NL-09-045, Official Exhibit - ENT000317-00-BD01 - 2008 Annual Radioactive Effluent Release Report (Apr. 17, 2009)

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Official Exhibit - ENT000317-00-BD01 - 2008 Annual Radioactive Effluent Release Report (Apr. 17, 2009)
ML12338A661
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 04/17/2009
From: Robert Walpole
Entergy Nuclear Northeast
To:
Atomic Safety and Licensing Board Panel, Document Control Desk
SECY RAS
References
RAS 22135, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, NL-09-045
Download: ML12338A661 (53)
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Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3) c,\.t.p.R REGU<..,,, ASLBP #: 07-858-03-LR-BD01

~~"vi Docket #: 05000247 l 05000286

  • 0 Exhibit #: ENT000317-00-BD01 Identified: 10/15/2012

~ ~

Admitted
10/15/2012 Withdrawn:

....~

~

.. d' Rejected:

Other:

Stricken: ENT000317 Submitted: March 29, 2012 Entergy Nuclear Northeast Indian Point Energy Center

~Entergx 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 9147346710 Robert Walpole Manager, Licensing NL-09-045 April 17, 2009 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

2008Annual Radioactive Effluent Release Report Indian Point Nuclear Generating Units 1, 2, and 3 Docket Nos. 50-3,50-247, and 50-286 License Nos. \

DPR-5, DPR-26, and 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 2008. 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 Mr. Robert Walpole, Manager, Licensing at (914) 734-6710. "I Sincerely, RW/dmt

Enclosure:

1. 2008 Annual Radioactive E;ffluent Release Report
2. Offsite Dose Calculation Manual Changes and Justification Packages, 2008
3. Summary of the Process Control Program (PCP) Changes for IPEC cc: next page

NL-09-045 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 Mr. Paul Eddy, New York State Dept. of Public Service 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-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 (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 concentratior:Js 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 SE-S uCiiml (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 mixtures in releases of fission and activation gases were as follows:

Units 1 and 2:

1st Quarter Ep= 1.49E-01 Mev/dis Ey= 6.56E-02 Mev/dis 2nd Quarter Ep= 2.00E-01 Mev/dis Ey= 2.41 E-01 Mev/dis 3rd Quarter Ep= 2.50E-01 Mev/dis Ey= 3.13E-03 Mev/dis 4th Quarter Ep= 3.53E-01 Mev/dis Ey= 7.92E-01 Mev/dis Unit 3:

1st Quarter Ep= 4.64E-01 Mev/dis Ey= 1.28E+00 Mev/dis 2nd Quarter Ep= 4.63E-01 Mev/dis Ey= 1.28E+00 Mev/dis 3rd Quarter Ep= 4.35E-01 Mev/dis Ey= 1.17E+00 Mev/dis 4th Quarter Ep= 4.41 E-01 Mev/dis Ey= 1.20E+00 Mev/dis

4. Measurements and Approximations of Total Radioactivitv 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 lodine-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 1.0E-13 uCi/cc, which is 100 times lower than ODCM requirements.

If 1-131 is identified in any routine weekly sample, it is added to the table and other iodine isotopic concentrations 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 8.0E-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 SE-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 1's North Curtain Drain), and water discharged through monitored pathways identified in the ODCM, but NOT processed (SG Blowdown and Unit 1's Sphere Foundation Drain Sump).

The unprocessed water may still contain trace levels of contamination (generally only tritium) and as such, is identified as liquid waste 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 1 and 2 Airborne Releases 'Qtr1,," Qtr 2 , ':Qtr 3 Qtr4 200B Number of Batch Releases 49 64 40 4B 201 Total Time Period (min) 4.35E+3 B.60E+3 2.54E+3 3.14E+3 1.B6E+4 Maximum Time Period (min) 3.02E+2 4.35E+2 1.B2E+2 1.51 E+2 4.35E+2 Average Time Period (min) B.B7E+1 1.34E+2 6.35E+1 6.53E+1 9.27E+1 Minimum Time Period (min) 5.00E+0 2.00E+0 4.00E+0 2.00E+0 2.00E+0 Unit 3 Airborne Releases Qtr1 Qtr2 Qtr 3 ' Qtr4; ,,200B Number of Batch Releases 16 19 20 21 76 Total Time Period min 1.95E+3 2.31E+3 2.2BE+3 2.35E+3 B.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 6.00E+0 7.00E+0 5.00E+0 2.00E+0 2.00E+0 Liquid:

Unit 1 and 2 Liquid Releases " Qtr 1 Qtr 2, Qtr 3 Qtr4 200B Number of Batch Releases 19 16 10 9 54 Total Time Period min) 1.5BE+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) B.32E+1 9.62E+1 1.55E+3 1.67E+2 3.72E+2 Minimum Time Period min) 2.00E+1 5.00E+1 B.40E+1 7.70E+1 2.00E+1 Unit 3 Liquid Releases Qtr 1 Qtr2 ' Qtr3 Qtr4 200B Number of Batch Releases 4 6 12 1B 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 1.1BE+2 1.16E+2 1.23E+2 1.2SE+2 Average Time Period min 1.1BE+2 1.12E+2 1.10E+2 1.12E+2 1.12E+2 Minimum Time Period min 1.0BE+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 1B 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 Fourth 93,200 2007 First 92,100 2007 Second 95,280 2007 Third 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/ml 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 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.

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:

Outof Service Instrument Details' Period 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 Jun 10,2008 2008, and the monitor appeared functional. Since the R-14, Unit 3 backup primary monitor (the WRGM) has a good performance plant vent noble gas (278 days) record, and the background problem has not returned, monitor 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 Jan 2, 2008 later found to be defective. Parts had to be re-ordered.

R-43/44, Unit 2 to plant vent Feb 11,2008 After multiple unsat tests, and parts replacements, particulate and (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 Out of Service Instrument Details Period The monitor was rendered officially inoperable due to a broken reset switch. There was an excessive delay in Mar 29, 2008 obtaining the replacement contact block. The switch R-61 , Unit 3 to was replaced and monitor declared operable.

condensate polisher Jun 20, 2008 TDS tank effluent Compensatory samples were obtained during the OOS (83 days) .

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, leaving only a local readout, which was not R-59, Unit 3 Aug 13,2008 considered acceptable. The failure was due to a radiation machine to severe electrical disturbance.

shop vent noble gas Oct 14, 2008 monitor and 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 SWoutlet.

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 ofOOS.

condensate polisher TDS tank effluent (98 days)

Long lead time of parts and planning were responsible for the extended outage.

(87 days in 2008)

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 (contin~ed)

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 lA INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2008)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A Fission & Activation Gases Units Qtr1 Qtr2 Qtr3 Qtr4 2008  % Error

1. Tolal Release Ci 1. 13E-+OO 4.69E-01 4.50E+01 7. 18E-01 4.73E+01 +25
2. Average release rate uO/sec 1.44E-01 5.97E-02 5. 66E+OO 9.03E-02 1.50E+OO B. lodines
1. Totallodine-131 Ci - - - - O.ooE+OO  :!:25
2. Average release rate uO/sec - - - - O.OOE+OO C. Particulates
1. Total Release, Wth half-life> 8 days Ci - - 1.28E-04 - 128E-04  :!:25
2. Average release rate uO/sec - - 1.61E-05 - 4.04E-06
3. Gross Alpha Ci - - 2.14E-06 - 2.14E-06  :!:25 D. Tritium
1. Total release Ci 1.83E-+OO 2.42E-+OO 3. 79E+OO 1.82E+OO 9.86E+OO +25
2. Average release rate uO/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 lC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2008)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 2008 IKr-85 Ci - - 4.49E+01 6.12E-01 4.55E+01 Total for Period Ci O.OOE+OO O.OOE+OO 4.49E+01 6.12E-01 4.55E+01 I
2) lodines 1-131 Ci - - - O.OOE+OO 1-133 Ci - - - - O.OOE+OO 1-135 Ci - - - - O.OOE+OO Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I
3) Particulates ICS-137 Ci - - 1.28E-04 - 1.28E-04 Total for Period Ci O.OOE+OO O.OOE+OO 1.28E-04 O.OOE+OO 1.28E-04 I

