NL-10-045, 2009 Annual Radioactive Effluent Release Report

2009 Annual Radioactive Effluent Release Report

ML101240989
Person / Time
Site:	Indian Point
Issue date:	04/29/2010
From:	Robert Walpole Entergy Nuclear Operations
To:	Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
NL-10-045
Download: ML101240989 (151)

Text

Indian Point Energy Center 450 Broadway, GSB SEntergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Licensing Manager NL-10-045 April 29, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

2009 Annual Radioactive Effluent Release Report Docket No. 50-03, 50-247, 50-286 License Nos. DPR-5, DPR-26, DPR-64

Dear Sir or Madam:

Enclosure 1 to this letter provides Entergy Nuclear Operations, Inc.'s (ENO's) Annual Effluent and Waste Disposal Report for 2009. This report is submitted in accordance with Technical Specification 5.6.3 and Regulatory Guide 1.21.

There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact my office at (914) 734-6710.

Sincerely, RW/dmt

Enclosures:

1. 2009 Annual Radioactive Effluent Release Report

2. 2009 Offsite Dose Calculation Manual Changes and Justification Package q

IU

NL-10-045 Page 2 of 2 cc: Mr. John P. Boska, NRC NRR Senior Project Manager Mr. Samuel J. Collins, Regional Administrator, NRC Region I IPEC NRC Senior Resident Inspectors Office Mr. Ted Smith, NRC Unit 1 Project Manager Mr. Francis J. Murray, President and CEO, NYSERDA (w/o attachment)

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

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. Robert Oliveira, American Nuclear Insurers Chief, Compliance Section, New York State DEC, Division of Water Regional Water Engineer, New York State DEC

ENCLOSURE 1 TO NL-10-045 2009 Annual Radioactive Effluent Release Report ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 1, 2, AND 3 DOCKET NOS. 50-03, 50-247, AND 50-286 LICENSE NO. DPR-5, DPR-26, AND DPR-64

Docket No. 50-3, 50-247, & 50-286 Page 1 of 49 Radioactive Effluent Release Report: 2009 Facility Indian Point Energy Center (Indian Point Units 1. 2, and 3)

Licensee Enter-gy Nuclear Operations, Inc (Entergy)

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 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 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 (P-) of the radionuclide mixtures in releases of fission and activation gases were as follows:

Units 1 and 2:

1st Quarter I = 3.05E-01 Mev/dis Ey = 6.28E-01 Mev/dis 2nd Quarter IE= 3.20E-01 Mev/dis Ey = 7.25E-01 Mev/dis 3rd Quarter = 1 1.74E-01 Mev/dis Ey = 1.34E-01 Mev/dis 4th Quarter I = 1 1.50E-01 Mev/dis Ey = 9.71 E-02 Mev/dis Unit 3:

1st Quarter I* 2.04E-01 Mev/dis y= 1.43E-01 Mev/dis 2nd Quarter I = 3.33E-01 Mev/dis y= 7.34E-01 Mev/dis 3rd Quarter F = 4.36E-01 Mev/dis E Y= 1.18E+00 Mev/dis 4th Quarter I*= 4.38E-01 Mev/dis Ey = 1.19E+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) Liquid Effluents A sample of each batch discharge is taken and an isotopic analysis is performed in compliance with requirements specified in the RECS. Proportional composite samples of continuous discharges are taken and analyzed in compliance with the applicable RECS table, 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/ml, 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 and included in total curie and dose summaries in the following tables, along with all other liquid effluent, continuous or batch, processed or not.

However, to prevent confusion with regard to measures. undertaken to convert liquid to solid waste (resin cleanup), the volumes of processed and unprocessed 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 Airborne Releases Qtr I  : Qtr 2 Qtr 3 Qtr 4 - 2009 Number of Batch Releases 43 49 62 64 218 Total Time Period (min) 3280 3470 4340 .4750 15800 Maximum Time Period (min) 125 236 173 175 236 Average Time Period (min) 76.3 70.9 70.0 74.2 72.7 Minimum Time Period (min) 4.00 27.0 10.0 2.00 2.00 Unit 3 Airborne Releases Qtrl . Qtr 2. Qtr 3- Qtr 4'-", 2009.

Number of Batch Releases 21 35 35 40 131 Total Time Period (min) 2520 3450 5100 6120 17200 Maximum Time Period (min) 419 174 233 216 419 Average Time Period (min) 120 98.5 146 153 131 Minimum Time Period (min) 3.00 4.00 9.00 4.00 3.00 Liquid:

Unit I and 2 Liquid Releases Qtr 1 Qtr 2 Qtr 3, Qtr 4 2009, Number of Batch Releases 5 4 11 11 31 Total Time Period (min) 535 408 1120 1090 3160 Maximum Time Period (min) 133 107 114 106 133 Average Time Period (min) 107 102 102 99.2 102 Minimum Time Period (min) 87.0 95.0 92.0 93.0 87.0 Unit 3 Liquid Releases Qtr l Qtr 2 Qtr 3 Qtr4 2009 Number of Batch Releases 38 33 23 7 101 Total Time Period (min) 4780 3900 2500 782 12000 Maximum Time Period (min) 256 272 118 117 272 Average Time Period (min) 126 118 109 112 118 Minimum Time Period (min) 106 77.0 92.0 103 77.0 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:

Year Quarter Flow (cfs) 2007 Fourth 53,970 2008 First 135,500 2008 Second 74,600 2008 Third 33,110

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 unchanged in 2009, from that of 2008. The resulting offsite dose as a result of the station's continuing natural attenuation was very small, similar to 2008'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 2009.

Unit 1 Foundation Drain (80-10)

A new 80-10 release path was added to the IPEC sampling regime in 2008, and continued through 2009. Contributors to this drain line are primarily roof and footing drains near Unit 1, but since it showed occasional trace levels of Cs-137, a project was initiated to determine the source and minimize flow. The trace contaminants were determined to originate in the South Curtain Drain around Unit 1, seeping into footing drains, and into this pathway (rather than diverting to the North Curtain Drain).

Activities underway (through the corrective action program) include efforts to minimize inputs to the line, and improve flow rate determination methods. During dry periods, the line has been evaluated to transport less than 2 gpm to the canal. An inspection cover has been installed in an area to observe flow, and efforts continue with regard to flow measurement methodologies in various atmospheric conditions.

Currently, only trace Cs-137 and H-3 have been identified in the system. Although this activity is included in monthly and annual effluent quantification, the integrated totals remain well below 80-10 or effluent threshold limits.

Storm Drain Contamination Event, March 2009 A small increase in routine levels of tritium was discovered in a storm drain well upstream of the Unit 3 effluent point, in March 2009. Investigation led to the most likely source being an episodic local spill of a small amount of primary water directly into the drain. An in-depth investigation and conclusions were captured in the corrective action program, including comparison and interface with the NEI 07-07 groundwater protection program. No contamination was observed downstream of the effected drain, with no measurable effluent impact. Nonetheless, the calculated micro-curies and offsite dose due to this tritium potentially being released to the canal were included in the monthly effluent report. The totals remain mathematically insignificant with regard to site totals, and less than one ten-millionth of effluent limits.

b) Gaseous None.

Docket No. 50-3, 50-247, & 50-286 Page 6 of 49

7. ODCM Reporting Requirements The ODCM (RECS) 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 IntedvalDetails

.Interval ' * .

09-18-09 Instrument failed regularly scheduled test. Parts were 15:51 determined necessary. After arrival on site, itwas determined Unit 2 liquid that these parts were not precisely "like and kind". After waste effluent to investigation and procurement of correct parts, the instrument flow rate meter, 12-16-09 was successfully tested and placed back in service.

CT-971 09:45 During this interval, flow rate measurement was estimated per (88.7 days) ODCM and lower tier requirements using level instruments.

Instrument failed its routine calibration. 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.

10-08-09 16:30 Parts for the ODCM instrument were deemed necessary and ordered from vendor. Parts were not readily available. After Unit 2 Plant Vent to parts arrived, re-calibration was scheduled but re-prioritized to flow rate meter, approximately April, 2010.

SV2-DPT 01-01-10 00:00 Compensatory measurements were made per the ODCM and (84.3 days lower tier procedures (and the redundant, non-ODCM in2009) instrument remains in service).

Additionally, a manual measurement of vent flow rate was performed to increase confidence. The manually determined flow rate compared favorably with the corrected values from the non-ODCM instrument.

12-19-09 The level instrument failed due to a problem with freeze 21:53 protection caused by a failure of an associated strip heater. The heater strip was replaced, but the level instrument failed its U3 Primary Water to calibration retest. A new instrument was pursued but eventually Storage Tank determined not to be feasible. Instead, parts were procured, level instrument, 01-01-10 installed, and the instrument was successfully calibrated and LT-1 131 00:00 returned to service on Jan 21, 2010 at 12:41.

(12.1 days in While out of service, compensatory measures (level estimates) 2009, but 32.6 were performed per the ODCM and lower tier procedures days total) whenever water was moved into or out of the tank.

Docket No. 50-3, 50-247, & 50-286 Page 7 of 49

7. ODCM Reporting Requirements (continued)

Other Reporting Criteria:

Tank Curie Limits During this reporting period, no tank curie limits in outdoor tanks were exceeded.

ODCM and PCP changes:

There was no change to the Process Control Program for IPEC.

The IPEC ODCM was updated to Revision 2, in July 2009, to include:

" a Monitoring Well at the Lafarge location, and to simultaneously reclassify two wells onsite as part of the Radiological Groundwater Monitoring Program (RGWMP) instead of the REMP.

" Some improvements in definition, controls, and details of the RGWMP in RECS Section 5.6 and Appendix J.

