changes in the land use census, the Radiological Environmental Monitoring Program (REMP), or exceeding the total curie content limitations in outdoor tanks.During this reporting period, the following ODCM required effluent monitoring equipment was out of service (OOS) for periods greater than 30 consecutive days: Effected Instrument Inter Details Interval This instrument failed its routine calibration in October of 2009.Further testing was performed to compare this ODCM-required instrument with a redundant instrument that appeared to be working. Investigation ensued as to why the values were outside desirable tolerances with each other. Parts (not readily available) for the ODCM instrument were deemed necessary and ordered Unit 2 from vendor. After parts arrived, calibration was scheduled after a Plant Vent 01-01-10 00:00 refueling outage. Test procedures were updated to improve the calibration process. Safety conditions related to frozen surfaces Process delayed completion of the calibration.

This instrument was Flow Rate 01-01-11 00:00 returned to service on March, 28, 2011.Indicator Compensatory measurements (estimates of process flow) were SV2-DPT conducted per the ODCM and lower tier procedures.

In addition, a (365 days) redundant, non-ODCM instrument was evaluated as a backup.This instrument's reading compared favorably with manual measurements of vent flow rate to increase confidence.

While compensatory action continued, the backup instrument readings provided additional continuous indication.

The level instrument failed in mid December, 2009, due to a failure Unit 3 of a freeze protection strip heater. The heater strip was replaced, Primary 1-1-10 00:00 but the level instrument then failed its calibration retest. A new Water instrument was pursued with no success and eventually Storage Tank to determined not to be feasible.

Instead, parts were procured, the instrument repaired and successfully calibrated.

It was returned to 01-21-10 12:41 service on Jan 21, 2010. The total duration of the out of service Level time was 33 days, splitting 2009 and 2010.Instrument (32.6 days total)LT-1131 (21.5 in 2010) While out of service, compensatory measures (level estimates) were performed per the ODCM and lower tier procedures whenever water was moved into or out of the tank.Unit 3 Steam The control room lost communication with monitor in the field.Generator 5-14-10 14:37 Continuous work to repair was not possible, due to prioritization Blowdown to established with high work load and limited resources.

Because it Monitor 6-16-10 10:40 could not be worked continuously, multiple teams were used to troubleshoot.

The complexity of the system and lack of continuity R-19 (32.6 days) of repair teams challenged timely resolution, which had been on track for completion several days earlier.

Docket No. 50-3, 50-247, & 50-286 Page 8 of 49 7. ODCM Reporting Requirements (continued)

Instrument Effected Details Interval Unit 3 9-22-10 15:03 This instrument failed it's 2-yr calibration, later determined to be due to Radioactive to after faulty testing equipment.

The instrument was tested on 1-25-11 and Machine Shop 1-01-11 00:00 determined to be functional.

It was then returned to service.Vent Process The instrument was officially listed as OOS during this interval, so all Flow meter (100.4 days) ODCM required compensatory actions were fulfilled.

Unit 3 Plant 11-3-10 08:35 This backup Plant Vent monitor's detector required repair. Due to the Vent Noble to primary instrument (R-27) being in service and unaffected, a high work Gas Monitor 12-14-10 09:36 load, and limited resources, repair and recalibration of R-14 was given secondary prioritization.

No compensatory action was required during R-14 (41.0 days) this interval because the primary instrument remained in service.Unit 1 Stack 12-12-10 00:15 The monitor's memory failed during calibration.

After repair, an Unit afe Sindependent failure occurred with a non-required sub-channel that Vent Noble to after rendered the noble gas channel inoperable.

Prioritization, high work Gas Monitor 1-01-11 00:00 load, limited resources, flooding in the work area, and an on-going ( > 45 days) modification to retire the superfluous (troubling) channel combined to R-60 (20.0 in 45d ) delay repairs, which are expected in April, 2011. Compensatory 0(20.0 in 2010) actions were completed during this interval.A containment isolation valve for one Steam Generator sample Unit 3 Steam line to this monitor was declared inoperable.

Therefore, the Generator 11-8-10 23:25 other valve was shut, securing flow from one SG. Difficulty in Blowdown 1-01-11 00:00 accessing and repairing the valve drove a decision to leave this Monitor line isolated until the upcoming refueling outage, while (>53.0 days) simultaneously investigating options for routing flow to the R-1 9 monitor from other lines. Compensatory sampling was performed from an unaffected line to SG Blowdown Recovery.Other Reporting Criteria: Tank Curie Limits During this reporting period, no tank curie limits in outdoor tanks were exceeded.ODCM and PCP chan-ges: There were no changes to the Process Control Program or ODCM in 2010.

Docket No. 50-3, 50-247, & 50-286 Page 9 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2010 Docket No. 50-3, 50-247, & 50-286 Page 10 of 49 TABLE 1A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES A Fission & Activation Gases Year Qtr2 Qtr3 Qtr4 2010 Est. Total% Error Units Qtr" B Iodines C. Particulates

1. Total Relea Ath Ci -3.59E-06 3.59E-06 +/-25 half-life

> 8 days 2. Average release rate ui/sec -4.52E-07 1.14E-07 3. Gross A pha Ci --0.00E+00 +/-25 D. Trib Lrn 1. Total release Ci 2.83E-400 1.76E+00 7.21E+00 2.52E+00 1.43E+01 +/-25 2. Average release rate uCi/sec 3.63E-01 2.24E-01 9.06E-01 3.17E-01 4.54E-01 E Carbon- 14 1. Total release Ci 2.30E400 2.30E-O0j 2_30E+00 2.30E+00 9.18E+00 2. Average release rate uCi/sec 2.95E-01 2.92E-01 2-89E-01 2.89E-01 2.91E-01 QrlI Qtr 2 Qtr 3 Qtr4 2010-Indicates

< "vY Docket No. 50-3, 50-247, & 50-286 Page 11 of 49 TABLE IC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)Nuclides Released 1) Fission Gases Year Qtr2 Qtr3 Qtr4 2010 Units Qtr I I I I I I I Total for Period Ci 0.00E+00 0.00E+00 0.00E+O0 0.00E+00 0.00E+00 2) lodines 1- 131 Cia -0.00E+00 1-133 Ci ---0.00E+00 1-135 Ci ---0.00E+00 Tota for Period Ci 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.001E+00 3) Particulates JCs-1I37 Ci -3.59E-06 3.59E-06 Total for Period C O.OOE+O0 0.001E+00 O.OOE+00 j59E-06 3.59E-06-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 12 of 49 TABLE IC INDIAN POINT 1 and 2 -BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)Nuclides Released 1) Fission Gases Year 2010 Units Qtrl Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 7.81E-02 1.28E-02 3.84E-02 2.14E-02 1.51E-01 Kr-85 Ci -0.OOE+00 Kr-85m Ci 1.32E-03 1.55E-06 5.83E-04 -1.90E-03 Kr-87 Ci 6.78E-04 1.21E-06 4.69E-04 -1.15E-03 Kr-88 Ci 1.57E-03 2.81 E-06 1.07E-03 -2.64E-03 Xe-131m Ci 3.86E-03 1.10E-03 14AOE-04 2.99E-04 5.40E-03 Xe-133 Ci 1.35E+00 2.43E-02 729E-02 1.78E-02 1.47E+00 Xe-133m Ci 1.61E-02 3.06E-06 4.15E-05 1.62E-02 Xe-135 Ci 5.03E-02 2.06E-03 8.58E-03 2.19E-05 6.1OE-02 Xe-135m Ci 3.37E-03 2.62E-06 1.09E-03 -4.47E-03 Xe-1 38 Ci 4.49E-04 8.41 E-07 2.75E-04 7.24E-04 tal for Period Ci 1.51E+00 I 4.04E-02 I 124E-01I 3.96E-021 1.71E+00 2) lodines Not Applicable for Batch Releases 3) Particulates Not Applicable for Batch Releases-Indicates<

MDA Docket No. 50-3, 50-247, & 50-286 Page 13 of 49 TABLE 1A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES A Fission & ,Adivation Gases uni Year Qtr2 Qtr3 Qtr4 2010 Est. Total% Error Qra-1 I P -F -P I P -U -1 1. Total Release I Ci 4.65E-02 5.42E-02 6.03E-02 4.98E-02 I 2.11E-01 2. Average release rate uCi/sec 5.98E-03 6.90E-03 7.59E-03 6.27E-03 B Iodines C. Particdates

