NL-03-074, Annual Radioactive Effluent Release Report - for Period January 1, 2002 Through December 31, 2002

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Annual Radioactive Effluent Release Report - for Period January 1, 2002 Through December 31, 2002
ML031220024
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/29/2003
From: Dacimo F
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-03-074
Download: ML031220024 (28)
v • d • e


Text

Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1

';En tergy P.O Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations NL-03-074 April 29, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, D.C. 20555

SUBJECT:

Indian Point 3 Nuclear Power Plant Docket No. 50-286 License No. DPR-64 Annual Radioactive Effluent Release Report -

For The Period January 1, 2002 Through December 31, 2002

Dear Sir:

Enclosed is the Annual Report of Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents for Indian Point 3 as required by Technical Specifications Section 5.6.3. The enclosed report covers the period January 1, 2002 through December 31, 2002 for Indian Point 3. It would include those releases from Indian Point 1 or 2 resulting from processing waste from Indian Point 3, if this pathway were utilized. During this reporting period, no waste was transferred from Indian Point 3 to Indian Point 1 or 2.

Entergy is making no new commitments in this letter.

Should you have any questions regarding this matter, please contact Mr. John McCann, Manager, Nuclear Licensing at (914) 734-5074.

Very ours, C .4 Fred R. Dacimo a Vice President, Operations Indian Point Energy Ceriter Enclosure L-(-- C>.-H%

Docket NO. 50-286 NL-03-074 Page 2 of 2 cc: Mr. Hubert J. Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406-1415 Mr. P. Milano, Project Manager Project Directorate 1-1 Division of Reactor Projects I/Il U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555 U.S. Nuclear Regulatory Commission Resident Inspectors' Office Indian Point 3 Nuclear Power Plant Mr. Paul Kolakowski Division of Water Department of Environmental Conservation 50 Wolf Road Albany, New York 12233-3505 Mr. Joseph Marcogliese Regional Water Engineer, Region 3 Department of Environmental Conservation 5th Floor 200 White Plains Road Tarrytown, New York 10591-5805 Mr. Robert A. Oliveira American Nuclear Insurers Town Center, Suite 300S 29 South Main Street West Hartford, Connecticut 06107-2445

Docket No. 50-286 NL-03-074 Page 1 of 26 Radioactive Effluent Release Report: 2002 Facility Indian Point 3 Licensee Entergy Nuclear Northeast 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 Regulatory Guide, pages 10 to 12.

A. Supplemental Information

1. Reculatory Limits Indian Point 3 is presently subject to limits on radioactive waste releases that are set forth in the Offsite Dose Calculation Manual, Parts I and 11,per the Technical Specifications. ODCM Part I, also known as the Radiological Effluent Controls (or RECS) is prescribed by Technical Specification Section 5.5.1, while the ODCM Part II is defined in Section 5.5.4. The percentages of the Technical Specification limits reported in Tables 1A and 2A are the percent of the ODCM quarterly limits.

If more than one limit applies to the release, the most restrictive limit is reported.

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 the 10 CFR 20 release rate limits is controlled for each release by the application of a calculated Allowed Diluted Concentration (ADC) and Radiation Monitor setpoints. The ADC is calculated as a function of the "10 times EC" limit, and includes limitations from Beta emitters. These measures, along with an administrative activity limit for effluent waste tanks, preclude approaching release rate limits, per the ODCM.

Docket No. 50-286 NL-03-074 Page 2 of 26

3. Average Energy The average energies (E) of the radionuclide mixtures in releases of fission and activation gases were as follows:

1st Quarter E = 2.07E-01 Mev/dis y= 3.13E-01 Mev/dis 2nd Quarter E = 1.78E-01 Mev/dis y= 1.75E-01 Mev/dis 3rd Quarter En = 1.53E-01 Mev/dis E y= 6.42E-02 Mev/dis 4th Quarter E = 1.96E-01 Mev/dis Py= 3.86E-02 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 Table 3.4.1-1 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.

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.

When no noble gas activity is identified for an entire quarter, a "less than" value is reported. This value is determined from the established Xe-133 minimum detectable concentration and the total volume of air released from all continuous release points.

Docket No. 50-286 NL-03-074 Page 3 of 26 b/c) lodines and Particulates Iodine-131 and particulate releases are quantified by collecting a continuous sample of ventilation air on a TEDA impregnated, activated charcoal cartridge and a glass-fiber filter paper. These samples are changed weekly as required in Table 3.4.1-1 of 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.