" Updates to the ODCM release point sketches (Appendices B & C), showing the effluent interface with programs like IE Bulletin 80-10, environmental, and groundwater.

See Section G of this report, and the Addendum covering the ODCM updates.

Lost ODCM airbornefilter sample at vendor lab:

In August, 2009, a vendor lab accidently lost sample media from Unit 3's Plant Vent millifilter prior to testing for gross alpha and strontium. IPEC requests Gross Alpha and strontium activities from the vendor on a monthly basis, although, strontium is only required quarterly. The loss of sample was due to broken glassware at the vendor lab.

The filters are tested for gamma several times before they are shipped to the vendor, and no gamma contamination was identified. No alpha or strontium has been identified on these filters in several decades of testing.

Upon discovery of the breakage, an evaluation was performed at IPEC regarding any special operational or maintenance activities at Unit 3 (during the specified interval), to determine whether or not a potential, rare activity could have contributed to a positive gross alpha or strontium on these filters.

No unique activities were performed during this interval at Unit 3.

Therefore, "less than" values from the months before and after August 2009 were applied to the effluent report.

The vendor is NUPIC approved, with a good history of acceptable cross-checks and inter-comparisons. Because the lab quickly identified the error and does not have a history of these kinds of rare occurrences, no further action was initiated. However, this issue was captured in IPEC's corrective action program for tracking / trending.

Docket No. 50-3, 50-247, & 50-286 Page 8 of 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2009

Docket No. 50-3, 50-247, & 50-286 Page 9 of 49 TABLE 1A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A PcIri~i, R. ArJ'hi*inn t"- :

............. Units Qtr" Qtr 2 Qtr 3 Or 4 2009  % Error

1. Total Release a 1.50E-01 5.141-02 9.15E-01 7.25E-01 1.84E+00 +25

2. Average relese rate uCVsec 1.93E-02 6.54E-03 1.15E-01 9.13E-02 5.84E-02 B. lodines C. Particulates

1. Total Release, with 1e 9.32E-06 - 9.32E-06 +25 half-life > 8 days

2. Average release rate uCi/sec 120E-06 - 2.956E-07

3. Gross lpha Ci +25 D. Tritium

1. Total release J Q 215E+00 3.42+00 3.69E+00 282E+00 1.21 E+01 +25

2. Average release rate uCi/sec 2.76E-01 4.35E-01 4.64E-01 355E-01 3.83E-01

- Indlicates < NUA

Docket No. 50-3, 50-247, & 50-286 Page 10 of 49 TABLE IC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Units Qtr I Qtr 2 Qtr 3 Qtr 4 2009 I I I I Total for Period Ci 0.00E+00 0.00E+00 .OOE00 0E000E+00

2) lodines 1-131 Ci - - 0.OOE+00 1-133 Ci - - 0.00E+00 1-135 Ci - - - - 0.OOE+00 FTotal fo eidCi 0.00E+00. 0.0OE+00 0.OO1E+00 0.00E+00 0.001E+00

3) Particulates JCs-137 Ci 9.32E-06_ - - 9.32E-06 Total for Period I CEi j L9932-6 jOOE+00 0.OOE+O0 0.00E+00 9.83E-0-6-j

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 11 of 49 TABLE IC INDIAN POINT 1 and 2 - BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Qtr 4 2009 Units Qtr 1 Qtr 2 Qtr3 Ar-41 Ci 6.38E-02 2.79E-02 3.94E-02 2.94E-02 1.60E-01 Kr-85 Ci 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Kr-85m Ci 9.04E-04 4.02E-05 3.59E-03 4.48E-05 4.58E-03 Kr-87 Ci 8.50E-04 0.OOE+00 1.20E-03 2.79E-06 2.05E-03 Kr-88 Ci 1.77E-03 2.11E-05 4.31E-03 4.12E-05 6.14E-03 Xe-131m Ci 4.88E-04 2.50E-04 4.12E-03 6.46E-03 1.13E-02 Xe-133 Ci 6.30E-02 2.13E-02 7.42E-01 6.80E-01 1.51E+00 Xe-133m Ci 8.98E-04 3.02E-04 1.19E-02 5.70E-03 1.88E-02 Xe-135 Ci 1.60E-02 1.53E-03 1.05E-01 3.88E-03 1.27E-01 Xe-135m Ci 2.27E-03 0.00E+00 2.34E-03 7.11E-06 4.63E-03 Xe-1 38 Ci 4.99E-04 0.OOE+00 6.06E-04 1.57E-06 1.11E-03

[Total for Period KCi ISQE-Ol jý5.ý:14E-02 .9.111E-01 725E-01 1i.84E+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 12 of 49 TABLE 1A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES A I.ccir, r.

Ariuztir(n e=

Year Est. Total

~L-its Un*I OrI Qtr2 O~r3 CWr4 2009  % Ernro 1.Total Release a 528E-01 6.30E4C2 3.39E-02 5.09E-C2 6.76E-01 J+25

2. Averag releaserate I ui/~sec 6.79E-12 &o1E-03 4.27E-03 6.40E-03 2.14E-02Jj B Iodines C. Particulates

1. Total IRlease,, mith a -- ooE+o +2 half-life > ~eeme 2.Ae 8 days i ~ ~ -- 0 O.OE+0O0 +2

2. Average release rate uCi/sec 0.0(E+00

3. Gross/Npha - - .OOE+00 +/-25 D. Tritiurn

1. Tctal release a a58E+oo 657E+00 4.96E+00 4.15E+00 1.93E+01 +25

2. Average release rate uCLsec 4.61 E01 &35E-01 6.24E-01 522E01 6.111501 E

- Indicais <M

Docket No. 50-3, 50-247, & 50-286 Page 13 of 49 TABLE IC INDIAN POINT 3 - CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases 2009 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 0.OOE+00 2.33E-02 0.OOE+00 0.00E+00 2.33E-02 Xe-1 33 Ci 2.98E-01 0.OOE+00 0.OOE+00 0.00E+00 2.98E-01 jXe-1 35 Ci 1.76E-01 0.OOE+00 0.OO1E+00 I 0.OOE+00 1.76E-01 Total for Pe nod Ci 4.74E-01 233E3-02 0.OOE+00 0 OOE+00 4.97E-O1

2) lodines 1-131 Ci 0.001E+00 1-133 Ci 0.001E+00 1-135 Ci -0.001E+00 Total for Peniod K.Ci 0.00 E+00,

3) Particulates Total for Period Ci ll- 0.OOE+00

- indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 14 of 49 TABLE IC INDIAN POINT 3 BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Units Qtr I Qtr 2 Qtr 3 Qtr 4 2009 Ar-41 Ci 1.28E-02 1.16E-02 3.11E-02 4.69E-02 1.02E-01 Kr-85 Ci 2.24E-03 5.82E-03 - 8.05E-03 Kr-85m Ci 7.94E-06 - - 7.94E-06 Kr-87 Ci - - 0.00E+00 Kr-88 Ci - - 0.00E+00 Xe-131 m Ci 3.13E-05 - - 3.13E-05 Xe-133 Ci 3.90E-02 2.01E-02 2.86E-03 3.96E-03 6.60E-02 Xe-1 33m Ci 5.79E-05 3.62E-04 - 420E-04 Xe-135 Ci 7.84E-04 1.70E-03 2.54E-05 - 2.50E-03 Xe-1 35m Ci 0.001E+00 otlfor Period Ci 5.49E-02 I3.96E-02 J3.40E-02 I5.09E-02 I 1.79E-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 15 of 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2009

Docket No. 50-3, 50-247, & 50-286 Page 16 of 49 TABLE 2A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission &Alcivation Products Units Qtr" Qtr 2 Qtr 3 Qtr 4 2009  % Error

1. Total Release (rot including Tritium, Gr Alpha, & Gases) a 3.10E-03 1.17E-02 1.54E-02 7.11E-03 3.73E-Q2 +25 2 Average Diluted Conc uCi/ml 6.56E-12 1.72E-11 1.79E-11 9.68E-12 1.36E-11

-.... A-B. Tritium

-Y-YI I

1. Total Release 1.14E+02 1.07E+02 2.77E+02 3.87E+02 8.86E+02 +25 2.42E-07 1.57E-07 3.23E-07 5.28E-07 3.22E-07 I I C. Dissdved & Entrained Gases D. Gross Alpha

1. Total Release a - - - +25 E. Vdl rne of Waste Released 1.Processed Waste (LW &NCD) liters 1.05E+06 1.83E+06 2.19E+06 2.40E+06 7.46E+06 +10 2 Urpocessed(SGBD, SFDS, UlFD) liters 4.49E+07 5.13E+07 4.49E+07 4.31E+07 1.84E+08 + 10 F. Vdume of Dilution Water liters 4.73E-+11 6.81E+111 8.59E+11 7.34E+1,1 275E+1,2 +/-10

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 17 of 49 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

CONTINUOUS RADIOACTIVE EFFLUENT Year Nuclides Released Units Qtr I Qtr 2 Qtr 3 Qtr 4 2009 Cs-137 Ci 1.02E-03 8.00E-03 4.58E-03 1.50E-03 1.51E-02 Ni-63 Ci - - - 0.OOE+00 Sr-89 Ci -- - 0.OOE+00 Sr-90 Ci 3.98E-04 5.23E-04 3.42E-04 3.02E-04 I 1.57E-03 Total for Period Ci 1i42&b03: ':8.52E-031] 4.9'21E03 I 1.80E-031 1.67E-02~

- 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 2009)