1. Total Release, with Ci 0.00E+00 +/-25 half-life>

8da~s 2. Average release rate ui/sec -0.00E+00 3. GrossAPpha Ci --0.00E+-00

+/- 25 D. Trin urn 1. Total release Ci 4.81 E400 4.37E)00 5.19E+00 3.65E+00 1.80E+01 + 25 2. Average release rate uC/sec 6.19E-01 5.56E-01 6.53E-01 4.59E-01 5.71E-01 E Carbon-14 QbrI Qtr'2 Qtr3 Qtr4 2010-Indlicates

< K/1A Docket No. 50-3, 50-247, & 50-286 Page 14 of 49 TABLE IC INDIAN POINT 3 -CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)Nuclides Released 1) Fission Gases Year 2010 U nits Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci --- 0.00E+00 Xe-1 33 Ci ---0.00E+00 Xe-1 35 Ci O.OOE+00 Tal for Period Ci 0.00E+00 0.00E+00 0.OOE+00 0.OOE+0O 0.OOE+00_________________I

~ .OOE00 1 .OOE000.00E+I00

2) lodines 1-131 Ci --O.OOE+00 1-133 Ci ---0.OOE+00 1-135 Ci ---0.OOE+00 alfor Period Ci ---0.OOE+00 3) Particulates Total for Period Ci I I I I000E+00-indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 15 of 49 TABLE IC INDIAN POINT 3 -BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)Nuclides Released 1) Fission Gases Year 2010 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 423E-02 4.88E-02 4.40E-02 446E-02 1.80E-01 Kr-85 Ci -9.70E-03 9.70E-03 Kr-85m Ci -0.00E+00 Kr-87 Ci -- 0.00E+00 Kr-88 Ci -- 0.OOE+00 Xe-131 m Ci -- 0.OOE+00 Xe-133 Ci 4.26E-03 5.41E-03 6.68E-03 524E-03 2.16E-02 Xe-1 33m Ci -0.OOE+00 Xe-135 Ci 5.29E-07 2.62E-06 3.15E-06 Xe-135m Ci 0.OOE+00I tal for Period Ci 4.65E-02 5.42E-02 6.03E-02 4.98E-02 2.1 1E-01 2) lodines Not Applicable for Batch Releases 3) Particulates Not Applicable for Batch Releases-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 16 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2010 Docket No. 50-3, 50-247, & 50-286 Page 17 of 49 TABLE 2A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES A. Fission & Activation Products 1. Total Release (not induding Tritium, Gr Alpha, & Gases)2 Average Diluted Conc Year Est. Total Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2010 % Error Ci 2.81E-Q2 1.60E-02 9.64E-03 2.41E-03 5.62E-02 +/-25 uCi/ml 5.99E-11 2.30E-11 1.13E-11 3.48E-12 2-07E-11-4-B. Tritium 1. Total Release Ci 4.40E+02 8.19E+01 1.36E+02 7.44E+01 7.32E+02 +/-25 2- Average Diluted Conc uCi/ml 9.37E-07 1.18E-07 1.59E-07 1.07E-07 270E-07 C. Dissolved

& Entrained Gases D. Gross Alpha 11. Tote[Reease I l -I 100 + 1+/-25 E. Volume of Waste Released 1. Processed Waste (LW & NCD) liters 4.03E+06 2.39E406 1.67E+06 1.87E+06 9.96E+06 +/-10 2. Urprcoessed (SGBD, SFDS, U1FD) liters 3.92E+07 4.81 E+07 3.93E+-07 3.97E+07 1.66E+08 +/- 10 IF. Volume of Dilution Water [liters 4.69E+11 6.96E+11 8.55E+11 6.93E+11 2.71E+12 +107-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 18 of 49 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)CONTINUOUS RADIOACTIVE EFFLUENT Nuclides Released Year Qtr 3 Qtr 4 2010 U nits Qtr I Qtr 2 Cs-137 Ci 2.08E-03 1.49E-03 1.25E-03 1.14E-03 5.96E-03 Ni-63 Ci 0- 0.OE+00 Sr-89 Ci -0.00E+00 Sr-90 Ci 5.40E-04 2.47E-04 8.77E-05 5.09E-05 9.25E-04 Total for Period Ci 2.62E-03 1.73E-03 1.34E-03 1.19E-03 6.89E-03 Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 19 of 49 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan Dec 2010)BATCH RADIOACTIVE EFFLUENT Nuclides Released Year 2010 U nits Qtr I Qtr 2 Qtr 3 Qtr 4 Co-57 Ci 1.46E-05 1.46E-05 Co-58 Ci 4.16E-03 5.37E-03 4.22E-04 5.33E-05 1.00E-02 Co-60 Ci 6.00E-03 3.50E-04 1.17E-05 1.35E-04 6.49E-03 Cr-51 Ci 2.64E-04 2.64E-04 Cs-137 Ci 2.84E-05 5.64E-06 1.88E-05 7.95E-06 6.08E-05 Ni-63 Ci 5.67E-03 1.03E-03 5.31E-04 1.85E-04 7.42E-03 Sb-124 Ci 5.73E-05 5.73E-05 Sb-125 Ci 6.80E-03 7.20E-03 7.32E-03 8.35E-04 2.22E-02 Te-125m Ci 2.82E-03 2.82 E-03 Toal for Period Ci 2.55E-02 1.43E-02 8.30E-03 1.22E-03 I~~jl ~iJ 2.5E-02_4.__3EI-I2 Dissolved

& Entrained Gas IKr-85 Ci -0.OOE+00 Xe-133 Ci 3.64E-04 -3.64E-04 Total for Period Ci 3.64E-04 0.OOE+00 O.OOE+00 0.OOE+00 3.64E-04-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 20 of 49 TABLE 2A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES A. Fission & Aclivation Products 1. Total Release (not including Tritium, Gr Alpha, &Gases)2. Average Diluted Conc Units Ci uCVml Year Qtrl Qtr 2 Qtr3 Qtr-4 2010 2.42E-03 2.08E-03 4.14E-03 1.92E-03 1.06E-02 5.15E-12 2.99E-12 4.84E-12 2.77E-12 3.89E-12 Est. Total% Error B. Tritium 1. Total Release 2. Average Diluted Conc Ci 9.57E+00 j8.43E+01 8.70E+01 4.77E+02 6.58E+02_

+/-25 uCi/mlI 2.04E-08 1.21 E-07 1.02E-07 6.89E-07 2.42E-07 C. Dissolved

& Entrained Gases 1. Total Release Ci 3.59E-06 1.06E-05 2.24E-05 1.85E-04 2.21E-04 +/- 25 2. AverageDiluted Conc uCi/ml 7.64E-15 1.52E-14 2.62E-14 2.66E-13 8.15E-14 D. Gross Alpha I1. Total Release -C I 0o.00E+00

+/-+25 E. Volume of Waste Released 1. Processed Fluids (Mon Tanks) liters 3.06E+05 2.08E405 4.37E+05 3.59E+05 1.31E+06 +/-10 2. Unprocessed Fluids (SGs) liters 2.02E+06 1.62E+06 2.32E+06 7.61E+06 1.36E+07 +/- 10 F. Volume of Dilution Water liters 4.69E11 6.96E+1 1 8.55E+1 1 6.93E+1 1 2.71E+12 +/- 10'- indicates<

