NL-07-050, Units, 1, 2 and 3 - 2006 Annual Radioactive Effluent Release Report

From kanterella
(Redirected from ML071230305)
Jump to navigation Jump to search
Units, 1, 2 and 3 - 2006 Annual Radioactive Effluent Release Report
ML071230305
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 04/25/2007
From: Jones T
Entergy Corp, Entergy Nuclear Operations
To:
Document Control Desk, NRC/FSME
References
FOIA/PA-2007-0324, NL-07-050, RG-1.021
Download: ML071230305 (49)
v • d • e


Text

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 1Buchanan,Entfffl(Tel N.Y. 10511-0249 (914) 734-6670 T.R. Jones Manager, Licensing April 25, 2007 Re: Indian Point Units No 1, 2, 3 Docket Nos. 50-3, 50-247, 50-286 NL-07-050 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

2006 Annual Radioactive Effluent Release Report

Dear Sir or Madam:

Enclosed is the 2006 Annual Effluent and Waste Disposal Report for Indian Point Unit Nos. 1, 2, and 3. Entergy Nuclear Operations, Inc. (Entergy) is submitting this report in accordance with Technical Specification 5.6.3 and Regulatory Guide 1.21.

Entergy Nuclear Operations, Inc. is making no new commitments in this letter.

Should you have any questions regarding this matter, please contact Mr. T.R. Jones, Manager, Licensing, at (914) 734-6670.

Respectfully, T.R. Jone Manager, Licensing Indian Point Energy Center

Enclosure:

2006 Annual Radioactive Effluent Release Report cc: next page 1qgo

Docket Nos. 50-3, 50-247, 50-286 NL-07-050 Page 2 of 2 cc: Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. John P. Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point 2 NRC Resident Inspector's Office, Indian Point 3 Chief, Compliance Section, New York State DEC, Division of Water Regional Water Engineer, New York State DEC Mr. Paul Eddy, NYS Department of Public Service Mr. Robert Oliveira, American Nuclear Insurers Mr. Robert Snyder, NYS Department of Health Mr. Larry Wilson, NYS Department of Environmental Conservation Director, Spent Fuel Project Office, Office of Nuclear Material Safety & Safeguards

ENCLOSURE TO NL-07-050 Indian Point Energy Center 2006 Annual Radioactive Effluent Release Report ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 1, 2, AND 3 NUCLEAR POWER PLANTS DOCKET NOS. 50-03, 50-247, AND 50-286

Docket No. 50-3, 50-247, & 50-286 Page 1 of 46 Radioactive Effluent Release Report: 2006 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, Technical Specifications, and an Offsite Dose Calculation Manual. Therefore, radioactive effluent from Unit 1 is included with Unit 2 in this report.

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.

It is defined in each unit's ODCM as the basis for the release concentration limits, and applies to the applicable version of 10CFR20 to which the unit is licensed. Unit 2's limit is defined at the higher of the those limits specified in the OLD 10CFR20, while Unit 3 is limited to "EC*10"from the NEW Part 20.

Unit 2's technical specifications were updated in late December, 2006, and the unit 2 ODCM was updated in Jan, 2007 to reflect the new 10CFR20. As of January 1, 2007, liquid effluent controls at both units are now identical, using the NEW version of 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, and a maximum gamma concentration of 5E-5 uCi/mI (without gas or tritium) for these routine effluents.

Docket No. 50-3, 50-247, & 50-286 Page 2 of 46

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:

1 st Quarter I* =1.56E-01 Mev/dis Ey= 4.15E-02 Mev/dis 2nd Quarter I* =1.46E-01 Mev/dis Ey= 5.21 E-02 Mev/dis 3rd Quarter E: = 2.52E-01 Mev/dis Ey= 2.70E-02 Mev/dis 4th Quarter = 2.45E-01 Mev/dis Ey = 4.67E-02 Mev/dis Unit 3:

1st Quarter 3.47E-01 Mev/dis y= 8.42E-01 Mev/dis 2nd Quarter EI 3.66E-01 Mev/dis E*y = 9.10E-01 Mev/dis 3rd Quarter = 2.72E-01 Mev/dis E y= 5.59E-01 Mev/dis 4th Quarter IE = 1.55E-01 Mev/dis Ey = 1.22E-01 Mev/dis

4. Measurements and Approximations of Total Radioactivity a) Fission and Activation Gases Analyses of effluent gases have been 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. This analysis is used in conjunction with a process monitor to obtain the isotopic mixture and quantification of each pressure relief. 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.

Docket No. 50-3, 50-247, & 50-286 Page 3 of 46 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.

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-1 3 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). Because the unprocessed water may contain trace levels of Tritium, etc, it is included in the report, but the volumes are differentiated to prevent confusion regarding the total volume of waste released to the Hudson River. The curies reported in the following tables, however, are totals of all liquid effluent, continuous and batch, whether processed or not.

Docket No. 50-3, 50-247, & 50-286 Page 4 of 46

5. Batch Releases Airborne:

Unit I and 2 Airborne Releases Qtr 1 Qtr 2. Qtr 3 Qtr 4 2006 Number of Batch Releases 53 56 45 39 193 Total Time Period (min) 2770 5330 2100 2640 12840 Maximum Time Period (min) 134 630 130 119 630 Average Time Period (min) 52.2 95.3 46.6 67.6 66.5 Minimum Time Period (min) 3 2 3 2 2 Unit 3 Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2006 Number of Batch Releases 21 21 24 17 83 Total Time Period (min) 3680 3950 3620 3650 14900 Maximum Time Period (min) 275 290 348 289 348 Average Time Period (min) 175 188 151 215 179 Minimum Time Period (min) 3 6 1 17 1 Liquid:

Unit I and 2 Liquid Releases Qtr 1 Qtr 2 Qtr3 I Qtr 4 2006 Number of Batch Releases 25 42 10 7 84 Total Time Period (min) 3240 7660 1030 895 12825 Maximum Time Period (min) 580 720 120 234 720 Average Time Period (min) 129 182 103 128 153 Minimum Time Period (min) 90 60 50 100 50 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr4 2006 Number of Batch Releases 10 8 20 10 48 Total Time Period (min) 1020 859 2200 1070 5149 Maximum Time Period (min) 121 114 120 170 170 Average Time Period (min) 102 107 110 107 107 Minimum Time Period (min) 61 95 103 53 53 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 become available.

Estimated Average Stream Flows of the Hudson River at Indian Point:

Va~,r r l I'%,

"O r I r" M WVV Jýfý I

ýIvl WUU1 Lýl 2004 Fourth 23000 2005 First 28000 2005 Second 28467 2005 Third 6667

Docket No. 50-3, 50-247, & 50-286 Page 5 of 46

6. Abnormal Releases a) Liqui The effluent contribution via ground water (broken up into storm drain and bedrock pathways) is discussed in Section H. Effluent dose calculations were performed from samples of numerous Monitoring Wells and Storm Drains, along with release and dilution flow rate analyses. Dose calculation results identified in the summary of Section H are added to the site total summary in the opening discussion of Section E, dose to man report.

b) Gaseous None

7. ODCM Reportinq Requirements The ODCM (RECS) requires reporting of prolonged outages of effluent monitoring equipment. Also required in this report is notification of any changes in the land use census, the Radiological Environmental Monitoring Program (REMP), or exceeding the total curie content limitations in outdoor tanks.

During this reporting period, the following ODCM required effluent monitoring equipment was out of service (OOS) for periods greater than 30 consecutive days:

  • Instrument Out of Service Details Period, The monitor was declared inoperable due to intermittent Unit 1, Sphere Jan 01,2006 functionality during this time period. Delay in returning to Foundation Drain to service was a result of the age of equipment, significant Sump Monitor, Feb 15, 2006 troubleshooting, and delays in procuring parts.

R-62 Compensatory grab samples were obtained during this interval.

The instrument was originally taken out of service for troubleshooting. During subsequent investigation, it was Unit 1, Sphere Mdetermined that the existing instrument was not suitable for Foundation Drain Mar 14, 2006 the application. Ultimately, a modification was required to Sump Flow Jun 30, 2006 be generated and installed to support resolution. This Integrator included modification design, equipment procurement, scheduling and installation. Compensatory estimates were performed during this interval.

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

There were no changes to the Process Control Programs during this reporting period.

There were no changes to the ODCMs during this reporting period. However, several significant additions to the ODCM were completed in Jan, 2007 to describe the ongoing actions from the Ground Water investigation. While these actions included significant analyses performed in 2006, the ODCMs were not updated until sufficient learnings could be captured. Since this occurred in January 2007, the ODCM updates will be included in the 2007 annual report. They are also available any time upon request.