BATCH RADIOACTIVE EFFLUENT Year Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2009 Ag-110m Ci -0.OOE+00 Co-58 Ci 4.21E-05 1.23E-05 1.18E-05 6.62E-05 Co-60 Ci 6.53E-05 3.80E-05 1.40E-04 6.83E-06 2.50E-04 Cr-51 Ci 0.OOE+00 Cs-134 Ci 1.10E-05 4.52E-05 3.13E-04 3.69E-04 Cs-137 Ci 2.18E-04 4.70E-04 3.17E-03 4.94E-04 4.35E-03 Mn-54 Ci - 0.OOE+00 Ni-63 Ci 2.69E-04 2.10E-03 5.50E-03 1.51E-03 9.37E-03 Sb-124 Ci 0.OOE+00 Sb-125 Ci 1.08E-03 5.14E-04 1.32E-03 3.30E-03 6.21E-03 Sr-90 Ci 0.OOE+00 Te-123m Ci 0.OOE+00 Te-1 25m Ci 0.00E+00 Tot~alforPeriod~ Ci 1'.69E1:-0 3 3.1' 8E- 03_ 1.05E-02 5.31 E-03J20E2I Dissolved & Entrained Gas Kr-85 Ci - 0.00E+00 Xe-133 Ci 3.34E-05 1.59E-04 1.92E-04 T*tal for Period C,*___..__>*.E..0.0

.1.92E-04, CE+00 3.34E-05 1._59E-04

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 19 of 49 TABLE 2A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission & Activation Products 2009  % Error Units QtrIl Qtr2 Qtr3 Qtr4

1. Total Release (not including Ci 3.87E-03 1.86E-02 2.35E-03 5.15E-04 2.53E-02 +25 Tritium, Gr Alpha, & Gases)

2. Average Diluted Conc uCi/ml 8.19E-12 2.73E-11 2.74E-12 7.01E-13 922E-12 B. Tritium

1. Total Release Ci 720E+02 1.08E+02 1.33E+02 125E+01 9.73E+02 +25

2. Average Diluted Conc uCi/ml 1.52E-06 1.58E-07 1.55E-07 1.71E-08 3.54E-07 C. Dissolved & Entrained Gases

1. Total Release Ci 7.43E-03 6.35E-04 4.62E-04 4.50E-06 8.53E-03 +25

2. AverageDiluted Conc uCi/ml 1.57E-11 9.32E-13 5.37E-13 6.13E-15 3.10E-12 D. Gross Alpha

1. Total Release Ci 0OOE+00 +2 E. Volume of Waste Released

1. Processed Fluids (Mon Tanks) liters 1.39E+06 8.48E+05 6.OOE+05 1.80E+05 3.02E+06 +10

2. Unprocessed Fluids (SGs) liters 1.77E+06 1.35E+07 2.77E+06 1.64E+06 1.97E+07 +10 F. Volume of Dilution Water liters 4.73E+1 11 6.81E+1 1 8.59E+11 7.34E+1 1 2-75E+12 +1

'-indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 20 of 49 TABLE 2B INDIAN POINT 3 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

BATCH and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT Batch Fission/ActivationProducts Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2009 Ag-110-n a 9.70E-05 5.22E-05 3.83E-06 0.00E+00 1.53E-04 Co-58 Ci 0.00E+00 6.88E-04 4.08E-04 5.63E-05 1.15E-03 Co-60 Ci 1.87E-03 1.62E-03 3.90E-04 9.36E-05 3.97E-03 Cr-51 Ci 0.OOE+00 3.36E-04 1.80E-05 0.OOE+00 3.54E-04 Cs-137 Ci 9.91E-06 5.OOE-05 9.98E-06 1.51E-05 8.50E-05 Fe-55 Ci 7.26E-04 0.OOE+00 0.OOE+00 0.OOE+00 7.26E-04 Mn-54 a 1.93E-05 9.81E-06 0.OOE+00 0.00E-+00 2.91E-05 Nb-95 a 0.OOE+00 1.81E-05 2.37E-06 0.OOE+00 2.05E-05 Ni-63 a 9.93E-04 4.28E-04 7.31 E-04 3.17E-04 2.47E-03 Rb-88 a 1.29E-4 0.OOE+00 0.00E+00 0.00E+00 1.29E-04 Sb-124 a 0.00E+00 1.95E-04 1.68E-05 0.OOE+00 2.12E-04 Sb-125 a 2.93E-05 6.71E-04 2.65E-04 3.25E-05 9.98E-04 Te-123m a 0.OOE+00 3.58E-04 3.20E-06 0.00E+00 3.61 E-04 Te-1 25m a 0.00E+00 1.42E-02 5.06E-04 O.OOE+00 1.47E-02 Tota fo Peiod0 387E,03 1.86E-02_j2135E-03_I_5.14E-04 2.54E-02 Dissolved and Entrained Gas (Batch)

Xe-133 a 7.42E-03 6.33E-04 4.62E-04 4.50E-06 8.52E-03 Xe-133m a 7.57E-06 0.OOE+00 0.OOE-+00 0.OOE+00 7.57E-06 Xe-135 Ci 1.99E-06 2-19E-06 0.00E+00 0.OOE+00 4.18E-06 l 74E3 6.35E-04 4.62E-04 4.50E-06 Continuous Releases (SG Blowdown)

H-3 (only) I a 1.78E-03 I .OOE+00 I 1.5E-03 I3.91E-03 17.1E0

'- indicates < mda

Docket No. 50-3, 50-247, & 50-286 Page 21 of 49 Indian Point Energy Center' (Units 1i 2, and 3)

RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2009

Docket No. 50-3, 50-247, & 50-286 Page 22 of 49 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2009 to 12/31/2009 Percent Cutoff: 0 (all identified isotopes are included)

Waste Stream : Resins, Filters, and EvapBottoms Cartidge Filters LWS Resin Plant Resin 8-120 U 1 West Pool 8-120 Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 1.79E+02 5.07E+00 2.85E +00 +/-25%

B 1.80E+02 5.10E+00 1.69E+02 +/-25%

C 2.46E+01 6.97E-01 1.15E+01 +/-25%

All 3.84E+02 1.09E+01 1.84E+02 +/-25%

Waste Stream Dry Active Waste DAW / Metals Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 5.OOE+01 1.42E+00 1.46E-05 +/-25%

B 0.OOE+00 0.00E+00 0.00E+00 +/-25%

C 0.OOE+00 0.00E+00 0.00E+00 +/-25%

All 5.OOE+01 1.42E+00 1.46E-05 +/-25%

Waste Stream Irradiated Components Waste Volume Curies  % Error (Ci) 3 Class ft 3 m Shipped A 0.OOE+00 0.OOE+00 0.00E+00 +/-25%

B 0.OOE+00 0.OOE+00 0.00E+00 +/-25%

C 0.OOE+00 0.00E+00 0.OOE+00 +/-25%

All 0.OOE+00 0.00E+00 0.00E+00 +/-25%

W aste Stream: Other Waste Waste Volume Curies  % Error (Ci) 3 Class ft 3 m Shipped A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.OOE+00 0.00E+00 +/-25%

All 0.00E+00 0.OOE+00 0.00E+00 +/-25%

Waste Stream : Sum of All 4 Categories Combined Packages:

Cartridge Filters U1 West Pool 8-120 LWS Resin DAW / Metals Plant Resin 8-120 Waste Volume Curies  % Error (Ci)

Class ft 3 m 3 Shipped A 2.29E+02 6.48E+00 2.85E+00 +/-25%

B 1.80E+02 5.1 OE+00 1.69E+02 +/-25%

C 2.46E+01 6.97E-01 1.15E+01 +/-25%

All 4.34E+02 1.23E+01 1.84E+02 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

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 01/01/2009 to 12/31/2009 Percent Cutoff: 0 Number of Shipments Mode of Transportation Destination 1 Hittman Transport Energy Solutions - Bear Creek 1 R & R Trucking Inc Studsvik Processing -

Memphis 3 Hittman Transport Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance Curies H-3 0.066% 1.88E-03 Mn-54 0.474% 1.35E-02 Fe-55 15.690% 4.47E-01 Co-58 0.288% 8.20E-03 Co-60 5.686% 1.62E-01 Ni-63 21.727% 6.19E-01 Sr-90 0.082% 2.35E-03 Cs-1 34 9.302% 2.65E-01 Cs-137 46.684% 1.33E+00 Total 2.85E+00 Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance Curies H-3 0.019% 3.18E-02 Mn-54 0.014% 2.39E-02 Fe-55 0.417% 7.06E-01 Co-57 0.015% 2.47E-02 Co-60 4.334% 7.34E+00 Ni-63 52.488% 8.89E+01 Sr-89 0.001% 1.79E-03 Sr-90 8.325% 1.41 E+01 Sb-125 0.348% 5.89E-01 Cs-134 2.539% 4.30E+00 Cs-137 31.292% 5.30E+01 Ce-144 0.168% 2.84E-01 Pu-238 0.002% 2.61E-03 Pu-239 0.001% 1.15E-03 Pu-241 0.037% 6.19E-02 Am-241 0.002% 2.72E-03 Cm-242 0.000% 4.71 E-05 Cm-243 0.001% 1.20E-03 Total 1.69E+02