For other iodine isotopes, concentrations are determined monthly on a 24-hour sample. 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 to improve efficiency. When no Gross Alpha or lodine-131 is identified for an entire quarter, a "less than' value is reported (in curies) on Table 1A. This value is derived from established minimum detectable concentrations and the total volume of air released from all continuous release points. This method generates a more accurate Minimum Detectable total curie level than summing MDCs and occasional false positives at the critical level. The values demonstrate that the RECS/ODCM required LLDs are not challenged.

d) Liquid Effluents A sample of each batch discharge is taken and an isotopic analysis is performed in compliance with requirements specified in Table 3.3.1-1 of the RECS. Proportional composite samples of continuous discharges are taken and analyzed in compliance with this table as well. Isotopic concentration data are combined with the information on volume discharged to determine the amount of each isotope discharged.

5. Batch Releases a) Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2002 Number of Batch Releases 8 6 14 25 53 Total Time Period (min) 8.94E+2 5.78E+2 1.56E+3 2.81 E+3 5.84E+3 Maximum Time Period (mi) 1.20E+2 1.12E+2 1.21 E+2 1.20E+2 1.21 E+2 Average Time Period (min) 1.12E+2 9.63E+1 1.09E+2 1.12E+2 1.1 OE+2 Minimum Time Period (min) 1.OOE+2 3.30E+1 1.05E+2 1.04E+2 3.30E+1

Docket No. 50-286 NL-03-074 Page 4 of 26 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:

VYmnr fnl enrfnr .

PAFAlIfel zvvsz>D;>l 2000 Fourth 16600 2001 First 18900 2001 Second 31300 2001 Third 5510 b) Airborne Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 2002 Number of Batch Releases 20 26 20 20 86 Total Time Period (min) 4.08E+03 4.08E+03 3.44E+03 4.30E+03 1.59E+04 Maximum Time Period (min) 3.96E+02 2.53E+02 2.37E+02 4.28E+02 4.28E+02 Average Time Period (min) 2.04E+02 1.57E+02 1.72E+02 2.15E+02 i 1.85E+02 Minimum Time Period (min) 4.OOE+00 1.OOE+00 4.OOE+00 7.OOE+00 1.OOE+00

6. Abnormal Releases a) Liquid None b) Gaseous None
7. ODCM Reportinq Requirements The ODCM (RECS) Sections 2.11.B and 2.2.B require 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 (RECS 2.10 and 2.11).

During this reporting period, no required ODCM or Technical Specification Effluent Monitoring equipment was out of service for periods greater than 30 consecutive days.

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

Neither the Offsite Dose Calculation Manual, nor the Process Control Program were updated during this reporting period.

Docket No. 50-286 NL-03-074 Page 5 of 26 Indian Point 3 RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2002

Docket No. 50-286 NL-03-074 Page 6 of 26 TABLE 1A RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2002)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission & Activation Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2002  % Error

1. Total Release Ci 1.81 E-01 2.29E-01 1.27E+00 2.08E+00 3.76E+00 + 25
2. Average release rate uCisec 2.33E-02 2.91 E-02 1.60E-01 2.62E-01 1.1 9E-01
3. Percent of onCM limit 6.06E-04 4.74E-04 2.32E-03 4.87E-03 4.05E-03 (N obleGases only)__ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ __ _ _ _ _

B. lodines

1. Total lodine-1 31 Ci <3.OOE-6 <3.OE-6 <3.OOE-6 <3.OOE-6 <1.20E-5 + 25
2. Average release rate uCVsec <3.858E-7 <3.816E-7 <3.77E-7 < 3.77E-7 < 3.81 E-7 C. Particulates
1. Total Release, with Ci N/D N/D NID N/D N/D + 25 half-life > 8 days _
2. Average release rate uCisec N/D N/D NID N/D N/D
3. Gross Alpha Ci N/D N/D N/D N/D N/D +25 D. Tritium
1. Total release J Ci [1.31 E+00 1.67E+00 1.54E+00 6.79E-01 l5.20E+00 + 25 l
2. Average release rate uCVsec l_1.68E-01__2.12E-01 1.94E-01 8.54E-02 1.64E-01 l E. Percent 0-CM limit, &P  % 2.55E-03 3.25E-03 3.OOE-03 1 .32E-03 5.06E 03 l+ 25 N/D = None Detected

Docket No. 50-286 NL-03-074 Page 7 of 26 TABLE 1C RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2002)

CONTINUOUS GASEOUS EFFLUENTS - GROUND RELEASES Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr2 Qtr 3 Qtr 4 2002 Kr-85m Ci O.OOE+0T Kr-85 Ci Kr-87 Ci Kr-88 Ci Xe-131m Ci Xe-i 33m Ci Xe-133 Ci 7.49E-01 4.87E-01 1.24E+00 Xe-1 35m Ci Xe-1 35 Ci O.OOE+00 Xe-138 Ci Ar-41 Ci I.

