ML091260208

Annual Radioactive Effluent Release Report

ML091260208
Person / Time
Site:	Indian Point
Issue date:	04/17/2009
From:	Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
References
NL-09-045
Download: ML091260208 (51)

Text

ENCLOSURE 1 TO NL-09-045 2008 Annual Radioactive Effluent Release Report ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NOS. 1, 2, and 3 DOCKETS 50-3, 50-247 and 50-286 Docket No. 50-3, 50-247, & 50-286 Page 1 of 50 Radioactive Effluent Release Report: 2008 Facility Indian Point Energy Center (Indian Point Units 1, 2, and 3)Licensee Entergy Nuclear Operations, Inc (Enterqy)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/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 50 3. Average Energy The average energies (E) of the radionuclide activation gases were as follows: Units 1 and 2: mixtures in releases of fission and Unit 3: 1st Quarter 1 = 1.49E-01 Mev/dis 2nd Quarter I = 2.00E-01 Mev/dis 3rd Quarter I = 2.50E-01 Mev/dis 4th Quarter I = 3.53E-01 Mev/dis 1st Quarter I = 4.64E-01 Mev/dis 2nd Quarter PH = 4.63E-01 Mev/dis 3rd Quarter I = 4.35E-01 Mev/dis 4th Quarter F = 4.41 E-01 Mev/dis E y = 6.56E-02 Mev/dis E y = 2.41 E-01 Mev/dis= 3.13E-03 Mev/dis F y = 7.92E-01 Mev/dis Y = 1 .28E+00 Mev/dis E F = 1.28E+00 Mev/dis E Y = 1.17E+00 Mev/dis E Y = 1.20E+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 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 50 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 ODCMs. 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 50 5. Batch Releases Airborne: Unit I and 2 Airborne Releases Qtr 1 Qtr 2 Qtr 3' Qtr4 2008 Number of Batch Releases 49 64 40 48 201 Total Time Period (min) 4.35E+3 8.60E+3 2.54E+3 3.14E+3 1.86E+4 Maximum Time Period (min) 3.02E+2 4.35E+2 1.82E+2 1.51 E+2 4.35E+2 Average Time Period (min) 8.87E+1 1.34E+2 6.35E+1 6.53E+1 9.27E+1 Minimum Time Period (min) 5.OOE+0 2.OOE+0 4.OOE+0 2.OOE+0 2.OOE+0 Unit 3 Airborne Releases Qtr I Qtr 2 Qtr 3 Qtr 4" 2008 Number of Batch Releases 16 19 20 21 76 Total Time Period (min) 1.95E+3 2.31 E+3 2.28E+3 2.35E+3 8.90E+3 Maximum Time Period (min) 1.70E+2 1.69E+2 1.72E+2 1.90E+2 1.90E+2 Average Time Period (min) 1.22E+2 1.22E+2 1.14E+2 1.12E+2 1.17E+2 Minimum Time Period (min) 6.OOE+0 7.OOE+0 5.OOE+0 2.OOE+0 2.OOE+0 Liquid: Unit I and 2 Liquid Releases Qtr I Qtr 2 Qtr 3 Qtr 4 2008 Number of Batch Releases 19 16 10 9 54 Total Time Period (min) 1.58E+3 1.54E+3 1.55E+4 1.51E+3 2.01E+4 Maximum Time Period (min) 9.90E+1 1.91 E+2 5.90E+3 7.32E+2 5.90E+3 Average Time Period (min) 8.32E+1 9.62E+1 1.55E+3 1.67E+2 3.72E+2 Minimum Time Period (min) 2.OOE+1 5.OOE+1 8.40E+1 7.70E+1 2.OOE+1 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr-3 Qtr 4 2008 Number of Batch Releases 4 6 12 18 40 Total Time Period (min) 4.73E+2 6.71 E+2 1.32E+3 2.02E+3 4.49E+3 Maximum Time Period (min) 1.25E+2 1.18E+2 1.16E+2 1.23E+2 1.25E+2 Average Time Period (min) 1.18E+2 1.12E+2 1.10E+2 1.12E+2 1.12E+2 Minimum Time Period (min) 1.08E+2 1.06E+2 1.03E+2 9.70E+1 9.70E+1 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)2006 2007 2007 2007 Fourth First Second Third 93,200 92,100 95,280 16,600 Docket No. 50-3, 50-247, & 50-286 Page 5 of 50 6. Abnormal Releases a) Liquid Groundwater IPEC's groundwater monitoring program and the process (model) for quantification of effluent remained unchanged in 2008, from that of 2007.The resulting offsite dose as a result of the station's continuing natural attenuation was very small, similar to 2007'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 2008.Unit 1 Foundation Drain (80-10)In September, 2008, samples of a roof and footing drain system were initiated, per improvements in the site's IE Bulletin 80-10 program. Trace Cs-137 on the order of approximately 2E-7 uCi/mI was identified in the water.Since the precise discharge rate was not known, an investigation ensued to not only determine the source of the Cs-137 contamination, but to better quantify the release to the discharge canal. (The Radiological Environmental Monitoring Program includes a composite sampler at the discharge point).The most likely source of the Cs-137 is contamination related to legacy Unit 1 Pool leakage. Impact quantification and assessment was performed in accordance with the NRC's IE Bulletin 80-10.A very conservative assessment performed on this pathway yields an extremely low dose of less than one one-thousandth of the limit. The annual summary in Sections C and E include this conservative assessment.

b) Gaseous None.

Docket No. 50-3, 50-247, & 50-286 Page 6 of 50 7. ODCM Reportinc 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.ODCM Instrumentation:

During this reporting period, the following ODCM required effluent monitoring equipment was out of service (OOS) for periods greater than 30 consecutive days: Out of Service Instrument DtisPeriod Dea Troubleshooting and engineering was initiated to investigate excessive background in the channel.Sept 6, 2007 to No cause was determined.

The noise subsided in early R-14, Unit 3 backup Jun 10, 2008 2008, and the monitor appeared functional.

Since the plant vent noble gas primary monitor (the WRGM) has a good performance monitor (278 days) record, and the background problem has not returned, it was decided to accept the current condition and (161 days in 2008) return this monitor to service.No compensatory samples were required for this OOS condition (the primary monitor was operable).

The monitor assembly was taken OOS due to frequent loss-of-power problems.

Many internal parts were changed, but most of the spare parts installed were R-43/44,Unit2 Jan 2, 2008 later found to be defective.

Parts had to be re-ordered.

to plant vent t particulate and Feb 11, 2008 After multiple unsat tests, and parts replacements, prilae gasmondtr (each with long lead time from the vendor), monitor noble gas monitor (40 days) database was reloaded and passed retest.Compensatory samples were obtained as required during this interval.At the conclusion of a quarterly test, a Control Room annunciator was found inoperable.

A decision was Mar 7, 2008 then rendered to identify the monitor as OOS.R-46, Unit 3 admin to Scheduling and prioritization challenges from a building noble gas May 9, 2008 refueling outage delayed troubleshooting.

The monitor monitor was returned to service upon repair of the annunciator.

(63 days)Compensatory sampling was performed during the OOS interval.

Docket No. 50-3, 50-247, & 50-286 Page 7 of 50 Instrument Out of Service Details.... -Period ..The monitor was rendered officially inoperable due to a broken reset switch. There was an excessive delay in R-61, Unit 3 to obtaining the replacement contact block. The switch condensate polisher Jun 20, 2008 was replaced and monitor declared operable.TDS tank effluent Compensatory samples were obtained during the OOS ( y interval. (The ODCM requires this monitor only during a Primary to Secondary leak, which was NOT in effect.)The monitor was declared out of service due to a communication failure with the control room console, R,-59, Unit 3 leaving only a local readout, which was not radiation machine Aug 13, 2008 considered acceptable.

The failure was due to a riopvent machie gato severe electrical disturbance.

shop vent noble gas Oct 14, 2008 monitor and O 1 2 Multiple parts were found inoperative, with resulting process flow rate (62 days) delays for procurement and further troubleshooting.

instrument Compensatory samples were collected during the OOS interval.Monitors were OOS due to isolation of Service Water, required for weld repair on the Service Water Mixing Tee at the FCU SW outlet.Complications were discovered after the system was Sep 18, 2008 apart, involving Ultrasonic testing of piping.R-49/46/53, Unit 2 to In-house welding was selected to lower the OOS SGBD and FCU Nov 10, 2008 duration (the other option involved a 6-month lead SW monitors time with the vendor supplying a new part).(53 days)These monitors were tested and successfully returned to service at completion of the maintenance.

Compensatory samples were collected for the OOS interval.Discovered non-functional during quarterly test.Found faulty tank selector switch, which negated a successful actuation of potential ALARM functions Oct 6, 2008 (tank isolation).

While the monitor was functional, the to inability to perform an auto-action forced a declaration R-61, Unit 3 Jan 12, 2009 of OOS.condensate polisher TDS tank effluent (98 days) Long lead time of parts and planning were responsible (87 days in 2008) for the extended outage.Compensatory samples were completed during this interval.