Docket No. 50-3, 50-247, & 50-286 Page 24 of 49 Resins, Filters, and Evap Bottoms Waste Class C Nuclide Name Percent Abundance Curies H-3 0.041% 4.75E-03 Mn-54 0.020% 2.35E-03 Fe-55 0.815% 9.37E-02 Co-57 0.020% 2.27E-03 Co-60 7.746% 8.91 E-01 Ni-63 61.725% 7.10E+00 Sr-89 0.000% 5.64E-05 Sr-90 0.775% 8.91 E-02 Sb-125 0.682% 7.85E-02 Cs-1 34 4.738% 5.45E-01 Cs-1 37 23.299% 2.68E+00 Ce-144 0.073% 8.36E-03 Pu-238 0.003% 3.OOE-04 Pu-239 0.001% 6.59E-05 Pu-241 0.061% 7.OOE-03 Am-241 0.000% 5.10E-05 Cm-242 0.000% 3.27E-06 Cm-243 0.001% 1.57E-04 Total 1.1 5E+01 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies H-3 0.021% 3.84E-02 Mn-54 0.022% 3.98E-02 Fe-55 0.680% 1.25E+00 Co-57 0.015% 2.69E-02 Co-58 0.004% 8.20E-03 Co-60 4.567% 8.39E+00 Ni-63 52.585% 9.66E+01 Sr-89 0.001% 1.85E-03 Sr-90 7.730% 1.42E1+01 Sb-125 0.363% 6.67E-01 Cs-134 2.782% 5.111E+00 Cs-137 31.029% 5.70E+01 Ce-144 0.159% 2.92E-01 Pu-238 0.002% 2.911E-03 Pu-239 0.001% 1.22E-03 Pu-241 0.038% 6.89E-02 Am-241 0.002% 2.77E-03 Cm-242 0.000% 5.04E-05 Cm-243 0.001% 1.35E-03 Total 1.84E+02

Docket No. 50-3, 50-247, & 50-286 Page 25 of 49 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies Co-60 1.188% 1.73E-07 Ni-63 45.996% 6.70E-06 Sr-90 14.554% 2.12E-06 Cs-137 38.032% 5.54E-06 Ce-144 0.210% 3.06E-08 Pu-238 0.001% 1.05E-10 Pu-239 0.001% 1.14E-10 Pu-241 0.016% 2.40E-09 Am-241 0.003% 3.75E-1 0 Cm-243 0.000% 2.62E-1 1 Total 1.46E-05 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies Co-60 1.188% 1.73E-07 Ni-63 45.996% 6.70E-06 Sr-90 14.554% 2.12E-06 Cs-137 38.032% 5.54E-06 Ce-144 0.210% 3.06E-08 Pu-238 0.001% 1.05E-10 Pu-239 0.001% 1.14E-10 Pu-241 0.016% 2.40E-09 Am-241 0.003% 3.75E-10 Cm-243 0.000% 2.62E-1 1 Total 1.46E-05 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 0.066% 1.88E-03 Mn-54 0.474% 1.35E-02 Fe-55 15.690% 4.47E-01 Co-58 0.288% 8.20E-03 Co-60 5.686% 1.62E-01 Ni-63 21.727% 6.19E-01 Sr-90 0.083% 2.36E-03 Cs-134 9.302% 2.65E-01 Cs-137 46.684% 1.33E+00 Ce- 144 0.000% 3.06E-08 Pu-238 0.000% 1.05E-10 Pu-239 0.000% 1.14E-10 Pu-241 0.000% 2.40E-09 Am-241 0.000% 3.75E-10 Cm-243 0.000% 2.62E-1 I Total 2.85E+00

Docket No. 50-3, 50-247, & 50-286 Page 26 of 49 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.019% 3.18E-02 Mn-54 0.014% 2.39E-02 Fe-55 0.417% 7.06E-01 Co-57 0.015% 2.47E-02 Co-60 4.334% 7.34E+00 Ni-63 52.488% 8.89E+01 Sr-89 0.001% 1.79E-03 Sr-90 8.325% 1.41 E+01 Sb-125 0.348% 5.89E-01 Cs-134 2.539% 4.30E+00 Cs-137 31.292% 5.30E+01 Ce-144 0.168% 2.84E-01 Pu-238 0.002% 2.61 E-03 Pu-239 0.001% 1.15E-03 Pu-241 0.037% 6.19E-02 Am-241 0.002% 2.72E-03 Cm-242 0.000% 4.71 E-05 Cm-243 0.001% 1.20E-03 Total 1.69E+02 Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies H-3 0.041% 4.75E-03 Mn-54 0.020% 2.35E-03 Fe-55 0.815% 9.37E-02 Co-57 0.020% 2.27E-03 Co-60 7.746% 8.91E-01 Ni-63 61.725% 7.10E+00 Sr-89 0.000% 5.64E-05 Sr-90 0.775% 8.91 E-02 Sb-125 0.682% 7.85E-02 Cs-134 4.738% 5.45E-01 Cs-137 23.299% 2.68E+00 Ce-144 0.073% 8.36E-03 Pu-238 0.003% 3.OOE-04 Pu-239 0.001% 6.59E-05 Pu-241 0.061% 7.OOE-03 Am-241 0.000% 5.10E-05 Cm-242 0.000% 3.27E-06 Cm-243 0.001% 1.57E-04 Total 1.15E+01

Docket No. 50-3, 50-247, & 50-286 Page 27 of 49 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 0.021% 3.84E-02 Mn-54 0.022% 3.98E-02 Fe-55 0.680% 1.25E+00 Co-57 0.015% 2.69E-02 C6-58 0.004% 8.20E-03 Co-60 4.567% 8.39E+00 Ni-63 52.585% 9.66E+01 Sr-89 0.001% 1.85E-03 Sr-90 7.730% 1.42E+01 Sb-125 0.363% 6.67E-01 Cs-134 2.782% 5.11 E+00 Cs-137 31.029% 5.70E+01 Ce-144 0.159% 2.92E-01 Pu-238 0.002% 2.91 E03 Pu-239 0.001% 1.22E-03 Pu-241 0.038% 6.89E-02 Am-241 0.002% 2.77E-03 Cm-242 0.000% 5.04E-05 Cm-243 0.001% 1.35E-03 Total 1.84E+02

Docket No. 50-3, 50-247, & 50-286 Page 28 of 49 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2009 to 12/31/2009 Percent Cutoff: 0 (all identified isotopes are included)

W aste Stream : Resins, Filters, and Evap Bottoms LWS Resin 14-170 Waste Volume Curies  % Error (Ci) 3 Class ft 3 m Shipped A 1.35E+02 3.82E+00 1.62E+00 +/-25%

B 0.00E +00 0.OOE +00 0.00E +00 +/-25%

C 0.0OE+00 0.0OE+00 0.00E+00 +/-25%

All 1.35E+02 3.82E+00 1.62E+00 +/-25%

Waste Stream Dry Active Waste U3 DAW B-25 Soi/Debris B-25 Unit 3 DAW-20' Sealand 20' Intermodal Soil DAW 20' Shielded SeaLand Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 1.26E+04 3.57E+02 8.49E-01 +/-25%

B 0.OOE+00 0.OOE+00 0.OOE+00 +i-25%

C 0.OOE+00 0.00E+00 0.OOE+00 +/-25%

All 1.26E+04 3.57E+02 8.49E-01 +/-25%

W aste Stream  : Irradiated Components Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 0.0OE+00 0.0OE+00 0.0OE+00 +/-25%

B 0.0OE+00 0.0OE+00 0.0OE+00 +/-25%

C 0.0OE+00 0.0OE+00 0.OE+00 +/-25%

All 0.0OE+00 0.00E+00 0.0OE+00 +/-25%

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

Class ft 3 m3 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 0.00E+00 +/-25%

All 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

Waste Stream Sum of All 4 Categories Unit 3 DAW B-25 Soil/Debris B-25 LWS Resin 14-170 20' Intermodal Soil DAW 20' Shielded SeaLand Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 1.27E+04 3.60E +02 2.47E+00 +/-25%

B 0.0OE+00 0.0OE+00 0.0OE+00 +/-25%

C 0.0OE+00 0.OE + 00 0.0OE+00 +/-25%

All 1.27E+04 3.60E+02 2.47E+00 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

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 01/01/2009 to 12/31/2009 Percent Cutoff: 0 Number of Shipments Mode of Transportation Destination 8 Hittman Transport Energy Solutions Bear Creek 3 R & R Trucking Inc Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Percent Nuclide Name Abundance Curies H-3 15.346% 2.48E-01 Mn-54 0.167% 2.70E-03 Fe-55 18.254% 2.95E-01 Co-57 0.074% 1.19E-03 Co-58 0.043% 7.03E-04 Co-60 17.635% 2.85E-01 Ni-63 36.074% 5.83E-01 Sr-90 0.003% 5.30E-05 Sb-125 2.525% 4.08E-02 Cs-134 2.358% 3.81 E-02 Cs-137 7.116% 1.15E-01 Ce-144 0.325% 5.26E-03 Pu-238 0.002% 3.78E-05 Pu-239 0.001% 9.73E-06 Pu-241 0.072% 1.17E-03 Am-241 0.002% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.003% 5.43E-05 Total 1.62E+00 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Curies Abundance H-3 15.346% 2.48E-01 Mn-54 0.167% 2.70E-03 Fe-55 18.254% 2.95E-01 Co-57 0.074% 1.19E-03 Co-58 0.043% 7.03E-04 Co-60 17.635% 2.85E-01 Ni-63 36.074% 5.83E-01 Sr-90 0.003% 5.30E-05 Sb-125 2.525% 4.08E-02 Cs-134 2.358% 3.81 E-02 Cs-137 7.116% 1.15E-01 Ce-144 0.325% 5.26E-03 Pu-238 0.002% 3.78E-05