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 12 of 50 TABLE lC INDIAN POINT 1 and 2 - BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2008)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr2 Qtr3 Qtr4 2008 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-85m Ci 7.87E-05 1.76E-03 13.57E-04 9.42E-04 3.13E-03 Kr-87 Ci 1.83E-05 1.09E-03 12.56E-04 7. 55 E-04 2.12E-03 Kr-88 Ci 4.66E-05 2.68E-03 16.73E-04 1.71 E-03 5.10E-03 Xe-131m Ci 3.13E-03 1.74E-03 I

- - 4.88E-03 Xe-133 Ci 1.03E+00 3.48E-01 2.48E-02 2. 77 E-02 1.43E+OO Xe-133m Ci 1.16E-02 4.33E-03 1.82E-04 5. 35 E-04 1.66E-02 Xe-135 Ci 2.40E-02 3.51E-02 5.64E-03 1.51 E-02 7.98E-02 Xe-135m Ci 5.95E-05 2.92E-03 4.32E-04 1.74E-03 5.15E-03 Xe-138 Ci 1.50E-05 7.39E-04 - 3.36E-04 1.09E-03 I Total for Period Ci 1.13E+00 4.69E-01 16.24E-02 1.06E-01 1.77E+00 I

2) lodines Not Applicable for Batch Releases
3) Pa rticulates No t App licable for Batch Re leases

- Indicates < MDA

Docket No. 50-3, 50-247, & 50~286 Page 13 of 50 TABLE lA INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2008)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Tdal A FisSon & Activation Gases Units Qtr1 Qtr2 . Clr3 Clr4 2008 %8'rcr

1. Tolal Release Ci 1.54E-02 1.67E-02 1.96E-02 1.96E-02 7. 12E-02 +25
2. Avemge release rate uO/sec 1.00E-03 2.12E-03 2.46E-03 2.46E-03 2.25E-03 B. Icx:fines
1. Tdallodine-131 Ci - - - - 0.00E+00 t25
2. Avemge release rate uO/sec' - - - - 0.00E+00 C. Particulates
1. Tdal Release, Wth half-life> 8 da',S Ci - - - - 0.00E+00 +25
2. Avemge release rate uO/sec - - - - 0.00E+00
3. Gross Alpha Ci - - - - 0.00E+00 t25 D. Tritium
1. Tdal release Ci 3.04E+OO 3.ooE+OO 3.43E+00 2.57E+00 1.20E+01 +25
2. Avemge release rate uO/sec 3. 86 E-01 3.82E-01 4. 31 E-01 3.24E-01 3.81E-01

- Indicates < 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 Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr3 Qtr4 2008 tx e-133 Ci - - - - O.OOE+OO I Total for Period Ci - - - - O.OOE+OO
2) lodines 1-131 Ci - - - - O.OOE+OO 1-133 Ci - - - - O.OOE+OO 1-135 Ci - - - - O.OOE+OO I Total for Period Ci - - - - O.OOE+OO
3) Particulates Total for Period Ci IO.OOE+OO I

- 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 Year

1) Fission Gases Units Qtr 1 Qtr2 Qtr3 Qtr4 2008 Ar-41 Ci 1.54E-02 1.66E-02 1.79E-02 1.82E-02 6.81E-02 Kr-85 Ci - - - - O.OOE+OO Kr-85m Ci - - - - O.OOE+OO Kr-87 Ci - - - - O.OOE+OO Kr-88 Ci - - - - O.OOE+OO Xe-131m Ci - - - - O.OOE+OO Xe-133 Ci - 6.96E-05 1.72E-03 1.38E-03 3.17E-03 Xe-133m Ci - - - - O.OOE+OO Xe-135 Ci - - - - O.OOE+OO Xe-135m Ci - - - - O.OOE+OO Total for Period I Ci 1.54E-02 1.67E-02 1.96E-02 1.96E-02 7.13E-02
2) lodines Not Applicable for Batch Releases
3) Particulates Not Applicable for Batch Releases

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 16 of 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 and'2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2008)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est Total A. Rssion & Activation Products 2008  % Error Units Qtr 1 Qtr2 Qtr3 Qtr4

1. Total Release (not including Ci 1.57E-02 2.01 E-02 1.24E-02 6. 37E-03 5.46E-02 + 25 Tritium, Gr Alpha, & Gases)
2. Average IJluted Conc uO/ml 2.71E-11 2.95E-11 1.44E-11 8.85E-12 1.92E-11 B. Tritium
1. Total Release Ci 6.42E+01 5. 52E +01 6. 16E+01 2. 92E +01 2.10E+02 .:!:. 25
2. Average IJluted Conc uO/ml 1.11E-07 8.10E-08 7. 14E-08 4. 05 E-08 7. 39E-08 C. Dissolved & Entrained Gases
1. Total Release Ci 1.63E-03 1.13E-05 3. 58E-02 - 3. 75E-02 + 25
2. AverageDiluted Conc uO/ml 2.81E~12 1.65E-14 4.1SE-11 - 1.32E-11 D. Gross Alpha
11. Total Release Ci .:!:.25 E. Volume of Was.e Released
1. Processa:l \l\.6ste O-W & Nm) liters 3.90E+06 2.10E+06 3.94E+06 2. 16E+06 1.21E+07 + 10 2 Ul1p'"ocessa:I (SGBD, SFCS, lJ1FO) liters 4. 13E+07 5. 62E +07 4.61E+07 4. 79E +07 1.91E+08 + 10 F. Volume of Dilution Water

- 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 Year Units Qtr 1 Qtr2 Qtr 3 Qtr4 2008 Cs-137 Ci 9.82E-04 2.53E-03 1.77E-03 1.S8E-03 6.86E-03 Ni-63 Ci - 4.22E-04 - - 4.22E-04

, Sr-89 Ci - - - - O.OOE+OO Sr-90 Ci 1.20E-04 1.91 E-04 S.S9E-04 7.84E-04 1.6SE-03 I Total for Period Ci 1.10E-03 3.14E-03 2.33E-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 Year Nuclides Released 2008 Units Qtr 1 Qtr2 Qtr 3 Qtr4 Ag-110m Ci 2.02E-04 5.09E-05 1.17E-04 - 3.70E-04 Co-58 Ci 2.81E-05 2.01 E-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 - - - 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 - 2.92E-05 Ni-63 Ci 3.89E-03 3.35E-03 6.52E-04 5.74E-04 8.46E-03 Sb-124 Ci 1.10E-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 - - 1.61 E-05 - 1.61 E-05 Te-123m Ci - 2.13E-05 - - 2.13E-05 Te-125m Ci - 2.19E-03 - - 2.19E-03 I Total for Perio d Ci 1.46E-02 1.69E-02 1.01E-02 4.01E-03 4.57E-02 Dissolved & Entrained Gas Kr-85 Ci I

- - 3.58E-02 - 3.58E-02 Xe-133. Ci I 1.63E-03 1.13E-05 - - 1.64E-03 I Total for Perio d Ci 11.63E-03 1.13E-05 3.58E-02 - 3.75E-02

- 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 Year Est Total A. Fission & Activation Products Units Qtr 1 Qtr2 Qtr3 Qtr4 2008  % Error