No radioactivity was identified in this normally clean system.

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

Other Reporting Criteria: During this reporting period, no tank curie limits in outdoor tanks were exceeded.The two independent Process Control Programs for Indian Point Units 2 and 3 were merged and applied as a Entergy Fleet document during this reporting period.The IPEC ODCM was updated in June 2008 to include some administrative REMP and Groundwater program improvements.

Detailed ODCM update information is discussed in Section G. A full copy of the ODCM and its justification package is included as an addendum to this report.

Docket No. 50-3, 50-247, & 50-286 Page 9 of 50 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2008 Docket No. 50-3, 50-247, & 50-286 Page 10 of 50 TABLE 1A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES A Fission & Activation Gases Year Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2008 Est. Total% Error 1. Total Release Ci 1.13E+00 4.69E-01 ~ 7.18E-01 14.73E+01 I 1. Total Release I Ci I 1.13E+00 I 4.69E-01 I 4.50E+01 I 7.18E-01 1 4.73 E+O 1 2. Average release rate uC]/sec 1.44E-01 5.97E-02 5.66E+00 I_9.03E-02 11.501 B. lodines C. Particulates

1. Total Release, with Ci 1.28E-04 -1 28E-04 +-25 half-life

> 8 days _2. Average release rate uC /sec 1.61E-05 -4.04E-06 3. GrossA~pha Ci 2.14E-06 -2.14E-06 +25 D. Tritium 1 1. Total release I CiI 1.83E+00-2.42E+00 I_3.79E+00 I 1.82E+00 J9.86E 2. Average release rate u(a/sec 2.33E-01 3.08E-01 4.77E-01 2.29E-01 3.12E-01-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 11 of 50 TABLE IC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)Nuclides Released 1) Fission Gases Year Qtr 4 2008 Units Qtr I Qtr 2 Qtr 3 1Kr-85 I CiI I I 4.49E+01 ý 6.12E-01 I4.55E+01 I Total for Period Ci 0.OOE+00 0.I00-E+00 4.49E+01 6.12E-01 4.55E+01 2) lodines-1 31 Ci 0,00E+00 1-1-33 Ci 0.00E+00 1-135 Ci -0.OOE+00 Total for Period Ci 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 3) Particulates Cs-1 37 Ci 1.28E-04 1.28E-04 Total for Period Ci 0.OOE+00 0.OOE+00 1.28E-04 0.OOE+00 1.28E-04-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 12 of 50 TABLE IC INDIAN POINT 1 and 2 -BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)Nuclides Released 1) Fission Gases Ye ar 2008 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 1.53E-02 6.20E-02 3.01 E-02 5.73E-02 1.65E;01 Kr-85 Ci 4.42E-02 8.68E-03 5.29E-02 Kr-85 m Ci 7.87E-05 1.76E-03 3.57 E-04 9.42 E-04 3.13E-03 Kr-87 Ci 1.83E-05 1.09E-03 2.56 E-04 7.55 E-04 2.12E-03 Kr-88 Ci 4.66E-05 2.68E-03 6.73 E-04 1.71 E-03 5.10E-03 Xe-1 31m Ci 3.13E-03 1.74E-03 4.88E-03 Xe-1 33 Ci 1.03E+00 3.48E-01 2.48E-02 2.77E-02 1.43E+00 Xe-133m Ci 1.16E-02 4.33E-03 1.82E-04 5.35E-04 1.66E-02 Xe-1 35 Ci 2.40E-02 3.5 1E-02 5.64 E-03 1.51 E-02 7.98E-02 Xe-1 35m Ci 5.95E-05 2.92E-03 4.32 E-04 1.74 E-03 5.15E-03 Xe-1 38 Ci 1.50E-05 7.39E-04 3.36 E-04 1.09E-03 Ttal for Period Ci 1.13E+00 4.69E-01 6.24E-02 1.06E-01 1.77E+00 2) todlnes 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 50 TABLE 1A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES A Fission & Adivation Gases Year Est.Total 2008 %Bror B. lodines C. Particulates

1. Total Release, vJth -000E400 +2 half-life

> 8 days _2. Average release rate ua/sec -.OOE+00 3. Gross Apha Ci -.OOE+00 +25 D. Tritium 1. Total release Ci 3.04E+00 3.0E+00 3a43E+00 2.57E+00 1.20E+01 +25 2. Average release rate ua/sec 3.86E-01 3.82E-01 4.31E-01 3.24E-01 a8lE-01-Indcates < MDA Docket No. 50-3, 50-247,, & 50-286 Page 14 of 50 TABLE IC INDIAN POINT 3 -CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)Nuclides Released 1) Fission Gases Yea r 2008 Units Qtr I Qtr 2 Qtr 3 Qtr 4 je-1 33 I CiI-I I I0.00E+00I Total for Period Ci -0.00E+00 2) lodines 1-131 Ci -O.OOE+00-1 33 Ci -0,OOE+00-135 Ci -- 0.OOE+00 Total for Period Ci 0.0OE+00 3) Particulates Total for Period Ci ----0.OOE+00-indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 15 of 50 TABLE IC INDIAN POINT 3 -BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)Nuclides Released 1) Fission Gases Year 2008 Units Qtr I Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 1.54E-02 1.66E-02 1.79 E-02 1.82 E-02 6.81E-02 Kr-85 Ci ----0.OOE +00 Kr-85 m Ci ----0.001E+00 Kr-87 Ci ----0. OE +00 Kr-88 Ci ----0.OOE+00 Xe-1 31m Ci ----0.00E+00 Xe-1 33 Ci -6.96E-05 1.72E-03 1.38E-03 3.17E-03 Xe-1 33m Ci -- 0.00E+00 Xe-1 35 Ci ---0 .OOE+00 Xe-1 35m Ci 0.OOE+00 Total for Period Ci 1.54E-02 1 67E-02 1.96E-02 J 1.96E-02 I 7.13E-02 2) Iodines 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 50 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2008 Docket No. 50-3, 50-247, & 50-286 Page 17 of 50 TABLE 2A INDIAN POINT 1 and2 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES A. Fission & Activation Products 1. Total Release (not including Tritium, Gr Alpha, & Gases)2. Average Diluted Conc Units Ci ua/ml Year Est Total Qtrl Qtr2 Qtr3 Qtr4 2008 %Error 1.57E-02 2.01 E-02 1.24E-02 6.37E-03 5.46E-02 + 25 2.71E-11 2.95E-11 1.44E-11 8.85E-12 1.92E-11 I I -& -I -I -d. -I I -i B. Tritium 1. Total Release 2. Average Diluted Conc Ci I 6.42E+01 5.52E+01 6.16E+01 I 2.92E+01 2.1OE+02 uQ/ml I 1.11E-07 8.10E-08 7.14E-08 I 4.05E-08 7.39E-08 I I --I -I --I -C. Dissolved

& Entrained Gases D. GrossAlpha

1. Total Release I -+25 E. Volumeof Waste Released 1. ProcessedWaste(LW&NCD) liters 3.90E+06 2.10E+06 3.94E+06 2.16E+06 1.21E+07 + 10 2- Unprocessed(SGBDSFDS, LA1FD) liters 4.13E+07 5.62E+07 4.61E+07 4.79E+07 1.91E+08 + 10 IF. Volume of Dilution Water liters 5.79E+11 6.81 E+11 8.63E+11 7.19E+11 2.84E+2 I + 10-Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 18 of 50 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)CONTINUOUS RADIOACTIVE EFFLUENT Nuclides Released Yea r Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2008 Cs-137 Ci 9.82E-04 2.53E-03 1.77E-03 1.58E-03 6.86E-03 Ni-63 Ci -4.22 E-04 -4.22E-04 Sr-89 Ci -0.00E+00 Sr-90 Ci 1.20E-04 1.91 E-04 5.59E-04 7.84E-04 1.65E-03 Total for Period Ci 1.10E-033 3.14E-03 E-03 -03 2.36E-03 8.94E-03-Indicates<

MDA Docket No. 50-3, 50-247, & 50-286 Page 19 of 50 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan Dec 2008)BATCH RADIOACTIVE EFFLUENT Nuclides Released Ye ar 2008 Units Qtr I Qtr 2 Qtr 3 Qtr 4 Ag-110m Ci 2.02E-04 5.09 E-05 1.17E-04 -3.70 E-04 Co-58 Ci 2.81E-05 2.01E-03 1.51E-03 1.32E-04 3.68E-03 Co-60 Ci 3.95E-04 6.87E-04 9.24E-04 3.70E-05 2.04E-03 Cr-51 Ci 1.85E-04 -I 1.85E-04 Cs-134 Ci 5.80E-05 1.52E-04 2.93E-04 1.33E-05 5.16E-04 Cs-137 Ci 8.50E-04 9.07E-04 4.64E-03 2.43E-04 6.64E-03 Mn-54 Ci 2.55E-06 1.90E-05 7.64E-06 2.92 E-05 Ni-63 Ci 3.89E-03 3.35E-03 6.52E-04 5.74E-04 8.46E-03 Sb-124 Ci 1.1OE-05 4.33E-04 -4.44E-04 Sb-125 Ci 8.99E-03 7.12E-03 1.95E-03 3.01E-03 2.11E-02 Sr-90 Ci --1.61E-05 1.61 E-05 Te- 123m Ci 2.13 E-05 -2.13E-05 Te-125m Ci 2.19 E-03 2.19E-03 Total for Period Ci 1.46E-02 1.69E-02 1.01E-02 4.01E-03 4.57E-02 Dissolved