Docket No. 50-3, 50-247, & 50-286 Page 30 of 49 Pu-239 0.001% 9.73E-06 Pu-241 0.072% 1.17E-03 Am-241 0.002% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.003% 5.43E-05 Total 1.62E+00 Dry Active Waste Waste Class A Nuclide Name Percent Curies Abundance H-3 0.483% 4.1 OE-03 C-14 0.031% 2.59E-04 Mn-54 0.397% 3.37E-03 Fe-55 27.691% 2.35E-01 Co-57 0.141% 1.20E-03 Co-58 30.754% 2.61 E-01 Co-60 18.028% 1.53E-01 Ni-63 20.856% 1.77E-01 Sr-90 0.015% 1.28E-04 Nb-95 0.016% 1.35E-04 Sb-124 0.033% 2.83E-04 Sb-125 0.109% 9.21 E-04 Cs-134 0.197% 1.67E-03 Cs-137 1.249% 1.06E-02 Total 8.49E-01 Dry Active Waste Waste Class All Nuclide Name Percent Curies Abundance H-3 0.483% 4.1 OE-03 C-14 0.031% 2.59E-04 Mn-54 0.397% 3.37E-03 Fe-55 27.691% 2.35E-01 Co-57 0.141% 1.20E-03 Co-58 30.754% 2.61 E-01 Co-60 18.028% 1.53E-01 Ni-63 20.856% 1.77E-01 Sr-90 0.015% 1.28E-04 Nb-95 0.016% 1.35E-04 Sb-124 0.033% 2.83E-04 Sb-125 0.109% 9.21 E-04 Cs-134 0.197% 1.67E-03 Cs-137 1.249% 1.06E-02 Total 8.49E-01

Docket No. 50-3, 50-247, & 50-286 Page 31 of 49 Sum of All 4 Categories Waste Class A Nuclide Name Percent Curies Abundance H-3 10.226% 2.52E-01 C-14 0.011% 2.59E-04 Mn.-54 0.246% 6.07E-03 Fe-55 21.506% 5.30E-01 Co-57 0.097% 2.39E-03 Co-58 10.631% 2.62E-01 Co-60 17.773% 4.38E-01 Ni-63 30.839% 7.60E-01 Sr-90 0.007% 1.81E-04 Nb-95 0.005% 1.35E-04 Sb-124 0.011% 2.83E-04 Sb-125 1.692% 4.17E-02 Cs- 134 1.615% 3.98E-02 Cs-137 5.072% 1.25E-01 Ce-144 0.213% 5.26E-03 Pu-238 0.002% 3.78E-05 Pu-239 0.000% 9.73E-06 Pu-241 0.047% 1.17E-03 Am-241 0.001% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.002% 5.43E-05 Total 2.46E+00

Docket No. 50-3, 50-247, & 50-286 Page 32 of 49 Sum of All 4 Categories Waste Class All Nuclide Name Percent Curies Abundance H-3 10.226% 2.52E-01 C-14 0.011% 2.59E-04 Mn-54 0.246% 6.07E-03 Fe-55 21.506% 5.30E-01 Co-57 0.097% 2.39E-03 Co-58 10.631% 2.62E-01 Co-60 17.773% 4.38E-01 Ni-63 30.839% 7.60E-01 Sr-90 0.007% 1.81 E-04 Nb-95 0.005% 1.35E-04 Sb-124 0.011% 2.83E-04 Sb-125 1.692% 4.17E-02 Cs- 134 1.615% 3.98E-02 Cs-137 5.072% 1.25E-01 Ce-144 0.213% 5.26E-03 Pu-238 0.002% 3.78E-05 Pu-239 0.000% 9.73E-06 Pu-241 0.047% 1.17E-03 Am-241 0.001% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.002% 5.43E-05 Total 2.46E+00

Docket No. 50-3, 50-247, & 50-286 Page 33 of 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2009 - Dec 31, 2009

Docket No: 50-3, 50-247, & 50-286 Page 34 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 have been determined from data generated at IP3 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). These estimates are consistent with NUREG 0017, Rev. 1. The maximum expected annual dose from C-14 releases at IP2 and IP3 have been calculated using rated electrical capacity, approximately 1000 MW(e) maintained for the entire year, and the given curies determined from the experiment, corrected for the fraction of C-14 determined to be in the Carbon Dioxide form, as doses are not expected from other forms (methane, etc). The resultant offsite doses are based upon this source term and the dose calculations described in Reg Guide 1.109 and the ODCM.

The annual dose to the maximally exposed individual (child) from gaseous releases of C-14 at IPEC (units 2 and 3) is 0.508 mrem to the critical organ.(bone) and 0.102 mrem to the total body.

The annual dose to the maximally exposed individual (child) from typical liquid releases of C-14 is 0.0117 mrem to the critical organ (bone) and 0.00234 mrem to the total body. Due to the unique nature of C-14, and the extremely conservative bounding measurements performed, the combined offsite dose attributable to C-14 alone (liquid and airborne) is reported on the Dose to Man section cover page (and not in the tables that follow), specifically to avoid confusion.

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.

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

Total Dose:

In compliance with 40CFR190, the following table indicates the Total Dose, including any measured direct shine component from the site property for 2009:

Whole Body. Max Organ 40CR10lmtIlPEC ~ 25 rnrem 75 mrem Routine Airborne Effluents' Units 1 and 2 2.28E-3 2.28E-3 Routine Liquid Effluents Units 1 and 2 9.OOE-4 1.71 E-3 Routine Airborne Effluents1 Unit 3 3.36E-3 3.36E-3 Routine Liquid Effluents Unit 3 2.49E-4 4.59E-4 Carbon-14 Totals:(Liquid & Airborne IPEC.....1 .04E-1 ... 5.20E-.1..

releases froml PEC. Units 1, 2, & 3).

Ground Water & Storm Drain Totals IPEC 2 2.56E-4 1..03E-3.

Direct Shine from ISFSI, Radwaste ~ IPEC3 5 , '< ,5<

Storage, SG etc. "Mausoleum.

Indian Point Energy Center 5.11 5.53 Total Dose, per 40 CFR 190 Note 1: Airborne dose in this table is conservatively represented as a sum of Iodine/Particulate Dose (mrem) and noble gas beta air energy (mrad, expressed as mrem) at the highest site boundary location, for purposes of demonstrating 40CFR1 90 compliance only.

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

Note 3: The direct shine component from sources other than ISFSI are indistinguishable from background. ISFSI doses were determined from net integrated quarterly TLD readings at the identified critical site boundary locations, and comparing these values with ISFSI boundary and REMP TLDs. No occupancy factors were applied for this conservative assessment. Details of this evaluation are available on site.

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 2009 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES

.. . .. . .. . . .. I .

Qtr 1 :Qtr i2i::*! Qtr 3 Qtr .4 !ANN:UAL.

Organ Dose (mrem) 3.02E-04 6.40E-04 5.70E-04 2.34E-04 1.71 E-03

[Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit M% 6.04E-03 1.28E-02 1.14E-02 4.68E-03 1.71 E-02

[Age Group Adult Child Child Child Child I ritical Organ Bone Bone Bone Bone Bone jAdultTotal Body (mrem) 1.41E-04 3.33E-04 2.74E-04 1.52E-04 9.OOE-04

[Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percentof Limit (%) 9.40E-03 2.22E-02 1.83E-02 1.01E-02 3.OOE-02 B. AIRBORNE NOBLE GAS DOSES

_ _ _ _Qtrl I Qtr.2,'ýý  : Qtr.3',ý, ,:. :: Qtr:4:i ANNUALJ Gamma Air (mrad) 2.95E-05 1.14E-05 4.62E-05 2.69E-05 1.14E-04 Applicable Limit (mrad) 5 5 5 5 10.

Percentof Limit (%) 5.90E-04 2.28E-04 9.24E-04 5.38E-04 1.14E-03 Beta Air (mrad) 2.36E-05 8.35E-06 8.63E-05 5.88E-05 1.77E-044 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 2.36E-04 8.35E-05 8.63E-04 5.88E-04 8.85E-04 C. AIRBORNE IODINE and PARTICULATE DOSES Qtrl::  ::Qtr3

.tr 3.,: Qtr 4 ANNUAL.

Iodine/Part (mrem) 4.34E-04 5.73E-04 6.18E-04 4.72E-04 2.10E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percentof Limit (%) 5.79E-03 7.64E-03 824E-03 6.29E-03 1.40E-02

[age Group I Child Child Child Child I hildi lCritical Organ IILi ver ILiver ILiver ILiver I Liver I

Docket No. 50-3, 50-247, & 50-286 Page 37 of 49 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2009 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES

,I':Qtrll iQtr ,2! Qtr 3:i !Qtr 4 :ANNUAL Organ Dose (mrem) 2.57E-04 1.67E-04 3.12E-05 1.37E-05 4.59E-04 Applicable Limit (morero) 5 5 5 5 10 Percent of ULmit (%) 5.14E-03 3.34E-03 6.24E-04 2.74E-04 4.59E-03 Age Group Adult Adult Adult Child Adult Critical Organ GI-LLI GI-LLI GI-LLI Bone GI-LLI Adult Total Body (mrem) 1.96E-04 2.89E-05 2.12E-05 3.10E-06 2.49E-04 Applicable Limit (mtrem) 1.5 1.5 1.5 1.5 3.0 Percentof Limit (%) 1.31 E-02 1.93E-03 1.41 E-03 2.07E-04 8.31E-03 B. AIRBORNE NOBLE GAS DOSES 1 Qtr:2 Qtr33 Qtr:4 ANN UAL.-

lGamma Air pplicable Limit (mrad)

(mrad)

_ Qtr 3.52E-05 5

1.07E-05 5

8.85E-06 5

1.34E-05 5

6.82E-05 10 Percent of ULmit (%) 7.04E-04 2.14E-04 1.77E-04 2.68E-04 6.82E-04 Beta Air pplicable Limit (mrad)

(mrad) 1.18E-04 10 2.15E-05 10 1.49E-05 10 2.24E-05 10 1.