1. Total Release (not including Ci 2.44E-04 2.00E-03 5.49E-03 6.54E-03 1.43E-02 + 25 Tritium, Gr Alpha, & Gases)
2. Average Diluted Cone uO/ml 4.22E-13 2.93E-12 6.37E-12 9.09E-12 5.02E-12 B. Tritium
1. Total Release Ci 1.88E+01 7.49E+01 8.13E+01 4. 92E+02 6.67E+02 .:!:.25
2. Average Diluted Cone uO/ml 3.24E-08 1.10E-07 9.42E-08 6.B4E-07 2.35E-07 C. Dissolved & Entrained Gases
1. Total Release Ci - - - 4. 96 E-05 4. 96E-05 + 25
2. AverageDiluted Cone uO/ml - - - 6.90E-14 1.75E-14 D. Gross AI pha
1. Total Release Ci I O.OOE+OO I .:!:. 25 E. Volume of Waste Released
1. Processed Fluids (lvbnTanks) 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 F. Volume of Dilution Water

'- indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 21 of 50 TABLE 2B INDIAN POINT 3 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2008)

BATCH and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT Bctch RssoniAdivciion Rnduds Units Qtr1 Qtr2 Qtr3 Qtr4 2008 Ag-110m Ci - 8.00E-OS 2.60E-OS - 1.06E-04 Co-S8 Ci 6.90E-06 1.31E-OS 2. 18E-OS 2. 33E-OS 6.S1 E-OS Ccr60 Ci 2. 69E-OS 9.3SE-04 1.69E-03 1.S6E-03 4.22E-03 Cs-134 Ci - 1.02E-04 9.61E-OS 1.98E-04 Cs-137 Ci - - 2.S0E-04 2.90E-04 S.40E-04 Fe-SS Ci - - 1. 14E-03 7.28E-04 1.87E-03 Mn-54 Ci - 1.63E-OS 3.07E-OS 1.07E-OS S.77E-OS Ni-63 Ci 1.S2E-04 8.36E-04 1.97E-03 2.26E-03 S.22E-03 Sb-12S Ci S.87E-OS 1.19E-04 2.60E-04 1.S7E-03 2. 00 E-03 I Total for Period Ci 2.44E-04 2.0 OE-O 3 S.49E-03 6. 54E-03 1.43E-02 Disrolved and Entrained Gas (Batch)

Kr-8S Ci - - - - O.OOE+OO Xe-133 Ci - - - 4. 96E-OS 4.96E-OS Xe-133m Ci - - - - O.OOE+OO I Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 4. 96E-OS 4.96E-OS Continuous Releases (SG Blowdown)

H-3 (only)

'- 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)

Class fe m 3

Shipped A 1.08E+02 3.06E+00 1.01 E-O 1 +/- 25%

B 3.71E+02 1.05E+01 7.27E+01 +/- 25%

C l 8.5 OE+ 01 2.41 E+OO 2.36E+02 +/- 25%

All 5.64E+02 1.60E+01 3.09E+02 +/- 25%

Waste Stream Dry Active Waste DAW / Equip DAW /Dirt;B-25 Box DAW 20' Sea La nd IF200 Cask Waste Volume Curies  % Error (Ci)

Class fe m 3

Shipped A 2.4 5E+ 04 6.93E+02 7.78E+00 +/-25%

B O.OOE+OO O.OOE+OO 0.00 E+OO +/-25%

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

All 2.45E+04 6.93E+02 7.78E+00 +/-25%

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

Class fe m 3

Sh ipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

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

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

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

Waste Stream: Other Waste Combined Packages River Silt - Intermodal Waste Volume Curies  % Error (Ci)

Class ft3 m3 Shipped A 3.28E+03 9.29E+01 9.2 OE-O 4 +/-25%

B 3.0 OE+ 01 8.48E-01 2.17 E+O 1 +/-25%

C O.OOE+OO O.OOE+OO 0.00 E+OO +/-25%

All 3.31 E+03 9.37E+01 2.17E+01 +/-25%

Waste Stream : Sum of All 4 Categories Combined Packages:

DAW /Dirt; B-25 Box DAW 20' Sea Land LW S Resin IF 200 Cask River Silt -Intermodal DAW-/ Equip Pia nt Resin 8-120 Waste Volume Curies  % Error (Ci)

Class fe m 3

Sh ipped A 2.79E+04 7.89E+02 7 .88E+00 . +/-25%

B 4.01E+02 1.14E+01 9.44 E+O 1 +/-25%

C 8.50E+01 2.41 E+OO 2.36E+02 +/-25%

All 2.84E+04 8.03E+02 3.38E+02 +/-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 Mode of Transportation Destination 18 Hittman Transport Energy Solutions - Bear Creek 2 Hittman Transport Energy Solutions - GRF 10 Horwith Trucks Studsvik Processing - Memphis 2 Studsvik Logistics Studsvik Processing - Memphis 5 Hittman Transport Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance Curies Fe-55 0.01% 1.05E-05 Co-60 0.30% 3.09E-04 Ni-63 1.84% 1.86E-03 Sr-90 0.02% 1.98E-05 Cs-137 97.70% 9.90E-02 Ce-144 0.13% 1.30E-04 Pu-238 0.00% 7.01E-08 Pu-239 0.00% 1.03E-07 Am-241 0.00% 1.75E-07 Cm-243 0.00% 4.48E-09 Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance Curies C-14 0.15% 1.07E-01 Mn-54 0.18% 1.34E-01 Fe-55 28.16% 2.05E+01 Co-57 0.08% 5.80E-02 Co-58 ,0.32% 2.31 E-01 Co-60 3.78% 2.75E+00 Ni-63 28.99% 2.11 E+01 Sr-90 0.13% 9.82E-02 Ag-110m 0.17% 1.21E-01 Sb-124 0.00% 3.76E-04 Sb-125 0.05% 3.29E-02 Cs-134 7.10% 5.17E+00 Cs-137 30.36% 2.21E+01 Ce-144 0.52% 3.80E-01 Pu-238 0.00% 2.91E-04 Pu-239 0.00% 1.31E-04 Pu-241 0.01% 6.51E-03 Am-241 0.00% 1.48E-04 Cm-242 0.00% 1.23E-05 Cm-243 0.00% 1.S3E-04

Docket No. 50~3, 50-247, & 50-286 Page 25 of 50 Resins, Filters, and Evap Bottoms Waste Class C jNuciide Name Percent Abundance Curies Mn-54 0.28% 6.55E-01 Fe-55 3.78% 8.92E+00 Co-57 0.05% 1.22E-01 Co-58 0.09% 2.19E-01 Co-60 6.10% 1.44E+01 Ni-63 37.51% 8.85E+01 Sr-90 0.09% 2.16E-01 Cs-134 16.91% 3.99E+01 Cs-137 34.84% 8.22E+01 Ce-144 0.30% 7.14E-01 Pu-238 0.00% 2.30E-03 Pu-239 0.00% 6.71 E-04 Pu-241 0.02% 5.84E-02 Am-241 0.00% 4.70E-04 Cm-242 0.00% 6.78E-05 Cm-243 0.00% 1.36E-03 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies C-14 0.03% 1.07E-01 Mn-54 0.26% 7.89E-01 Fe-55 9.52% 2.94E+01 Co-57 0.06% 1.80E-01 Co-58 0.15% 4.50E-01 Co-60 5.54% 1.71 E+01 Ni-63 35.63% 1.10E+02 Sr-90 0.10% 3.14E-01 Ag-110m 0.04% 1.21E-01 Sb-124 0.00% 3.76E-04 Sb-125 0.01% 3.29E-02 Cs-134 14.61% 4.51E+01 Cs-137 33.68% 1.04E+02 Ce-144 0.35% 1.09E+00 Pu-238 0.00% 2.59E-03 Pu-239 0.00% 8.02E-04 Pu-241 0.02% 6.49E-02 Am-241 0.00% 6.18E-04 Cm-242 0.00% 8.02E-05 Cm-243 0.00% 1.52E-03 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 5.71% 4.44E-01 C-14 0.87% 6.75E-02 Mn-54 0.75% 5.86E-02 Fe-55 0.00% 1.30E-04 Co-57 0.130/0 9.81E-03 Co-58 4.98% 3.87E-01 Co-60 22.25% 1.73E+00

Docket No. 50-3, 50-247, & 50-286 Page 26 of 50 Ni-63 1.21% 9.40E-02 Sr-89 0.00% 1.46E-06 Sr-90 0.10% 7.91E-03 .