MDA Docket No. 50-3, 50-247, & 50-286 Page 21 of 49 TABLE 2B INDIAN POINT 3 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2010)BATCH and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT Batch Fission/Activa on Prod uds Urits Qtr I Qtr2 Qtr3 Qtr 4 2010 Ag-110m a -3.49E-06 --3.49E-06 Co-58 a 1.42E-04 1.23E-04 5.69E-06 3.15E-05 3.03E-04 Co-60 a 3.48E-04 2.18E-04 1.38E-04 1.90E-04 8.94E-04 Cs- 134 a 9.64E-05 1.17E-05 1.59E-06 2-02E-05 1.30E-04 Cs- 137 a 4.92E-04 1.24E-04 8.77E-05 248E-04 9.52E-04 N-63 a 1.09E-03 1.34E-03 3.83E-03 1.25E-03 7.50E-03 Sb-124 Ci -206E-06 2.06E-06 Sb-125 a 248E-04 2.631E-04 8.21 E-05 1.83E-04 7.75E-04 Total for Perod Ca 2-42E-03 2.08E-03 4.14E-03 1.92E-03 1.06E-02 Dissolved and Ertrained Gas (Batch)Xe-133 a 3.59E-06 1.06E-05 224E-05 1.85E-04 221E-04 Total for Perod a 3.59E-06 1.06E-05 2.24E-05 1.85E-04 221E-04 Continuous Releases (SG Blwalow)I H-3 (only) I a 4.77E-03 I5.25E-03 I6.04E-03 I8.7WE-03 I2.48E-02'- indcates < mda Docket No. 50-3, 50-247, & 50-286 Page 22 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2010 Docket No. 50-3, 50-247, & 50-286 Page 23 of 49 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2010 to 12/31/2010 Percent Cutoff: 0 (all identified isotopes are included)Waste Stream : Resins, Filters, and Evap Bottoms Cartidge Filters LWS Resin Plant Resin 8-120 Waste Volume Curies % Error (Ci)Class ft 3 m 3 S hipped A 3.25E+02 9.20E+00 2.93E+00 +/-25%B 0.00E+00 0.OOE+00 0.OOE+00 +/-25%C 9.20E+ 01 2.61E+00 2.94E+02 +1-25%All 4.17E+02 1 .18E+01 2.97E+02 +/- 25%Waste Stream Dry Active Waste DAW /Dirt B-25 Box DAW 20' Sea Land Waste Volume Curies % Error (Ci)Class ft 3 m 3 Shipped A 9.02E+03 2.55E+02 2.89E-01 +/-25%B 0.00E+00 0.00 E+00 0.OOE+00 +/-25%C 0.00E+00 0.00E+00 0.00E+00 +/-25%All 9.02 E+03 2.55E+02 2.89 E-01 +/-25%W aste Stream

  • Irradiated Components Waste Volume Curies % Error (Ci)Class ft 3 m 3 Shipped A 0.00 E+00 0.OOE+00 0.OOE+00 +/-25%B 0.00E+00 0.00E+00 0.OOE+00 +/-25%C 0.00E+00 0.OOE+00 0.OOE+00 +/-25%All 0.00 E+00 0.OOE+00 0.OOE+00 +/-25%Waste Stream: Other Waste Combined Packages Waste Volume Curies % Error (Ci)Class ft 3 m3 S hipped A 6.80E+02 1.93 E+01 1.18E+00 +/-25%B 0.00 E+00 0.OOE+00 0.OOE+00 +/-25%C 0.00E+00 0.OOE+00 0.OOE+00 +/-25%All 6.80 E+02 1.93E+01 1.18E+00 +/-25%Waste Stream : Sum of AI14 Categories Combined Packages DAW /Dirt B-25 Box PlantResin 8-120 LWS Resin DAW 20' Sea Land Waste Volume Curies % Error (Ci)Class ft 3 m 3 S hipped A 1.OOE+04 2.84E+02 4.40E+00 +/-25%B 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%C 9.20E+01 2.61 E+00 2.94E+02 +/-25%All 1.01 E+04 2.86E+02 2.99E+02 +/-25%Combined Waste Type Shipment, Major Volume Waste Type Shown Docket No. 50-3, 50-247, & 50-286 Page 24 of 49 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Number of Shipments 1 5 1 1 1 Mode of Transportation Clean Harbors Hittman Transport Hittman Transport R & R Trucking Inc Hittman Transport Destination Energy Solutions

-Bear Creek Energy Solutions

-Bear Creek Energy Solutions

-GRF Studsvik Processing

-Memphis Studsvik Processing Facility Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period 01/01/2010 to Waste Class All Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Zr-95 Nb-95 Ag- 110m Sb-125 Cs-1 34 Cs-1 37 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Other Waste Waste Class A Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Zr-95 Nb-95 12/31/2010 Percent Abundance 0.571%0.129%0.526%35.658%10.317%28.318%14.679%0.113%1.226%1.959%0.260%0.654%0.848%3.912%0.367%0.015%0.004%0.419%0.005%0.001%0.020%Percent Abundance 0.580%0.131%0.524%35.907%9.716%28.726%14.870%0.114%1.141%1.707%Percent Cutoff: 0 Curies 1.65E-03 3.73E-04 1.52E-03 1.03E-01 2.98E-02 8.18E-02 4.24E-02 3.26E-04 3.54E-03 5.66E-03 7.50E-04 1.89E-03 2.45E-03 1.13E-02 1.06E-03 4.19E-05 1.19E-05 1.21 E-03 1.49E-05 2.51 E-06 5.73E-05 Curies 6.86E-03 1.55E-03 6.20E-03 4.25E-01 1.15E-01 3.40E-01 1.76E-01 1.35E-03 1.35E-02 2.02E-02 Ag-11 Oin Sb-125 Cs-134 Cs-1 37 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 0.258%0.660%0.853%3.979%0.366%0.015%0.004%0.425%0.005%0.001%0.020%Docket No. 50-3, 50-247, & 50-286 Page 25 of 49 3.05E-03 7.81 E-03 1.01E-02 4.71 E-02 4.33E-03 1.75E-04 4.97E-05 5.03E-03 6.21 E-05 1.01E-05 2.38E-04 Other Waste Waste Class All Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Zr-95 Nb-95 Ag-110m Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.580%0.131%0.524%35.907%9.716%28.726%14.870%0.114%1.141%1.707%0.258%0.660%0.853%3.979%0.366%0.015%0.004%0.425%0.005%0.001%0.020%Curies 6.86E-03 1.55E-03 6.20E-03 4.25E-01 1.15E-01 3.40E-01 1.76E-01 1.35E-03 1.35E-02 2.02E-02 3.05E-03 7.81 E-03 1.01E-02 4.71 E-02 4.33E-03 1.75E-04 4.97E-05 5.03E-03 6.21 E-05 1.01E-05 2.38E-04 Curies 9.76E-03 1.93E-03 1.99E-02 1.04E+00 3.59E-03 5.81E-01 6.02E-01 8.88E-01 3.24E-03 1.71 E-02 2.59E-02 3.80E-03 2.26E-03 Sum of All 4 Categories Waste Class A Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Zr-95 Nb-95 Ag-110m Sb-124 Percent Abundance 0.221%0.044%0.451%23.582%0.081%13.174%13.651%20.136%0.073%0.388%0.587%0.086%0.051%