Docket No. 50-3, 50-247, & 50-286 Page 6 of 46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2006

Docket No. 50-3, 50-247, & 50-286 Page 7 of 46 TABLE 1A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A Fission&Activation Gases %Error Units Qtr1 Qtr2 Qtr3 Qtr4 2006

1. Total Release a) 4.30E+01 1.73E+02 1.64E-+00 5.70E-01 2.19E-.02 +25
2. Average release rate u(/sec 5.53E+00 2.20E+01 2.07E-01 7.17E-02 6.93E+00 B. lodnes
1. Total lodine-131 Ca 2-15E-06 7.85E-04 - 7.87E-04 +25
2. Average release rate uC/sec 2.77E-07 9.99E-05 - - 2.50E-05 C Particulates
1. Total Release, wth a 9.84E-06 1.83E-05 1.94E-05 - 4.76E-05 + 25 half-life > 8 days
2. Average release rate uCi/sec 1.27E-06 2.33E-06 2.44E-06 - 1.51E-06
3. GrossApha C3 +25 D. Tritium
1. Total release C) 1.74E500 6.12E+00 3.68E+00 2.83E+00 1.44E+01 +25
2. Average release rate u(3/sec 2.24E-01 7.79E-01 4.63E-01 3.57E-01 4.56E-01

- Indcates < NMD

Docket No. 50-3, 50-247, & 50-286 Page 8 of 46 TABLE IC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2006 Xe-1 31m Ci I 1.91E-02 - 1.91E-02 Xe-133 Ci I 3.28E+00 4.02E+01 - 4.34E+01 IXe-135 Ci 6.12E-02 6.12E-02 Ttal for Period Ci 3.28E+00 4.02E+01 0.OOE+00 I_0.00E+00 4.35E+01
2) lodines Ci [-131 2.15E-06 7.85E-04 - 7.87E-04 1-133 Ci 1.21E-04 - 1.21E-04

-- Toal1-135 for Period Ci Ci 2,15E-06 9.07E-04 0.00E+00 0.OOE+00 Tot -. 9.09E-04

3) Particulates Co-58 Ci - 2.75E-06 2.75E-06 Cs-1 37 Ci 9.07E-06 1.39E-05 1.17E-05 3.46E-05 Ni-63 Ci 7.66E-07 1.72E-06 7.75E-06 1.02E-05 Total for Period Ci 9.84E-06 1.83E-05 1.94E-05 0.OOE+00 4.76E-05

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 9 of 46 TABLE IC INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

BATCH GASEOUS EFFLUENTS Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2006 Ar-41 Ci 4.79E-02 1.33E-01 2.52E-02 1.64E-02 2.23E-01 Kr-85 Ci 7.13E+00 7.40E+00 1.57E+00 4.90E-01 1.66E+01 Kr-85m Ci 1.55E-02 2.77E-01 1.00E-03 1.98E-04 2.94E-01 Kr-87 Ci 5.15E-03 1.01E-03 6.90E-04 3.05E-05 6.88E-03 Kr-88 Ci 1.79E-02 1.43E-01 1.51E-03 1.97E-04 1.63E-01 Xe-131m Ci 6.18E-01 1.34E+00 - 0 1.95E+00 Xe-133 Ci 3.16E+01 1.18E+02 2.96E-02 5.65E-02 1.49E+02 Xe-133m Ci 1.60E-01 1.48E+00 2.32E-04 4.64E-04 1.64E+00 Xe-135 Ci 1.62E-01 4.73E+00 1.17E-02 5.65E-03 4.90E+00 Xe-135m Ci 5.83E-03 2.34E-03 1.47E-03 1.81E-05 9.66E-03 Xe-1 38 Ci 1.49E-03 6.16E-04 4.45E-06 2.11 E-03 Total for Period Ci 3.98E+01 J1.33E+02I 1.64E+00I 5,70E-01 I 1.75E+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 10 of 46 TABLE 1A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A Fission & bvabon Gases %Eror Wnits QIrl1 Qtr2 Qtr3 Qtr4 2006 1.Total Release a 3.51E-02 4.31E-02 6.93E-02 6.45E-01 7.93E-01 + 25

2. Average release rate ui/sec 4.52E-03 5.49E-03 8.72E-03 8.12E-02 2.51E-02 B. locdnes
1. Total lodine-131
2. Average release rate C

uCL/sec ji

- +25

]

C. Particulates

1. Total Release, wth half-life > 8 days
2. Average release rate ui/sec
3. Gross Apha C - +25 D. Tritium
1. Total release 0 1.14E+00 1.66E+00 2.23E&j0 1.42E-0
2. Average release rate ui/sec 1.47E-01 2.111E-01 2.81E-01 1.79E-01 I2.05E-01

- Irdcates < NUA

Docket No. 50-3, 50-247, & 50-286 Page 11 of 46 TABLE IC INDIAN POINT 3 - CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

Nuclides Released Year

1) Fission Gases 2006 Units Qtrl1 Qtr2 Qtr3 Qtr4 Y

1Xe-1 33 Ci 0.OOE+00 0.OOE+00 0.OOE+00 5,21E-01 5.21E-01

-9 I

Total for Period Ci 0.OOE+00 0.OOE+00 0.00E+00 5.21E-01 5.21E-01

2) lodines
3) Particulates Total for Period Ci

- indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 12 of 46 TABLE IC INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

BATCH GASEOUS EFFLUENTS Nuclides Released Year

1) Fission Gases 2006 Units Qtr I Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 2.26E-02 3.01E-02 2.87E-02 3.94E-02 1.21E-01 Kr-85 Ci - - - - -

Kr-85m Ci - - - - -

Kr-87 Ci - - - - -

Kr-88 Ci - - - - -

Xe-131m Ci - - - -

Xe-133 Ci 1.25E-02 1.27E-02 4.05E-02 8.40E-02 1.50E-01 Xe-133m Ci Xe-1 35 Ci - 4.07E-04 9.02E-05 4.77E-04 9.74E-04 Xe-1 35m Ci Total for Period Ci 3.51E-02 4.31E-02 6.93E-02 1.24E-01 2.72E-01

2) lodines Not Applicable for Batch Releases
3) Particulates Not Applicable for Batch Releases

Docket No. 50-3, 50-247, & 50-286 Page 13 of 46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2006

Docket No. 50-3, 50-247, & 50-286 Page 14 of 46 TABLE 2A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A Fission &Activation Products Qtr 2 Qtr 3 Qtr 4 2006  % Error Units Qtr I Ci 3.45E-02 1.49E-02 2.02E-03 2.21 E-03 5.37E-02 +25 uCi/mI 5.89E-11 2.35E-11 2.36E-12 3.09E-12 1.92E-11 B. Tritium r Y I

1. Total Release 2.06E+02 1.35E+01 3.29E+01 8.27E+02 +25 3.24E-07 1.57E-08 4.60E-08 2.96E-07 I

C. Dissolved & Entrained Gases I~I p

1. Total Release Ci 2.54E-01 1.27E-01
2. AverageDiluted Conc uCi/ml 4.33E-10 2.OOE-10 D. Gross Alpha
1. TotalRelae I E. Volume of Waste Released
1. Processed (LW, NCD) liters 3.66E+06 4.34E+06 2.36E+06 2.50E+06 1.29E+07 + 10
2. Unprocessed (SGBD, SFDS) liters 5.88E+07 4.84E+07 4.17E+07 4.27E+07 1.92E+08 + 10 IF. Volume of Dilution Water liters I5.87E+11 16.36E+11 18.55E+11 17.15E+11 12.79E+12 I 10

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 15 of 46 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

CONTINUOUS RADIOACTIVE EFFLUENT Nuclides Released Year Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2006 Cs-137 Ci 1.41E-02 5.92E-04 3.58E-05 1.36E-04 1.49E-02 Ni-63 Ci 3.28E-04 7.74E-05 4.29E-05 4.48E-04 Sr-89 Ci 4.34E-05 8.66E-05 3.05E-05 - 1.60E-04 Sr-90 Ci 3.56E-04 4.62E-04 1.80E-04 2.22E-04 1.22E-03 Total for Period J Ci 1.49E-02 1.22E-03 j 2.89E-04 3.58E-04 1.67E-02

- Indicates < MDA TABLE 2B

Docket No. 50-3, 50-247, & 50-286 Page 16 of 46 INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

BATCH RADIOACTIVE EFFLUENT Year Nuclides Released 2006 Units Qtr I Qtr 2 Qtr 3 Qtr 4 Ag-110m Ci 1.98E-03 3.58E-04 2.34E-03 Co-57 Ci 1.04E-05 - 1.04E-05 Co-58 Ci 4.53E-04 3.92E-03 4.58E-04 9.75E-05 4.93E-03 Co-60 Ci 9.04E-03 2.32E-03 3.61E-05 7.33E-06 1.14E-02 Cr-51 Ci - 1.22E-04 1.22E-04 Cs-134 Ci - 1.47E-05 1.82E-05 3.29E-05 Cs-137 Ci 3.50E-04 8.59E-05 5.94E-06 1.51E-04 5.93E-04 1-131 Ci - 1.47E-03 - 1.47E-03 1-132 Ci - 1.39E-05 - 1.39E-05 Mn-54 Ci 2.91E-04 - - 2.91E-04 Nb-95 Ci 1.14E-05 - 1-.14E-05 Ni-63 Ci 2.01E-03 1.04E-03 5.23E-05 - 3.11E-03 Sb-124 Ci 1.48E-05 2.95E-04 6.39E-05 - 3.74E-04 Sb-125 Ci 5.51E-03 3.96E-03 1.11E-03 1.57E-03 1.22E-02 Te-123m Ci 6.88E-05 8.38E-06 - 7.72E-05 Te- 132 Ci 2.88E-05 2.88E-05 Total for Period Ci 1.97E-02 1.37E-02 1.73E-03 1.85E-03 3.