Nb-95 0.00% 1.58E-05 Ag-110m 0.37% 2.88E-02 Sb-125 0.63% 4.89E-02 Cs-134 8.73% 6.79E-01 Cs-137 54.27% 4.22E+00 Ce-144 0.00% 6.94E-05 Pu-238 0.00% 1.23E-05 Pu-239 0.00% 6.30E-06 Pu-241 0.00% 1.61E-04 Am-241 0.00% 3.89E-05 Cm-242 0.00% 1.48E-07 Cm-243 0.00% 6.94E-06 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 5.71% 4.44E-01 C-14 0.87% 6.75E-02 Mn-54 0.75% 5.86E-02 Fe-55 0.00% 1.30E-04 Co-57 0.13% 9.81E-03 Co-58 4.98% 3.87E-01 Co-60 22.25% 1.73E+00 Ni-63 1.21% 9.40E-02 Sr-89 0.00% 1.46E-06 Sr-90 0.10% 7.91E-03 Nb-95 0.00% 1.58E-05 Ag-110m 0.37% 2.88E-02 Sb-125 0.63% 4.89E-02 Cs-134 8.73% 6.79E-01 Cs-137 54.27% 4.22E+00 Ce-144 0.00% 6.94E-05 Pu-238 0.00% 1.23E-05 Pu-239 0.00% 6.30E-06 Pu-241 0.00% 1.61 E-04 Am-241 0.00% 3.89E-05 Cm-242 0.00% 1.48E-07 Cm-243 0.00% 6.94E-06 Other Waste Waste Class A Nuclide Name Percent Abundance Curies Fe-55 12.06% 1.11 E-04 Co-58 1.33% 1.22E-05 Co-60 36.60% 3.37E-04 Ni-63 30.52% 2.81E-04 Sr-90 0.27% 2.46E-06 Cs-137 19.23% 1.77E-04

Docket No. 50-3, 50-247, & 50-286 Page 27 of 50 Other Waste Waste Class 8 Nuclide Name Percent Abundance Curies Mn-54 0.33% 7.22E-02 Fe-55 3.93% 8.53E-01 Co-57 0.06% 1.39E-02 Co-58 0.25% 5.37E-02 Co-60 6.13% 1.33E+00 Ni-63 36.67% 7.96E+00 Sr-90 0.09% 1.95E-02 Cs-134 17.92% 3.89E+00 Cs-137 34.23% 7.43E+00 Ce-144 0.37% 8.05E-02 Pu-238 0.00% 2.07E-04 Pu-239 0.00% 6.03E-05 Pu-241 0.02% 5.31E-03 Am-241 0.00% 4.23E-05 Cm-242 0.00% 9.16E-06 Cm-243 0.00% 1.23E-04 Other Waste Waste Class All Nuclide Name Percent Abundance Curies Mn-54 0.33% 7.22E-02 Fe-55 3.93% 8.53E-01 Co-57 0.06% 1.39E-02 Co-58 0.25% 5.37E-02 Co-60 6.13% 1.33E+00 Ni-63 36.67% 7.96E+00 Sr-90 0.09% 1.95E-02 Cs-134 17.92% 3.89E+00 Cs-137 34.23% 7.43E+00 Ce-144 0.37% 8.05E-02 Pu-238 0.00% 2.07E-04 Pu-239 0.00% 6.03E-05 Pu-241 0.02% 5.31E-03 Am-241 0.00% 4.23E-05 Cm-242 0.00% 9.16E-06 Cm-243 0.00% 1.23E-04 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 5.64% 4.44E-01 C-14 0.86% 6.75E-02 Mn-54 0.74% 5.86E-02 Fe-55 0.00% 2.52E-04 Co-57 0.12% 9.81E-03 Co-58 4.91% 3.87E-01 Co-60 21.96% 1.73E+00 Ni-63 1.22% 9.62E-02 Sr-89 0.00% 1.46E-06 Sr-90 0.10% 7.93E-03 Nb-95 0.00% 1.58E-05

Docket No. 50-3, 50-247, & 50-286 Page 28 of 50 Ag-110m 0.37% 2.88E-02 Sb-125 0.62% 4.89E-02 Cs-134 8.62% 6.79E-01 Cs-137 54.83% 4.32E+00 Ce-144 0.00% 1.99E-04 Pu-238 0.00% 1.23E-05 Pu-239 0.00% 6.40E-06 Pu-241 0.00% 1.61 E-04 Am-241 0.00% 3.90E-05 Cm-242 0.00% 1.48E-07 Cm-243 0.00% 6.95E-06 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies C-14 0.11% 1.07E-01 Mn-54 0.22% 2.07E-01 Fe-55 22.57% 2.13E+01 Co-57 0.08% 7.19E-02 Co-58 0.30% 2.85E-01 Co-60 4.33% 4.09E+00 Ni-63 30.73% 2.90E+01 Sr-90 0.13% 1.18E-01 Ag-110m 0.13% 1.21 E-01 Sb-124 0.00% 3.76E-04 Sb-125 0.03% 3.29E-02 Cs-134 9.61% 9.07E+00 Cs-137 31.26% 2.95E+01 Ce-144 0.49% 4.61E-01 Pu-238 0.00% 4.98E-04 Pu-239 0.00% 1.91 E-04 Pu-241 0.01% 1.18E-02 Am-241 0.00% 1.90E-04 Cm-242 0.00% 2.15E-05 Cm-243 0.00% 2.77E-04 Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies Mn-54 0.28% 6.55E-01 Fe-55 3.78% 8.92E+00 Co-57 0.05% 1.22E-01 Co-58 0.09% 2.19E-01 Co-60 6.10% 1.44E+01 Ni-63 37.51% 8.85E+01 Sr-90 0.09% 2.16E-01 Cs-134 16.91% 3.99E+01 Cs-137 34.84% 8.22E+01 Ce-144 0.30% 7.14E-01 Pu-238 0.00% 2.30E-03 Pu-239 0.00% 6.71E-04 Pu-241 0.02% 5.84E-02 Am-241 0.00% 4.70E-04 Cm-242 0.00% 6.78E-05 Cm-243 0.00% 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 Percent Abundance Curies H-3 0.13% 4.44E-01 C-14 0.05% 1.74E-01 Mn-54 0.27% 9.20E-01 Fe-55 8.92% 3.02E+01 Co-57 0.06% 2.04E-01 Co-58 0.26% 8.91 E-01 Co-60 5.97% 2.02E+01 Ni-63 34.86% 1.18E+02 Sr-89 0.00% 1.46E-06 Sr-90 0.10% 3.42E-01 Nb-95 0.00% 1.58E-05 Ag-110m 0.04% 1.49E-01 Sb-124 0.00% 3.76E-04 Sb-125 0.02% 8. 17E-02 Cs-134 14.65% 4.96E+01 Cs-137 34.27% 1.16E+02 Ce-144 0.35% 1.18E+00 Pu-238 0.00% 2.81E-03 Pu-239 0.00% 8.69E-04 Pu-241 0.02% 7.04E-02 Am-241 0.00% 7.00E-04 Cm-242 0.00% 8.95E-05 Cm-243 0.00% 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 12/3112008 Percent Cutoff: 0 (al\ identified isotopes are included)