Total for Period I Ci I O.OOE+00 O.OOE+00 7.49E-01I 4.87E-01_[ 1.24E+00

2) lodines 1-131 Ci <3.OOE-6 <3.OOE-6 <3.OOE-6 <3.OOE-06 <1 .20E-5 1-133 Ci NI/D N/D NDD 1-135 Ci NID N/D N/D NID al for Period I Ci I <3.OOE-6 I <3.OOE-6 I <3.OOE-6 I< 3.OOE-061 <1 .20E-5 1
3) Particulates I Total for Period I Ci I N/D I N/D I NID I N/D I N/D N/D= None Detected

Docket No. 50-286 NL-03-074 Page 8 of 26 TABLE 1C RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2002)

BATCH GASEOUS EFFLUENTS - GROUND RELEASES Nuclides Released Year

1) Fission Gases 2002 Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 3.89E-02 2.43E-02 2.29E-02 2.39E-02 1.1 OE-01 Kr-85 Ci 1.40E-02 1.28E-01 1.03E+00 1.17E+CO Kr-85m Ci O.OOE+OO Kr-87 Ci O.OOE+OO Kr-88 Ci O.OOE+OO Xe-131m Ci 6.71 E-03 6.71 E-03 Xe-133 Ci 1.41 E-01 1.90E-01 3.71E-01 5.23E-01 1.23E+OO Xe-1 33m Ci 7.08E-04 1.22E-03 1.93E-03 Xe-1 35 Ci 1.11 E-03 8.88E-04 2.33E-03 2.94E-03 7.27E-03 r

Xe-1 35m Ci Tal for Period I Ci 11.81 E-01 2.29E-01 5.25E-01 I1.59E+00 2.52E+OO J

2) lodines 1-131 Ci N/D N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D N/D Total for Period Ci N/D N/D N/D N/D N/D
3) Particulates I Total for Period I Ci I N/D I N/D I N/D I N/D I N/D I N/D= None Detected

Docket No. 50-286 NL-03-074 Page 9 of 26 Indian Point 3 RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2002

Docket No. 50-286 NL-03-074 Page 10 of 26 TABLE 2A RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2002)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission & Activation Products Units Otr 1 Qtr 2 Qtr 3 Qtr 4 2002  % Error

1. Total Release (not including Ci 14.45E-03 2.46E-03 7.59E-03 1.40E-02 2.85E-02 Tritium, Gr Alpha, & Gases)
2. Average Diluted Conc uCi/ml 1.63E-11 7.11E-12 1.76E-11 4.99E-11 2.14E-11 EB. Tritium
1. Total Release
2. Average Diluted Conc Ci uCi/ml l_3.19E+01 l 1.96E+01 5.14E+01 1.17E-07l 5.67E-08l 1.19E-07 6.92E+02 2.47E-06 7.95E+02J 5.97E-07 l

+25 C. Dissolved & Entrained Gases

[1. Total Release Ci 4.10E-05 lO.OOE+00l 1.68E-05 1.57E-01_l 1.57E-01 +25

[ 2. AverageDiluted Conc uCi/ml 1.50E-13 0.OOE+00l 3.89E-14 5.60E-10 1.18E-10 D. Gross Alpha

1. Total Release I Ci 1<8.33E-051<4.47E-051 <1.67EO-41 9.45E-04 I 9.45E-04 l+25 E. Volume of Waste Released liters l2.08E+05l 1.34E+051 3.60E+05 I 6.45E+05 1 .35E+06 I + 25 F. Volume of Dilution Water liters 2.73E+1 1 3.46E+11 4.32E+11 2.80E+11 1.33E+12 + 10 E. Percent of the ODM l 2.80E-03 2.12E-03 5.46E-03 l 6.32E-02 l 3.42E-02 25