Dissolved & Entrained Gas Kr-85 Ci 1.30E-03 3.73E-03 - - 5.03E-03 Xe-131m Ci 5.35E-03 2.83E-03 - - 8.18E-03 Xe-133 Ci 2.45E-01 1.20E-01 - - 3.65E-01 Xe-133m Ci 1.55E-03 5.62E-04 - - 2.11E-03 Xe-135 Ci 1.51E-04 6.85E-05 - - 2.20E-04

[Tal for Period Ci 2.54E-01 1.27E-01 0.OOE+00 0.OOE+00 3.81E-01

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 17 of 46 TABLE 2A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A Fission &Activation Products Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2006  % Error

1. Total Release (not including Ci 2.32E-03 1.38E-03 1.36E-03 4.90E-04 5.55E-03 Tritium, Gr Alpha, & Gases)
2. Average Diluted Conc uCi/ml 3.96E-12 2.16E-12 1.59E-12 6.85E-13 1.99E-12 I i - d- d- i I I B. Tritium I
1. Total Release
2. Average Diluted Conc f -

Ci uCi/ml 3.23E+011 8.64E+01

d. -

5.51E-08 1.36E-07

~ -'

4.52E+02 5.29E-07 I

1.60E+02 2.24E-07 I -

7.31E+02 2.62E-07 C. Dissolved & Entrained Gases

1. Total Release
2. AverageDiluted Conc Ci 0.00E+00 0.OOE+00 uCi/ml 0.00E+00 0.OOE+00 3.80E-04 F 4.74E-04 4.45E-1 3 6.63E-13 8.55E-04 3.06E-13 D. Gross Alpha
1. Total Release Ci c - -- I - 25 1 E. Volume of Waste Released
1. Processed Fluids (Mon Tanks) liters 2.29E+05 2.01 E+05 5.24E+05 2.62E+05 1.22E+06 + 10
2. Unprocessed Fluids (SGs) liters 1.60E+06 1.62E+06 5.48E+06 1.21E+07 2.08E+07 + 10 F. Volume of Dilution Water liters I5.87E+1 16.36E+1 18.55E+11 7.15E+ 1 2.79E+12 +10

Docket No. 50-3, 50-247, & 50-286 Page 18 of 46 TABLE 2B INDIAN POINT 3 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2006)

BATCH and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT Batch Fission/ActivationProducts Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2006 Ag-110m Ci 8.73E-05 1.25E-05 7.99E-06 - 1.08E-04 Co-58 Ci 3.88E-05 8.60E-06 7.91 E-05 - 1.26E-04 Co-60 Ci 2.95E-04 4.04E-05 5.59E-04 2.93E-04 1.19E-03 Cs-134 Ci 2.96E-05 - 2.96E-05 Cs-137 Ci 7.13E-05 1.15E-05 4.98E-05 1.37E-05 1.46E-04 Fe-55 Ci - 1.03E-04 1.03E-04 Mn-54 Ci 1.26E-05 1.26E-05 Ni-63 Ci 2.28E-04 5.12E-05 2.20E-04 5.OOE-04 Sb-125 Ci 1.56E-03 1.15E-03 4.48E-04 1.79E-04 3.33E-03 Sn-113 Ci 4.58E-06 4.58E-06 Total for Period Ci 2.32E-03 1.38E-03 I1.36E-03 4.90E-04 5.55E-03 Dissolvedand EntrainedGas (Batch)

Xe-131m Ci 6.12E-05 6.12E-05 Xe-133 Ci 3.80E-04 4.13E-04 7.93E-04 Total for Period Ci 0.00E+00 O.OOE+00 3.80E-04 4.74E-04 8.55E-04 ContinuousReleases (SG Blowdown)

IH-3 (only) I c .79E-031 3.80E-031 1.43E-02 1.70E-02 3

Docket No. 50-3, 50-247, & 50-286 Page 19 of 46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2006

Docket No. 50-3, 50-247, & 50-286 Page 20 of 46 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2006 to 12/31/2006 Percent Cutoff: 0 (all identified isotopes are included)

Waste Stream : Resins, Filters, and Evap Bottoms LWS Resin Plant Resin 8-120 Cartridge Filters Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 8.23E+02 2.33E+01 1.26E+01 +/- 25%

B 1.OOE+03 2.84E+01 3.82E+02 +/- 25%

C 4.59E+02 1.30E+01 4.28E+02 +/- 25%

All 2.28E+03 6.47E+01 8.22E+02 +/- 25%

Waste Stream

  • Dry Active Waste DAW 40' Sea Land DAW/Dirt;B-25 Box DAW 20' Sea Land Soil/Debris - Intermodal Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 4.38E+04 1.24E+03 2.49E+00 +/-25%

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

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

All 4.38E+04 1.24E+03 2.49E+00 +/-25%

Waste Stream

  • Irradiated Components Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

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

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

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

Waste Stream

  • Other Waste Combined Packages Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 2.56E+03 7.25E+01 9.66E-01 +/-25%

B 1.28E+03 3.62E+01 5.51E+00 +/-25%

C 1.20E+02 3.41E+00 1.38E+01 +/-25%

All 3.96E+03 1.12E+02 2.03E+01 +/-25%

Waste Stream : Sum of All4 Categories Combined Packages:

DAW/Dirt; B-25 Box DAW 20' Sea Land LWS Resin DAW-40' Sea Land Cartridge Filters Plant Resin 8-120 Soil/Debris - Intermodal Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 4.72E+04 1.34E+03 1.61 E+01 +/-25%

B 2.28E+03 6.46E+01 3.88E+02 +/-25%

C 5.79E+02 1.64E+01 4.41E+02 +/-25%

All 5.01E+04 1.42E+03 8.45E+02 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

Docket No. 50-3, 50-247, & 50-286 Page 21 of 46 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2006 to 12/31/2006 Percent Cutoff: 0 Number of Mode of Shipments Transportation Destination 5 Hittman Transport Duratek, Inc. - GIC 15 Hittman Transport GTS Duratek 11 Hittman Transport Studsvik Processing Facility 1 R & R Trucking Inc. Studsvik Processing Facility 1 Hittman Transport Studsvik RACE 1 R & R Trucking Inc. Studsvik RACE 8 Studsvik Logistics Studsvik RACE Resins, Filters, and Evap Bottoms Waste Class A Percent Nuclide Name Abundance Curies H-3 9.67% 1.22E+00 Cr-51 0.00% 4.55E-04 Mn-54 0.21% 2.61 E-02 Fe-55 8.64% 1.09E+00 Co-57 0.06% 7.27E-03 Co-58 0.43% 5.43E-02 Co-60 3.76% 4.74E-01 Ni-63 25.05% 3.16E+00 Sr-90 0.18% 2.23E-02 Ag-1 10m 0.07% 8.84E-03 Sb-125 0.28% 3.55E-02 Cs-134 18.39% 2.32E+00 Cs-137 33.06% 4.17E+00 Ce-144 0.21% 2.59E-02 Pu-238 0.00% 1.31E-06 Pu-239 0.00% 1.92E-06 Am-241 0.00% 3.26E-06 Cm-243 0.00% 8.34E-08 Resins, Filters, and Evap Bottoms Waste Class B Percent Nuclide Name Abundance Curies H-3 7.01% 2.68E+01 Cr-51 0.00% 1.83E-02 Mn-54 0.40% 1.53E+00 Fe-55 2.04% 7.81 E+00 Co-57 0.03% 1.30E-01 Co-58 0.63% 2.39E+00 Co-60 1.77% 6.78E+00 Ni-63 9.37% 3.58E+01 Sr-90 0.18% 6.91 E-01 Nb-95 0.07% 2.66E-01