Waste Stream: Resins, Filters, and Evap Bottoms LWS Resin 14-170 Waste Volume Cu ries  % Error (Ci) 3 Class fe m Sh ipped A O.OOE+OO . O.OOE+ 00 O.OOE+OO +/- 25%

B 1.3 OE+ 02 3.68E+ 00 8.47E+01 +/- 25%

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

All 1.3 OE+ 02 3.68E+ 00 8.47E+01 +/- 25%

Waste Stream : Dry Active W aste,---=-~~~--:

Unit 3 DA W -2 0' Se aland DA W 40' Sea La nd Waste Volume Cu ries  % Error (Ci) 3 Class fe m Sh ipped A 6.5 OE+ 02 1.84E+01 4.5 4E-0 5 +/-25%

B 0.0 OE+ 00 O.OOE+ 00 0.00 E+O 0 +/-25%

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

All 6.50E+02 1.84E+01 4.5 4E-0 5 +/-25%

Waste Stream Irradiated Components Waste Volume Cu ries  % Error (Ci) 3 Class fe m Sh ipped A O.OOE+OO O.OOE+OO 0.00 E+O 0 +/-25%

B 0.0 OE+ 00 O.OOE+OO O.OOE+OO +/-25%

C 0.0 OE+ 00 O.OOE+OO 0.00 E+O 0 +/-25%

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

Waste Stream Other Waste C om bin ed Package s Waste Vo lum e Cu ries  % Error (Ci) 3 3 Class ft m Sh ipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

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

C 0.0 OE+ 00 O.OOE+OO 0.00 E+O 0 +/-25%

All O.OOE+OO O.OOE+OO 0.00 E+O 0 +/-25%

Waste Stream Sum of All 4 Categories Unit 3 DAW-20' Sealana LWS Resin14-170 Combined Pa cka ges DAW 40'Sea Land Waste Volume  !

Cu ries  % Error (Ci)

Class 3 fe m Sh ipped A 6.5 OE+ 02 1.84E+Ol 4.5 4E-0 5 +/-25%

B 1.30E+02 3.68E+ 00 8.47E+01 +/-25%

C 0.0 OE+ 00 O.OOE+ 00 O.OOE+OO +/-25%

All 7.8 OE+ 02 2.21E+01 8.47E+01 +/-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 Mode of Transportation Destination 2 S-J Transportation Perma-Fix of Florida 1 Hittman Transport Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance Curies H-3 0.02% 1.32E-02 Mn-54 2.23% 1.89E+00 Fe-55 22.55% 1.91 E+01 Co-57 0.05% 4.32E-02 Co-58 0.07% 6.17E-02 Co-60 11.09% 9.39E+00 Ni-63 27.86% 2.36E+01 Sr-90 0.03% 2.43E-02 Sb-125 0.93% 7.86E-01 Cs-134 11.07% 9.38E+00 Cs-137 23.85% 2.02E+01 Ce-144 0.24% 2.07E-01 Pu-238 0.00% 4.99E-05 Pu-239 0.00% 1.48E-05 Am-241 0.00% 4.89E-05 Cm c242 0.00% 4.02E-05 Cm-243 0.00% 1.99E-04 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies H-3 0.02% 1.32E-02 Mn-54 2.23% 1.89E+00 Fe-55 22.55% 1.91E+01 Co-57 0.05% 4.32E-02 Co-58 0.07% 6.17E-02 Co-60 11.09% 9.39E+00 Ni-63 27.86% 2.36E+01 Sr-90 0.03% 2.43E-02 Sb-125 0.93% 7.86E-01 Cs-134 11.07% 9.38E+00 Cs-137 23.85% 2.02E+01 Ce-144 0.24% 2.07E-01 Pu-238 0.00% 4.99E-05 Pu-239 0.00% 1.48E-05 Am-241 0.00% 4.89E-05 Cm-242 0.00% 4.02E-05 Cm-243 0.00% 1.99E-04 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies Co-60 18.19% 8.25E-06 Cs-137 81.81% 3.71E-05

Docket No. 50-3, 50-247, & 50-286 Page 32 of 50 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies Co-60 18.19% 8.2SE-06 Cs-137 81.81% 3.71E-OS Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies Co-60 18.19% 8.2SE-06 Cs-137 81.81% 3.71E-OS Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.02% 1.32E-02 Mn-S4 2.23% 1.89E+00 Fe-SS 22.SS% 1.91 E+01 Co-S7 O.OS% 4.32E-02 Co-S8 0.07% 6.17E-02 Co-60 11.09% 9.39E+00 Ni-63 27.86% 2.36E+01 Sr-90 0.03% 2.43E-02 Sb-12S 0.93% 7.86E-01 Cs-134 11.07% 9.38E+00 Cs-137 23.8S% 2.02E+01 Ce-144 0.24% 2.07E-01 Pu-238 0.00% 4.99E-OS Pu-239 0.00% 1.48E-OS Am-241 0.00% 4.89E-OS Cm-242 0.00% 4.02E-OS Cm-243 0.00% 1.99E-04 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 0.02% 1.32E-02 Mn-S4 2.23% 1.89E+00 Fe-SS 22.SS% 1.91E+01 Co-S7 O.OS% 4.32E-02 Co-S8 0.07% 6.17E-02 Co-60 11.09% 9.39E+00 Ni-63 27.86% 2.36E+01 Sr-90 0.03% 2.43E-02 Sb-12S 0.93% 7.86E-01 Cs-134 11.07% 9.38E+00 Cs-137 23.8S% 2.02E+01 Ce-144 0.24% 2.07E-01 Pu-238 0.00% 4.99E-OS Pu-239 0.00% 1.48E-OS Am-241 0.00% 4.89E-OS Cm-242 0.00% 4.02E-OS Cm-243 0.00% 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-141:

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: 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 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 Unit 3 1.S6E-4 2.83E-4 Indian Point Energy Center IPEC 6.0S7E+OO 6.267E+00 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 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 3.47E-04 3.93E-04 4.04E-04 3.81 E-04 1.47E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 6.94E-03 7.86E-03 8.08E-03 7.62E-03 1.47E-02 Age Group Child Child Child Adult I Child Critical Organ Bone Bone Bone Bone Bone Ad ult Total Bod y (mrem) 1.03E-04 1.49E-04 2.25E-04 1.34E-04 I 6.11 E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 I 3 Percent of Limit (%) 6.87E-03 9.93E-03 1.50 E-02 8.93E-03 I 2.04E-02 B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 I ANNUAL Gamma Air (mrad) 3.16E-05 3.79E-05 4.95E-05 2.66E-05 I 1.46E-04 Applicable Limit (mrad) 5 5 5 5 I 10 Percent of Limit (%) 6.32E-04 7.58E-04 9.90E-04 5.32E-04 I 1.46E-03 Beta Ai r (mrad) 9.17E-05 4.99E-05 6.17 E-03 1.97E-05 6.33E-03 Ap plicable Lim it (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 I ANNUAL 10dineIPart (mrem) 3.07E-04 4.05E-04 1.65 E-03 3.05E-04 I 2.67E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 I 15 Percent of Limit (%) 4.09E-03 5.40E-03 2.20E-02 4.07E-03 I 1.78E-02 Age Group Child Child Critical Organ Liver 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 Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 7.B4E-06 3.99E-05 1.07E-04 1.32E-04 I 2.B3E-04 Applicable Limit (mrem) 5 5 5 5 10 Pe rcent of Limit (%) 1.57E-04 7.9BE-04 2.14 E-03 2.63E-03 2.B3E-03 Age Group Child Adult Child Child Child Critical Organ Bone GILLI Bone Bone Bone Ad ult Total Bod y (mreml 4.26E-06 1.64E-05 2.96E-05 1.06E-04 I 1.56E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 I 3 Percent of Limit (%) 2.B4E-04 1.10E-03 1.97E-03 7.07E-03 I 5.21E-03 B. AIRBORNE NOBLE GAS DOSES atr 1 atr 2 atr 3 atr 4 ANNUAL Gamma Air (mrad) 4.29E-06 5.01 E-06 5.07E-06 5.00E-06 1.94E-05 Applicable Lim it (mrad) 5 5 5 5 10 Percent of Limit (%) B.5BE-05 1.00E-04 1.01E-04 1.00E-04 1.94E-04 Beta Ai r (mrad) 7.0BE-06 B.26E-06 B.53E-06 B.3BE-06 I 3.23E-05 Ap plicable Lim it ( mrad) 10 10 10 10 I 20 Percent of Limit (%) 7.0BE-05 B.26E-05 B.53E-05 B.3BE-05 I 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 5.67E-04 4.25E-04 1.99E-03 Ap plicable Lim it (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 6.69E-03 6.61 E-03 7.56E-03 5.67E-03 1.33E-02 Age Group Child Critical Organ 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 aDCM 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 03.5.1-1. Additionally, Ni-63 data was added to Tables 3.5.1-2 and 3.5.1.3, and Section 05.6 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 (1a1-1a4) 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 IPEG 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 aDCM 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 aDCM 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 JPEe Summaryfo(storin & 'Gr'oundWatElr relea,ses (H~j C:o-60,t-.li~3, Sr-!W,ar(cj C~-'t~7); 2008 yefjr' Northern Clean Zone, Adult Doses.in mrem' l'-,;@!it!Ci* .