Docket No. 50-286 NL-03-074 Page 11 of 26 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2002)

TABLE 2B BATCH LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2002 Year Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Otr 4 2001 Cr-51 Ci O.OOE+0O Mn-54 Ci 5.09E-05 1.32E-05 1.1 5E-04 8.09E-05 2.60E-04 Fe-55 Ci 4.95E-04 3.57E-04 4.77E-04 1.33E-03 Co-57 Ci 2.79E-06 2.79E-06 Co-58 Ci 6.69E-04 1.1 6E-04 2.52E-04 8.34E-05 1.12E-03 Co-60 Ci 9.88E-04 4.73E-04 2.29E-03 2.41 E-03 6.16E-03 Ni-63 Ci 1.18E-03 5.50E-04 1.37E-03 2.33E-03 5.43E-03 Sr-90 Ci 1.79E-06 1.79E-06 Zr-95 Ci O.OOE+0O Nb-95 Ci 8.33E-05 1.82E-05 1.02E-04 Ag-i1 Om Ci 4.62E-04 3.26E-04 1.02E-03 5.71 E-04 2.38E-03 Sb-1 24 Ci O.OOE+OO Sb- 125 Ci 4.80E-04 5.28E-04 2.26E-03 1.83E-03 5.1 OE-03 Te-123m Ci O.OOE+OO 1-131 Ci O.OOE+OO Cs-1 34 Ci 4.68E-06 9.31 E-06 2.90E-03 2.91 E-03 Cs-1 37 Ci 4.55E-05 7.66E-05 2.74E-04 3.34E-03 3.74E-03 La-140 Ci I O.OOE+0O Total for Period Ci 4.45E-03 2.46E-03 7.59E-03 1.40E-02 2.85E-02 Xe-131 m Ci 1.79E-03 1.79E-03 Xe-1 33m Cl O.OOE+OO Xe-133 Ci 4.1 OE-05 1.68E-05 6.19E-02 6.20E-02 Xe-1 35 Ci 9.37E-02 9.37E-02 Kr-85m Ci O.OOE+OO TotIlfor Period Ci 4.1 OE-05 O.OOE+OO 1.68E-05 1.57E-01 1.57E-01

Docket No. 50-286 NL-03-074 Page 12 of 26 Indian Point 3 RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2002

Docket No. 50-286 NL-03-074 Page 13 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12/31/2002 Percent Cutoff: 0 Waste Stream: Resins, Filters, and Evap Bottoms BR D NA PRIMARY Waste Volume Curies  % Error Class Ft3 M3 Shipped (Ci)

A 0.OOE+00 0.OOE+00 0.OOE+00 +I- 25%

B 1.20E+02 3.41 E+00 2.82E+01 +/- 25%

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

All 1.20E+02 3.41 E+00 2.82E+01 +I- 25%

Waste Stream : Dry Active Waste DAW/B-25 BOX Waste Volume Curies %Error Class Ft3 Shipped (Ci)

A 2.54E+03 7.20E+01 3.24E-02 +/-25%

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

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

All 2.54E+03 7.20E+01 3.24E-02 +/-25%

Waste Stream  : Irradiated Components Waste Volume Curies  % Error Class Ft3 M3 Shipped (Ci)

A 0.OOE+00 0.OOE+00 O.OQE+00 +/-25%

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

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

All Al.OOE+00 0.OOE+00 0.OOE+00 +-5

+I-25%

Docket No. 50-286 NL-03-074 Page 14 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12/31/2002 Percent Cutoff: 0 Waste Stream : Other Waste Combined Packages Waste Volume Curies  % Error Class Ft3 M3 Shipped (Ci)

A 2.04E+02 5.78E+o0 3.18E+00 +/-25%

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

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

All 2.04E+02 5.78E+00 3.18E+00 +/-25%

Waste Stream : Sum of All 4 Categories Combined Packages DAW/B-25 BOX, DAW/SEALAND, BR D NA PRIMARY Waste Volume Curies  % Error Class Ft3 M Shipped (Ci)

A 2.75E+03 7.78E+01 3.21 E+00 +/-25%

B 1.20E+02 3.41 E+00 2.82E+01 +/-25%

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

All 2.87E+03 8.12E+01 3.14E+01 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown Number of Shipments Mode of Transportation Destination 2 HITTMAN TRANSPORTATION Barnwell Waste Management Facility 4 HITTMAN GTS---DURATEK

