Text

Official Exhibit - ENT00316A-00-BD01 - 2007 Annual Radioactive Effluent Release Report. Part 1 of 3
	ML12338A647
Person / Time
Site:	Indian Point
Issue date:	04/23/2008
From:	Robert Walpole; Entergy Corp
To:	; Atomic Safety and Licensing Board Panel, Document Control Desk, Office of Nuclear Reactor Regulation
	SECY RAS
References
	RAS 22132, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR, NL-08-068
	Download: ML12338A647 (309)
	v • d • e

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

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3) v....f;.p.fl. REGU<.,,, ASLBP #: 07-858-03-LR-BD01

!~~\""

Docket #: 05000247 l 05000286

< Exhibit #: ENT00316A-00-BD01 Identified: 10/15/2012

'"~

0 Admitted: 10/15/2012 Withdrawn:

....~ 0' f Rejected: Stricken: ENT00316A

? ..

Jf.***. Other: Submitted: March 29, 2012 Indian Point Energy Center

~Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Manager, Licensing April 23, 2008 Re: Indian Point Units No 1, 2, 3 Docket Nos. 50-3, 50-247, 50-286 NL-08-068 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

2007 Annual Radioactive Effluent Release Report

Dear Sir:

Enclosed are the 2007 Annual Effluent and Waste Disposal Report for Indian Point Unit Nos. 1, 2, and 3. Entergy Nuclear Operation, Inc. is submitting this report in accordance with Technical Specification 5.6.3 and Regulatory Guide r.21.

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

Should you have any questions regarding this matter, please contact Mr. Robert Walpole, Manager, Licensing,. at (914) 734-6710.

Respectfu lIy, Robert Walpole Manager, Licensing Indian Point Energy Center

Enclosure:

2007 Annual Radioactive Effluent Release Report, including Addendum 1, Offsite Dose Calculation Manual Changes and Justification Packages, 2007 cc: next page

---;--~utO

~ 70 A'CCCf

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Docket Nos. 50-3, 50-247, 50-286 NL-08-068 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 Energy Center 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. Chuck Nieder, NYS Department of Environmental Conservation

ENCLOSURE TO NL-08-68 Indian Point Energy Center 2007 Annual Radioactive Effluent Release Report with Addendum 1, ODCM changes and justification packages, 2007 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 55 Radioactive Effluent Release Report: 2007 Facility Indian Point Energy Center (Indian Point Units 1. 2. and 3)

Licensee Entergy Nuclear Operations. Inc (Entergy)

This information is provided in accordance with the requirements of Regulatory Guide 1.21. The numbered sections of this report reference corresponding sections of the subject Guide, pages 10 to 12.

This report includes effluent information from Indian Point units 1, 2, and 3. Units 1 and 2 share effluent processing equipment and Technical Specifications. In this site report, releases from Unit 1 are included with Unit 2, while Unit 3 releases are calculated and shown separately.

A. Supplemental Information

1. Regulatory Limits Indian Point Energy Center is subject to limits on radioactive waste releases that are set forth in the Offsite Dose Calculation Manual (ODCM), Parts I and II, as defined in the Technical Specifications. ODCM Part I, also known as the Radiological Effluent Controls (or RECS) contains the specific requirements and controls, while ODCM Part II (calculational methodologies) contains the details necessary to perform offsite dose calculations from the sampling and monitoring outlined in the RECS.

2. Maximum Permissible Concentration a) Airborne Releases Maximum concentrations and compliance with 10CFR20 release rate limits are controlled by the application of Radiation Monitor setpoints, preliminary grab sampling, and conservative procedural guidance for batch and continuous releases. These measures, in conjunction with plant design, preclude approaching release rate limits, per the ODCM.

b) Liquid Effluents Proximity to release rate and total release limits is controlled through the application of a calculated Allowed Diluted Concentration (ADC) and ALARA guidance with regard to dilution flow and maximum tank concentration. The ADC is used to determine a Radiation Monitor setpoint associated with an estimated amount of Beta activity, as well as the measured gamma activity. ADC is defined in the station ODCM as a means of assuring compliance with the release rate limits of 10CFR20, as defined by the application of ten times the Effluent Concentrations of the new 10CFR20.