4.:15E+02 C<r60' ~'>O'OOEfOO\. +iO:OOE+OO., O:OOE+OO;;"c\'i i'"LO.OOE+OOt 'O.OOE+OO O:OOE+OO"'; .~ ;O:OOE+OO;:A .O'OOE+OO Ni"63  :<O,OOEtOOJ,< ;'O.OOE+OO': >.'O*OOEfOO# "~iii:, J;,: O.OOE+OO O.OOE+OO O;OOE+OOE) : ',.O.OOEfom> :O.ooE+oo Src90  ;:';:YO.OOE+OO";;"; : O:OOE+OO:(*~ O:OOE+OO, 'i" '*,:O.OOE+OO O.OOE+OO O:OOE+OOi:i: Z:.. O.OOE+oo';r O,OOE+oo.

Cs"13T t'O.OOE+OO *O.OOE+OO;t:2 :,i:J);:,O:OOEtOO:': ,. '"O:OOE+OO'" iF*O.OOEfOO:gO:OOE+OOi,!,: D?\O:OOEfOO~:i '0:00£,:00, totals A

  • O,OOE+OO.* 4.64E-09' 4.64E-09 . 4;64E~09 I" *4.64E"09*' 4,64E-D9,' A.64E-D9 E.4f15Ef02i..

Uilif2 North Unit 112 l+i:lsp;rQPE,:"i; ;;'.BQNEf(t\!l!iJi' &j~~'IHYER~:J:\':  ;;;;:qOOl'~BOoY;irf;, !'~'iliHYROIDJm;; f;:m!iI<lDNEy,,:;}3;\ ~{I&:!iiI1UNI:3m':mm.l! iii,l'iil:3lfIlUl'$li¥ ,

. H-3 }:::,OOOEfOO,',,':\S:99E-OS S.99E~OS,; :8. 99ElOS ".' S'99E08 8: 99E::OS\,", ':}S:99E"08:'

.C<r60 '.O.OOE+OO.' :;:",n5E~06 ; "':2'97E-06, I," O;OOE+OO O.OOE+OO O.OOE+OO* ';2;53E~05Y Ni-63 O:OOE+OO*>\.,O.OOE+OO O:OOE+OO';* O'OOE+OO ' ";O;OOE+OOO:OOE+OO" !i .O:OOE+OO.c*

Sr-90' ,*.*.;645E-04 . O.OOE+OO*":* '.:t58Ec04', . f;,:O:OOE+OO;:::,~ /',";O.OOEtOO'; ;'/:O'OOEtOO;': ;'\,f86E05' :'"

Csc 137  !';;\:329E,054.50E-05 ',. .. 2.95E'05<'L; O:OOE+oO'" ;PfT1(53Ec05",1>i: :r~5'07E-D6':'" ", 8:6SE~07Y' totals 6.7SEc04 4.64E~05 1.9*1 E~04 899E,OS 1.53E,05* 5. 16E-Q6 4,49E"05 Uriit3 North

'!j};UCi.i1)E 3.83E+03 C<r60 ,O.OOE+OO 5.53F07 ';'t,22E,06 O:OOE+oO'- ">O.OOE+OO/* '*"'O.OOEfOO  ;':',;,t04E,05':'i '9A2E+00 Ni-63 'O.ooE+oo

)"
: O.OOE+OO',,,,
  • O.OOE+OO O:OOE;l:OO" i/* o. . OOE+O ....0'<1,:,*.,** .,* .',,.* *,. O. . OOE+. 00.*. *.' ' 0 . ODE +00'" ;; ,;O:OOE+OO.i:';:;

Sr-90 E':c'6::15Ei05/;"" O:OOE+OOi' . 1.51 Ec05,ji}i i" O.OOE+( ,. :., .O.OOE+OO O.OOE+OO :',1 i:;'.:!\1'.77F06i' '2.45E+00 Cs-137  :;, "OOOE+OO'i", 'XO:OOE+oO ';,'LOOOE+OO';;'J: "" O.OOE+O  ::.\O.OOE+OO. ",O:OOE+oO,,(, H1*'O.OOE+00"" O.OOE+OO totals . 6.15E"05 5:S6E-07 1.63E-05 3.26E~OS I. 3.26EC08 3:26E-DS 1.22E"05 ,31849031 Unit3' SOuth

~: ** i iJCj "'>'"
  • 1,65E+05 C<r60  ;: ,.'O:OOE-tOO,>, ", O,OOE+OO:;'.* . ,',:, 'O:OOE+OO'*",:.'" O'OOE+OO"" , 'O'OOE+OO}::'c "O.OOE+OO:'~ * '.O,OOE+OO*' O:ooE+oo Ni-63 ~" O:OOE+OO" '{O:OOEfOO : . O:OOE+OO ".:O:OOE+OO "*O.OOE+OO'* 'O:OOE+OO; O.OOE+OO. 0.00£+00
  • 9:.47E+00 2.'05E+.01 totals 1:95E-04 5.89EC05 T59Ec05 3. 99E-D8 2:00E:05* 6.68E-D6 ,5.56Ec06 'l,1!65905' ,

!,ii).;ioq,ti&i .

3.38E+03 2:22£+01'

'O:OOE+.oo O:ooE+oo.

  • O:ooE+oo.

'3[4()903 Totals: AdUit'Doses, in mrem H-30nly I O.OOEfOO I 2.19E,07 I 2.19E-07 I 2. 19E"D7I ' 2.19E"07 I 2. 19E-D7 I 2:.19E"07 I TotaFuCis

',;;,iJ<f'SONE,U"GllllO/i:1IIIIlER':;;';lfl1TOI*SODYffiNVIIW.;"THYROID~IWlif':KIDNEY' *:Y'IYi*ul'LUNG' * 'I!'* X;YGllLLI:;;t;i,0'1 2:12E+05 Hi all isotopes' 9.35E,,()4 11.07E~04 I 2.B6E~4 I 2. 19E-07 . I 3.55E-05 I 1: 19Ec05 I S.72E-05

  • 5A6E+01 CO O,OOE+OO NI

'9:30E+'01 Sr' 5'.45E+01 cs

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 aDeM and NEI 07-07.