Sb-1 25 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 1.730%4.104%21.360%0.122%0.005%0.001%0.141%0.002%0.000%0.007%Docket No. 50-3, 50-247, & 50-286 Page 26 of 49 7.63E-02 1.81 E-01 9.42E-01 5.39E-03 2.16E-04 6.17E-05 6.24E-03 7.70E-05 1.26E-05 2.96E-04 Sum of All 4 Categories Waste Class C Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-60 Ni-63 Sr-89 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Sum of All 4 Categories Waste Class All Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-89 Sr-90 Zr-95 Nb-95 Ag-110m Sb-124 Sb-125 Cs-134 Cs-137 Percent Abundance 0.043%0.041%1.021%0.044%8.648%60.262%0.010%0.238%0.848%6.367%22.266%0.145%0.003%0.001%0.063%0.000%0.000%0.001%Percent Abundance 0.046%0.001%0.047%1.351%0.044%0.195%8.719%59.690%0.010%0.235%0.006%0.009%0.001%0.001%0.862%6.338%22.233%Curies 1.27E-01 1.19E-01 3.OOE+00 1.28E-01 2.54E+01 1.77E+02 3.06E-02 6.99E-01 2.49E+00 1.87E+01 6.54E+0 1 4.25E-01 7.60E-03 1.59E-03 1.84E-01 1.02E-03 2.92E-04 4.07E-03 Curies 1.37E-01 1.93E-03 1.39E-01 4.03E+00 1.31E-01 5.81E-01 2.60E+01 1.78E+02 3.06E-02 7.02E-01 1.71E-02 2.59E-02 3.80E-03 2.26E-03 2.57E+00 1.89E+01 6.63E+01 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 0.144%0.003%0.001%0.064%0.000%0.000%0.001%Docket No. 50-3, 50-247, & 50-286 Page 27 of 49 4.30E-01 7.82E-03 1.65E-03 1.90E-01 1.09E-03 3.05E-04 4.36E-03 Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Sb-124 Sb-125 Cs-1 34 Cs-137 Resins, Filters, and Evap Bottoms Waste Class C Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-60 Ni-63 Sr-89 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.043%0.416%17.380%0.122%14.858%6.134%22.798%0.053%0.077%2.270%5.725%30.125%Percent Abundance 0.043%0.041%1.021%0.044%8.648%60.262%0.010%0.238%0.848%6.367%22.266%0.145%0.003%0.001%0.063%0.000%0.000%0.001%Curies 1.25E-03 1.22E-02 5.10E-01 3.59E-03 4.36E-01 1.80E-01 6.69E-01 1.56E-03 2.26E-03 6.66E-02 1.68E-01 8.84E-01 Curies 1.27E-01 1.19E-01 3.OOE+00 1.28E-01 2.54E+01 1.77E+02 3.06E-02 6.99E-01 2.49E+00 1.87E+01 6.54E+01 4.25E-01 7.60E-03 1.59E-03 1.84E-01 1.02E-03 2.92E-04 4.07E-03 Docket No. 50-3, 50-247, & 50-286 Page 28 of 49 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-89 Sr-90 Sb-124 Sb-125 Cs-1 34 Cs-1 37 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.044%0.045%1.186%0.044%0.147%8.619%59.827%0.010%0.237%0.001%0.865%6.354%22.410%0.144%0.003%0.001%0.062%0.000%0.000%0.001%Curies 1.29E-01 1.32E-01 3.51 E+00 1.31E-01 4.36E-01 2.55E+01 1.77E+02 3.06E-02 7.OOE-01 2.26E-03 2.56E+00 1.88E+01 6.63E+01 4.25E-01 7.60E-03 1.59E-03 1.84E-01 1.02E-03 2.92E-04.4.07E-03 Dry Active Waste Waste Class A Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Zr-95 Nb-95 Ag-110m Sb-125 Cs-134 Cs-137 Ce-1 44 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.571%0.129%0.526%35.658%10.317%28.318%14.679%0.113%1.226%1.959%0.260%0.654%0.848%3.912%0.367%0.015%0.004%0.419%0.005%0.001%0.020%Curies 1.65E-03 3.73E-04 1.52E-03 1.03E-01 2.98E-02 8.18E-02 4.24E-02 3.26E-04 3.54E-03 5.66E-03 7.50E-04 1.89E-03 2.45E-03 1.13E-02 1.06E-03 4.19E-05 1.19E-05 1.21E-03 1.49E-05 2.51 E-06 5.73E-05 Docket No. 50-3, 50-247, & 50-286 Page 29 of 49 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2010 to 12/31/2010 Percent Cutoff: 0 (all identified isotopes are included)Waste Stream : Resins, Filters, and Evap Bottoms Waste Volume Curies % Error (Ci)Class ft 3 m 3 S hipped A 0.00E+00 0.OOE+00 -0.00E+00 +/-25%B 0.OOE+00 0.OOE+00 0.OOE+00 +1- 25%C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%All 0.OOE+00 0.00E+00 0.OOE+00 +/- 25%W aste Stream : Dry Active Waste U3 DAW B-25 Unit 3 DAW-20' Sealand 20' Intermodal Soil Waste Volume Curies % Error (Ci)Class ft 3 m 3 Shipped A 1.38E+04 3.92E+02 9.10E-02 +/-25%B 0.00E+00 0.OOE+00 0.OOE+00 +/-25%C 0.00E+00 0.00E+00 0.OOE+00 +/-25%All 1.38E+04 3.92E+02 9.10E-02 +/-25%Waste Stream " Irradiated Coom ponents Waste Volume Curies % Error (Ci)Class ft 3 m 3 S hipped A 0.00E+00 0.00 E+00 0.OOE+00 +/-25%B 0.00E+00 0.00E+O0 O.OOE+00 +/-25%C 0.00E+00 0.00E+00 0.OOE+00 +/-25%All 0.00E+00 0.OOE+00 0.OOE+00 +/-25%Waste Stream

  • Other Waste Combined Packages Waste Volume Curies % Error (Ci)Class ft 3 m 3 Shipped A 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%B 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%All 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%W aste Stream : Sum of All 4 Categories Unit3 DAW B-25 20' Intermodal Soil DAW 20' Shielded SeaLand Waste Volume Curies % Error (Ci)Class ft 3 m 3 S hipped A 1.38E+04 3.92E+02 9.10E-02 +/-25%B 0.00E+00 0.OOE+00 0.OOE+00 +/-25%C 0.00E+00 0.00E+00 0.OOE+00 +/-25%All 1.38 E+ 04 3.92 E+02 9.10E -02 +/-25%Combined Waste Type Shipment, Major Volume Waste Type Shown Docket No. 50-3, 50-247, & 50-286 Page 30 of 49 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Number of Shipments 1 1 22 Mode of Transportation TO State Motor Transit Hittman Transport R & R Trucking Inc Destination Energy Solutions Bear Creek Studsvik Processing

-Memphis Studsvik Processing

-Memphis Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period 01/01/2010 to 12/31/2010 Percent 0 Cutoff: Dry Active Waste Waste Class A Nuclide Name H-3 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Cs-1 34 Cs-137 Dry Active Waste Waste Class All Nuclide Name H-3 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Cs-1 34 Cs-1 37 Sum of All 4 Categories Waste Class A Nuclide Name H-3 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Percent Abundance 0.363%0.267%22.193%0.026%18.787%13.843%0.012%0.123%44.386%Percent Abundance 0.363%0.267%22.193%0.026%18.787%13.843%0.012%0.123%44.386%Percent Abundance 0.363%0.267%22.193%0.026%18.787%13.843%0.012%0.123%44.386%Curies 3.30E-04 2.43E-04 2.02E-02 2.39E-05 1.71E-02 1.26E-02 1.09E-05 1.12E-04 4.04E-02 Curies 3.30E-04 2.43E-04 2.02E-02 2.39E-05 1.71E-02 1.26E-02 1.09E-05 1.12E-04 4.04E-02 Curies 3.30E-04 2.43E-04 2.02E-02 2.39E-05 1.71 E-02 1.26E-02 1.09E-05 1.12E-04 4.04E-02 Docket No. 50-3, 50-247, & 50-286 Page 31 of 49 Sum of All 4 Categories Waste Class All Nuclide Name H-3 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Cs-1 34 Cs-1 37 Percent Abundance 0.363%0.267%22.193%0.026%18.787%13.843%0.012%0.123%44.386%Curies 3.30E-04 2.43E-04 2.02E-02 2.39E-05 1.71 E-02 1.26E-02 1.09E-05 1.12E-04 4.04E-02 Docket No. 50-3, 50-247, & 50-286 Page 32 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2010 -Dec 31, 2010 Docket No. 50-3, 50-247, & 50-286 Page 33 of 49 RADIOLOGICAL IMPACT ON MAN Routine Effluent Dose Calculations:

The Radiological Impact on Man due to radioactive effluent from the site is determined from NRC approved modeling, per Reg 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 information and management.

Site airborne effluent dose calculations include annual average dispersion and deposition factors, averaged from data collected over approximate 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 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 NUREG 0133. Details of the calculations, site-specific data, and their bases are presented in the ODCM.Carbon-14 (C-14): 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). Dose calculations were performed on the fraction of C-14 determined to be in the Carbon Dioxide form (26%), as no dose to man is expected from other forms (methane, etc). Reg Guide 1.109 methodology was applied to determine the offsite maximum dose, per the ODCM. For a single unit, the following data was reported fromi1984-2004, based on the measurements at IP#3 (Kunz, 1983): N 0.07 curies released in liquid form E 9.6 curies per year total C-14 released in airborne form (normalized to 100% power)0 26% of the airborne C-14 was C0 2 , or 2.5 curies per unit affecting offsite dose Liquid Dose, Airborne Dose, Child mrem Child mrem IP3 Critical Organ (Bone) Dose 5.83E-3 2.54E-1 IP3 Total Body Dose 1.17E-3 5.08E-2 In 2004, Indian Point was consolidated as Indian Point Energy Center (IPEC), Units 1, 2, & 3.The operating units (2 and 3) are very similar, so C-14 values reported at Unit 3 were doubled for the corrected site totals in reports through 2009. However, after June 2009, an effort was initiated within the industry to better characterize and report C-14 airborne effluent.