Docket No. 50-286 NL-03 -074 Page 15 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/0112002 to 12/31/2002 Percent Cutoff: 0 Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance Curies H-3 0.023% 6.43E-03 C-14 0.004% 9.91 E-04 Mn-54 2.191% 6.17E-01 Fe-55 5.707% 1.61 E+00 Co-57 0.065% 1.82E-02 Co-58 1.500% 4.23E-01 Co-60 24.976% 7.04E+00 Ni-63 50.867% 1.43E+01 Zn-65 0.159% 4.48E-02 Sr-90 0.022% 6.24E-03 Zr-95 0 235% 6.64E-02 Nb-95 0.580% 1.63E-01 Tc-99 0.015% 4.37E-03 Ag-11 Om 0.270% 7.61 E-02 Sn-113 0 076% 2.15E-02 Sb-124 0.068% 1.93E-02 Sb-125 2.188% 6.16E-01 Cs-134 4.617% 1.30E+00 Cs-137 6.431% 1.81 E+00 Ce-144 0.002% 4.97E-04 Pu-238 0.000% 3.31 E-05 Pu-239 0.000% 4.35E-06 Pu-241 0.003% 8.44E-04 Am-241 0.000% 1.30E-05 Am-243 0.000% 4.16E-06 Cm-242 0.000% 8 94E-05 Cm-243 0.000% 5.13E-05

Docket No. 50-286 NL-03-074 Page 16 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12131/2002 Percent Cutoff: 0 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 32.604% 1.05E-02 Be-7 0.250% 8.08E-05 Cr-51 0.773% 2.50E-04 Mn-54 0.009% 2.81 E-06 Fe-55 3.945% 1.28E-03 Co-58 0.723% 2.34E-04 Co-60 15.905% 5.15E-03 Ni-63 19.726% 6.38E-03 Sr-90 0.154% 4.98E-05 Zr-95 2.097% 6.79E-04 Nb-95 1.849% 5.S8E-04 Ag-11 Om 0.003% 8.77E-07 Sb-125 1.525% 4.93E-04 Cs-134 3.031% 9.81 E-04 Cs-137 16 956% 5.49E-03 Ce-144 0.006% 2.09E-06 Pu-241 0.337% 1.09E-04 Am-241 0.056% 1.81 E-05 Am-243 0.048% 1.57E-05 Cm-242 0.003% 8.78E-07

Docket No. 50-286 NL-03-074 Page 17 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12/31/2002 Percent Cutoff: 0 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 2.439% 7.76E-02 Be-7 0.000% O.OOE+00 C-14 0.098% 3.13E-03 Cr-51 0.000% 1.98E-09 Mn-54 1.151% 3.66E-02 Fe-55 26.801% 8.52E-01 Fe-59 0.000% 1.89E-07 Co-57 0.068% 2.17E-03 Co-58 0.376% 1.20E-02 Co-60 47.509% 1.51 E+00 Ni-59 0.222% 7.07E-03 Ni-63 16.845% 5.36E-01 Zn-65 0.123% 3.91 E-03 Sr-89 0.000% 5.63E-10 Sr-90 0.029% 9.21 E-04 Zr-95 0.003% 9.39E-05 Nb-95 0.000% 2.63E-06 Tc-99 0.009% 2.71 E-04 Ru-103 0.000% 1.20E-09 Ru-1i06 0.038% 1.20E-03 Ag-1 Om 0.272% 8.66E-03 Sn-113 0.011% 3.36E-04 Sb-1 24 0.000% 4.24E-06 Sb-1 25 2.907% 9.25E-02 Cs-1 34 0.088% 2.80E-03 Cs-1 37 0.845% 2.69E-02 Ce-I44 0.012% 3.76E-04 Np-237 0.019% 6.02E-04 Pu-238 0.001% 2.73E-05 Pu-239 0.000% 6.77E-06 Pu-241 0.132% 4.21 E-03 Am-241 0.000% 1.1 OE-05 Am-243 0.000% 9.99E-06 Cm-242 0.000% 2.46E-06 Cm-243 0 001% 4.31 E-05