Docket No. 50-3, 50-247, & 50-286 Page 22 of 46 Ag-110m 0.01% 2.88E-02 Sn-113 0.05% 1.76E-01 Sb-124 0.00% 6.03E-04 Sb-125 0.23% 8.76E-01 Cs-134 9.29% 3.55E+01 Cs-137 68.28% 2.61 E+02 Ce-144 0.64% 2.43E+00 Pu-238 0.00% 1.51E-03 Pu-239 0.00% 1.01 E-03 Pu-241 0.01% 2.71 E-02 Am-241 0.00% 1.52E-03 Cm-242 0.00% 1.42E-04 Cm-243 0.00% 3.67E-04 Resins, Filters, and Evap Bottoms Waste Class C Percent Nuclide Name Abundance Curies H-3 0.10% 4.31 E-01 Mn-54 0.17% 7.22E-01 Fe-55 1.38% 5.91 E+00 Co-57 0.02% 7.26E-02 Co-58 0.10% 4.27E-01 Co-60 1.90% 8.14E+00 Ni-63 13.45% 5.75E+01 Sr-90 0.09% 3.66E-01 Ag-110m 0.00% 5.06E-03 Sb-125 0.49% 2.11 E+00 Cs-134 6.41% 2.74E+01 Cs-137 75.31% 3.22E+02 Ce-144 0.58% 2.47E+00 Pu-238 0.00% 2.27E-03 Pu-239 0.00% 1.82E-03 Pu-241 0.01% 3.28E-02 Am-241 0.00% 2.85E-03 Cm-242 0.00% 5.78E-05 Cm-243 0.00% 4.77E-04 Resins, Filters, and Evap Bottoms Waste Class All Percent Nuclide Name Curies Abundance H-3 3.45% 2.84E+01 Cr-51 0.00% 1.88E-02 Mn-54 0.28% 2.28E+00 Fe-55 1.80% 1.48E+01 Co-57 0.03% 2.10E-01 Co-58 0.35% 2.88E+00 Co-60 1.87% 1.54E+01

Docket No. 50-3, 50-247, & 50-286 Page 23 of 46 Ni-63 11.73% 9.64E+01 Sr-90 0.13% 1.08E+00 Nb-95 0.03% 2.66E-01 Ag-110m 0.01% 4.27E-02 Sn-113 0.02% 1.76E-01 Sb-124 0.00% 6.03E-04 Sb-125 0.37% 3.02E+00 Cs-134 7.93% 6.52E+01 Cs-137 71.40% 5.87E+02 Ce-144 0.60% 4.92E+00 Pu-238 0.00% 3.79E-03 Pu-239 0.00% 2.84E-03 Pu-241 0.01% 5.98E-02 Am-241 0.00% 4.38E-03 Cm-242 0.00% 2.OOE-04 Cm-243 0.00% 8.44E-04 Dry Active Waste Waste Class A Percent Nuclide Name Curies Abundance C-14 0.02% 4.50E-04 Mn-54 4.38% 1.09E-01 Fe-55 44.96% 1.12E+00 Co-58 21.08% 5.25E-01 Co-60 24.33% 6.06E-01 Ni-63 4.50% 1.12E-01 Sr-90 0.07% 1.78E-03 Cs-137 0.10% 2.41 E-03 Ce-144 0.25% 6.14E-03 Pu-238 0.01% 1.78E-04 Pu-239 0.00% 4.57E-05 Pu-241 0.29% 7.15E-03 Am-241 0.00% 4.03E-05 Cm-242 0.02% 4.08E-04 Cm-243 0.01% 2.56E-04 Dry Active Waste Waste Class All Percent Nuclide Name Curies Abundance C-14 0.02% 4.50E-04 Mn-54 4.38% 1.09E-01 Fe-55 44.96% 1.12E+00 Co-58 21.08% 5.25E-01 Co-60 24.33% 6.06E-01 Ni-63 4.50% 1.12E-01 Sr-90 0.07% 1.78E-03 Cs-137 0.10% 2.41E-03 Ce-144 0.25% 6.14E-03 Pu-238 0.01% 1.78E-04

Docket No. 50-3, 50-247, & 50-286 Page 24 of 46 Pu-239 0.00% 4.57E-05 Pu-241 0.29% 7.15E-03 Am-241 0.00% 4.03E-05 Cm-242 0.02% 4.08E-04 Cm-243 0.01% 2.56E-04 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.00% 2.11 E-06 C-14 0.02% 1.81E-04 Mn-54 3.80% 3.67E-02 Fe-55 42.04% 4.06E-01 Co-57 0.04% 3.40E-04 Co-58 13.05% 1.26E-01 Co-60 23.40% 2.26E-01 Ni-63 7.32% 7.07E-02 Sr-90 0.07% 7.02E-04 Cs-134 4.27% 4.12E-02 Cs-137 5.37% 5.19E-02 Ce-144 0.32% 3.10E-03 Pu-238 0.01% 6.62E-05 Pu-239 0.00% 1.70E-05 Pu-241 0.27% 2.64E-03 Am-241 0.00% 1.50E-05 Cm-242 0.01% 1.17E-04 Cm-243 0.01% 9.49E-05 Other Waste Waste Class B Nuclide Name Percent Abundance Curies C-14 0.02% 1.20E-03 Mn-54 4.32% 2.38E-01 Fe-55 50.67% 2.79E+00 Co-58 10.55% 5.81 E-01 Co-60 28.33% 1.56E+00 Ni-63 5.32% 2.93E-01 Sr-90 0.08% 4.67E-03 Cs-137 0.08% 4.45E-03 Ce-144 0.24% 1.31 E-02 Pu-238 0.01% 4.74E-04 Pu-239 0.00% 1.22E-04 Pu-241 0.34% 1.88E-02 Am-241 0.00% 1.07E-04 Cm-242 0.01% 7.41 E-04 Cm-243 0.01% 6.78E-04

Docket No. 50-3, 50-247, & 50-286 Page 25 of 46 Other Waste Waste Class C Percent Nuclide Name Curies Abundance H-3 0.01% 1.40E-03 C-14 0.00% 2.25E-05 Mn-54 0.45% 6.29E-02 Fe-55 5.42% 7.51E-01 Co-57 0.04% 5.88E-03 Co-58 0.14% 1.96E-02 Co-60 5.94% 8.23E-01 Ni-59 0.00% 1.25E-04 Ni-63 27.08% 3.75E+00 Sr-90 0.08% 1.05E-02 Nb-94 0.00% 4.60E-07 Tc-99 0.00% 2.35E-06 Ag-110m 0.01% 1.95E-03 Sb-125 1.66% 2.30E-01 Cs-134 21.95% 3.04E+00 Cs-137 36.90% 5.11E+00 Ce-144 0.29% 3.95E-02 U-235 0.00% 9.65E-07 Np-237 0.00% 1.14E-09 Pu-238 0.00% 1.45E-04 Pu-239 0.00% 3.12E-05 Pu-240 0.00% 1.29E-08 Pu-241 0.03% 3.86E-03 Am-241 0.00% 2.33E-05 Am-243 0.00% 1.16E-15 Cm-242 0.00% 3.83E-06 Cm-243 0.00% 4.87E-05 Cm-244 0.00% 6.65E-16 Other Waste Waste Class All Percent Nuclide Name Abundance Curies H-3 0.01% 1.40E-03 C-14 0.01% 1.40E-03 Mn-54 1.66% 3.37E-01 Fe-55 19.39% 3.94E+00 Co-57 0.03% 6.22E-03 Co-58 3.58% 7.27E-01 Co-60 12.85% 2.61 E+00 Ni-59 0.00% 1.25E-04 Ni-63 20.28% 4.12E+00 Sr-90 0.08% 1.59E-02 Nb-94 0.00% 4.60E-07 Tc-99 0.00% 2.35E-06 Ag-110m 0.01% 1.95E-03 Sb-125 1.13% 2.30E-01