Docket No. 50-3, 50-247, & 50-286 Page 34 of 49 In 2010, IPEC and other facilities participated in an EPRI task force to build a model to accurately estimate C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc). This work was completed in November 2010. The estimates from this model, for IPEC, closely match the measured observations of 1982 (the new model results in an increase in estimated curies by approximately 8%). For purposes of industry standardization, this report uses the output from the EPRI model. The maximum C-14 curies and dose for a year's operation are shown below: Maximum (Bounding)

Annual C-14 releases from IPEC Unit 2 Unit 3 Liquid Effluent C 1 4 Released Curies 0.07 0.07 Total Airborne C14 Released Curies 11.19 11.05 Airborne C1 4 as CO 2 Curies 2.91 2.87 Airborne Eff Child TB Dose, C 1 4 Airborne Eff Child Bone Dose, C14 Liquid Eff Child TB Dose, C14 Liquid Eff Child Bone Dose, C 1 4 mrem 0.0690 0.0675 mrem 0.346 0.338 mrem 0.00117 0.00116 mrem 0.00583 0.00577 These bounding values are then normalized with actual effective full power days (EFFD) to yield annual curies and mrem for each unit, for each reporting year. Tables 1A (shown earlier) include the curie data. Doses are shown in the Radiological Impact on Man section, following this discussion.

In each case, calculated annual totals were simply divided by four to estimate the quarterly contribution.

Future reports may refine this methodology as we continue to evaluate improvements in C-14 measurement and reporting.

C-14 doses are grouped with "Iodine and Particulate" and reported in Table D in the following Radiological Impact on Man tables, for each unit. Table "C" provides doses from this category excluding C-14, for information and comparison purposes only. Table "D" includes dose from all categories of this group (Iodine, Particulate, Tritium, and Carbon-14).

Members of the Public: Members of the public visiting the site receive minimal dose as a result of airborne and liquid 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 <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> (the number of hours in a year, used in calculations in the ODCM).example 1: Several students visit the site for an 8-hour guided tour.Their occupancy factor is: 8 / 8760 or .0009.example 2: A man drives his wife to work and drops her off at the security gate each morning, with a total stay-time on site for 2 minutes per day. His occupancy factor is calculated as follows: 2 min/60 min per hour =.0333 hr; 0.0333 / 8760 = 3.8E-6 These factors, when multiplied by doses calculated per the ODCM, demonstrate that dose to MEMBERS OF THE PUBLIC within the site boundary is negligible, despite a potential reduction in the atmospheric dispersion.

Docket No. 50-3, 50-247, & 50-286 Page 35 of 49 Groundwater:

Curies and dose contribution from activity discovered in onsite ground water and storm drain pathways during the year are discussed in detail in Section H. The offsite dose calculation involves multiple source term measurements, as well as determinations for release and dilution flow. A summary of the quantification methodology, and the resulting calculated doses, is provided at the end of Section H. The Total Dose table below provides a means to compare ground water doses with those of other components making up the site's total dose.Total Dose: 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 for 2010: Whole Body Max Organ 40 CFR 190 limit ===- IPEC 25 mrem 75 mrem Routine Airborne Effluents 1 Units 1 and 2 0.00276 0.00276 Routine Liquid Effluents Units 1 and 2 0.000518 0.00109 Liquid Releases of C 1 4 Units 1 and 2 0.00117 0.00583 Airborne Releases of C 1 4 Units 1 and 2 0.0566 0.284 Routine Airborne Effluents 1 Unit 3 0.00508 0.00508 Routine Liquid Effluents Unit 3 0.000170 0.000973 Liquid Releases of C 1 4 Unit 3 0.00117 0.00583 Airborne Releases of C14 Unit 3 0.0665 0.333 Ground Water & Storm Drain Totals IPEC 2 0.000173 0.000706 Direct Shine from areas such as dry cask storage, radwaste storage, SG IPEC 3 0.061 0.061 Mausoleum, etc.Indian Point Energy Center 0.195 0.700 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 beta 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 are provided in Section H.Note 3: 40CFR1 90 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 this evaluation are available on site from Radiation Protection.

Docket No. 50-3, 50-247, & 50-286 Page 36 of 49 INDIAN POINT UNITS 1 and 2 NUCLEAR POWER PLANTS RADIOLOGICAL IMPACT ON MAN JANUARY -DECEMBER 2010 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Qtr 3 Qtr 4 ANNUAL Qir 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 7.41E-04 1.86E-04 8.87E-05 7.62E-05 1.09E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (M) 1.48E-02 3.72E-03 1.77E-03 1.52E-03 1.09E-02 Age Group Child Child Child Child Child Critical Organ Bone Bone Bone Bone Bone I Adult Total Body (mrem) 3.16E-04 8.88E-05 5.90E-05 5.38E-05 [5.E-Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 2.11E-02 5.92E-03 3.93E-03 3.59E-03 1.73E-02 B. AIRBORNE NOBLE GAS DOSES Q_ _ I Qj" 2 Qtr 3 Qtr 4 ANNUAL GammaAir (mrad) 6.72E-05 5.71E-06 1.83E-05 8.66E-06 9.99E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 1.34E-03 1.14E-04 3.66E-04 1.73E-04 9.99E-04 Beta Air (mrad) 1.30E-04 5.21E-06 1.65E-05 6.29E-06 1.58E-04 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 1.30E-03 5.21E-05 1.65E-04 6.29E-05 7.90E-04 C. AIRBORNE IODINE, PARTICULATE, &TRITIUM DOSES (excluding C-14, for info only)IQt I Qt 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 4.74E-04 4.32E-04 1.21 E-03 4.81E-04 2.60E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 6.32E-03 5.76E-03 1.61 E-02 6.41 E-03 1.73E-02 Age Group -AChild Child Child Child Child Critical Organ Liver Liver Liver Liver Liver D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Total Body Dose (mrem) 1.42E-02 1.42E-02 1.42E-02 1.42E-02 5.66E-02 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 1.89E-01 1.89E-01 1.89E-01 1.89E-01 3.77E-01 Qt- 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Child Bone Dose (mrem) 7.1OE-02 7.10E-02 7.10E-02 7.10E-02 2.84E-O1 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percentof Lmit (%) 9.47E-01 9.47E-01 9.47E-01 9.47E-01 1.89E+00 Docket No. 50-3, 50-247, & 50-286 Page 37 of 49 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY -DECEMBER 2010 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES-S ---.-.Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 1.06E-04 6.35E-05 1.39E-04 1.01E-04 9.73E-04 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 2.12E-03 1.27E-03 2.78E-03 2.02E-03 9.73E-03 Age Group Child Child Child Adult Child Cnrical Organ I Bone Bone Bone Uver Bone AdultTotal Body (mrem) 3.40E-05 2.11E-05 1.84E-05 9.61E-05 1.70E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Limit (%) 2.27E-03 1.41 E-03 1.23E-03 6.41 E-03 5.65E-03 B. AIRBORNE NOBLE GAS DOSES Qtr I Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 1.20E-05 1.39E-05 1.26E-05 1.27E-05 5.12E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 2.40E-04 2.78E-04 2.52E-04 2.54E-04 5.12E-04 Beta Air (mrad) 2.03E-05 2.35E-05 2.41E-05 2.15E-05 8.94E-05 Applicable Limit (mrad) 10 10 10 10 20 Percentof Limit (%) 2.03E-04 2.35E-04 2.41E-04 2.15E-04 4.47E-04 C. AIRBORNE IODINE, PARTICULATE, & TRITIUM DOSES (excluding C-14, for info only)Qtr I Qtr 2 Qtr3 Qtr 4 ANNUAL Iodine/Part (mrem) 7.95E-04 1.18E-03 1.64E-03 1.37E-03 4.99E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 1.06E-02 1.57E-02 2.19E-02 1.83E-02 3.32E-02 Age Group Child Child Child 7hild Child Crilical Organ I Liver Liver Liver Liver Liver D. AIRBORNE IODINE, PARTICULATE, TRITIUM, and CARBON-14 DOSES Total Body Dose (mrem) 1.69E-02 1.69E-02 1.69E-02 1.69E-02 6.75E-02 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percentof Limit (%) 2.25E-01 2.25E-01 2.25E-01 2.25E-01 4.50E-01 Q_" 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL I Child Bone Dose (mrem) 8.45E-02 8.45E-02 8.45E-02 8.45E-02 3.38E-01 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 1.13E+00 1.13E+00I 1.13E+00 1.13E100 2.25E+00 Docket No. 50-3, 50-247, & 50-286 Page 38 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2010 -Dec 31, 2010 This data is stored onsite and is available in printed or electronic form.