Docket No. 50-286 NL-03-074 Page 18 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12/3112002 Percent Cutoff: 0 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 2.743% 8.81 E-02 Be-7 0.003% 8.08E-05 C-14 0.097% 3.13E-03 Cr-51 0.008% 2.50E-04 Mn-54 1.140% 3.66E-02 Fe-55 26.571% 8.54E-01 Fe-59 0.000% 1.89E-07 Co-57 0.068% 2.17E-03 Co-58 0.379% 1.22E-02 Co-60 47.190% 1.52E+00 Ni-59 0.220% 7.07E-03 Ni-63 16.874% 5 42E-01 Zn-65 0.122% 3.91 E-03 Sr-89 0.000% 5.63E-10 Sr-90 0.030% 9.71 E-04 Zr-95 0.024% 7.73E-04 Nb-95 0.019% 6.01 E-04 Tc-99 0.008% 2.71 E-04 Ru-103 0.000% 1.20E-09 Ru-1 06 0.037% 1.20E-03 Ag-1 Om 0.269% 8.66E-03 Sn-113 0.010% 3.36E-04 Sb-1 24 0.000% 4.24E-06 Sb-125 2.894% 9.30E-02 Cs-134 0.118% 3.78E-03 Cs-137 1.007% 3.24E-02 Ce-144 0.012% 3.78E-04 Np-237 0.019% 6.02E-04 Pu-238 0.001% 2.73E-05 Pu-239 0.000% 6.77E-06 Pu-241 0.134% 4.32E-03 Am-241 0.001% 2.91 E-05 Am-243 0.001% 2.57E-05 Cm-242 0.000% 3.34E-06 Cm-243 0.001% 4.31 E-05

Docket No. 50-286 NL-03-074 Page 19 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12/31/2002 Percent Cutoff: 0 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.023% 6.43E-03 C-I 4 0.004% 9.91 E-04 Mn-54 2.191% 6.17E-01 Fe-55 5.707% 1.61 E+00 Co-57 0.065% 1.82E-02 Co-58 1.500% 4.23E-01 Co-60 24.976% 7.04E+00 Ni-63 50.867% 1.43E+01 Zn-65 C.159% 4.48E-02 Sr-90 0.022% 6.24E-03 Zr-95 0.235% 6.64E-02 Nb-95 0.580% 1.63E-01 Tc-99 0.015% 4.37E-03 Ag-110m 0.270% 7.6 1E-02 Sn-113 0.076% 2.15E-02 Sb-1 24 0.068% 1.93E-02 Sb-125 2.188% 6.16E-01 Cs-134 4.617% 1.30E+00 Cs-137 6.431% 1.81 E+00 Ce-144 0.002% 4.97E-04 Pu-238 0.000% 3.31 E-05 Pu-239 0.000% 4.35E-06 Pu-241 0.003% 8.44E-04 Am-241 0.000% 1.30E-05 Am-243 0.000% 4.16E-06 Cm-242 0.000% 8.94E-05 Cm-243 0.000% 5.13E-05

Docket No. 50-286 NL-03-074 Page 20 of 26 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2002 to 12/3112002 Percent Cutoff: 0 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 0.301% 9.45E-02 Be-7 0.000% 8.08E-05 C-14 0.013% 4.12E-03 Cr-51 0.001% 2.50E-04 Mn-54 2.084% 6.54E-01 Fe-55 7.842% 2.46E+00 Fe-59 0.000% 1.89E-07 Co-57 0.065% 2.04E-02 Co-58 1.386% 4.35E-01 Co-60 27.249% 8.55E+00 Ni-59 0.023% 7.07E-03 Ni-63 47.388% 1.49E+01 Zn-65 0.155% 4.87E-02 Sr-89 0.000% 5.63E-1 0 Sr-90 0.023% 7.21 E-03 Zr-95 0.214% 6.71 E-02 Nb-95 0.522% 1.64E-01 Tc-99 0.015% 4.64E-03 Ru-1 03 0 000% 1.20E-09 Ru-1 06 0.004% 1.20E-03 Ag-1i1m 0.270% 8.47E-02 Sn-113 0.070% 2.19E-02 Sb-1 24 0.061% 1.93E-02 Sb-125 2.260% 7.09E-01 Cs-1 34 4.157% 1.30E+00 Cs-137 5.876% 1.84E+00 Ce-144 0.003% 8.75E-04 Np-237 0.002% 6.02E-04 Pu-238 0.000% 6.04E-05 Pu-239 0.000% 1.11E-05 Pu-241 0.016% 5.16E-03 Am-241 0.000% 4.21 E-05 Am-243 0.000% 2.98E-05 Cm-242 0.000% 9.28E-05 Cm-243 0.000% 9.44E-05

Docket No. 50-286 NL-03-074 Page 21 of 26 Indian Point 3 RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2002 - Dec 31, 2002

Docket No. 50-286 NL-03-074 Page 22 of 26 RADIOLOGICAL IMPACT ON MAN 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).