Docket No. 50-3, 50-247, & 50-286 Page 26 of 46 Cs-134 15.16% 3.08E+00 Cs-137 25.40% 5.16E+00 Ce-144 0.27% 5.57E-02 U-235 0.00% 9.65E-07 Np-237 0.00% 1.14E-09 Pu-238 0.00% 6.84E-04 Pu-239 0.00% 1.70E-04 Pu-240 0.00% 1.29E-08 Pu-241 0.12% 2.53E-02 Am-241 0.00% 1.46E-04 Am-243 0.00% 1.16E-15 Cm-242 0.00% 8.62E-04 Cm-243 0.00% 8.22E-04 Cm-244 0.00% 6.65E-16 Sum of All 4 Categories Waste Class A Percent Nuclide Name Curies Abundance H-3 7.60% 1.22E+00 C-14 0.00% 6.30E-04 Cr-51 0.00% 4.55E-04 Mn-54 1.07% 1.72E-01 Fe-55 16.25% 2.61 E+00 Co-57 0.05% 7.61E-03 Co-58 4.39% 7.05E-01 Co-60 8.16% 1.31E+00 Ni-63 20.80% 3.34E+00 Sr-90 0.15% 2.48E-02 Ag-110m 0.06% 8.84E-03 Sb-125 0.22% 3.55E-02 Cs-134 14.69% 2.36E+00 Cs-137 26.27% 4.22E+00 Ce-144 0.22% 3.51E-02 Pu-238 0.00% 2.45E-04 Pu-239 0.00% 6.46E-05 Pu-241 0.06% 9.78E-03 Am-241 0.00% 5.86E-05 Cm-242 0.00% 5.25E-04 Cm-243 0.00% 3.51 E-04 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 6.91% 2.68E+01 C-14 0.00% 1.20E-03 Cr-51 0.00% 1.83E-02 Mn-54 0.46% 1.77E+00 Fe-55 2.73% 1.06E+01 Co-57 0.03% 1.30E-01

Docket No. 50-3, 50-247, & 50-286 Page 27 of 46 Co-58 0.77% 2.98E+00 Co-60 2.15% 8.34E+00 Ni-63 9.31% 3.61E+01 Sr-90 0.18% 6.96E-01 Nb-95 0.07% 2.66E-01 Ag-110m 0.01% 2.88E-02 Sn-113 0.05% 1.76E-01 Sb-124 0.00% 6.03E-04 Sb-125 0.23% 8.76E-01 Cs-134 9.15% 3.55E+01 Cs-1 37 67.31% 2.61E+02 Ce-144 0.63% 2.45E+00 Pu-238 0.00% 1.99E-03 Pu-239 0.00% 1.13E-03 Pu-241 0.01% 4.59E-02 Am-241 0.00% 1.63E-03 Cm-242 0.00% 8.83E-04 Cm-243 0.00% 1.04E-03 Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies H-3 0.10% 4.32E-01 C-14 0.00% 2.25E-05 Mn-54 0.18% 7.85E-01 Fe-55 1.51% 6.66E+00 Co-57 0.02% 7.85E-02 Co-58 0.10% 4.47E-01 Co-60 2.03% 8.96E+00 Ni-59 0.00% 1.25E-04 Ni-63 13.87% 6.12E+01 Sr-90 0.09% 3.77E-01 Nb-94 0.00% 4.60E-07 Tc-99 0.00% 2.35E-06 Ag-110m 0.00% 7.01 E-03 Sb-125 0.53% 2.34E+00 Cs-1 34 6.91% 3.05E+01 Cs-137 74.09% 3.27E+02 Ce-144 0.57% 2.51 E+00 U-235 0.00% 9.65E-07 Np-237 0.00% 1.14E-09 Pu-238 0.00% 2.42E-03 Pu-239 0.00% 1.86E-03 Pu-240 0.00% 1.29E-08 Pu-241 0.01% 3.66E-02 Am-241 0.00% 2.87E-03 Am-243 0.00% 1.16E-15 Cm-242 0.00% 6.16E-05 Cm-243 0.00% 5.26E-04 Cm-244 0.00% 6.65E-16

Docket No. 50-3, 50-247, & 50-286 Page 28 of 46 Sum of All 4 Categories Waste Class All Percent Nuclide Name Abundance Curies H-3 3.36% 2.84E+01 C-14 0.00% 1.85E-03 Cr-51 0.00% 1.88E-02 Mn-54 0.32% 2.72E+00 Fe-55 2.35% 1.99E+01 Co-.57 0.03% 2.16E-01 Co-58 0.49% 4.13E+00 Co-60 2.20% 1.86E+01 Ni-59 0.00% 1.25E-04 Ni-63 11.95% 1.01 E+02 Sr-90 0.13% 1.10E+00 Nb-94 0.00% 4.60E-07 Nb-95 0.03% 2.66E-01 Tc-99 0.00% 2.35E-06 Ag-110m 0.01% 4.46E-02 Sn-113 0.02% 1.76E-01 Sb-124 0.00% 6.03E-04 Sb-125 0.38% 3.25E+00 Cs-134 8.08% 6.83E+01 Cs-1 37 70.04% 5.92E+02 Ce-144 0.59% 4.99E+00 U-235 0.00% 9.65E-07 Np-237 0.00% 1.14E-09 Pu-238 0.00% 4.65E-03 Pu-239 0.00% 3.05E-03 Pu-240 0.00% 1.29E-08 Pu-241 0.01% 9.23E-02 Am-241 0.00% 4.56E-03 Am-243 0.00% 1.16E-15 Cm-242 0.00% 1.47E-03 Cm-243 0.00% 1.92E-03 Cm-244 0.00% 6.65E-16

Docket No. 50-3, 50-247, & 50-286 Page 29 of 46 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2006 to 12/31/2006 Percent Cutoff: 0 (all identified isotopes are included)

Waste Stream : Resins, Filters, and Evap Bottoms LWS Resin 14-170 Primary Resin 8-120 Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 3.42E+02 9.67E+00 7.07E+00 +1- 25%

B 2.91 E+02 8.24E+00 9.65E+01 +/- 25%

C 0.OOE+00 0.OOE+00 0.OOE+00 +1- 25%

All 6.33E+02 1.79E+01 1.04E+02 +1- 25%

Waste Stream : Dry Active Waste Unit 3 DAW-20' Sealand Unit 3 DAW B-25 Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 2.42E+03 6.86E+01 5.20E-02 +/-25%

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

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

All 2.42E+03 6.86E+01 5.20E-02 +/-25%

Waste Stream

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

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

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

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

Waste Stream

  • Other Waste Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

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

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

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

Waste Stream

  • Sum of All 4 Categories LWS Resin 14-170 Unit 3 DAW-20' Sealand Unit 3 DAW-B25 Primary Resin 8-120 Waste Volume Curies  % Error (Ci)

Class ft 3 m3 Shipped A 2.76E+03 7.83E+01 7.12E+00 +/-25%

B 2.91E+02 8.24E+00 9.65E+01 +/-25%

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

All 3.05E+03 8.65E+01 1.04E+02 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

Docket No. 50-3, 50-247, & 50-286 Page 30 of 46 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2006 to 12/31/2006 Percent Cutoff: 0 Number of Mode of Transportation Destination Shipments 3 Hittman Transport GTS Duratek Bear Creek Ops 4 Hittman Transport Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Percent Nuclide Name Curies Abundance H-3 13.66% 9.66E-01 Cr-51 0.00% 2.OOE-04 Mn-54 0.44% 3.12E-02 Fe-55 5.92% 4.19E-01 Co-57 0.26% 1.87E-02 Co-58 5.12% 3.62E-01 Co-60 5.84% 4.13E-01 Ni-63 16.82% 1.19E+00 Sr-89 0.42% 3.OOE-02 Sr-90 0.15% 1.05E-02 Ag-110m 0.23% 1.63E-02 Sb-124 2.60% 1.84E-01 Sb-125 6.74% 4.77E-01 Cs-134 12.67% 8.96E-01 Cs-137 22.05% 1.56E+00 Ce-144 7.05% 4.99E-01 Pu-238 0.00% 1.93E-04 Pu-239 0.00% 5.91 E-05 Am-241 0.00% 9.97E-05 Cm-242 0.00% 6.24E-05 Cm-243 0.00% 3.20E-04 Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Curies Abundance Mn-54 0.08% 7.64E-02 Fe-55 8.73% 8.43E+00 Co-57 0.00% 0.OOE+00 Co-58 0.15% 1.49E-01 Co-60 17.71% 1.71E+01 Ni-63 47.96% 4.63E+01 Sr-90 0.03% 2.63E-02 Sb-125 0.96% 9.27E-01 Cs-134 8.06% 7.78E+00 Cs-137 15.85% 1.53E+01 Ce-144 0.45% 4.33E-01