& Entrained Gas t .I*IKr-85 I Ci i-3.58E-02* 4. 4 IXe-133.Ci 1.63E-03 1.13E-05 U -! ~9 -I -I Total for Period Ci 1.63E-03 1.13E-05 3.58E-02 a & i Indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 20 of 50 TABLE 2A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES A. Fission & Activaton Products 1. Total Release (not including Tritium, Gr Alpha, & Gases)2. Average Diluted Conc Year Units Qtr I Qtr 2 Qtr 3 Qtr 4 2008 Ci 2.44E-04 2.00E-03 5.49E-03 6.54E-03 1.43E-02 ui/ml 4.22E-13 2.93E-12 6.37E-12 9.09E-12 5.02E-12 Est Total% Error+ 25 h I -A --A I II-B. Tritium I -* -.-.-S S -1. Total Release 2. Average Diluted Conc Ci 1.88E+01 7.49E+01 8.13E+01 4.92E+02 6.67E+02 uai/ml 3.24E-08 1.10E-07 9.42E-08 6.84E-07 2.35E-07 h I -A -A -A -I I -C. Dissolved

& Entrained Gases D. Gross Alpha 1. Total Release Ci I ---0o0E+00 + 25l E. Volume of Waste Released 1. Processed Fluids(vlnnTanks) liters 1.04E+05 1.56E+05 3.08E+05 4.66E+05 1.04E+06 + 10 2. Unprocessed Fluids (SGs) liters 1.62E+06 1.62E+06 1.64E+06 1.64E+06 6.52E+06 + 10 IF. Volume of Dilution Water liters 5.79E+1 1 6.81E+11 8.63E+11 I7.19E+11 2.84E+12 _ 10'- indicates

< MDA Docket No. 50-3, 50-247, & 50-286 Page 21 of 50 TABLE 2B LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT INDIAN POINT 3 BATCH Batc Rsdon/Adwvaion roducts Units Qtr 1 Qtr 2 Qtr 3 Qtr4 2008 Ag-110m Ci 8.OOE-05 2.60E-05 1.06E-04 Co-58 Ci 6.90E-06 1.31E-05 2.18E-05 2.33E-05 6.51 E-05 Co-60 Ci 2.69E-05 9.35E-04 1.69E-03 1.56E-03 4.22 E-03 Cs-134 Ci -1.02E-04 9.61E-05 1.98E-04 Cs-137 Ci -2.50E-04 2.90E-04 5.40E-04 Fe-55 Ci -1.14E-03 7.28E-04 1.87 E-03 Mn-54 Ci -1.63E-05 3.07E-05 1.07E-05 5.77E-05 Ni-63 Ci 1.52E-04 8.36E-04 1.97E-03 2.26E-03 5.22 E-03 Sb -125 Ci 5.87E-05 1.1 9E-04 2.60E-04 1.57E-03 2.00 E-03 Total for Period Ci 2.44E-04 2.OOE-03 5.49E-03 6.54E-03 1.43E-02 Dissolved and Entrained Gas (Batch)Kr-85 Ci --O.E00 Xe-133 Ci -4.96E-05 4.96E-05 Xe-133m Ci -0.OOE+00 Tal for Period Ci 0.OOE+00 0.OOE+00 0.OOE+00 4.96E-05 4.96E-05 Continuous Releases (SG Blowdown)I H-3 (only) I c, 4.02E-03 I 4.35E-03 5.43E-03 I4.OOE-03 1.7E-0'- indicates

< mda Docket No. 50-3, 50-247, & 50-286 Page 22 of 50 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2008 Docket No. 50-3, 50-247, & 50-286 Page 23 of 50 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2008 to 12/31/2008 Percent Cutoff: 0 (all identified isotopes are included)Waste Stream: Resins, Filters, and Evap Bottoms LWS Resin Plant Resin 8-120 Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Shipped A 1.0 8E+ 02 3.06E+ 00 1.0 1 E-0 1 +/-25%B 3.7 1E+02 1.05E+01 7.27E+0 1 +/-25%C 8.50E+01 2.41E+00 2.36E+02 +/-25%All 5.64E+02 1.60E+01 3.09 E+0 2 +/-25%Waste Stream : DryActiveWaste DAW /Equip DAW/Dirt;B-25 Box DAW 20' Sea Land IF200 Cask Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Sh ipped A 2.4 5E+ 04 6.93E+02 7.78 E+0 0 +/-25%B 0.0 0E+ 00 0.00E+ 00 0.00E+00 +/-25%C 0.0 0E+ 00 0.00E+ 00 0.00 E+0 0 +/-25%All 2.4 5E+ 04 6.93E+02 7.78 E+0 0 +/-25%Waste Stream : Irradiated Components Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Shipped A 0.0 0E+ 00 0.00 E+ 00 0.00E+00 +/-25%B 0.0 0E+ 00 0.00E+00 0.00E+00 +/-25%C 0.0 0E+ 00 0.00E+00 0.00E+00 +/-25%All 0.0 0E+ 00 0.00E+00 0.00E+00 +/-25%Waste Stream: OtherWaste Combined Packages River Silt- Intermodal Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Sh ipped A 3.2 8E+ 03 9.29E+01 9.2 0E-0 4 +/-25%B 3.0 OE+ 01 8.48E-01 2.17 E+0 1 +/-25%C 0.0 0E+ 00 0.00E+ 00 0.00E+00 +/-25%All 3.3 1E+03 9.37E+ 01 2.17 E+0 1 +/-25%Waste Stream : Sum of All4 Categories Combined Packages: DAW/Dirt; B-25 Box DAW 20' Sea Land LW S Resin IF 200 Cask River Silt -Intermodal DAW-/ Equip Plant Resin 8-120 Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Sh ipped A 2.79E+04 7.89E+02 7.88E+00 +/-25%B 4.0 1 E+ 02 1.14E+01 9.44 E+0 1 +/-25%C 8.5 0E+ 01 2.41 E+ 00 2.36 E+0 2 +/-25%All 2.84E+04 8.03E+ 02 3.38 E+0 2 +/-25%Combined Waste Type Shipment, Major Volume Waste Type Shown Docket No. 50-3, 50-247, & 50-286 Page 24 of 50 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2008 to 12/31/2008 Percent Cutoff: 0 Number of Shipments 18 2 10 2 5 Mode of Transportation Hittman Transport Hittman Transport Horwith Trucks Studsvik Logistics Hittman Transport Destination Energy Solutions