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

  1. # Positive Average Minimum Maximum Samples Samples in Positive Positive Positive Well Name in 2008 2008 Activit~ Activit~ Activit~

8-1 2 2 6.99E+02 2.27E+02 1.17E+03 8-6 2 1 4.72E+02 4.72E+02 4.72E+02 MH-5 1 1 9.28E+02 9.28E+02 9.28E+02 MW-107 2 1 1.91E+02 1.91E+02 1.91E+02 MW-111 3 3 6.27E+04 4.77E+04 7.39E+04 MW-30-69 6 6 1.32E+05 7.36E+04 1.99E+05 MW-30-84 6 6 4.29E+03 3.78E+03 5.25E+03 MW-31-49 5 5 3.20E+03 3.97E+02 1.36E+04 MW-31-63 6 6 1.85E+04 1.02E+04 2.55E+04 MW-31-85 6 6 4.37E+03 1.31E+03 8.34E+03 MW-32-131 2 2 7.67E+02 5.04E+02 1.03E+03 MW-32-149 4 4 7.67E+02 5.03E+02 ,1.15E+03 MW-32-173 5 5 1.63E+03 9.72E+02 3.40E+03 MW-32-190 5 5 5.50E+03 3.35E+03 8.89E+03 MW-32-59 6 6 5.02E+03 4.13E+02 1.87E+04 MW-32-85 6 6 9.05E+03 7.48E+03 1.11E+04 MW-33 2 2 6.33E+04 5.85E+04 6.80E+04 MW-35 1 1 1.04E+03 1.04E+03 1.04E+03 MW-36-24 3 3 1.13E+03 2.01E+02 2.16E+03 MW-36-52 3 3 1.16E+04 1.10E+04 1.26E+04 MW-37-22, 3 3 4.51E+03 2.68E+03 6.52E+03 MW-37-32 3 3 4.94E+03 2.89E+03 6.76E+03 MW-37-40 3 3 5.82E+03 5.24E+03 6.73E+03 MW-37-57 3 3 5.41E+03 4.27E+03 6.63E+03 MW-39-102 3 1 5.03E+02 5.03E+02 5.03E+02 MW-39-124 3 3 2.04E+02 1.67E+02 2.31E+02 MW-39-195 3 1 2.74E+02 2.74E+02 2.74E+02 MW-39-67 3 3 3.63E+02 3.18E+02 4.15E+02 MW-39-84 3 1 ' 2.34E+02 2.34E+02 2.34E+02 MW-40-100 4 1 1.93E+02 1.93E+02 1.93E+02 MW-40-127 4 1 1.68E+02 1.68E+02 1.68E+02 MW-40-162 3 1 2.30E+02 2.30E+02 2.30E+02 MW-40-27 3 1 2.22E+02 2.22E+02 2.22E+02 MW-40-46 3 1 1.68E+02 1.68E+02 1.68E+02 MW-40-81 3 1 2.42E+02 2.42E+02 2.42E+02 MW-41-40 2 2 1.21E+03 2.15E+02 2.21E+03 MW-41-63 2 2 4.97E+02 3.03E+02 6.91E+02 MW-42-49 6 6 4.11E+03 1.12E+03 1.32E+04 MW-42-78 3 3 5.09E+02 3.46E+02 6.18E+02 MW-43-28 2 2 2.86E+02 2.65E+02 3.06E+02 MW-43-62 2 1 2.25E+02 2.25E+02 2.25E+02

Docket No. 50-3, 50-247, & 50-286 Page 45 of 50 Tritium (H-31 Summary page 2 of 3

  1. # Positive Samples Samples Avg Pos Min Pos Max Pos Well Name in 2008 in 2008 Act Act Act MW-44-102 4 4 3.65E+02 2.56E+02 4.75E+02 MW-44-66 4 3 4.28E+02 3.18E+02 5.50E+02 MW-45-42 4 4 2.01E+03 1.13E+03 3.14E+03 MW-45-61 4 4 1.99E+03 1.27E+03 2.66E+03 MW-46 4 4 8.05E+02 5.21E+02 1.38E+03 MW-49-26 4 4 4.16E+03 3.47E+03 5.00E+03 MW-49-42 4 4 2.77E+03 2.52E+03 3.20E+03 MW-49-65 4 4 1.65E+03 1.26E+03 1.93E+03 MW-50-42 4 3 6.45E+02 3.73E+02 9.48E+02 MW-50-66 7 7 2.83E+03 2.08E+03 3.74E+03 MW-51 -104 3 1 2.82E+02 2.82E+02 2.82E+02 MW-51-135 3 1 2.09E+02 2.09E+02 2.09E+02 MW-51-40 4 1 3.29E+02 3.29E+02 3.29E+02 MW-52-11 1 1.13E+03 1.13E+03 1.13E+03 MW-52-162 1 1.45E+02 1.45E+02 1.45E+02 MW-52-18 1 1 2.79E+02 2.79E+02 2.79E+02 MW-52-181 1 1 1.56E+02 1.56E+02 1.56E+02 MW-52-48 1 1 2.30E+02 2.30E+02 2.30E+02 MW-53-120 6 6 5.93E+03 5.04E+03 7.48E+03 MW-53-82 3 3 9.82E+02 7.94E+02 1.21E+03 MW-54-123 4 4 6.06E+02 5.33E+02 6.98E+02 MW-54-144 4 4 1.21E+03 1.13E+03 1.40E+03 MW-54-173 4 4 1.92E+03 1.66E+03 2.11E+03 MW-54-190 4 4 1.69E+03 1.25E+03 2.24E+03 MW-54-37 4 4 1.04E+03 8.70E+02 1.25E+03 MW-54-58 4 4 6.64E+02 5.78E+02 7.33E+02 MW-55-24 4 4 1.09E+03 7.82E+02 1.40E+03 MW-55-35 3 3 1.89E+03 1.60E+03 2.33E+03 MW-55-54 4 4 6.88E+03 5.96E+03 7.76E+03 MW-56-53 2 2 3.31E+02 2.63E+02 3.99E+02 MW-56-83 2 2 2.46E+03 1.94E+03 2.98E+03 MW-57-11 2 2 2.73E+03 2.17E+03 3.28E+03 MW-57-20 2 2 1.12E+03 7.27E+02 1.51E+03 MW-57-45 2 2 8.48E+02 5.65E+02 1.13E+03 MW-58-26 2 2 2.67E+02 2.38E+02 2.95E+02 MW-58-65 2 2 2.97E+02 2.81E+02 3.13E+02 MW-60-135 4 4 4.70E+02 3.79E+02 5.85E+02 MW-60-154 4 4 5.54E+02 4.53E+02 6.87E+02 MW-60-176 4 4 7.93E+02 6.68E+02 8.95E+02 MW-60-35 4 1 1.95E+02 1.95E+02 1.95E+02 MW-60-72 4 1.94E+02 1.94E+02 1.94E+02

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

  1. # 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 S.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.S6E+02 3.99E+02 4.98E+02 MW-62-37 3 3 4.42E+02 3.94E+02 S.3SE+02 MW-62-S3 3 3 3.69E+02 3.48E+02 4.08E+02 MW-62-71 3 3 4.43E+02 3.S3E+02 S.12E+02 MW-62-92 3 3 4.S7E+02 3.94E+02 4.9SE+02 MW-63-112 4 4 3.31 E+02 2.07E+02 4.69E+02 MW-63-121 4 4. 4.S8E+02 3.44E+02 S.4OE+02 MW-63-163 4 4 S.36E+02 4.44E+02 6.8SE+02 MW-63-174 4 4 S.10E+02 4.49E+02 6.23E+02 MW-63-18 4 2 2.89E+02 2.S7E+02 3.20E+02 MW-63-34 4 4 4.18E+02 3.26E+02 4.90E+02 MW-63-S0 4 4 3.20E+02 2.70E+02 3.S6E+02 MW-63-93 4 4 2.86E+02 2.1SE+02 3.90E+02 MW-66-21 4 4 7.72E+02 S.34E+02 9.S3E+02 MW-66-36 4 4 S.9SE+03 S.01E+03 7.26E+03 MW-67-10S 4 4 2.48E+03 2.16E+03 2.93E+03 MW-67-173 4 4 8.88E+02 6.9SE+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 S S 3.73E+03 3.07E+03 4.35E+03 U1-CSS 6 6 1.54E+03 4.95E+02 2.66E+03 U3-40 4 4 4.32E+02 3.19E+02 S.68E+02 U3-T1 4 4 6.48E+02 S.S6E+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-S1. 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 MOC is 200 pC ilL.