Docket No. 50-3, 50-247, & 50-286 Page 31 of 46 Pu-238 0.00% 1.88E-04 Pu-239 0.00% 4.83E-05 Pu-241 0.01% 6.76E-03 Am-241 0.00% 9.07E-05 Cm-242 0.00% 4.49E-04 Cm-243 0.00% 5.19E-04 Resins, Filters, and Evap Bottoms Waste Class All Percent Nuclide Name Abundance Curies H-3 0.93% 9.66E-01 Cr-51 0.00% 2.OOE-04 Mn-54 0.10% 1.08E-01 Fe-55 8.55% 8.85E+00 Co-57 0.02% 1.87E-02 Co-58 0.49% 5.11E-01 Co-60 16.90% 1.75E+01 Ni-63 45.88% 4.75E+01 Sr-89 0.03% 3.OOE-02 Sr-90 0.04% 3.68E-02 Ag-110m 0.02% 1.63E-02 Sb-124 0.18% 1.84E-01 Sb-125 1.35% 1.40E+00 Cs-134 8.38% 8.68E+00 Cs-137 16.23% 1.68E+01 Ce-144 0.90% 9.32E-01 Pu-238 0.00% 3.81 E-04 Pu-239 0.00% 1.07E-04 Pu-241 0.01% 6.76E-03 Am-241 0.00% 1.90E-04 Cm-242 0.00% 5.11E-04 Cm-243 0.00% 8.39E-04 Dry Active Waste Waste Class A Percent Nuclide Name Curies Abundance Cr-51 11.23% 5.84E-03 Mn-54 0.37% 1.94E-04 Fe-55 2.56% 1.33E-03 Co-57 0.18% 9.56E-05 Co-58 68.87% 3.58E-02 Co-60 1.77% 9.21E-04 Ni-63 3.64% 1.89E-03 Nb-95 0.23% 1.17E-04 Sb-124 5.04% 2.62E-03 Sb-125 4.81% 2.50E-03 Cs-134 0.71% 3.69E-04 Cs-137 0.59% 3.06E-04

Docket No. 50-3, 50-247, & 50-286 Page 32 of 46 Dry Active Waste Waste Class All Percent Curies Nuclide Name Abundance Cr-51 11.23% 5.84E-03 Mn-54 0.37% 1.94E-04 Fe-55 2.56% 1.33E-03 Co-57 0.18% 9.56E-05 Co-58 68.87% 3.58E-02 Co-60 1.77% 9.21 E-04 Ni-63 3.64% 1.89E-03 Nb-95 0.23% 1.17E-04 Sb-124 5.04% 2.62E-03 Sb-125 4.81% 2.50E-03 Cs-134 0.71% 3.69E-04 Cs-1 37 0.59% 3.06E-04 Sum of All 4 Categories Waste Class A Percent Curies Nuclide Name Abundance H-3 13.56% 9.66E-01 Cr-51 0.08% 6.04E-03 Mn-54 0.44% 3.14E-02 Fe-55 5.90% 4.20E-01 Co-57 0.26% 1.88E-02 Co-58 5.59% 3.98E-01 Co-60 5.81% 4.14E-01 Ni-63 16.70% 1.19E+00 Sr-89 0.42% 3.OOE-02 Sr-90 0.15% 1.05E-02 Nb-95 0.00% 1.17E-04 Ag-110m 0.23% 1.63E-02 Sb-124 2.62% 1.87E-01 Sb-125 6.74% 4.80E-01 Cs-134 12.58% 8.96E-01 Cs-137 21.90% 1.56E+00 Ce-144 7.00% 4.99E-01 Pu-238 0.00% 1.93E-04 Pu-239 0.00% 5.91 E-05 Am-241 0.00% 9.97E-05 Cm-242 0.00% 6.24E-05 Cm-243 0.00% 3.20E-04 7.12E+00

Docket No. 50-3, 50-247, & 50-286 Page 33 of 46 Sum of All 4 Categories Waste Class B Percent Nuclide Name Curies Abundance Mn-54 0.08% 7.64E-02 Fe-55 8.73% 8.43E+00 Co-57 0.00% 0.OOE+00 Co-58 0.15% 1.49E-01 Co-60 17.71% 1.71E+01 Ni-63 47.96% 4.63E+01 Sr-90 0.03% 2.63E-02 Sb-125 0.96% 9.27E-01 Cs-134 8.06% 7.78E+00 Cs-137 15.85% 1.53E+01 Ce-144 0.45% 4.33E-01 Pu-238 0.00% 1.88E-04 Pu-239 0.00% 4.83E-05 Pu-241 0.01% 6.76E-03 Am-241 0.00% 9.07E-05 Cm-242 0.00% 4.49E-04 Cm-243 0.00% 5.19E-04 Sum of All 4 Categories Waste Class All Percent Nuclide Name Abundance Curies H-3 0.93% 9.66E-01 Cr-51 0.01% 6.04E-03 Mn-54 0.10% 1.08E-01 Fe-55 8.54% 8.85E+00 Co-57 0.02% 1.88E-02 Co-58 0.53% 5.47E-01 Co-60 16.89% 1.75E+01 Ni-63 45.85% 4.75E+01 Sr-89 0.03% 3.OOE-02 Sr-90 0.04% 3.68E-02 Nb-95 0.00% 1.17E-04 Ag-110m 0.02% 1.63E-02 Sb-124 0.18% 1.87E-01 Sb-125 1.36% 1.41E+00 Cs-134 8.38% 8.68E+00 Cs-137 16.22% 1.68E+01 Ce-144 0.90% 9.32E-01 Pu-238 0.00% 3.81 E-04 Pu-239 0.00% 1.07E-04 Pu-241 0.01% 6.76E-03 Am-241 0.00% 1.90E-04 Cm-242 0.00% 5.11E-04 Cm-243 0.00% 8.39E-04

Docket No. 50-3, 50-247, & 50-286 Page 34 of 46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2006 - Dec 31, 2006

Docket No. 50-3, 50-247, & 50-286 Page 35 of 46 RADIOLOGICAL IMPACT ON MAN Routine Effluent Dose Calculations:

The radiological impact on man is determined by conservatively calculating doses to a hypothetical maximally exposed individual offsite based on plant effluents. These calculations are divided into 3 categories: Noble Gases, Particulates and Iodine, and Liquid Releases (fish and invertebrate consumption).

A 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 Manuals (ODCMs). Annual average dispersion and deposition factors are used in airborne effluent calculations. Liquid calculations involve fish and invertebrate consumption pathways. Details of these calculations are presented in the ODCM, along with the applicable assumptions in Regulatory Guide 1.109 and NUREG 0133.

Indian Point Energy Center is a multi-unit site owned and operated by Entergy Nuclear Operations, Incorporated.

Carbon-14:

Concentrations and offsite dose from Carbon-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 Carbon 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 worst case 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 annual dose to the maximally exposed individual (child) from gaseous releases of Carbon-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 Carbon-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, specifically to exclude them in the earlier tables, 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 (by quarter), 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 at the end of this section 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 36 of 46 Members of the Public:

Doses to members of the public from airborne and liquid releases are minimal due to the relatively insignificant total duration of these individuals on site. Their doses can be calculated from standard ODCM methodology, with typical occupancy factors employed.

These factors are determined by comparing the 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 mini60 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 2006:

Whole Body Max Organ (mrem) (mrem)

Routine Airborne Effluents Units 1 and 2 1.19E-02 1.19E-02 Routine Liquid Effluents Units I and 2 8.80E-04 1.26E-03 Routine Airborne Effluents Unit 3 1.07E-03 1.07E-03 Routine Liquid Effluents Unit 3 1.27E-04 1.60E-04 Carbon-14 Liquid & Airborne Totals IPEC 5.20E-02 2.60E-01 Ground Water & Storm Drain Totals IPEC1 - 1.78E-03 7.21 E-03 Radwaste Storage, Direct Shine IPEC 2 <7 <7 Indian Point Energy Center <7.28 Total Dose, per 40 CFR 190E Note 1: Groundwater curie and dose calculations are provided in Section H.

Note 2: The direct shine component is indistinguishable from background. Seven mrem is conservatively used from a one mrem siting criteria established for each area.