Docket No. 50-3, 50-247, & 50-286 Page 39 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT G. OFFSITE DOSE CALCULATION MANUAL, REMP SAMPLING LOCATIONS, PROCESS CONTROL PROGRAM, OR LAND USE CENSUS LOCATION CHANGES 2010 There were no changes to the ODCM, REMP, or PCP in 2010.There were no changes to the Land Use Census in year 2010.

Docket No. 50-3, 50-247, & 50-286 Page 40 of 49 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT H. GROUNDWATER and STORM WATER REPORT ACTIVITY ON SITE and OFFSITE DOSE CALCULATION FOR THE PERIOD: Jan 1, 2010 -Dec 31, 2010 Docket No. 50-3, 50-247, & 50-286 Page 41 of 49 Summary of IPEC Groundwater and Storm Water Activity, 2010 The Unit 1 Spent Fuel, which had been considered the source of most of the groundwater contamination, was removed in 2008, to integrated spent fuel storage. This process demanded pool levels to be increased in April, 2008, for the defueling operation.

During this evolution, the pool water was continuously demineralized and carefully monitored.

After defueling, the pools were further processed with additional cleanup. For dewatering, two sets of composite samplers were installed, and the slow, permitted release was carefully integrated.

Resin-specific cleanup systems were added during the pump down to the routine liquid effluent release line. The empty pools were then cleaned, closed, and covered.As a result of aggressive processing before, during, and after the defueling operation, the effluent release from draining the pools (Sep, 2008) resulted in curies and mrem consistent with or slightly lower than routine monthly effluent.

Stontium-90 releases, in particular, were essentially non-existent, because the pool water had been cleaned up for months prior draining.Because the pool levels had to be increased for a time in 2008 (as mentioned above), some increases in groundwater contamination were expected through 2009. Wells near the Unit 1 pools did in fact start to show somewhat elevated activity in 2009, but by the end of the year, a clear downward trend was visible. Monitored Natural Attenuation continues to be evident through 2010 as curie and dose values continue to decline.The precipitation mass balance model applied in 2007 through 2009 was applied for offsite dose calculations in 2010, 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. The USGS, as well as IPEC local MET data verified annual precipitation averaging approximately 3 feet per year.Results of 2010 Groundwater and Storm water offsite dose evaluation The results of the assessment are shown on the following table. These dose values are again a small portion of the annual limits (<0.01%), and were added to the Total Dose table in the opening summary of the Dose to Man section of this report (Section E).Based on the above analysis, the total GW and storm water Tritium released from IPEC was approximately 0.12 Curies in 2010, resulting in a total body dose of significantly less than 0.1 mrem (1.9E-7 mrem). It is evident that tritium alone, whether from ground water or routine effluents, does not arithmetically contribute to integrated offsite dose.While trace levels of Co-60, Cs-137, and Ni-63 were identified in a few upstream wells in 2010, sampling near the effluent points identified only trace levels of Tritium and Strontium-90 during the year, indicating continued reduction through natural attenuation.

Sr-90, a legacy isotope from Unit 1, contributed approximately 0.000042 curies to site effluent from the groundwater pathway. Combined groundwater releases from IPEC in 2010 (all radionuclides) resulted in a calculated annual dose of less than 0.01% of the annual limits for whole body and critical organ: IPEC Groundwater and Storm Water Effluent Dose, 2010 0.000173 mrem to the total body, (0.00578%

limit)0.000706 mrem to the critical organ, adult bone (0.00706%

limit)The annual dose from combined groundwater and storm water pathways remains well below applicable limits. When combined with routine liquid effluents, the total dose also remains significantly below ALARA limits of 3 mrem total body, and 10 mrem to the critical organ.I Docket No. 50-3, 50-247, & 50-286 Page 42 of 49 IPEC Summary for Storm & Ground Water releases (H-3, Co-60, Ni-63, Sr-90, and Cs-137)Northern Clean Zone Adult Doses~in mrem--r-TOT PLODY I tUI I i LUNG 1 GI-LLI-I. --9-H-3 0.O0E+00 4.08E-09 4.08E-09 4.08E-09 4.08E-09 4.08E-09 I 4.08E-09 Co-60 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 OOOE+00 O.OOE+00 OOOE+00 Ni-63 0.0OE+00 0001E+00 0.00E+00 O.00E000 O.O0E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.O0E+00 0 00E+00 0.OOE+00 0+00E+00 0.OOE+00 0OOE+00 Cs-137 0.00OE+00 .OOE+00 0.00E+00 j OOE+00 j 0OE+00 OOOE+00 0.OOE+00 totals 0.00E+00 4.08E-09 4.08E-09 4.08E-09 4.08E-09 4.08E-09 4.08E-09 Unit 2 North H-3 O.OOE+00 1.66E-08 1.66E-08 1.66E-08 1.66E-08 1,66E-08 1.66E-08 Co-60 0.00E+00 000E+00 0OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ni-63 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.O0E+00 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 Cs-i37 o0ooE+00 o .OOE+00 o 0.OE+00 0.O0E+00 0.OOE+00 0 OOE+00 0.00E+00 totals 0.00E+00 1.66E-08 1166E-08 1.66E-08 1,66E-08 1.66E-08 1.66E-08 Unit 1/2 H-3 C0OOE+00 6,62E-08 682E-08 6.62E-08 6.62E-08 6.62E-08 6.62E-08 Co-60 0.00E+00 0.00E+00 O0E+O0 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+0 0.OOE+00 0.OOE+00 Sr-90 4.16E-04 0.00E+00 1.02E-04 0.OOE+00 0.00E+0O 0.00E+00 1.20E-05 Cs-137 0.OOE+00 0.O0E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 totals 4.16E-04 6.62E-08 1.02E-04 6.62E-08 6.62E-08 6.62E-08 1.21E-05 Unit 3 North H-3 0.00E+00 3.11E-08 3.11E-08 3.11E-08 43.11E-08 3.11E-08 3.11E-08 Co-60 0.OOE+00 0.00E+00 O ,00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Ni-63 0.002+00 0.00E+00 0,OOE+00 .0.0EE00 i0.0E+00 0.00E+00 O0E+00 Sr-90 0.11E-04 0.00+E00 2.72E-05 0.00E+00 0.00E+00 0.00E+00 3.19E-06 Cs-137 0.OOE+00 Q09E+00 0,00E+00 0O0E+00 0 .O0E+00 0.00E+00 OOOE+00 totals 1.11E-04 3.11E-08 2.72E-05 3.11E-08 3.11E-08 3.11E-08 .322E-06 Unit 3 South H-3 0(O+ 2,38E-08 2.38E-08 2.38E-08 2.38E-08 2138E-06 2.78=E-8 Co-60 O.00E+00 0.0E+00 0-00E+00 O.00E+00 0.0E+O0 0,00E+O0 0.00E+00 Ni-63 0.00E+00 0.00E+00 0,00E+00 0.OOE+00 OM0E+00 0.0E÷00 0.OOEF00 St-90 I 79E-04 0,00E÷00 4.40E-05 O.OOE+00 0.00E+00 0.0E+00 5.16E-06 Cs-137 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 , .00E+00 0.00E+00 0.001E+00 totals 1.79E-04 2.38E-08 I 4.40E-05 2138E-08 2.38E-08 138E-081&

9E0 Southern Clean Zone I H-3 I0.00E+00 4 468E-0U8 I 4.68E-08 I4.68E-08 I4.68E-08 4.68E-08 4.68E-08 Co-60 0,00E+00 0.00E+00 0.OE00EO 0.00E+00 I .00E+00 0.00E+00 0.0OE+00 Ni-63 0,00E+00 0.00E+00 0.0E+00 0.00E+00 OV,0E+00 0.00E+00 O.00E+00 Sr-90 0.00E+00 0.00E+00 0.0E+00 0.00E+00 IO.00E+00 O.00E+00 0.OOE+00 Cs-137 0.0E+00 O.DGE+O0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 totals 0 .00E+00 4.68E-08 I 4,6E-08 I4.68E-08 1 4.68E-08 4,68E-08 14.68E-087 2010 year 1064E+02 0.00E+00 0. 00E+00 0.00+00 70.00E+00 Totals: Adult Doses, in mrem H-3 only 0.00E+00 1.89E-07 1,89E-07 1.89E-07 1.89E-07 1,89E-07 1.89E-07 BONE LNI TOTBOD THYOID KIDNY I LUNG Gt-L1 1. 18E+05 M3 all isotopes 7.06E.04 1.89E-07 1.73E-04 1.89E-07 1.89E-07 1.89E-07 2.05E-05 0.00E+00 Co_._,,,,,,.