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

  1. Positive
  1. Samples in Samples in Ave Pos Min Pos Max Pos Well Name 2008 2008 Act Act Act MW-40-162 3 1 3.15E+00 3.15E+00 3.15E+00 MW-42-49 6 2 1.12E+01 5.47E+00 1.69E+01 MW-54-123 4 4.12E+00 4.12E+00 4.12E+00 MW-62-92 3 5.16E+00 5.16E+00 5.16E+00 MW-67-39 5 1.59E+01 1.59E+01 1.59E+01 Note 1: All results are in pCi/L Note 2: 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.

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 15 pCi/L.

Nickel-63 Summary

  1. Positive
  1. Samples in Samples in Ave Pos Min Pos Max Pos Well Name 2008 2008 Act Act Act MW-42-49 6 6 4.21E+02 2.44E+02 7.34E+02 MW-53-120 6 4 2.23E+01 1.94E+01 2.65E+01 Note 1: All results are in pC ilL Note 2: 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.

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 30 pCilL.

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

  1. # Positive Samples Samples in Ave Pos Min Pos Max Pos Well Name in 2008 2008 Act Act Act LAF-002 2 1 4.73E-01 4.73E-01 4.73E-01 MW-111 3 2 1.79E+OO 1.02E+OO
  • 2.56E+OO MW-32-173 5 6.80E-01 6.80E-01 6.80E-01 MW-36-52 3 3 6.26E+OO 4.85E+OO 8.27E+OO MW-37-22 3 3 1.30E+01 8.73E+OO 1.80E+01 MW-37-32 3 3 1.81 E+01 1.52E+01 2.06E+01 MW-37-40 3 3 1.13E+OO 9.48E-01 1.31E+OO MW-37-57 3 3 2.47E+01 2.12E+01 2.89E+01 MW-39-102 3 3 1.03E+OO 8.83E-01 1.23E+OO MW-39-124 3 3 1.40E+OO 9.42E-01 1.79E+OO MW-39-183 3 2 9.75E-01 8.29E-01 1.12E+OO MW-39-195 3 3 9.96E-01 8.81E-01 1.21E+OO MW-39-67 3 3 3.01E+OO 2.21E+OO 3.52E+OO MW-39-84* 3 3 1.68E+OO 1.04E+OO 2.23E+OO MW-41-40 2 2 4.48E+OO 3.05E+OO 5.91E+OO MW-41-63 2 2 4.73E+OO 3.76E+OO 5.69E+OO MW-42-49 6 6 9.78E+01 2.36E+01 2.96E+02 MW-42-78 3 1 3.91E-01 3.91 E-01 3.91E-01 MW-43-62 2 1 1.00E+OO 1.00E+OO 1.00E+OO MW-46 4 1 9.33E-01 9.33E-01 9.33E-01 MW-49-26 4 4 1.81E+01 1.53E+01 . 2.29E+01 MW-49-42 4 4 2.40E+01 2.16E+01 2.94E+01 MW-49-65 4 4 2.03E+01 1.72E+01 2.73E+01 MW-5O-42 4 4 - 4.29E+OO 2.40E+OO 9.28E+OO MW-5O-66 7 7 3.61E+01 3.20E+01 4.99E+01 MW-52-162 1 1.03E+OO 1.03E+OO 1.03E+OO MW-53-120 6 6 3.19E+01 2.53E+01 4.25E+01 MW-53-82 3 1 6.95E-01 6.95E-01 6.95E-01 MW-54-123 4 4 8.78E+OO 6.45E+OO 1.26E+01 MW-54-144 4 4 1.71 E+01 1.53E+01 2.02E+01 MW-54-173 4 4 1.38E+01 1.22E+01 1.61 E+01 MW-54-190 4 4 2.35E+01 1.93E+01 3.38E+01 MW-54-37 4 4 6.10E+OO 5.08E+OO 7.33E+OO MW-54-58 4 4 3.69E+OO 1.69E+OO 9.02E+OO MW-55-24 4 4 2.03E+01 1.08E+01 2.55E+01 MW-55-35 3 3 2.87E+01 2.54E+01 3.44E+01 MW-55-54 4 4 2.30E+01 1.94E+01 2.67E+01 MW-56-83 2 2 2.85E+OO 2.13E+OO 3.56E+OO

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

  1. # Positive Samples Samples in Ave Pos Min Pos Max Pos Well Name in 2008 2008 Act Act Act MW-57-11 2 2 3.22E+01 2.27E+01 4.16E+01 MW-57-20 2 2 2.15E+00 1.23E+00 3.06E+00 MW-57-45 2 2 1.73E+00 1.20E+00 2.26E+00 MW-62-138 3 3 1.06E+00 7.34E-01 1.24E+00 MW-62-18 3 1 5.31 E-01 5.31 E-01 5.31E-01 MW-62-37 3 1 1.36E+00 1.36E+00 1.36E+00 MW-63-121 4 1 6.63E-01 6.63E-01 6.63E-01 MW-66-21 4 4 1.01 E+OO 9.07E-01 1.09E+00 MW-66-36 4 4 1.35E+01 1.20E+01 1.51 E+01 MW-67-105 4 :3 1.07E+00 9.63E-01 1.13E+00 MW-67-39 5 5 1.83E+01 1.37E+01 2.59E+01 U1-CSS 6 6 7.42E+00 4.83E+00 9.38E+00 U3-T1 4 1 7.01 E-01 7.01E-01 7.01 E-01 U3-T2 4 1 6.52E-01 6.52E-01 6.52E-01 Note 1: All results are in pC ilL.

Note 2: 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.

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 1 pC ilL.

Docket No. 50-3, 50-247, & 50-286 Page 50 of 50 Cesium-137 Summary

  1. # Positive Samples Samples in Ave Pos Min Pos Max Pos Well Name in 2008 2008 Act Act Act B-1 2 1 2.00E+01 2.00E+01 2.00E+01 MW-41-40 2 1 2.67E+00 2.67E+00 2.67E+00 MW-42-49 6 6 1.90E+04 1.06E+04 3.3SE+04 MW-42-7S 3 1 1.0SE+02 1.0SE+02 1.0SE+02 MW-44-102 4 1 1.73E+01 1.73E+01 1.73E+01 MW-44-66 4 1 1.1SE+01 1.1SE+01 1.1SE+01 MW-SO-42 4 1 1.63E+01 1.63E+01 1.63E+01 MW-SO-66 7 1 1.S6E+01 1.S6E+01 1.S6E+01 MW-SS-24 4 1 3.33E+00 3.33E+00 3.33E+00 MW-67-10S 4 1 9.32E+00 9.32E+00 9.32E+00 MW-67-173 4 1 S.S2E+00 S.S2E+00 S.S2E+00 MW-67-219 4 1 4.2SE+00 4.2SE+00 4.2SE+00 MW-67-276 4 4.SSE+00 4.SSE+00 4.SSE+00 MW-67-340 4 1 S.S2E+00 S.S2E+00 S.S2E+00 Note 1: All results are in pC ilL Note 2: A total of 406 samples were analyzed for Cs-137 in 200S with only 19 positive results. This total includes samples from REMP wells MW-40 and MW-S1. 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 MOC is 1S pC ilL.

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