20 1E-04 Percent of ULmit (%) 1.18E-03 2.15E-04 1.49E-04 2.24E-04 8.84E-04 C. AIRBORNE IODINE and PARTICULATE DOSES I'~ Qtrl Qtr 2 I Qtr3 , Qt 4: IANNUAL:I Iodine/Part (mrem) 5.92E-04 1.08E-03 8.20E-04 6.86E-04 3.18E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 , 15 Percentof Limit (%) 7.89E-03 1.44E-02 1.09E-02 9.15E-03 2.12E-02

[Age Group I I Child I Child I Child I Child I Chd I Critical Organ Li ver Liv er Liver Liver IU ver

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, 2009 - Dec 31, 2009 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 2009 There was an additional GW well added to the REMP sampling locations, and two wells were reclassified as part of the Radiological Groundwater Monitoring Program in year 2009.

Details of the changes in the REMP are included in the ODCM and justification package, provided as an Addendum to this report.

There were no changes to the Land Use Census in year 2009.

There were no changes to the Process Control Program (PCP) in 2009.

There was one ODCM update in 2009.

In July, 2009 the station ODCM was upgraded to revision 2.

A complete copy of the revised IPEC ODCM, as well as the Rev 2 justification package, are provided in an Addendum to this report.

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, 2009 - Dec 31, 2009

Docket No. 50-3, 50-247, & 50-286 Page 41 of 49 Summary of IPEC Groundwater and Storm Water Activity, 2009 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 is expected to continue.

The precipitation mass balance model applied in 2007 and 2008 was applied for offsite dose calculations in 2009. Hydraulic conductivity readings continued to validate the model throughout the year, and the USGS, as well as IPEC local MET data verified annual precipitation averaging 2.68 feet per year. No changes to the model were required.

Results of 2009 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 (<0.1%), 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 0.07 Curies in 2009, resulting in a total body dose of significantly less than 0.1 mrem (1.4E-7 mrem). It is evident that tritium alone, whether from ground water or routine effluents, does not arithmetically contribute to integrated offsite dose.

Strontium-90, Cesium-137, and Co-60 collectively contributed approximately 0.00025 curies to site effluent from the groundwater pathway. Combined groundwater releases from IPEC in 2009 (all radionuclides) resulted in a calculated annual dose of significantly less than 0.1% of the annual limits for whole body and critical organ, as follows:

IPEC Groundwater and Storm Water Effluent Dose, 2009 0.000256 mrem to the total body, (0.0085% limit) 0.00103 mrem to the critical organ, adult bone (0.0103% 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. This comparison is provided in the opening discussion of Section E, Radiological Impact on Man.

Docket No. 50-3, 50-247, & 50-286 Page 42 of 49 IPEC Sumimary for Stofrm& Ground Water releases ((H1-3 Co-6, Ni-63, Sfr90, and Cs4137). 2009 year, "Mn.4karaPiann L~na

. -IIl IlI w - iII u l "'ir .. -* * ~

1 , ,IG ,

ISOT~OPE J~ONE LIVFFý T, mT;BoDY' -1HYROID ' KIDNEY INI, GTLI' H-3 OOOE+00E 464E+9 4 64E-09 4 64E-09 4,64E-09 4 64E-09 4.ý64E-,O 4415E+02 Co-60 ' OOOE+OO 0OOE+OO OOOE+O0 OOOE+00 0,00E+00 0.00E+00 0.00E.,O0E  :

Ni-63 O.OOE"OO ' ,O0E+00 ,-0E+00" 0 OOE4OO OOOE+O OCOE+00 0:00+OE+OO;

,Sr-90 I '.OOE4-00 O;OOE400E 0 OOE+:E004 0O,00 0 OOE+00* OME-00EEO< O0E+0.7kI Cs-137, 0:00E+00 O.OOE+00 0OOE+00 000EOO O.0E00 i O.00 000E+00. *.00E00E  : o 00E+00, totals,,: 0.0050E+ 464E-09 1 4.64E&09' I 4:64E-9 I 4.64E-09 4.64E,09 4.64E-09: I Unit 2 North ISOIO-PEý 7 I '

17IN LIJVER K'TOT BODY ~ THYROID KIDNEY L~UNG (-,GI-[li 415OE+00 H-,3 000E+00' 1:1.2E08 1 12E.08 - 1 12E-1*O8'" 1:2E;08 1.12E-08;' :1.12E-08:

Co-6o O.OOE+*O0 OOOE+OO 0 OOE+O 0OOOE+O0 0 OOE+OO 0 OOE+OO 0 OOE+O Ni-63 ,O0E+0 V0OO.OE+OO0 OOE+OO " 0;* E+00 0* OE+OO 0.OOE+OO - 0OOE+OO -

005O+00 Sr-90 O OOOE+O0 000E+OO OOE+00O. O'OOE+.-O 0 00+00 0.00E+00 000+00.

Cs-i37 &896E-06 1.23E*-0 8.03E-06 0OOOE+00 41i6E706 1.38&-06 2,37E107' 4i6-00 totals &896E706

• 1 23E-05 : 8.04E-06 1.,12E-08 I 4:17E-06 . 1.39E-.06. 2485E-07 4:83E-041 Unit 1/2 ISOTOPE~ BONE' LI/VER7 TOT BODY~ THYROID 'KIDNEY LUNG .GI-LUI H .. OOE+.O 6,75E-08 6 75E-08 6.75E-08 675E-08 6.75E-08 6.75E-:8 ,9.57E+03.

Co-60 .0.00E+00 O:OOE+O0 000E+00

.OOE+00 O.OOE+00 O

• .00E00. OOE*00+ 0005O+00 Ni-63 2,86E-04 I 99E-05 9,61E-06 0 00E+00, 0.00E+00- ' 0.00E+00 4*1'4E-06 Sr-90 7 4,62E-04 0 OOE+00 1,13E-04 0,00E+00: 0 OE+OO 0 00E+00 ,133E-05 2 91501-Cs-I 37 8:54E-05 1,17E-04-- 7.65,E-,05 00005+00 3'96E-05 1,32E-05 126E-06 totals 8 345-04 ' 1337E-04 . 2.OOE04 6.75E-08 3 :97E-05 1.32E-05; 1.98E-05 Unit 3 North 4 44E+O1

'ISOTOPE. ,BONE. LIVER~ TOT B307Y THYROID KIDNEY LUNG ~ LLI-(-'~,GI 4,94E+00; H-3 113E-08

O::E+O 1 13E-08 : I 13E-08 1 13E-08 ,l13E-08: 1:13E-08 CO-S60. ,.0:.00+Eý00. 5.98E-07 >1.32E-06 0.00E+00 0..OE+O0 0.00E+00 1'.12E-05.

Ni-63 I E00+00 0 00E+00. 0

,00E+00 0.00+00 0.00O+00 0 OO+00E 0 OOE+O0 Sr-9o 8i 5E-05 . O 2.0E-06 2.00E-E+00 O.OOE+00 O.OOE+O00M.OE+000;. 2.35E-06ý, 005+00:

Cs-137. 0.00E+00 0 00E+00 O.00E+0 0,00400 O.:0.00E00K 0.00+E00 O.OOE+00

,:.,:! totals', I :&15E0.&.I 6A10E-07

• 2.13E-05 '1.13E-08. I 1:13E-08 1.13E-08 I 136E-05 Unit 3 South, 7,04E+03' ISOTOPEF BONE L1V5R 2TOT BODY~ 'THYROID KIDNEY' LU NG 71.~G-LLI H-3 .000E+00.  :: 1-22E-08  : 1:22E-08 *,1 22E-08 *; 1*.22E *:0 1t22E-08 1,.22E-08 0 0 ,11 Co-60 0.00E+00- O.OOE+0C0 0OOOE+. 0,00E+00 0,00E+00 0:00+00' 0.005+00 . 0E00 Ni-63 O.OOE+00 *O O.0E+00*:,..$ 0 00E+00 0.00O0 Q, E.+00 O.O0E+0: .,O.00E+0'. "'OO50.00 Sr-90: 1:09E-04' I O.OOE+-00 *7 267E-05' .. 0;00E+00 0,00E+00 0,00E+00' "'314E-06.

Cs-137 OO: +0* *:::000E+0 0.005+00; ' .00E+O0 0.005+.000*E0 0 00E+00 7000E+00.

totals', 109E-04 1 1.22E-08 I.2:67E-05 "1,22E-08 1.22E-08 1,22E-08 3,15E-06" Southern Clean Zone.

LUG" JGI-1LI~

7 08 E+0-3 ISOTOPE' 21BONE hL E E."

R TOT BODY THYROID " KDEY H-3 0 005+00 2 98E-08 2 98E-08 2 98F-08 2 9BE-08 ' 2,98E-08 2.98E-08 Co-6O -0.00+E00 0.005+00 , 000OE0o+00000E+00- 0.00E+00 0,00E+00 '0,O0E+00 Ni-63 0.00E+00 0 OOE+. 0 0 OOE+00

• 00*E+00 0; 00+E00 0 00E+00 0.00E+00:

005O+00, Sr-9O. 0

.0I00+E00 OOE+0 0 O0E+OO 0 005tOO O000E+00 0 OOE+00 :O0E+00 0

Cs-137 0.OOE+0 .0.00E*OG 0 00E+00 0,OOE+0 0 0OOE+0 0 +00 O.OOE+00 .00E'00 2 G6Et-03 totals 0.OOE+00" 2,98E-08 I 2.98E-08 2.98-08 2.98E-08  : 2.98E-08: 298E-08 Totals'. AýdIlt Doses, in rmremn

ýH-3 only [ 0.00E+00 ] :37E-07 I I 137E-07 I 1,37E-07 I i:37E-07: I 1.37E-07 1.37E-07 ' Total Cis F BONE JLIVERY TOT BODY' THYROID) KIDNEY~ LUNG GILI 679Et04 1H3

'all isotopes 1-13E-03 I 150E-04 '2.56E-04 1.37-07:'"3'E- 1437E7-07 1147E05 E01 co

. . . . . . . . ... . .. .5E.2 I WN IAdUltDoses oj5r*o :f; o°

%AnnuaiLimit. .0003 0.001 0.0080502

o. 0.000 0.000 0.O07 0000 4.870ifcs

Docket No. 50-3, 50-247, & 50-286 Page 43 of 49 INDIAN POINT RADIOLOGICAL GROUNDWATER MONITORING PROGRAM 2009 Summary of Results The following pages represent a summary of isotopic radio-analytical data for all onsite groundwater testing performed at Indian Point in 2009, as required per the ODCM and NEI 07-07.