-Bear Creek Energy Solutions

-GRF Studsvik Processing

-Memphis Studsvik Processing

-Memphis Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Fe-55 Co-60 Ni-63 Sr-90 Cs-137 Ce-144 Pu-238 Pu-239 Am-241 Cm-243 Percent Abundance 0.01%0.30%1.84%0.02%97.70%0.13%0.00%0.00%0.00%0.00%Curies 1.05E-05 3.09E-04 1.86E-03 1.98E-05 9.90E-02 1.30E-04 7.01 E-08 1.03E-07 1.75E-07 4.48E-09 Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Ag-110m Sb-1i24 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.15%0.18%28.16%0.08%0.32%3.78%28.99%0.13%0.17%0.00%0.05%7.10%30.36%0.52%0.00%0.00%0.01%0.00%0.00%0.00%Curies 1.07E-01 1.34E-01 2.05E+01 5.80E-02 2.31 E-01 2.75E+00 2.11E+01 9.82E-02 1.21E-01 3.76E-04 3.29E-02 5.17E+00 2.21 E+01 3.80E-01 2.91 E-04 1.31 E-04 6.51 E-03 1.48E-04 1.23E-05 1.53E-04 Docket No. 50-3, 50-247, & 50-286 Page 25 of 50 Resins, Filters, and Evap Bottoms Waste Class C.Nuclide Name Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Cs-1 34 Cs-1 37 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Ag-110m Sb-124 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Dry Active Waste Waste Class A Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Percent Abundance 0.28%3.78%0.05%0.09%.6.10%37.51%0.09%16.91%34.84%0.30%0.00%0.00%0.02%0.00%0.00%0.00%Percent Abundance 0.03%0.26%9.52%0.06%0.15%5.54%35.63%0.10%0.04%0.00%0.01%14.61%33.68%0.35%0.00%0.00%0.02%0.00%0.00%0.00%Curies 6.55E-01 8.92E+00 1.22E-01 2.19E-01 1.44E+01 8.85E+01 2.16E-01 3.99E+01 8.22E+01 7.14E-01 2.30E-03 6.71 E-04 5.84E-02 4.70E-04 6.78E-05 1.36E-03 Curies 1.07E-01 7.89E-01 2.94E+01 1.80E-01 4.50E-01 1.71E+01 1.10E+02 3.14E-01 1.21E-01 3.76E-04 3.29E-02 4.51E+01 1.04E+02 1.09E+00 2.59E-03 8.02E-04 6.49E-02 6.18E-04 8.02E-05 1.52E-03 Percent Abundance 5.71%0.87%0.75%0.00%0.13%4.98%22.25%Curies 4.44E-01 6.75E-02 5.86E-02 1.30E-04 9.81 E-03 3.87E-01 1.73E+00 Ni-63 Sr-89 Sr-90 Nb-95 Ag-110m Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 1.21%0.00%0.10%0.00%0.37%0.63%8.73%54.27%0.00%0.00%0.00%0.00%0.00%0.00%0.00%Docket No. 50-3, 50-247, & 50-286 Page 26 of 50 9.40E-02 1.46E-06 7.91E-03 1.58E-05 2.88E-02 4.89E-02 6.79E-01 4.22E+00 6.94E-05 1.23E-05 6.30E-06 1.61E-04 3.89E-05 1.48E-07 6.94E-06 Dry Active Waste 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 Nb-95 Ag-110m Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Other Waste Waste Class A Nuclide Name Fe-55 Co-58 Co-60 Ni-63 Sr-90 Cs-137 Percent Abundance 5.71%0.87%0.75%0.00%0.13%4.98%22.25%1.21%0.00%0.10%0.00%0.37%0.63%8.73%54.27%0.00%0.00%0.00%0.00%0.00%0.00%0.00%Curies 4.44E-01 6.75E-02 5.86E-02 1.30E-04 9.81 E-03 3.87E-01 1.73E+00 9.40E-02 1.46E-06 7.91E-03 1.58E-05 2.88E-02 4.89E-02 6.79E-01 4.22E+00 6.94E-05 1.23E-05 6.30E-06 1.61E-04 3.89E-05 1.48E-07 6.94E-06 Percent Abundance 12.06%1.33%36.60%30.52%0.27%19.23%Curies 1.11E-04 1.22E-05 3.37E-04 2.81 E-04 2.46E-06 1.77E-04 Docket No. 50-3, 50-247, & 50-286 Page 27 of 50 Other Waste Waste Class B Nuclide Name Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Other Waste Waste Class All Nuclide Name Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.33%3.93%0.06%0.25%6.13%36.67%0.09%17.92%34.23%0.37%0.00%0.00%0.02%0.00%0.00%0.00%Curies 7.22E-02 8.53E-01 1.39E-02 5.37E-02 1.33E+00 7.96E+00 1.95E-02 3.89E+00 7.43E+00 8.05E-02 2.07E-04 6.03E-05 5.31E-03 4.23E-05 9.16E-06 1.23E-04 Curies 7.22E-02 8.53E-01 1.39E-02 5.37E-02 1.33E+00 7.96E+00 1.95E-02 3.89E+00 7.43E+00 8.05E-02 2.07E-04 6.03E-05 5.31 E-03 4.23E-05 9.16E-06 1.23E-04 Percent Abundance 0.33%3.93%0.06%0.25%6.13%36.67%0.09%17.92%34.23%0.37%0.00%0.00%0.02%0.00%0.00%0.00%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-89 Sr-90 Nb-95 Percent Abundance 5.64%0.86%0.74%0.00%0.12%4.91%21.96%1.22%0.00%0.10%0.00%Curies 4.44E-01 6.75E-02 5.86E-02 2.52E-04 9.81 E-03 3.87E-01 1.73E+00 9.62E-02 1.46E-06 7.93E-03 1.58E-05 Ag-110m Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 0.37%0.62%8.62%54.83%0.00%0.00%0.00%0.00%0.00%0.00%0.00%Docket No. 50-3, 50-247, & 50-286 Page 28 of 50 2.88E-02 4.89E-02 6.79E-01 4.32E+00 1.99E-04 1.23E-05 6.40E-06 1.61 E-04 3.90E-05 1.48E-07 6.95E-06 Sum of All 4 Categories Waste Class B Nuclide Name C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Ag-11im Sb-124 Sb-1i25 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 C Nuclide Name Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.11%0.22%22.57%0.08%0.30%4.33%30.73%0.13%0.13%0.00%0.03%9.61%31.26%0.49%0.00%0.00%0.01%0.00%0.00%0.00%Percent Abundance 0.28%3.78%0.05%0.09%6.10%37.51%0.09%16.91%34.84%0.30%0.00%0.00%0.02%0.00%0.00%0.00%Curies 1.07E-01 2.07E-01 2.13E+01 7.19E-02 2.85E-01 4.09E+00 2.90E+01 1.18E-01 1.21E-01 3.76E-04 3.29E-02 9.07E+00 2.95E+01 4.61E-01 4.98E-04 1.91 E-04 1.18E-02 1.90E-04 2.15E-05 2.77E-04 Curies 6.55E-01 8.92E+00 1.22E-01 2.19E-01 1.44E+01 8.85E+01 2.16E-01 3.99E+01 8.22E+01 7.14E-01 2.30E-03 6.71 E-04 5.84E-02 4.70E-04 6.78E-05 1.36E-03 Docket No. 50-3, 50-247, & 50-286 Page 29 of 50 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 Nb-95 Ag-110m Sb-124 Sb-1i25 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.13%0.05%0.27%8.92%0.06%0.26%5.97%34.86%0.00%0.10%0.00%0.04%0.00%0.02%14.65%34.27%0.35%0.00%0.00%0.02%0.00%0.00%0.00%Curies 4.44E-01 1.74E-01 9.20E-01 3.02E+01 2.04E-01 8.91 E-01 2.02E+01 1.18E+02 1.46E-06 3.42E-01 1.58E-05 1.49E-01 3.76E-04 8.17E-02 4.96E+01 1.16E+02 1.18E+00 2.81E-03 8.69E-04 7.04E-02 7.OOE-04 8.95E-05 1.65E-03 Docket No. 50-3, 50-247, & 50-286 Page 30 of 50 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2008 to 12/31/2008 Percent Cutoff: 0 (all identified isotopes are included)Waste Stream : Resins, Filters, and Evap Bottoms LWS Resin 14-1 70 Waste Volume Cu ries % Error (Ci)C lass ft 3 m 3 Sh ipped A 0.0OE+00 0.OOE+00 0.00E+00 +/-25%B 1.3 0E+ 02 3.68E+ 00 8.47 E+0 1 +/-25%C 0.0 OE+00 0.OOE+ 00 0.00 E+0 0 +/-25%All 1.3 0E+02 3.68E+ 00 8.47 E+0 1 +/-25%Waste Stream : DryActive Waste Unit 3 DAW-20'Sealand DAW 40' Sea Land Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Shipped A 6.5 0E+ 02 1.84E+ 01 4.5 4E-0 5 +/-25%B 0.0 OE+ 00 0.OOE+ 00 0.00 E+0 0 +/-25%C 0.0 OE+ 00 0.OOE+ 00 0.00 E+0 0 +/-25%All 6.5 0E+02 1.84E+01 4.54E-0 5 +/-25%Waste Stream

• Irradiated Components Waste Volume Cu ries % Error (Ci)C lass ft 3 m 3 Sh ipped A 0.0 OE+ 00 0.OOE+ 00 0.00 E+0 0 +/-25%B 0.0 OE+00 0.OOE+00 0.00 E+0 0 +/-25%C 0.0 OE+00 0.OOE+00 0.00 E+0 0 +/-25%All 0.0 )E+00 0.OOE+00 0.00 E+0 0 +/-25%Waste Stream

• Other Waste Combined Packages Waste Volum e Curies % Error (Ci)C lass ft 3 m 3 Shipped A 0.0 OE+ 00 0.OOE+ 00 0.00 E+0 0 +/-25%B 0.0 OE+00 0.OOE+00 0.00 E+0 0 +/-25%C 0.0 OE+ 00 0.OOE+ 00 0.00 E+0 0 +/-25%All 0.0 OE+00 0.OOE+00 0.00 E+0 0 +/-25%Waste Stream