Docket No. 50-3, 50-247, & 50-286 Page 37 of 46 INDIAN POINT UNITS 1 and 2 NUCLEAR POWER PLANTS RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2006 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Utr ~3 L~tr4 ANNUAL Qtr 1 L~tr 1 Qtr Qtr 2 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 1.03E-03 2.67E-04 6.26E-05 9.66E-05 1.26E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 2.06E-02 5.33E-03 1.25E-03 1.93E-03 1.26E-02 Age Group Child Adult Adult Adult Adult Critical Organ Bone Bone Bone Bone Bone Adult Total Body (mrem) 7.04E-04 1.22E-04 1.78E-05 3.64E-05 8.80E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3 Percent of Limit (%) 4.69E-02 8.15E-03 1.19E-03 2.43E-03 2.93E-02 B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 8.31E-04 4.16E-03 1.42E-05 8.70E-06 5.01E-03 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 1.66E-02 8.32E-02 2.84E-04 1.74E-04 5.01E-02 Beta Air (mrad) 3.67E-03 1.38E-02 2.26E-04 7.63E-05 1.78E-02 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 3.67E-02 1.38E-01 2.26E-03 7.63E-04 8.89E-02 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 3.64E-04 1.04E-02 7.12E-04 4.75E-04 1.19E-02 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 4.85E-03 1.39E-01 9.49E-03 6.33E-03 7.93E-02 jAge Group IChild I Child I Child I Child I child lCritical Organ Liver Thyroid Liver Liver Thyroid

Docket No. 50-3, 50-247, & 50-286 Page 38 of 46 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2006 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Qtr I Qtr 2 Qtr 3 Qtr4 ANNUAL Organ Dose (mrem) 2.84E-05 2.27E-05 7.58E-05 3.32E-05 1.60E-04 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 5.68E-04 4.54E-04 1.52E-03 6.64E-04 1.60E-03 Age Group Adult Adult Adult Adult Adult Critical Organ GILLI GILLI GILLI GILLI GILLI Adult Total Body (mrem) 1.21 E-05 1.77E-05 6.82E-05 2.88E-05 1.27E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3 Percent of Limit (%) 8.07E-04 1.18E-03 4.55E-03 1.92E-03 4.23E-03 B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 6.75E-06 8.90E-06 9.28E-06 2.87E-05 5.36E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 1.35E-04 1.78E-04 1.86E-04 5.74E-04 5.36E-04 Beta Air (mrad) 1.24E-05 1.60E-05 1.94E-05 1.09E-04 1.57E-04 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 1.24E-04 1.60E-04 1.94E-04 1.09E-03 7.84E-04 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 1.89E-04 2.74E-04 3.69E-04 2.35E-04 1.07E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 2.52E-03 3.65E-03 4.92E-03 3.13E-03 7.11E-03 lAge Group I I Child I Child I Child I Child I Child I Critical Organ Liver Liver Liver Liver Liver

Docket No. 50-3, 50-247, & 50-286 Page 39 of 46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2006 - Dec 31, 2006 This data is stored onsite and is available in printed or electronic form.

Docket No. 50-3, 50-247, & 50-286 Page 40 of 46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT G. OFFSITE DOSE CALCULATION MANUAL, PROCESS CONTROL PROGRAM, OR LAND USE CENSUS LOCATION CHANGES 2006 There were no changes in the REMP locations for dose calculations and/or environmental monitoring in year 2006.

There were no changes to the Land Use Census in year 2006.

The were no changes to the PCPs or ODCMs in this period.

Docket No. 50-3, 50-247, & 50-286 Page 41 of46 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT H. GROUNDWATER and STORM WATER ACTIVITY ON SITE Jan 1, 2006 - Dec 31, 2006

Docket No. 50-3, 50-247, & 50-286 Page 42 of 46 IPEC Groundwater and Storm Water Activity and Dose Calculation, 2006 The water mass balance methodology applied in 2005 was used to determine the effluent curie and dose impact from Groundwater for the 2006 annual effluent report. Significant data was accumulated in 2006 from Monitoring Wells across the site, and, as such, the concentrations at the release points were significantly updated from the bounding estimates applied in 2005. The source terms applied to releases in affected areas and zones were based on multiple samples and integrated on a quarterly bases. Despite significant improvements in obtaining accurate and abundant source term information at the points of release, it should be understood that effluent curie and dose calculations are highly dependant upon the release and dilution flow rates determined. Therefore, the specific processes for release and dilution flow determination is defined in the following text.

The basic methodology for this dose assessment was based on an overall mass balance driven by precipitation. The hydrology portion of this assessment was performed by representatives from IPEC's consultant company, GZA GeoEnvironmental, Inc. IPEC concurs with this methodology.

This "watershed analysis" partitions the precipitation falling on the watershed catchment area (i.e.,

that portion of the Facility area where the surface topography is sloped towards the river) into water that infiltrates the ground to become groundwater (GW), water that flows off the surface as storm water (SW) and that water which directly moves back into the atmosphere via evapotranspiration and other processes. Relative porosity is applied in each area and zone to determine the average flow rate to the river or discharge canal, from each source location. This "top down" method of analysis is based on well established hydrologic principles of relative porosity of each area and zone applied.

Over the entire watershed catchment area of 3.2 million ft2 , the GW and SW has been segmented 3 relative to the areas of the facility through which it flows (primarily established based on H concentrations in the various facility areas). The bulk of the GW activity however, is identified near the transformer yard of Unit 2.

Overall, the partitioning was established as follows for infiltration areas contributing to GW flow (does not include paved or building areas):

GROUNDWATER AREAS:

  • AREA 1. The northwestern most area where GW appears to move directly to the river, but passes to the north of the Unit 2 Turbine Building Road (area of 0.25 million ft 2). This GW is unlikely to contain appreciable H3 concentrations based on the data available to date and the lack of likely H3 sources;
  • AREA 2. The area where the GW appears to move through Unit 2 facilities (area of 0.57 2

million ft );

  • AREA 3a. The area where the GW appears to move through Unit 1 facilities (area of 0.963 million ft2);
  • AREA 3b. The area where the GW appears to move through Unit 1/3 facilities (area of 0.737 million ft 2);

" AREA 4. The southwestern most area where GW appears to move directly to the river, but passes to the south of the Unit 3 Turbine Building Road (area of 0.67 million ft2). This GW is unlikely to contain appreciable H3 concentrations based on the data available to date and the lack of likely H3 sources.

Docket No. 50-3, 50-247, & 50-286 Page 43 of 46 SW flow from paved areas and building roof areas has also been partitioned into various zones within the above Facility GW areas as follows:

STORM WATER AREAS:

  • ZONE A. The eastern most parking lots which likely drain along flow paths where the SW is unlikely to contain H3, and storm drain exfiltration into the GW flow zone is also unlikely to pick up H3 (area of 0.35 million ft2);
  • ZONE B. Within the Unit 2 Facility, the eastern and western zones where SW appears to discharge to the river, but does not pass through the Unit 2 Transformer Yard (area of 0.21 million ft2);
  • ZONE C. Within the Unit 2 Facility, the middle zone where SW flows to the Discharge Canal, and does pass through the Unit 2 Transformer Yard (area of 0.15 million ft2);
  • ZONE D. Within the Unit 1 Facility where SW flows to the Discharge Canal (area of 0.13 million ft2); and
  • ZONE E. Within the Unit 3 Facility where SW flows to the Discharge Canal (area of 0.75 million ft2).

A portion of the SW has been assumed to leak out of storm drains and thus increases the GW flow to the river as follows:

  • ZONE A. Storm drain exfiltration =0% - Exfiltration from pipes in this zone are unlikely to contribute flow to GW which contains H3 and the SW itself is unlikely to contain H3 ;
  • ZONE B. Storm drain exfiltration =0% - Exfiltration from pipes in this zone are unlikely to contribute flow to GW which contains H3 and the SW itself is unlikely to contain H3 ;
  • ZONE C. Storm drain exfiltration =25% - set to a relatively high value to result in higher than anticipated GW flow through the Unit 2 Transformer Yard which contains the highest H 3 GW values, so as to be conservative;
  • ZONE D. Storm drain exfiltration =50%; set very high given current knowledge of these drains; and
  • ZONE E. Storm drain exfiltration =10%; set to a nominal value given current lack of specific data and limited impact on overall H3 flux due to low H3 concentrations.

Concentrations of identified radioisotopes have been established for all Areas and Zones using accumulated Monitoring Well and Storm Drain sample data in 2006. Analyses by gamma spectroscopy were conducted, as well as specific analyses for H-3, Ni-63, and Sr-90.

On a quarterly basis, all results (from all levels) of effected wells in the effluent locations were ranked, and a 75 percentile value was used to define this location's source term. If, due to the predominance of tests with no detectable activity, the 75 percentile (3 rd quartile) value resulted in a ZERO, the MEAN value was used instead, to avoid using a zero value for any location that had an identified positive value, at any given time within the quarter. Similarly, conservative historical values were used for the quarterly determination, if there were insufficient data in the effected quarter.

Inclusion of all data pieces in the effluent sectors, for each quarter, provided the desired confidence of obtaining a proper source term for these sectors. This resulted in a significant improvement over the 2005 assessment of Groundwater's dose contribution, in that, unlike 2005, hundreds of data results were available to formulate a defendable statistical basis for the 2006 source term.

Docket No. 50-3, 50-247, & 50-286 Page 44 of 46 The 3 rd quartile function was applied to incorporate a good balance of conservativism with actual data results. The application of a MEAN, in place of a ZERO (value when the 3 rd quartile function would otherwise suggest the zero), provided additional conservativism.