Docket No. 50-3, 50-247, & 50-286 Page 44 of 49 Tritium Summary page 1 of 3

1. Positive

1. samples H-3 Samples- Avg Pos. Min: Pos: Max Posý WeliVName in 2009 in 2009 Act Act Act U

B-1 1. 85.8i, E+0.2 8,81 E+02 8.81 E+022 8.,81E.-+02, LAF-002. 2 i .80E-i02 1 .80E+02! 1:.80E+02 MH-5 3 3 ii.iE+03 6.26Eý+ 02! 1.50E+03, MW-i 07 i .96E+02 1 .96E+02J 1 .96E+02

ýMW- 1-1 2 2 '3.08 E+04 2.26E-+04, 3.89E+041:

,MW-:30-69 6 6 1.07E+05 8,210E+04 1.64E+05 MW-30-84 7 6 6.11E+03 4.69E-+03 7.76E+03 MW-3i -491 7 7 2.1,4E+04 7.36E+02 4.84E+04 MW-31863' 7 1 .99E+04 1.28E+04* 3.24E+04 7

MW-31-85 7 7.31.E+03 2.96E+03 1.88E+04 7 7 1.99E+02 MW-32-i 49 3:07E+02 4.57E+02 MW-32-i173: 7 :7 7.48E+02 4,31 E+02 1.72E+03 MW i90,, 7 2.1IIE03 1 .63E+03 2.69E+03 MW-32-591 77 7 1.71 E÷.04 8.85E+02 6.43E+04 1M.W-32-851 7 8.16E+03 6.54 E+03 9.16E+03 MW-33, 1. 3.44E+04 3.44E+÷04 3.44E+04 MW-35 1, 1.46E+03 1.46E+03 1.46E+03 MW-36-24 4 4 1.28E+03 2.37E+02 2.92 E+03 MW-36-41 3 3 I .05E+04 1.01E+04 1.13E+04 MW-/36-52 4 4 7.42E÷+03 6.06E+03 8.61 E+03 MW-37-22 4 4 4.60E+03 3.85E+03 5.27EI03 MW-37-32 4 4 4.66E+03 3.76E+03 5.48E+03 I MW-37-40ý 4 4 4.51 E+03 4.22 E+03 4.91 E+03

MW-37-57: 4 4 4:81 E+03 4.05E+03 5.94E.+03.,,

MW-39-i02. 2 2 2.44E+02 2..20E+02- 2.67E+02 MW-39-i 24, 2 2.:33 E+02 1.98E+02: .2.68E+02 2

MW-739-183i 2 1 9.85E+01 9.85E+'0.1 :9.85E+011 1'i 1 *.09E+02 M.W39.1i95 2 i .09E+02 17.09E+02 MW-39--67 2 2 3.90E+02 3.38E+02, 4.41 E+02

.MW439-84: 2.i4E+02 .2.42E+02 2 .2 1..85E+02:

MW-40-iO00 '2.62E+02 2.62EE+02 :2.62E+02 4

MW,-40-127' 4 2 1,28E+02 1 .04E+024: 1.52E4-02 MW 162, 4 1 A42E+02 i!.42E+02 1,42E+02 MW-40-27 2 1.58E402 i,.17E+02 4 1.98E+02 MW-40-46: 4 1 .52E+02 1.52E+I02 i.52E+02 4

MW-40-81 4 1 ;74E+02 9.11 E+01 2.31iE402 MW-41740: 3 3 5.01 E+102 3.i5E+02 6.17E+02 SMW,41! .-63: 3 3 4:.72E+02 4,40E-+02 5.26E+02

.MW-42-49. 5 5. 1.58E+04 1 .28E+03 7.22E+04 MW-,42-78' 4 4 4.27E+02 :2.174E+02: 5.51E+02

.2 MW-43-28.! 3 :2'.44E+02 1:.73E+02 :3.14E+02 MW-43-62 3 1 .96E+02 1.96E+02 .96E+02 MW-44-102 4 4.34E+02 2.57E+02: 5.15E+02 MW-44-66: 4

.4 4.94E+02 2.06E+02 7.44E+02 MVV-45-42 4 4 2.95E+03 1.4, E+03 5.99E+03

Docket No. 50-3, 50-247, & 50-286 Page 45 of 49 Tritium Summary page 2 of 3

1. Pbsitive

1. 'Samples H-3 Samplies Av,g*Pos MinmPosq Max Pos in. 2009 Well Name 4in2009 Act Act Act U U MW-45-61 4 I'33E+03 1. 1:1 E+03 :1.46E+03 MW-46 4 .4 922E +02 7.56E-i02. 1:.10E+03 S3.:26E+03 3.156E+032 *3.56E+03 MW 26: 4 14 MW-49-42* .4 4 2..49E403 2.25E+03 2.68E+03:

MW+-49-65! 1 .66E+03 4 4 1552E+03 1 .4E'+03' MW-50-42' 4 4 I5.1 9E+02 1.06E+031

'5 5: *2 95E+03 2.30E+03 3.45E+03 MW-50-66.1 MW-*SI -04, 4 2 2.18E4-02 S1,44E402 2.91'E+02 4 3, 2,.08E+02 1.55E+02 2.67E+02 1.,.99E+0.2 1-.99E+02 .1.99E+ý02 MW-52-1.1 5.19E+02 5.19E+02 5.19E+02 MW-52-1 26 2 111.5E+02 '1 .i5E+02. 1..15E+'02 vMW-52-1`62: 4;92E+02 4.92E+02 MW-52.'18 2 .29E+02: 2.:29E+-02 MW-52-:181 27.29E'+02 1 .,47E+02 :1' .4E+02 1439E+02

'1 ,i.47..!E+O2 1,.43:E+/-02i MW-52-48, MW-53-1 201 4  :,4 1.2.

I.43E,+02 1 .43E+02 14 5.25E+03 5.05E+03 5.65E+03 MW-53-82ý 4 .3 1.911 E+03 6B64E+02 4.26E+103 MW-54-11 23 4 6.51 E+02 5.31 E+02 7.49E+02 MW-54-1!44:

1 .32E+03 1.13E+03 1.45E-÷03 MW-54-173 4 1.81 E+03 1 .57E+03 1.98E,+03 M*W-54-1 0: 1.75E+03 1.43E+03 2.01 Et03

.4 4 1 .36E+03 MW-54-3,7 4 4 I1..16E+03. 1.60E+03:

.MW-54-58; 4 7.40E+02 6.58E+02 8.38EL02 MW-55-24, 4 1.29E+03 1.04E+03 1.59E+03

,MW-55-35i A 2.19E+03 8.53E÷02 2.83E+03 4

MW-;55-54 .4 2 6.41 E+03 5.47E+03 7.33E+03 MW-56-53 2 5.93E+02 5.OOE+02 6.86E+02 MW-56.-83. 4 3.20E+03 3.15E+03 3.24E+03

• 4 ,4.22E+03 4.22E+03 4.22 E+03 MW-57:-20:

MW-57m-1 1 4 1 .52E+03 1.52E+ 03 1i.52E÷03 MW-57-45. 4 13 1.19E+03 1 .19E+03 1 .19E+03

• 4:

,MW-58-26, :3 4.52E+02 4. 3E+02 5.19Eo02 MW-58-65 A4 ,2.48E+t02 21331E+02 2.75E+02

4 MW-ý60-135. 4 4 3.41 E+/-02 3.17 E+02 3.83E+02 MW-GO-154s *4 3. 4.44E+02 4.09 E+02 5.13E+02

• MW-60-.176 MW-60-35 4 A. 1.00E+,03 9.16E÷02 1.04E÷03 MW-60-:53, 4: 2.30E+02 2.OOE,+02 2.60E+02

.4 3'.51 E+02 2.03E+02 4.99E+02 MW-60-72 4 1.71 E+02 1.67E+02 1.73E+02 MW-627-!38, 4 :6.51 E'+02 5.76E+02, 7.72,E+02 MW-62-21 8 ;4 3.60E+02 2 .36E+02. 4.64E+02 4 5.53E+02 4.66E+02, 7.36E+02.