• Sum of All4 Categories Unit 3 DAW-20'Sea'land LW S Resin 14-170 Combined Packages DAW 40'Sea Land Waste Volume Curies % Error (Ci)C lass ft 3 m 3 Sh ipped A 6.5 0E+ 02 1.84E+ 01. 4.5 4E-0 5 +/-25%B 1.3 OE+ 02 3.68E+ 00 8.47 E+0 1 +/-25%C 0.0 OE+ 00 0.OOE+ 00 0.00 E+0 0 +/-25%All 7.80E+02 2.21 E+01 8.47 E+0 1 +/-25%Combined Waste Type Shipment, Major Volume Waste Type Shown Docket No. 50-3, 50-247, & 50-286 Page 31 of 50 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2008 to 12/31/2008 Percent Cutoff: 0 Number of Shipments 2 1 Mode of Transportation S-J Transportation Hittman Transport Destination Perma-Fix of Florida Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Am-241.Cm-242 Cm-243 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-90 Sb-125 Cs-1 34 Cs-137 Ce-144 Pu-238 Pu-239 Am-241 Cm-242 Cm-243 Dry Active Waste Waste Class A Nuclide Name Co-60 Cs-137 Percent Abundance 0.02%2.23%22.55%0.05%0.07%11.09%27.86%0.03%0.93%11.07%23.85%0.24%0.00%0.00%0.00%0.00%0.00%Percent Abundance 0.02%2.23%22.55%0.05%0.07%11.09%27.86%0.03%0.93%11.07%23.85%0.24%0.00%0.00%0.00%0.00%0.00%Percent Abundance 18.19%81.81%Curies 1.32E-02 1.89E+00 1.91E+01 4.32E-02 6.17E-02 9.39E+00 2.36E+01 2.43E-02 7.86E-01 9.38E+00 2.02E+01 2.07E-01 4.99E-05 1.48E-05 4.89E-05 4.02E-05 1.99E-04 Curies 1.32E-02 1.89E+00 1.91E+01 4.32E-02 6.17E-02 9.39E+00 2.36E+01 2.43E-02 7.86E-01 9.38E+00 2.02E+01 2.07E-01 4.99E-05 1.48E-05 4.89E-05 4.02E-05 1.99E-04 Curies 8.25E-06 3.71 E-05 Docket No. 50-3, 50-247, & 50-286 Page 32 of 50 Dry Active Waste Waste Class All Nuclide Name Co-60 Cs-137 Percent Abundance 18.19%81.81%Sum of All 4 Categories Waste Class A Nuclide Name Co-60 Cs-1 37 Sum of All 4 Categories Waste Class B Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Am-241 Cm-242 Cm-243 Sum of All 4 Categories Waste Class All Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Am-241 Cm-242 Cm-243 Percent Abundance 18.19%81.81%Percent Abundance 0.02%2.23%22.55%0.05%0.07%11.09%27.86%0.03%0.93%11.07%23.85%0.24%0.00%0.00%0.00%0.00%0.00%Percent Abundance 0.02%2.23%22.55%0.05%0.07%11.09%27.86%0.03%0.93%11.07%23.85%0.24%0.00%0.00%0.00%0.00%0.00%Curies 8.25E-06 3.71 E-05 Curies 8.25E-06 3.71E-05 Curies 1.32E-02 1.89E+00 1.91 E+01 4.32E-02 6.1 7E-02 9.39E+00 2.36E+01 2.43E-02 7.86E-01 9.38E+00 2.02E+01 2.07E-01 4.99E-05 1.48E-05 4.89E-05 4.02E-05 1.99E-04 Curies 1.32E-02 1.89E+00 1.91E+01 4.32E-02 6.17E-02 9.39E+00 2.36E+01 2.43E-02 7.86E-01 9.38E+00 2.02E+01 2.07E-01 4.99E-05 1.48E-05 4.89E-05 4.02E-05 1.99E-04 Docket No. 50-3, 50-247, & 50-286 Page 33 of 50 Indian Point Energy Center (Units 1, 2, and 3)RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2008 -Dec 31, 2008 Docket No. 50-3, 50-247, & 50-286 Page 34 of 50 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 estimated using data generated at IP3 from August 1980 to June 1982 after a study conducted by the NY State Department of Health.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 the maximum dependable gross electrical capacity, which is approximately 1000 MW(e) maintained for the entire year.The resultant bounding doses are based upon site specific assumptions of source term released for an entire year at 1000 MW(e) output, as outlined in the ODCM.The resulting annual dose to the maximally exposed individual (child) from gaseous releases of C-14 is 0.254 mRem to the critical organ (bone) and 0.0508 mRem to the total body. The annual dose to the maximally exposed individual (child) from liquid releases of C-14 is 0.00583 mRem to the critical organ (bone) and 0.00117 mRem to the total body. These curies and doses are reported in this section (and not in the earlier tables), specifically to avoid confusion.

The data is listed separately from other isotopes (in the familiar table format) to preserve consistency with the format of Reg Guide 1.21 and the listed isotopes of concern, which do NOT include C-14.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 50 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: example 2: Several students visit the site for an 8-hour guided tour.Their occupancy factor is: 8 / 8760 or .0009.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 2008: Routine Airborne Effluents Units 1 and 2 2.07E-3 2.67E-3 Routine Liquid Effluents Units 1 and 2 6.11 E-4 1.47E-3 Routine Airborne Effluents Unit 3 1.99E-3 1.99E-3 Routine Liquid Effluents Unit 3 1.56E-4 2.83E-4 Carbon-14 Liquid & Airborne Totals IPEC 5.20..0 " 2.60E-01 Ground Water& Storm Drain Totals IPE5' 2.86E-04 9.35E-04 Direct Shine from ISFSl, Radwaste IPEC 2 <66 Storage, SG Mausoleum, etc.- I Indian Point Energy Center Total Dose, per 40 CFR 190 Note 1: Groundwater curie and dose calculations are provided in Section H.Note 2: 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 50 INDIAN POINT UNITS 1 and 2 NUCLEAR POWER PLANTS RADIOLOGICAL IMPACT ON MAN JANUARY -DECEMBER 2008 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES T ___ r ___ 1 I Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 3.47E-04 3.93E-04 4.04 E-04 3.81E-04 1.47E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 6.94E-03 7.86 E-03 8.08 E-03 7.62E-03 1.47E-02 Age Group Child Child Child Adult Child Critical Organ Bone Bone Bone Bone Bone Adult Total Body (mrem) 1.03E-04 1.49E-04 2.25E-04 1.34E-04 6.11E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 __3 Percent of Limit (%) 6.87E-03 9.93E-03 1.50E-02 8.93E-03 2.04E-02 B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 3.16E-05 3.79E-05 4.95E-05 2.66E-05 .1.46E-04 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 6.32E-04 7.58E-04 9.90E-04 5.32E-04 1.46E-03 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 9.17E-04 4.99E-04 6.17E-02 1.97E-04 3.17E-02 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 3.07E-04 4.05E-04 1.65E-03 3.05E-04 I 2.67E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 4.09E-03 5.40E-03 2.20E-02 4.07E-03 1.78E-02 Ag e Group Child cChild Child Child Child Critical Organ Liver Liver Liver Liver I Liver Docket No. 50-3, 50-247, & 50-286 Page 37 of 50 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY -DECEMBER 2008 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Qtrl Qtr 2 Qtr 3 Qtr4 ANNUAL I Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 7.84E-06 3.99E-05 1.07E-04 1.32E-04 r 2.83E-04 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 1.57E-04 7.98 E-04 2.14 E-03 2.63E-03 2.83E-03 Age Group Child Adult Child Child Child Critical Organ Bone GILLI Bone Bone L Bone Adult Total Body (mrem) 4.26E-06 1.64 E-05 2.96E-05 1.06E-04 1.56E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3 3 Percent of Limit (%) 2.84E-04 1.10E-03 1.97E-03 7.07E-03 5.21E-03 B. AIRBORNE NOBLE GAS DOSES Qtr I Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 4.29E-06 5.01 E-06 5.07E-06 5.OOE-06 1.94E-05 Applicable Limit (mrad) 5 5 5 5 -10 Percent of Limit (%) 8.58E-05 1.OOE-04 1.01 E-04 1.OOE-04 1.94E-04 I Beta Air (mrad) 7.08E-06 8.26E-06 8.53E-06 8.38E-06 3.23E-05 J Applicable Limit (mrad) 10 10 10 10 20 I Percent of Limit (%) 7.08E-05 8.26 E-05 8.53E-05 8.38E-05 1.61 E-04 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 5.02E-04 4.96E-04 5.67 E-04 4.25E-04 1.99E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 6.69E-03 6.61E-03 7.56E-03 5.67E-03 1.33E-02 IAge Group I Child I ChildI Child Child Child I Critical Organ Liver Liver Liver Liver I Liver Docket No. 50-3, 50-247, & 50-286 Page 38 of 50 Indian Point Energy Center (Units 1, 2, and 3)RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2008 -Dec 31, 2008 This data is stored onsite and is available in printed or electronic form.

Docket No. 50-3, 50-247, & 50-286 Page 39 of 50 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 2008 There were no changes to REMP sampling locations in year 2008.There were no changes to the Land Use Census in year 2008.IPEC was added to the Entergy Fleet Process Control Program (PCP) in 2008.In July, 2008, IPEC was added to the Entergy Fleet Process Control Program, EN-RW-105, Revision 1, per a combined fleet 10CFR50.59 review process. The Entergy Fleet PCP is attached to this report as an addendum.There was one ODCM update in 2008.In June, 2008 the station ODCM was upgraded to revision 1. This revision made some minor changes to the Table of Contents and REMP Table D3.5.1-1.