An annual average dispersion factor is used in the calculations, the details of which are presented in the Offsite Dose Calculation Manual (ODCM).

The computer code used to perform gaseous dose calculations incorporates the models and parameters presented in the Indian Point 3 ODCM, which utilizes the assumptions in Regulatory Guide 1.109 and NUREG 0133.

These doses were calculated using radioactive releases from the Indian Point #3 Nuclear Power Plant. Although Indian Point is a multi-unit site owned and operated by Entergy Nuclear Northeast, doses resulting from releases from Indian Point Units 1 and 2 are independently reported.

Doses to individuals from liquid pathways for the fish and invertebrate consumption pathways are computed using the methodology and parameters in the Indian Point 3 ODCM, which incorporates the calculational models that are present in Regulatory Guide 1.109 and NUREG 0133 where site specific data do not exist.

Carbon 14 release concentration and resulting dose 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 IP3 has been calculated using the maximum dependable gross electrical capacity of Indian Point 3, which is 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.

Docket No. 50-286 NL-03-074 Page 23 of 26 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 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.

In compliance with 40CFR190, the following table indicates the measured direct shine dose component for Indian Point 3 property in 2002:

Whole Body Max Organ (mrem) (mrem) 40 CFR 190 limit 25 75 Airborne Effluents .00076 .00076 Liquid Effluents .0010 .0013 Radwaste Storage <4 <4 Station Total < 4.0 < 4.0

Docket No. 50-286 NL-03-074 Page 24 of 26 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2002 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Q . .r ANNUA..........

Qtr 1 Qtr 2 Qtr 3 Utr 4 ANNUAL Organ Dose (mrem) 1.40E-04 1.06E-04 2.73E-04 1.17E-03 1.28E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 2.80E-03 2.12E-03 5.46E-03 2.35E-02 1.28E-02 Age Group Adult Adult Adult Adult Adult Critical Organ GILLI GILLI GILLI Liver Liver Adult Total Body (mrem) 2.07E-05 1.78E-05 3.99E-05 I 9.48E-04 11.03E-03 Applicable Limit (mrem) 1.5 1.5 1 1.5 1.5 3 Percent of Limit (%) 1.38E-03 1.19E-03 2.66E-03 6.32E-02 3.42E-02 B. AIRBORNE NOBLE GAS DOSES Otr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 3.03E-05 2.32E-05 6.13E-05 5.89E-05 1.74E-04 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 6.06E-04 4.64E-04 1.23E-03 1.1 8E-03 1.74E-03 Beta Air (mrad) 4.27E-05 4.74E-05 l 2.32E-04 4.87E-04 8.09E-04 l Applicable Limit (mrad) 10 l 10 l 10 10 20 j Percent of Limit (%) 4.27E-04 4.74E-04 2.32E-03 4.87E-03 4.05E-03 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUALl llodine/Part l(mrem) l1.91 E-04 l2.44E-04 l2.25E-04 l9.90E-05 l7.59E-04l lApplicable Limit l me)l 7.5 l 7.5 l 7.5 7.5 l 15 Percent of Limit (%) 2.55E-03 3.25E-03 3.OOE-03 1.32E-03 5.06E-03 lAge Group I l Child I Child I Child I Child I Child Critical Organ I Liver I Liver I Liver I Liver I Liver

Docket No. 50-286 NL-03-074 Page 25 of 26 Indian Point 3 RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2002 - Dec 31, 2002 This data is stored onsite and is available electronically or in writing, upon request.

Docket No. 50-286 NL-03-074 Page 26 of 26 Indian Point 3 RADIOACTIVE EFFLUENT REPORT G. OFFSITE DOSE CALCULATION MANUAL, PROCESS CONTROL PROGRAM, OR LAND USE CENSUS LOCATION CHANGES 2002 The ODCM was not upgraded in year 2002.

There were no changes in the REMP locations for dose calculations and/or environmental monitoring in year 2002.

The PCP was not upgraded in this period and remains at Revision 7.

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