As expected, after accumulating source term data over the year, we verified that our 2005 assessment was in fact conservative and 2006's assessment is significantly more accurate.

Selected Source Terms (uCi/ml) for Areas and Zones, in 2006, using the 3 rd quartile value from all analytical results of effected wells/drains indicating plant effluent in the selected area or zone:

Area 2 Area 3a Area 3b Zone B Zone C Zone D/E H-3) 3.03E-5 Ni-63) 4.56E-8 H-3) 1.13E-5 H-3) 4,28E-7 H-3) 5.24E-8 H-3) 1.04E-5 H-3) 5,68E-7 Qtr I Sr-90) 1,79E-8 Sr-90) 2.09E-8 Cs-137) 1.19E-9 H-3) 1.89E-5 Ni-63) 3.39E-8 H-3) 1.01E-5 H-3) 7.10E-7 Qtr 2 Sr-90) 1.33E-8 Sr-90) 1.90E-8 Sr-90) 2,80E-10 none H-3) 7.19E-8 H-3) 8.48E-7 Cs-137) 1,24E-9 H-3) 1 28E-5 H-3) 8.72E-6 Qtr 3 Ni-63) 3.82E-8 Ni-63) 7.34E-9 H-3) 3.16E-7 none H-3) 5.61E-6 H-3) 3,83E-7 Sr-90) 1.50E-8 Sr-90) 1.83E-8 H-3) 1.20E-5 H-3) 3-54E-6 Qtr 4 Ni-63) 3,82E-8 Sr-90) 1.64E-8 H-3) 3.OOE-7 none H-3) 2.67E-6 H-3) 1.69E-7 Sr-90) 1.50E-8 Cs-137) 2,99E-8 These source terms, sample results from all wells and drains on site, and documents showing the application of the 3 rd quartile function from all quarterly data, are available in plant records.

No source term was applied to Areas 1 and 4, nor to Zone A. These areas and zones have not exhibited contamination in the ground water, and they include no known sources. Additionally, hydrological studies show that flow through these areas/zones is driven from areas East of the plant and unrelated to potential contamination from within the site boundary.

The infiltration rate in non-paved/building areas was established at 0.46 feet/year based on the USGS report: Water Use, Groundwater Recharge and Availability, and Quality in the Greenwich Area, Fairfield County, CT and Westchester County, NY, 2000 - 2002. The precipitation rate for the area was set at 3.74 feet/year based on onsite meteorological data.

There remain some conservative assumptions with the 2006 assessment, including the following:

  • All GW flow has been assumed to discharge directly to the river. Some of this GW flow must infiltrate the Discharge Canal thus reducing the apportionment to the river;

" All storm drain pipe leakage has been assumed to be exfiltration which will increase GW flow values. However, current data in the Unit 2 Transformer Yard indicates that significant GW infiltrates the storm drain during rainfall events, thus flowing to the Discharge Canal via SW rather than directly to the river as GW. In addition, it is noted that SW H3 concentrations were typically obtained during non-storm events and thus represent the high end of H3 values associated with low flow conditions. However, these high H3 concentrations, were then applied to the much higher storm flows where much lower H3 values should exist;

Docket No. 50-3, 50-247, & 50-286 Page 45 of 46

  • All precipitation falling on paved/building areas was assumed to result in SW flow. Some of this water actually evaporates directly to atmosphere from pavement and buildings; and
  • The very large value of GW flow extracted from the GW system via the Unit 1 curtain and footing drains has not been subtracted from the GW flows adopted in the analysis.

Results:

The results of the assessment are shown on the following table. These dose values 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 0.19 Curies of Tritium migrated directly to the river via the GW flow path in 2006, resulting in an approximate total body dose of 2.1E-6 mrem. The curies of Tritium released via this pathway is approximately 0.015 percent of the Tritium released to the river from routine releases. Tritium releases in total (ground water as well as routine liquid effluent), represent less than 0.001 percent of the Federal dose limits for radioactive effluents from the site.

Strontium-90, Nickel-63, and Cesium-137 collectively contributed approximately 0.00057 Curies from the Ground Water pathway. Combined Ground Water releases from IPEC in 2006 resulted in a calculated annual dose of approximately 0.00178 mrem to the total body, and 0.00721 mrem to the critical organ, which was the Adult Bone (due primarily to Strontium-90).

Storm Drain releases to the Discharge Canal were conservatively calculated to be approximately 0.094 curies of Tritium, resulting in an approximate total body dose of 0.00000002 mrem.

The annual dose from combined groundwater and storm water pathways at IPEC (with all conservativism described above) remains well below the applicable limits.

ODCM Updates:

The ODCM was updated to include the Ground Water Monitoring Program in January, 2007.

Therefore, per Reg Guide 1.21, the changes to the ODCM are NOT included in this report, despite the fact that corrective action has been ongoing throughout 2006. The ODCM updates reflect both the requirements of the Ground Water Monitoring Program, and specifics on calculating offsite dose. Detailed discussion of each change will be included in the 2007 annual report, per Reg Guide 1.21 Groundwater-related updates to the ODCM have been a product of communication with multiple stakeholders, NEI, the NRC, and industry peers.

Like all records or procedures on site, the specific methods applied to administer the IPEC Ground Water Monitoring Program are available upon request at any time.

Dose Summary:

See the following groundwater annual offsite dose summary table.

Docket No. 50-3, 50-247, & 50-286 Page 46 of 46 2006 Adult mrem Sum of IPEC monitoring well calculations for units 1, 2, & 3 (Areas 2, 3a, & 3b)

ADULT Doses, in mrem ISOTOPE BONE LIE TOT BODY' THYROID KIDNEY, ~LUNG ~GI-LLI H-3 O.OOE+00 I2:08E-06' 2.08E-06 2.08E-06, 2.08E-06, 2.08E-06 2.08E1-06 H-3 .8E05 Ni-63 4.49E-04 "3'11E-05 1.51,E-05 I0.OOE+001 .. 00E+O0 1t0OOEE00 6.49E706, Ni-63 -2:'27E-02 Sr-90 6. 61E-03 0.OOE+00 1 .62E-03 .O00E+00 I0OOE+0000 0.°OE°+700j- 1.90E-04 Sr-90.' 2.63E021 Cs-137 1.60E-04 2"19E-04 1.44E-04 -O'0E÷00 744E-05 2.'47E-05j -,423E-06 Cs-I371 3 7 . 1 1 totals 721 E-03 2.52E-04 1.78E-03 2:08E-06 7.65E-05 2.68E-05 I2.03E-04 I Storm Drain Water from Zone B, East/West: Unit 2, near MH-2, going to river directly Doses, in mrem ISOTOPE I BONE I LIVER <ITOT BODYI TH~YROID I KIDNEY I LUNG I GI-LLI H-3 I.00E+OO 2.64E-09: 2.64E09 I 2"64E-09 I 2'64E-091 264E-09 2.64E-09 2.J0E Storm Drain Water from Zones C and D/E (Central U2, & UI/U3) to Discharge Canal Doses, in mrem ISOTOPE BONE LIVER, TOT BODY THYROID KIDNEY ILNG IGI-LLI UCi, - -

H-3 O.OOE+O0 1.74E-08 I 1.74E-08 I 174E-08 1.74E-08 I .74E-08 1:74E'-08 Totals: Doses, in mrem H-3only O.OOE+00 2.11E-06 2.11E-06 211E-06 2.11E-06 2.11E-06 211E-06I se2180E,5 B0NE I <LIVER' ]TOTBOQDYI THYROID ' KIDNEY] LUNG. GI-IJLLI All identified isotopes 7.21E-03 2.'52E-04 178E-03 2 11E-°6 7.65E-05 2268E-I05 2.03E-04, I :see-aboveý

% Annual Limit 0.072, 0.003 '06059V 0 "0.00,00, 00.6008 I :0:.0003I:a 0.002 1 teen mrem. total I 6.14E-03 I I

262E-04 I 1.46E-03 I 1.62E-06 II 7.93E-05 I 3.16E-05 I -1.94E-04 I

% limit I 0.061 1 0.003 I 0o049 I 0.000 I 0.001 I 0.000 I 0:002 I

  • =
  • child mrem, total I 5.73E-03 I2ý42E-04 I 130E-03 I 1.35E-06I 6&91E-05 I 2:57E-05 I 7.07E-05 I ii

% im 0.5 I I

_ .02ooz I OCQ ooo R oIo 0.0

% limit 1 0.057 1 0.002 1 0.0-43 1 0.000 1 0.0101 1 0.000 1 0.001 1

Retrieved from "https://kanterella.com/w/index.php?title=NL-07-050,_Units,_1,_2_and_3_-_2006_Annual_Radioactive_Effluent_Release_Report&oldid=2660814"