Additionally, Ni-63 data was added to Tables 3.5.1-2 and 3.5.1.3, and Section D5.6 was expanded to more completely describe the Radiological Groundwater Monitoring Program.Updates to Part 2 included a modification to section 2.1.16 to reference a new Attachment for detailed Groundwater monitoring, Existing REMP sample nomenclature (lal-1a4) was added to Appendix G, and references to a discontinued air sampling station at the dismantled Lovett Power Station were removed. Also included in this ODCM revision is the identification of a historical sampling location (Cold Spring Hudson River) as a "control location" in Appendix G, and an updated Appendix J, for Groundwater, with a more detailed description of groundwater flow and dose determinations.

The revised ODCM and the justification package for the updates are provided in an Addendum to this report. All historical revisions to the station's ODCM remain available on site.

Docket No. 50-3, 50-247, & 50-286 Page 40 of 50 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, 2008 -Dec 31, 2008 Docket No. 50-3, 50-247, & 50-286 Page 41 of 50 Summary of IPEC Groundwater and Storm Water Activity, 2008 The Unit 1 Spent Fuel, which has 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.The period to offload the fuel, necessitated some time of known and expected increased leakage into groundwater, as the pool water height was increased for offload operations.

Wells near the Unit 1 pool did in fact start to show somewhat elevated activity, as expected, by the end of 2008.This activity is expected to peak and subside, per natural attenuation plans, in the coming months, as all of the old fuel assemblies have now been removed from Unit 1, and the pools are empty.The precipitation mass balance model applied in 2007 was applied for offsite dose calculations in 2008. 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 2.92 feet per year. No changes to the model were required.

The ODCM was updated in 2008 to include more details of the Ground Water Monitoring Program. These updates are discussed in Section G of this report, and in the addendum for the ODCM update, and reflect both the requirements of the GW Monitoring Program, and specifics on calculating offsite dose.Results of 2008 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, it is estimated that approximately 0.2 Curies of Tritium migrated directly to the river via the GW flow path in 2008, resulting in an approximate total body dose of less than 0.1 mrem (2.2E-7 mrem). It is evident that tritium alone, whether from ground water or routine effluents, does not significantly add to offsite dose.Strontium-90, Cesium-137, and Co-60 collectively contributed approximately 0.00016 curies to site effluent from the groundwater pathway. Combined groundwater releases from IPEC in 2008 (all radionuclides) resulted in a calculated annual dose of less than 0.1 mrem to the whole body and critical organ: 0.000286 mrem to the total body, (<0.01% limit)0.000935 mrem to the critical organ, adult bone (<0.01% 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 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 50 IPEC Summairyfor Storm & Ground Water releases (H-3, Co-60,Ni-.63, Sr-90,:and Cs-137): Northern Clean Zone.Adult Doses~in rero'ISOTOPE BONEý J LIVER' TJO- HODY, T;HYROID ~ KIDNEY< ZLUNG (GI:ILr 7 I H-3 0 OOE+00 4 64E-09 4.64E-09 .4.64E-09 4&094.64&

09_4:64E09 Co-60ý 0.OOE+00 0.00E+00 0 00E+00 .,OE0 0.00E+0 E09 0 OO4.6 00 'OO6E-O00 I

_00E+00_,_:

O0,0E+-00 0.OOE+000,÷Oi." Ni63 0 00E+00 0.OOE+00 0 0.0E+00 0.OOE+00 0:00&E00 l [ Sr-90 0 00E+00 0;OOE+00 1: 0M:0 E+00 '0.OOE+00 0.OOE+O 0.00E4-000 1,0.00E+00 Cs-137' -.OOE+0 0 .0 00 7OoE+00 0,0E+00 0.O0E+00 O:00E+001

0Q00E+00, totals-. 10.:OOE+0.

1 4.64E&09 .4,64E-09 *464E-09 ';4.64E&09 464E-09 , 4.64EL09 Unit:2: North _ISOTOPE' BONE LIVER TOT BODY> THYROID~ KIDINEY ~ LUNG GI-LLI-H-3 I 0O.E+00 1,44E-08 1 44E08 1,44E-08 ,1,44E-08 1,44E-08 1,44E-08/ o-6 0!OOE+00 0 OOE+o00 00E+00 '0 .0E00 &000E+000

,,00E+00 00E+00 Ni-63ý 0 OOE+00 0 OOE+00 01OOE+00 0 00E+-00 0.00E+00" 9.00E+00 D'0.0E4-00 sr-90ý 0 00E+007 ~ .OOE+00 0 0 0 &00E+00 .000E+00 0.OOE+00 0:OOE+00 0100E+00 Cs-137 0 OE08:C 00E+007 0 0E+00. -05OOE+00 0.001E+00 0.00E+00 ~0.00E+00-totals, 1 ..00 .1144E&08 7777E708 1.44Eý08 1.44E-08 1.44E-08 1.44E-08 Unit 112 _'i SPTOIPE. .OEM 4 E 7 LIVER TOTLBODYi

~ThYROID.>'

KIDNEY L. -UNG7 -SILUY7: H-3 0 OOE+-00 8:99E-08 8.99E708 8.99Eý08 8 99E-08 8,99E-08'

.899E-`08 Co-60 o 0.0E+00 '35E706 -- 297E 06 OOE+00 0.OOE00 0OOE+00 2;53E-05.Ni-63 0.00E+00 0.OOE+00 :.OOE+00 0 O:E+00 &00E+00 0 OOE+00E"ý

!i::0 0E+00E:4.Sr-90, 645E-04 0.OOE+00 1 58E-04i, 0 00E+00 E+00 .0OOE+00. :,I'186E-05ýý:;, Cs-137 3 ' 29E705 4.50E-05 2.95E-'05~

0.00E+,00~

~153E-0 .: 5'07E-06:.', 8:68E-07T totals 6.78E-041 1.91E04 &899E-08 1.53E05. 5.16E-06 4.49&(M5 unit 3 North ,MISQOT;PE' .BONE 'LIVER27:

TOT'BODY THYROID KIDNEY ~ 'LUNG GI-LLI H-3 0 OOE+00 3 26E-08 3 26E-08 3 26E-08 126E-08 3 2CE-08 3,26E-08 Co-60 0 008+00 5,53E-07 I1 22E-06 &00E+00 0.00E+00 0 OOE+00 1 74E-05 Ni-63 0.008+00 ..OOE+00 -0:008+00' 0.OE+00 0.008+00 0.OOE+00 0.OOf+-00 Sr-90 6.15&-05 0.OOE+00 1.51E-05 0.008+-00 0.OOE+00 0 OOE'+00 1.778-06 Cs-i 37 1 0OOE+ý00K 0 008+00 O.. 000+00 .70.001140 O. 0.0+00 ,.. 0.00800 , 0.00E4ý00, totals I 6.15E-05 586E-07 1 .63E-05 3.26E708 26-08 3:26E-08 Unit 3 South_'. ISOTPE. SBOME LIVER~ TOT BODY 'THYROID KIDNEY, LUNG"' GI4,LLI 'H-3 0.00E+00 ,3+99E-'08 3 99E-08' :3:99E-08:'.'

3 3.99E-08 3.99E-08', Co-60 -.0.00E+00 ,O.00E+00

000E+00, 0'00E+00 0.00E+00 0',00E+00' O OE+00, Ni-63 .O::OE+000 O: E,-00-. 0.:OOE+00 0.0:00E+00

0.00E+00 ,000E+00' 0,.000E+00.

Sr-90 :1'52&-04 0-OOE+00 ..,:.. 3.73E-05 '-" 0.0E+00:'

'0.OOE+00

.0.00E+00W

.4:38E-06 Cs-i137 E43-05 5.89E-05 3.86E-05' 0C0OE+00 2.00-05 ' L' 6.64E-06 : 1' 14E-0 totals ,195E-04 5.89E-05; 7,59E-05 3.99E-08 2OO&E-05 6.68E-06 5.56E-06 Southern Clean Zone 1ISOTOQPE',, BONE~j LIVER 7:TOT BODY' 7:THYROID

,..KIDNEY.

LUNGS , .,GI-LLI~H-3 .0 .0+00 3,78E-08 337808 3.78E-08 3.78E-08 3.78E-08 3 0788-08 Co-60 0 00E+00 i31E-'06 1'I.-2.88E-06T.

": OOOE+00 0 '0.00E+00 0.8OOE+00 2.45E-05"

Ni-63 l' 0.OOE+00 .0.00E+00.

0.OOE+00 ::, 0.OOE+00 I. o.00+E00 17 0,00E+00." 0.00+E-00' Sr-90 I 0.00E+00 0.OOE+00 W0:00E+00 0.:OOE+00 0.00+E00 0.I E+00,: .0.OE+00 .Cs-i 37 "'0,00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.008+00

0 00E+00 "2 0 00+00,,: totals 0.OOE+00 *. 1 .34E-06 2.92E-06 I 3.78E-08 33.8E-08 3.78E&08 2A46E-05 2008.year,-4J5E02 4155+02 2,78E+04 OME+00W I165&04i 3,84E+03,[.2&0099.,165E+05 3AOOE-+03 Totals. AdultDoses, in mrem H-3only 0.OOE+00 I 2.19E-07 I 2.19E-07 I 2"19E-07 I 2.19E-07 I 2.19E-07 2:19E-07 TotaluCis 30 BNE' ':L'IVER I4 'TOT'BODY>

'J THYROID KIDNEY I'"LUNG I :GI-LLI -1' 21-2E+05 H3 all isotopes 9.35E-04 1 1.07E&04 j 2.86E-04 I 2.19E-07 3.55E-05 1. 19E-05 8.72E-05 5.46E401lCo

_:.. .. ... NI I Adsurt SeS: s+%Anualimt

<O.O93'.~..0.01.