MW-62-182 MW-62-37ý 4 3.56E+02 2I.7E+02. 4.87E+02 MW-62-53', 3.28E+02 2.40E+02 4.33E+02

Docket No. 50-3, 50-247, & 50-286 Page 46 of 49 Tritium Summary page 3 of 3

1. Positive

1. Samples, H-3 Samples Avg'Pos MimPos Max Pos Well Name in 2009 in 2009 Act Act Act MW62-71! 4 4 3.99E+02 2.99E+02 4.78E+02 MW-62-92' 4 4 4.74E+02 2q80E+02 6.08E+02 MW-63-i1 2! 4 4 4.60E+02 4.37E+02: 4.96E+o2 MW.-63;4121 4 4 :51.32E402 4.,66E+02 6.23E+02 MW-63-163 4 4 i5.59E-02 4.36E+02. 6.96E+02

.MW-63-74 4 4 4"67E+02 4.22E+02 4.98E+02 MW-63-18 4 2 2:89E+02 1.97E+02 3.80E÷02 MW-63-34 4 4 3.48E+02 3.;1OE02E40.240E+02 MWM63-50. 4 4 3.31 E+02 2.98E+02 3.60E-02 MW-63-93, 4 4 2:.68E+02 1.66E+02 :3.40E+02 MW066-21 5 4 .6.66E+02 4,.29E+02 9.51 E+02 MW-66-36 4 4 ý3.85E+03 3.05E÷03 4.39E+03 MW-67-1Q56 4 4 1.96E÷03 1.77E+03 -2.12E+03 MW-67-173 5 .5 8.07E+02 6.73E+02 I105E+03 MW-67-2i9 4 4, 1.13E+03 9.22E+02' 1.44E+03 MW-67-276 4 4 1.00E-03 9.17E+021 1.1OE+03 MW-67-323 4 4 3.94E-02 3.655E+02 4.21 E+02 MW-67-340 4 4 5.07E+02 4.70E+02 5.37E+02 MW-67-39 4 4 3.26E+03 2.69E+03 3,88E+03 U-CSS 3 3 2.59E+03 1.57E+03 3.28E+03 U3-4D*4 4 4.55E+02 3.82E÷02 4.82E+02 03-TV 4 4 44.455+02 328E+02 6.755÷02 U3-T2 4 4 1.04E+03 8.94E+02 1.12E+03*

Note 1: All results are:in,"pCi/L Note 2: A total of 431 samples were analyzed for H-3 in 2009, with 385 positive results.

Note63: A sample is positive if the result is greater thanhor eqUal at 3 times the 1'sigma uncertainty. The target MDCI isI200 pCiUL

Docket No. 50-3, 50-247, & 50-286 Page 47 of 49 Cobalt-60 Summary

1. Positive

1. Sampl!esý Samples in AvgPos. Min Pos Max Pos:

in 2009 ,2009 Act Act Act Well Name MW-42-49 5 I1 5.23E+00 5.23E+00 5.23E+00 I1 MW-44-66 4 3.09 E÷00 3.09E+00 MW-63-163 4 6.80E+00 6.80E+00 ,6.80E+00 Note 1:: All results are in pCifL Note 2: A total of 431 samhples were :analyzbd for-Co-60 in 2009 with 3rpositive.results.

Note 3: A sample is positive ifthe result is. greater than or equal to13 times.the I sigma uncertainty. Thetarget MDC' is1.5 pCi!L.

Nickel-63 Summary

1. Positive

1. Samples Samplesin Avg Pos Min Pos Max Pos Well Name in 20091 2009 .Act Act Act MWI-42-49 5 5 6.49E+02 7.46E+0.1 1.16&E03 MW-49-26" 4 I .2.31E+01 2.31 E+.01 2.31(E+01 MW-;67-173 5 1 8.40E+01 8.40E+01 8.40E+-01 MW-67-276 4 1 2.21 E+01 2.21i E+0ol Note 1: All results are in pCiIL Note,2: A total of 176 samples were analyzed for Ni-63 in 2009 with 8 positive results;.

Note,3: A sample is positive ifthe result is'greater than or equal to 3 timesthe 1 sigma uncertainty. The target MDC is 30 pCi/L.

Docket No. 50-3, 50-247, & 50-286 Page 48 of 49 Strontium-90 Summary page 1 of 2

1. Positive

1. sampl.es; Sr-90 Samples Avg Pos Min POS Max POs, Well'Name in 2009 in 2009* Act Act Act

ý2 I MW-1:11. 2 1.51 E+O00 8 46E-01 2.+17E+00 7 1 5.58E-01 5.58E-01 5.58E-01 MW-,31-49 7 7.67E-0l 5.59E-01 1.1OE+÷O0 8.00E-01 7 3 8.OOE-01 8.00E-01 MWM36-41 3 5.43 E+00- 4'.03E+00 7.11 2E+00 MW-36-52 4 3.50 E+00 2.40E-00 4.70E+00 MW-37-22+ 4 4 1.07E+01 8.8.1E+00 1.24E+01 MW-37-32 4 14 1.85E+01 1.11 E101 2.38E+01 4;

MW-W3-40 4 835E+00 1.1A1E+00 1.69E+01 MW-37-57 4 2 2.63E+01 1.99E+01 3A17E+01 1.24E+00 MW-39-1 02 2 2 1 .82E+00 2:40E+00 MW-39-11i24 2 1 .39E+00 9.1 6E-01 1.87E+00 1 6.89E-01 MW-39-:195 2 6.89E-01 6.89E-01 MW-739-67 2 2 2.86E+00 2.37E400 3.35E+O0

,MW-39-84 2 2: 1.58E+00 1.1,1 E+00 2.05E+00 MW-41-40 3 3: 4.56E+00 4.OOE+Q0 5.38E+00 MW-41-63. 3.54E+00 2.67E+00 4.08E+00 MW-42-49 3 5 3.09E+02 4.83E+00 6.77E+02 MW-43-62 4 3 9.36E-01 6.85,E&01 1 .241E+O0 MW-44-1.02 4 7.80E'-01 7.80E-01 7.80E601 MW-46 8.60E-01 8.60E-01 8.60E-01 4

MW-49-26; 1.36E÷01 11.23E+01 4 4 MW-49-42, 4 4 1.83E-01 1.74E÷01 21!07E+01

MW-49-65. 1,.35E+01 4 1.414E+01 1.73E+0:1 MW-50-42: 4.1 OE+00: 1.96E+00 6.73E+O0 4 1.5*

MW-5,0-66: 5 2.78E+01 2..42E+01' 3.OOE+O!

MW-53-1 20 4 4 2.77E+0i 2.37E+01 3.IOE+/-01 MW-53-821. 4 4 2.30E+00 .2.30E+00 2:30E+00 MW-54-1.23 4. 4.54E+00I 3.77E+00 5.91 E+00 MW-54,l 44: 1 .46E+01 1.43E+01 .1.51 E+01',

4 1 .o2 E+0i MW-54-17.34 4 8.85E+00: 7.42E+00 MW-54-1 90 1.96E001 1.9OE+01 1:,98E+01 4 4

.4, 15.53E+00 MW-54-37' 4 ,4 5.90E+00: 6.35E-+00 MW-54-258 4 24 I .`83E+00 1.41 E+. 0 2.'OOE6+0 MW-55-24 4 2.06E+01 1.55E+01 3.07E+01 Mw-55-35 4 3.06E+01 1.71 E+01: 4.,14E+01 2.64E+01 12,11E+01 MW555-54. 3.27E+01 MW-56-83. 2.75E+00 2.71 E+00 2,78E+00 MW-157-lI 4 4 4.72E+01 4.72E+01 4.72E+01 MWI-'57-2 0 4 2.77E+00 2 .77E+00 2.77E+00 MW-57-45 2.25E+00 ,2.25E+00 2.25E+00 MW-58-65 1 6.33E-01 6.33E-01 6,33E-01 MW-62-138 2.l OE+00 1.31 E+00 2.83E+00 MW-62-18 1 .09E+0Q A1.09E+0O 1.09E+40

Docket No. 50-3, 50-247, & 50-286 Page 49 of 49 Strontium-90 Summary page 2 of 2

1. Positive

1. Samples, S'r-90 Samples Avg Pos Mir Pos Max Pos Well.Name in 2009 in 2009. Act Act Act

-1 MW-63-1 21 4 1 7.30E-01; 7.30E-W01 7.30E-01 M.V*63-93. 4 .14 5.44E-01 5.44E-'01 5,44E-01 MW-66-36 4 9:31 E-+00. .6.82E4-00 1.22E+01 2 6.91 E-01 8.49E-01 MW-67-105 4 5.33E601 MW-67-39ý 4 4 1.13E+01 6.37E+/-00 1 .42E+01 u1 css ,3, 2.24E+01 1.41E+O1 3.56E+01 U3-Ti1 4 1J.04E+00. 1;04E+00 1.104ýE+O0 U3-T2 4 1 1.76E+00 1.76E+-00 1.76E+00 Note 1: All results are:in.pCiiL A total of 431 saMpleswere analyzed forSr-90 in 2009 Note 2:

with 145positive results.

Note 3:

A sample is positive if the..resuit is greater than or equal to 3 times.the 1 sigma, uncertainty. The target MDC is, 1 pCi/L.

Cesium-137 Summary

1. Positive

1. 'Samplesý Samples in Avg, Pos Min Pos Max Pos Well Name in: 2009: 2009 Act Act Act

-1 MW-30-84 6 8.97E+00 8,,97E+00 8.97E+00 MW-4 -ý40' 3 1 4.26 E+00 4.26E+0o 4!.26E+O00 MW-42-49 5 6.73E+04 5.42E+03 1 .40E+05 MW-43-62 3 11 8E+01 I1.8E01 MW-53-82 4 7.76E+00 7.76E+00 7.76.E+00 1

MW-55-241 4 1.03E+01 I.03E+01 1'.03E+01!

• MW-57-11 1 ,3.89E+00 3Z89E+00 3.89E+00 MW-60-1.54' 4 1 .34E+01 1.34E+01 1.34E+01 MW-66-21 5 1. 8.99E+01 8.99E+O0 8.99E+00:

MW-67-173 5 1 .34E+01 1.34E+01 1.34E+014 Note 1: All: results are. in pCi/L Note 2,: A total of:431. samples were analyzed for Cs--137 in 2009 with 14 positive results. . .

Note&3: A sample is positive if %theresult is' greater thanwor equal to 3 times the 1.sigma uncertainty: The target M DC. is; 18 pCiVL,