_ IAdillt Doses I413E+01 sr%kmwaIt ndt 0,.O@7U 0.000 0-05111 0,000 0.000 0.000 0 00 0.OE+0 CS I Docket No. 50-3, 50-247, & 50-286 Page 43 of 49 INDIAN POINT RADIOLOGICAL GROUNDWATER MONITORING PROGRAM 2010 Summary of Results The following pages represent a summary of isotopic radio-analytical data for all onsite groundwater testing performed at Indian Point in 2010, as required per the ODCM and NEI 07-07.Tritium and Strontium were the only isotopes identified in Groundwater in 2010.

Docket No. 50-3, 50-247, & 50-286 Page 44 of 49 Tritium Summary page 1 of 3# Samples in 2010# Positive Samples in 2010 Ave Pos Act Min Pos Act Max Pos Act Well Name B-1 B-6 1-2 MH-5 MW-11 MVV-30-69 MW-30-84 MW-31-49 MW-31-63 MW-31 -85 MW-32-149 MW-32-173 MW-32-1 90 MW-32-48 MW-32-59 MW-32-85 MW-33 MW-35 MW-36-24 MW-36-41 MW-36-52 MW-37-22 MW-37-32 MW-37-40 MW-37-57 MW-39-1 02 MW-39-124 MW-39-195 MW-39-67 MW-39-84 MW-40-100 MW-40-27 MW-40-46 MW-40-8I1 MW-41-40 MW-41 -63 MW-42-49 MW-42-78 MW-43-28 MW-43-62 MW-44-1 02 MW-44-66 MW-45-42 MW-45-61 MW-46 4.67E+03 3.78E+02 1.74E+02 2.11 E+03 3.82E+04 1.33E+05 9.01 E+03 2.83E+04 4.77E+04 7.93E+03 4.53E+03 1.89E+03 1.69E+03 2.91 E+04 7.02E+04 1.20E+04 2.57E+04 2.82E+03 1.77E+03 1.26E+04 7.15E+03 5.69E+03 5.93E+03 5.87E+03 6.07E+03 3.31 E+02 3.41 E+02 2.16E+02 3.46E+02 2.82E+02 1.39E+02 2.0oE+02 1 .74E+02 2 .20E+02 1.65E+03 4.27E+02 1.31 E+03 4.99E+02 2.11 E+02 2.16E-+-02 4.32E+02 3.49E+02 3.08E+03 1.23E+03 1.74E+03 8.15E+02 3.78E+02 1.74E+02 2.08E+02 2.63E+04 1.11 E+05 6.60E+03 4.46E+02 1.84E+04 2.69E+03 1.55Et+03 1.33E+03 1 .53E+03 3.69E+03 5.78E+03 8.03E+03 3.69E+03 2.82E+03 2.64E+02 9.56E+03 5.97E+03 3.70E+03 4.80E+03 4.70E+03 5.07E+03 2.39E+02 3.08E+02 2.16E+02 2.86E+02 2.25E+02 1.39E+02 1.93E+02 1.24E+02 1 .92E+02 4.32E+02 2.48E+02 9.79E+02 3.57E+02 1.95E+02 2.16E+02 2.76E+02 1.75E+02 2.02E+03 9.89E+02 7.62E+02 1.40E+04 3.78E+02 1.74E+02 9.96E+03 4.69E+-04 1.61 E+05 1.02E+04 1.04E+05 7.35E+04 2.25E+04 9.76E+03 2.47E+03 1.98E+03 6.18E+04 1.55E+05 1.49E+04 6.31 E+04 2.82E+03 3.53E+03 1.56E+04 8.49E+03 9.06E+03 7.24E+03 7.OOE+03 7.30E+03 3.93E+02 3.73E+02 2.16E+02 3.79E+02 3.70E+02 1.39E+02 2.06E+02 2.35E+02 2.48E+02 2.79E+03 5.18E+02 1.69E+03 6.31 E+02 2.25E+02 2.16E+02 5.12E+02 4.75E+02 3.86E+03 1.51 E+03 3.13E+03 Docket No. 50-3, 50-247, & 50-286 Page 45 of 49 page 2 of 3 Tritium Summary MW-49-26 MW-49-42 MW-49-65 MW-50-42 MW-50-66 MW-51-40 MW-51-79 MW-52-1 1 MW-52-162 MW-52-18 MW-52-181 MW-53-120 MW-53-82 MW-54-123 MW-54-144 MW 173 MW 190 MW-54-37 MW-54-58 MW-55-24 MW-55-35 MW-55-54 MW-56-53 MW-56-83 MW-57-1 1 MW-57-20 MW-57-45 MW-58-26 MW-58-65 MW-60-135 MW-60-154 MiW 176 MW-60-35 MW-60-53 MW-60-72 MW-62-138 MW-62-118 MW-62-182 MW-62-37 MW-62-53 MW-62 -71 MW-62-92 MW-63-1 12 MW-63-1 21 aw-63-1 63 MW-63-1 74 MW-63-1 8 MW-63-34 MW-63-50 2.86E+03 2.41 E+03 1.42E+03 6.90E+02 3.21 E+03 1.59E+02 1 .10E+02 3.73E+02 2.60 E+02 3.01 E+02 2.18E+02 4.12E+03 4.17E+03 8.42E+02 1.325+03 1.67E+03 1.70E+03 1.29E+03 9.01 E+02 1.61 E+03 91.99E+03 9.495+03 3.61 E+02 2.34E+03 3.27E+03 8.07E+02 8.79E+02 4.71 E+02 4.205+02 2.90E+02 3.94E+02 9.07E+02 2.53E+02 2.845+02 3.01 t+02 5.89E+02 2.46E+02 4.25E+02 2.81 E+02 2.59E+02 3.94E+02 4.81 5+02 3.75E+02 5.45E+02 4.95E+02 4.OOE+02 2.53E+02 3.04E+02 3.37E+02 2.59E+03 2.20E+03 1.32E+03 1.61 E+02 2.76E+03 1.48E+02 1.10E+02 3.73E+02 2.60E+02 3.01 E+02 2.18E+02 3.81 E+03 2.25E+03 7.83t+02 1 .20E+03 1.51 E+03 1 .575+03 1.18E+03 7.67E+02 1.21 5i+03 1.57E+03 8.23E+03 2.58E+02 1.93E+03 3.27E+03 8.07 E+02 8.79E+02 3.66E+02 3.595+02 1.87E+02 2.93E+02 8.1 3E+02 2.35E+02 2.49E+02 3.01 E+02 3.31 E+02 2 .04E+02 2.78E+02 1.91 E+02 1.59E+02 3.25E+02 3.18 5+02 3.01 E+02 5.15E+02 4.13E+02 2.63E+02 1.62E+02 1.89E+02 2.72 E+02 3.03E+03 2.76E+03 1.55E+03 1.36E+03 3.72E+03 1.70E+02 1 .1OE+02 3.73E+02 2.605+02 3.01 E+02 2.18E+02 4.66E+03 7.1 4E+03 9.16E+02 1.44E+03 2.03E+03 1.93E+03 1.45E+03 1.11 E+03 2.21 E+03 2.49E+03 1.13E+04 4.64E+02 2.74E+03 3.27E+03 8.07E+02 8.79E+02 5.75E+02 4.81 E+02 4.18E+02 4.68E+02 9.93E+02 2.85E+02 3.45E+02 3.01 5+02 7.81 E+02 2.87E+02 4.77E+02 3.93E+02 3.46E+02 4.56E+02 5.96E+02 4.47E+02 6.06E+02 5.94E+02 5.05E+02 3.38E+02 3.96E+02 4.13E+02 Docket No. 50-3, 50-247, & 50-286 Page 46 of 49 page 3 of 3 Tritium Summary MW63-93 MW-66-21 MW-66-36 MW-67-105 MW-67-1 73 MW-67-219 MW-67-276 MW-67-323 MW-67-340 MW-67-39 UI-CSS U3-4D U3-4S U3-T1 U3-T2 4 4 4 4 4 4 4 4 4 4 2 4 2 4 4 2.57E+02 1.44E+03 2.70E+03 1.38E+03 7.11E+02 1.14E+03 1.04E+03 4.34E+02 5.68E+02 3.20E+03 2.07E+03 8.33E+02 3.63E+02 4.16E+02 1.07E+03 1.95E+02 3.22E+02 9.60E+02 1.14E+03 6.25E+02 1.09E+03 9.33E+02 3.88E+02 4.86E+02 2.55E+03 1.88E+03 6.84E+02 3.51 E+02 3.04E+02 8.76E+02 3.03E+02 3.43E+03 3.64E+03 1.59E+03 8.70E+02 1.20E+03 1.11 E+03 4.71 E+02 6.57E+02 3.56E+03 2.26E+03 1.07E+03 3.74E+02 5.OOE+02 1.47E+03 Note 1: Note 2: Note 3: All results are in pCi/L A total of 465 samples were analyzed for H-3 in 2010 with 403 positive results. See the AREOR for additional data.A sample is positive if the result is greater than or equal to 3 times the 1 sigma uncertainty.