0.00953, ý0000 0.0000," 00. ,00.

Docket No. 50-3, 50-247, & 50-286 Page 43 of 50 INDIAN POINT RADIOLOGICAL GROUNDWATER MONITORING PROGRAM 2008 Summary of Results The following pages represent a summary of isotopic radio-analytical data for all onsite groundwater testing performed at Indian Point in 2008, as required per the ODCM and NEI 07-07.

Docket No. 50-3, 50-247, & 50-286 Page 44 of 50 page 1 of 3 Tritium (H-3) Summary Well Name B-1 B-6 MH-5 MW-107 MW-111 MW-30-69 MW-30-84 MW-31-49 MW-31-63 MW-31-85 MW-32-131 MW-32-149 MW-32-173 MW-32-190 MW-32-59 MW-32-85 MW-33 MW-35 MW-36-24 MW-36-52 MW-37-22.MW-37-32 MW-37-40 MW-37-57 MW-39-102 MW-39-124 MW-39-195 MW-39-67 MW-39-84 MW-40-1 00 MW-40-127 MW-40-162 MW-40-27 MW-40-46 MW-40-81 MW-41-40 MW-41-63 MW-42-49 MW-42-78 MW-43-28 MW-43-62 Samples in 2008 2 2 1 2 3 6 6 5 6 6 2 4 5 5 6 6 2 1 3 3 3 3 3 3 3 3 3 3 3 4 4 3 3 3 3 2 2 6 3 2 2# Positive Samples in 2008 2 1 1 1 3 6 6 5 6 6 2 4 5 5 6 6 2 1 3 3 3 3 3 3 1 3 1 3 1 1 1 1 1 1 2 2 6 3 2 1 Average Positive Activity 6.99E+02 4.72E+02 9.28E+02 1.91 E+02 6.27E+04 1.32E+05 4.29E+03 3.20E+03 1.85E+04 4.37E+03 7.67E+02 7.67E+02 1.63E+03 5.50E+03 5.02E+03 9.05E+03 6.33E+04 1.04E+03 1.13E+03 1.16E+04 4.51 E+03 4.94E+03 5.82E+03 5.41 E+03 5.03E+02 2.04E+02 2.74E+02 3.63E+02 2.34E+02 1.93E+02 1.68E+02 2.30E+02 2.22E+02 1.68E+02 2.42E+02 1.21 E+03 4.97E+02 4.11E+03 5.09E+02 2.86E+02 2.25E+02 Minimum Positive Activity 2.27E+02 4.72E+02 9.28E+02 1.91 E+02 4.77E+04 7.36E+04 3.78E+03 3.97E+02 1.02E+04 1.31 E+03 5.04E+02 5.03E+02 9.72E+02 3.35E+03 4.13E+02 7.48E+03 5.85E+04 1.04E+03 2.01 E+02 1.10E+04 2.68E+03 2.89E+03 5.24E+03 4.27E+03 5.03E+02 1.67E+02 2.74E+02 3.18E+02 2.34E+02 1.93E+02 1.68E+02 2.30E+02 2.22E+02 1.68E+02 2.42E+02 2.15E+02 3.03E+02 1.12E+03 3.46E+02 2.65E+02 2.25E+02 Maximum Positive Activity 1.17E+03 4.72E+02 9.28E+02 1.91 E+02 7.39E+04 1.99E+05 5.25E+03 1.36E+04 2.55E+04 8.34E+03 1.03E+03 1.15E+03 3.40E+03 8.89E+03 1.87E+04 1.11E+04 6.80E+04 1.04E+03 2.16E+03 1.26E+04 6.52E+03 6.76E+03 6.73E+03 6.63E+03 5.03E+02 2.31 E+02 2.74E+02 4.15E+02 2.34E+02 1.93E+02 1.68E+02 2.30E+02 2.22E+02 1.68E+02 2.42E+02 2.21 E+03 6.91 E+02 1.32E+04 6.18E+02 3.06E+02 2.25E+02 Docket No. 50-3, 50-247, & 50-286 Page 45 of 50 page 2 of 3 Tritium (H-3) Summary Well Name MW-44-102 MW-44-66 MW-45-42 MW-45-61 MW-46 MW-49-26 MW-49-42 MW-49-65 MW-50-42 MW-50-66 MW-51-104 MW-51-135 MW-51-40 MW-52-11 MW-52-162 MW-52-18 MW-52-181 MW-52-48 MW-53-120 MW-53-82 MW-54-123 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-58-26 MW-58-65 MW-60-135 MW-60-154 MW-60-176 MW-60-35 MW-60-72 Samples in 2008 4 4 4 4 4 4 4 4 4 7 3 3 4 1 1 1 1 6 3 4 4 4 4 4 4 4 3 4 2 2 2 2 2 2 2 4 4 4 4 4# Positive Samples in 2008 4 3 4 4 4 4 4 4 3 7 6 3 4 1 1 4 4 4 4 3 4 2 2 2 2 2 2 2 4 4 4 2 1 Avg Pos Act 3.65E+02 4.28E+02 2.01 E+03 1.99E+03 8.05E+02 4.16E+03 2.77E+03 1.65E+03 6.45E+02 2.83E+03 2.82E+02 2.09E+02 3.29E+02 1.13E+03 1.45E+02 2.79E+02 1.56E+02 2.30E+02 5.93E+03 9.82E+02 6.06E+02 1.21E+03 1.92E+03 1.69E+03 1.04E+03 6.64E+02 1.09E+03 1.89E+03 6.88E+03 3.31 E+02 2.46E+03 2.73E+03 1.12E+03 8.48E+02 2.67E+02 2.97E+02 4.70E+02 5.54E+02 7.93E+02 1.95E+02 1.94E+02 Min Pos Act 2.56E+02 3.18E+02 1.13E+03 1.27E+03 5.21 E+02 3.47E+03 2.52E+03 1.26E+03 3.73E+02 2.08E+03 2.82E+02 2.09E+02 3.29E+02 1.13E+03 1.45E+02 2.79E+02 1.56E+02 2.30E+02 5.04E+03 7.94E+02 5.33E+02 1.13E+03 1.66E+03 1.25E+03 8.70E+02 5.78E+02 7.82E+02 1.60E+03 5.96E+03 2.63E+02 1.94E+03 2.17E+03 7.27E+02 5.65E+02 2.38E+02 2.81iE+02 3.79E+02 4.53E+02 6.68E+02 1.95E+02 1.94E+02 Max Pos Act 4.75E+02 5.50E+02 3.14E+03 2.66E+03 1.38E+03 5.OOE+03 3.20E+03 1.93E+03 9.48E+02 3.74E+03 2.82E+02 2.09E1+02 3.29E+02 1.13E+03 1.45E+02 2.79E+02 1.56E+02 2.30E+02 7.48E+03 1.21E+03 6.98E+02 1.40E+03 2.111E+03 2.24E+03 1.25E+03 7.33E+02 1.40E+03 2.33E+03 7.76E+03 3.99E+02 2.98E+03 3.28E+03 1.511E+03 1.13E+03 2.95E+02 3.13E+02 5.85E+02 6.87E+02 8.95E+02 1.95E+02 1.94E+02 Docket No. 50-3, 50-247, & 50-286 Page 46 of 50 Tritium (H-3) Summary page 3 of 3# # Positive Samples Samples Avg Pos Min Pos Max Pos Well Name in 2008 in 2008 Act Act Act MW-62-138 3 3 6.84E+02 5.33E+02 7.69E+02 MW-62-18 3 3 3.42E+02 2.69E+02 4.08E+02 MW-62-182 3 3 4.56E+02 3.99E+02 4.98E+02 MW-62-37 3 3 4.42E+02 3.94E+02 5.35E+02 MW-62-53 3 3 3.69E+02 3.48E+02 4.08E+02 MW-62-71 3 3 4.43E+02 3.53E+02 5.12E+02 MW-62-92 3 3 4.57E+02 3.94E+02 4.95E+02 MW-63-112 4 4 3.31E+02 2.07E+02 4.69E+02 MW-63-121 4 4 4.58E+02 3.44E+02 5.40E+02 MW-63-163 4 4 5.36E+02 4.44E+02 6.85E+02 MW-63-174 4 4 5.1OE+02 4.49E+02 6.23E+02 MW-63-18 4 2 2.89E+02 2.57E+02 3.20E+02 MW-63-34 4 4 4.18E+02 3.26E+02 4.90E+02 MW-63-50 4 4 3.20E+02 2.70E+02 3.56E+02 MW-63-93 4 4 2.86E+02 2.15E+02 3.90E+02 MW-66-21 4 4 7.72E+02 5.34E+02 9.53E+02 MW-66-36 4 4 5.95E+03 5.01 E+03 7.26E+03 MW-67-105 4 4 2.48E+03 2.16E+03 2.93E+03 MW-67-173 4 4 8.88E+02 6.95E+02 9.93E+02 MW-67-219 4 4 1.26E+03 1.17E+03 1.37E+03 MW-67-276 4 4 1.11E+03 1.03E+03 1.18E+03 MW-67-323 4 4 4.42E+02 3.38E+02 6.84E+02 MW-67-340 4 4 5.38E+02 4.78E+02 6.69E+02 MW-67-39 5 5 3.73E+03 3.07E+03 4.35E+03 U1-CSS 6 6 1.54E+03 4.95E+02 2.66E+03 U3-4D 4 4 4.32E+02 3.19E+02 5.68E+02 U3-T1 4 4 6.48E+02 5.56E+02 7.29E+02 U3-T2 4 4 1.07E+03 9.28E+02 1.33E+03 Note 1: All results are in pCi/L Note 2: A total of 406 samples were analyzed for H-3 in 2008 with 344 positive results. This total includes samples from REMP wells MW-40 and MW-51. 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 200 pCi/L.

Docket No. 50-3, 50-247, & 50-286 Page 47 of 50 Cobalt-60 Summary# Samples in 2008# Positive Samples in 2008 Well Name MW-40-162 MW-42-49 MW-54-123 MW-62-92 MW-67-39 3 6 4 3 5 1 2 I I 1 Ave Pos Act 3.15E+00 1.12E+01 4.12E+00 5.16E+00 1.59E+01 Min Pos Act 3.15E+00 5.47E+00 4.12E+00 5.16E+00 1.59E+01 Max Pos Act 3.15E+00 1.69E+01 4.12E+00 5.16E+00 1.59E+01 Note 1: Note 2: Note 3: All results are in pCi/L A total of 406 samples were analyzed for Co-60 in 2008 with 6 positive results. This total includes samples from REMP wells MW-40 and MW-51. 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 2008# Positive Samples in 2008 Ave Pos Act Min Pos Max Pos Act Act Well Name MW-42-49 MW-53-120 6 6 6 4 4.21 E+02 2.44E+02 7.34E+02 2.23E+01 1.94E+01 2.65E+01 Note 1: Note 2: Note 3: All results are in pCi/L A total of 167 samples were analyzed for Ni-63 in 2008 with 10 positive results. This total includes samples from REMP wells MW-40 and MW-51. 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.

Docket No. 50-3, 50-247, & 50-286 Page 48 of 50 Page 1 of 2 Strontium-90 Summary Well Name LAF-002 MW-111 MW-32-173 MW-36-52 MW-37-22 MW-37-32 MW-37-40 MW-37-57 MW-39-102 MW-39-124 MW-39-183 MW-39-195 MW-39-67 MW-39-84.MW-41-40 MW-41-63 MW-42-49 MW-42-78 MW-43-62 MW-46 MW-49-26 MW-49-42 MW-49-65 MW-50-42 MW-50-66 MW-52-162 MW-53-120 MW-53-82 MW-54-123 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-56-83 Samples in 2008 2 3 5 3 3 3 3 3 3 3 3 3 3 3 2 2 6 3 2 4 4 4 4 4 7 1 6 3 4 4 4 4 4 4 4 3 4 2# Positive Samples in.2008 1 2 1 3 3 3 3 3 3 3 2 3 3 3 2 2 6 4 1 1 4 4 4 4.7 1 6 1 4 4 4 4 4 4 4 3 4 2 Ave Pos Act 4.73E-01 1.79E+00 6.80E-01 6.26E+00 1.30E+01 1.81 E+01 1.13E+00 2.47E+01 1.03E+00 1.40E+00 9.75E-01 9.96E-01 3.01E+00 1.68E+00 4.48E+00 4.73E+00 9.78E+01 3.91 E-01 1.00E+00 9.33E-01 1.81E+01 2.40E+01 2.03E+01 4.29E+00 3.61E+01 1.03E+00 3.19E+01 6.95E-01 8.78E+00 1.71 E+01 1.38E+01 2.35E+01 6.10E+00 3.69E+00 2.03E+01 2.87E+01 2.30E+01 2.85E+00 Min Pos Act 4.73E-01 1.02E+00 6.80E-01 4.85E+00 8.73E+00.1.52E+01 9.48E-01 2.12E+01 8.83E-01 9.42E-01 8.29E-01 8.81E-01 2.21 E+00 1.04E+00 3.05E+00 3.76E+00 2.36E+01 3.91 E-01 1.00E+00 9.33E-01 1.53E+01 2.16E+01 1.72E+01 2.40E+00 3.20E+01 1.03E+00 2.53E+01 6.95E-01 6.45E+00 1.53E+01 1.22E+01 1.93E+01 5.08E+00 1.69E+00 1.08E+01 2.54E+01 1.94E+01 2.13E+00 Max Pos Act 4.73E-01 2.56E+00 6.80E-01 8.27E+00 1.80E+01 2.06E+01 1.31 E+00 2.89E+01 1.23E+00 1.79E+00 1.12E+00 1.21 E+00 3.52E+00 2.23E+00 5.91E+00 5.69E+00 2.96E+02 3.91E-01 1.00E+00 9.33E-01 2.29E+01 2.94E+01 2.73E+01 9.28E+00 4.99E+01 1.03E+00 4.25E+01 6.95E-01 1.26E+01 2.02E+01 1.61 E+01 3.38E+01 7.33E+00 9.02E+00 2.55E+01 3.44E+01 2.67E+01 3.56E+00 Docket No. 50-3, 50-247, & 50-286 Page 49 of 50 Strontium-90 Summary Page 2 of 2 Well Name MW-57-11 MW-57-20 MW-57-45 MW-62-138 MW-62-18 MW-62-37 MW-63-121 MW-66-21 MW-66-36 MW-67-105 MW-67-39 U1-CSS U3-T1 U3-T2 Samples in 2008 2 2 2 3 3 3 4 4 4 4 5 6 4 4# Positive Samples in 2008 2 2 2 3 I 1 1 4 4 3 5 6 1 1 Ave Pos Act 3.22E+01 2.15E+00 1.73E+00 1.06E+00 5.31 E-01 1.36E+00 6.63E-01 1.01 E+00 1.35E+01 1.07E+00 1.83E+01 7.42E+00 7.01 E-01 6.52E-01 Min Pos Act 2.27E+01 1.23E+00 1.20E+00 7.34E-01 5.31 E-01 1.36E+00 6.63E-01 9.07E-01 1.20E+01 9.63E-01 1.37E+01 4.83E+00 7.01E-01 6.52E-01 Max Pos Act 4.16E+01 3.06E+00 2.26E+00 1.24E+00 5.31E-01 1.36E+00 6.63E-01 1.09E+00 1.51 E+01 1.13E+00 2.59E+01 9.38E+00 7.01 E-01 6.52E-01 Note 1: Note 2: All results are in pCi/L.A total of 406 samples were analyzed for Sr-90 in 2008 with 153 positive results. This total includes samples from REMP wells MW-40 and MW-51. See the AREOR for additional data.A sample is positive if the result is greater than or equal to 3 times the I sigma uncertainty.

The target MDC is 1 pCi/L.Note 3:

Docket No. 50-3, 50-247, & 50-286 Page 50 of 50 Cesium-137 Summary Well Name B-1 MW-41-40 MW-42-49 MW-42-78 MW-44-102 MW-44-66 MW-50-42 MW-50-66 MW-55-24 MW-67-105 MW-67-173 MW-67-219 MW-67-276 MW-67-340 Samples in 2008 2 2 6 3 4 4 4 7 4 4 4 4 4 4# Positive Samples in 2008 6 1 6 1 ,1 1 1 1 1 1 1 1 1 1 Ave Pos Act 2.OOE+01 2.67E+00 1.90E+04 1.08E+02 1.73E+01 1.18E+01 1.63E+01 1.56E+01 3.33E+00 9.32E+00 5.82E+00 4.25E+00 4.55E+00 5.82E+00 Min Pos Act 2.00E+01 2.67E+00 1.06E+04 1.08E+02 1.73E+01 1.18E+01 1.63E+01 1.56E+01 3.33E+00 9.32E+00 5.82E+00 4.25E+00 4.55E+00 5.82E+00 Max Pos Act 2.OOE+01 2.67E+00 3.38E+04 1.08E+02 1.73E+01 1.18E+01 1.63E+01 1.56E+01 3.33E+00 9.32E+00 5.82E+00 4.25E+00 4.55E+00 5.82E+00 Note 1: Note 2: Note 3: All results are in pCi/L A total of 406 samples were analyzed for Cs-1 37 in 2008 with only 19 positive results. This total includes samples from REMP wells MW-40 and MW-51. 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 18 pCi/L.