The target MDC is 200 pCi/L.I Docket No. 50-3, 50-247, & 50-286 Page 47 of 49 Cobalt-60 Summary# Samples in 2010# Positive Samples in 2010 Ave Pos Min Pos Max Pos Act Act Act Well Name MW-39-84 MW-39-195 3 3 1 7.47E+00 7.47E+00 7.47E+00 1 8.70E+00 8.70E+00 8.70E+00 Note 1: Note 2: Note 3: All results are in pCi/L A total of 465 samples were analyzed for Co-60 in 2010 with 2 positive results. See the AREOR for additional data.A sample is positive if the result is greater than or equal to 3 times the 1 sigma uncertainty.

The target MDC is 15 pCi/L.Nickel-63 Summary# Samples in 2010# PO Sam 24 Well Name MW-42-49 MVV-60-53 MVV-66-21 isitive pies in Ave Pos 010 Act 4 3.37E+02 1 1.10E+01 1 9.56E+00 4 4 4 Min Pos Act 1.77E+02 1.10E+01 9.56E+00 Max Pos Act 7.1OE+02 1 .1OE+01 9.56EE+00-I Note 1: Note 2: Note 3: All results are in pCi/L A total of 135 samples were analyzed for Ni-63 in 2010 with 6 positive results. See the AREOR for additional data.A sample is positive if the result is greater than or equal to 3 times the 1 sigma uncertainty.

The target MDC is 30 pCi/L.Cesium-137 Summary# Samples in 2010# Positive Samples in 2010 Well Name B-1 MW-1Ill MW-32-59 MW-42-49 MW-49-65 MW-55-24 MW-63-18 MW-66-21 MW-66-36 4 5 8 4 4 4 4 4 4 3 1 1 4 1 1 1 1 1 Ave Pos Act 1.71 E+01 6.79E+00 4.95 E+00 3.29E+04 6.99E+00 4.99E+00 5.09E+00 6.04E+00 5.42E+00 Min Pos Act 9.79E+00 6.79E+00 4.95E+00 1.87E+04 6.99E+00 4.99E+00 5.09E+00 6.04E+00 5.42E+00 Max Pos Act 2.27E+-01 6.79E+00 4.95E+00 6.52E+04 6.99E+00 4.99E+00 5.09E+00 6.04E+00 5.42E+00-1 Note 1: All results are in pCi/L Note 2: A total of 465 samples were analyzed for Cs-1 37 in 2010 with 14 positive results. See the AREOR for additional data.Note 3: A sample is positive if the result is greater than or equal to 3 times the 1 sigma uncertainty.

The target MDC is 18 pCi/L.

Docket No. 50-3, 50-247, & 50-286 Page 48 of 49 Strontium-90 Summary page 1 of 2# Positive# Samples in 2010 Samples in 2010 Ave Pos Act Min Pos Act Max Pos Act Well Name MW-111 MW-30-69 MVV-36-41 MW-36-52 MW-37-22 MW-37-32 MW-37-40 MW-37-57 MW-39-102 MW-39-1 24 MW-39-67 MW-39-84 MW-41-40 MW-41-63 MW-42-49 MW-45-42 MW-46 MW-49-26 MW-49-42 MW-49-65 MW-50-42 MW-50-66 MWV53-1 20 MW-53-82 MW-54-1 23 MW-54-144 MW-54-173 MW-54-190 MW-54-37 MW-54-58 MW-55-24 MW-55-35 MW-55-54 MW-56-53 MW-56-83 MW-57-11 MW-57-20 MW-57-45 MW-62-138 MW-62-1 8 MW-62-182 MW-62-37 MW-66-21 MW-66-36 MW-67-1 05 1.45E+00 9.69E-01 3.99E+00 4.07E+00 1.10E+01 1.77E+01 1.42E+01 1.84E+01 2.73E+00 1.71 E+00 1.65E+00 1.30E+00 3.64E+00 3.68E+00 4.50E+01 6.43E-01 8.57E-01 1.40E+01 1.86E+01 1.31 E+01 5.52E+00 2.62E+01 3.305+01 1.52EE+00 4.07E+00 1.27E+01 6.10E+00 2.02E+01 4 .60E+00 1.71 E+00 1 .49E+01 2.13E+01 1.96E+01 1.27E+00 1.51 E+O0 2.46E+01 1.125.+-00 1.30E+00 1.21 E+00 6.60E-01 1.025+00 7.62 E-01 4.10E+00 5.44E+00 1.93E+00 1.07E+00 9.69E-01 1.88E+00 2.1 2E+00 5.19E+00 1.41 E+01 1.25E+01 1.73E+01 1.40E+00 1.17E+00 1.26E+00 8.43E-01 2.09E+00 2.01 E+O0 1.39E+01 6.43E-01 8.57E-01 1.28E+01 1.75E+01 1.04E+01 3.73E+00 2.33E+01 2.965+01 8.07E-01 2.25E+00 1.08E+01 4.65E+00 1.57E+01 4.OOE+00 1.36E+00 8.64E+00 1.13E+01 1.67E+01 1.27E+00 1.02E+00 2.46E+01 1.1252t+00 1.30E+00 8.78E-01 6.60E-01 I1.02E+00 7.62E-01 1.17E+00 8.97E-01 1.41 E+00 1.80E+00 9.69E-01 5.95E+00 5.36E+00 1.38E+01 2.03E+01 1.71 E+01 1.97E+01 4.05E+00 2.25E+00 1.96E+00 1.80E+00 4.37E+00 4.79E+00 1.24E+02 6.43E-01 8.57E-01 1.55E+01 1.99E+01 1.55E+01 8.43E+00 2.99E+01 3.94E+01 2.23E+00 7.65E+00 1.44E+01 7.51 E+00 2.35E+01 5.17E+00 2.67E+00 2.06E+01 3.1OE+01 2.32E+01 1.27E+00 1.99E+00 2.46E+01 1.12 E+00 1.30E+00 1.47E+00 6.60E-01 1.02E+00 7.62E-01 7.03E+00 7.43E+00 2.61 E+00 Docket No. 50-3, 50-247, & 50-286 Page 49 of 49 Strontium-90 Summary MW-67-323 MW-67-39 U1-CSS U3-T2 Note 1: Note 2: Note 3: 4 4 2 4 1 6.38E-01 4 9.03E+00 2 1.04E+01 1 6.31 E-01 6.38E-01 5.43E+00 8.95E+00 6.31 E-01 page 2 of 2 6.38E-01 1.24E+01 1.18E+01 6.31 E-01 All results are in pCi/L A total of 465 samples were analyzed for Sr-90 in 2010 with 140 positive results. See the AREOR for additional data.A sample is positive if the result is greater than or equal to 3 times the 1 sigma uncertainty.

The target MDC is 1 pCi/L.

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