Liquid effluents are further controlled by the application of proceduralized ALARA limits such as a MINIMUM dilution flow of 100,000 gpm required for batch discharges, a maximum gamma concentration of SE-S uCi/ml (without gas or tritium) for routine effluents, and procedural guidance for optimizing decay and treatment of liquid waste.

Docket No. 50-3, 50-247, & 50-286 Page 2 of 55

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

Units 1 and 2:

1st Quarter E~= 2.48E-01 Mev/dis Ey= 1.49E-01 Mev/dis 2nd Quarter E~= 2.62E-01 Mev/dis Ey= 2.35E-01 Mev/dis 3rd Quarter Ef3= 2.62E-01 Mev/dis Ey= 3.80E-01 Mev/dis 4th Quarter E~= 2.06E-01 Mev/dis Ey= 2.56E-01 Mev/dis Unit 3:

1st Quarter Ef3= 1.37E-01 Mev/dis Ey= 5.11 E-02 Mev/dis 2nd Quarter E~= 2.67E-01 Mev/dis Ey= 1.90E-01 Mev/dis 3rd Quarter E~= 4.53E-01 Mev/dis Ey= 1.24E+00 Mev/dis 4th Quarter E~= 4.47E-01 Mev/dis Ey= 1.22E+00 Mev/dis

4. Measurements and Approximations of Total Radioactivity a) Fission and Activation Gases Analyses of effluent gases are performed in compliance with the requirements of the RECS (ODCM Part I). In the case of isolated tanks (batch releases), the total activity discharged is based on an isotopic analysis of each batch with the volume of gas in the batch corrected to standard temperature and pressure.

Vapor containment purge and pressure relief (vent) discharges routinely total less than 150 hour0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months s/quarter in duration have been treated as batch releases.

However, both types of releases from the Vapor Containment are performed randomly with regard to time of day* and duration (release periods were not dependant solely on time of day or atmospheric condition). Therefore, determination of doses due to Vapor Containment releases includes the use of annual average dispersion data, as defined in NUREG 0133, Section 3.3.

At least one complete isotopic concentration analysis of containment air IS performed monthly and compared to a process monitor's reading. Pressure reliefs are quantified by scaling subsequent releases with the monitor's reading, applying the mixture from the grab sample. In this fashion, the base grab sample defines the mixture and the activity released. The monitor scales the release up or down and provides continuous indication of potential leaks.

Isotopic analyses for each vapor containment purge are taken prior to and during the purge. This information is combined with the volume of air in each discharge to calculate the quantity of activity released from these discharges.

The continuous building discharges are based on weekly samples of ventilation air analyzed for isotopic content. This information is combined with total air volume discharged and the process radiation monitor readings to determine the quantity of activity from continuous discharges.

Docket No. 50-3, 50-247, & 50-286 Page 3 of 55 b/c) lodines and Particulates lodine-131 and particulate releases are quantified by collecting a continuous sample of ventilation air on a Triethylenediamine (TEDA) impregnated, activated charcoal cartridge and a glass-fiber filter paper. These samples are changed weekly as required in the RECS. The concentration of isotopes found by analysis of these samples is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged.

If no 1-131 is identified in weekly vent samples, "-" is entered in Table 1A. A typical Minimum Detectable Activity (MDA) for weekly 1-131 analyses is 1.OE-13 uCi/cc, which is 100 times lower than aDCM requirements.

If 1-131 is identified in any routine weekly sample, it is added to the table and other iodine isotopic concentrations are then determined on a 24-hour sample at least once per month. The concentration of each isotope is analytically determined by ratioing the activities with weekly media for 1-131. This activity is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged.

A compositing method of analyzing for gross alpha is used per the station ODCMs. An absence of any positive Gross Alpha value for the quarter is identified on Table 1A as "-". A typical MDA for gross alpha is 8.0E-14 uCi/cc, which is over 100 times lower than aDCM 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 REC~ 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 aDCMs. When there has been no positive Gross Alpha identified in a quarter, "-"

is entered in Table 2A. A typical MDA value for Gross Alpha in liquids is SE-8 uCi/ml, which is two times lower than aDCM requirements.

liquid Effluent volumes of waste released on Table 2A are differentiated between processed fluids (routine liquid waste and Unit 1's North Curtain Drain), and water discharged through monitored pathways identified in the aDCM, but NaT processed (SG Blowdown and Unit 1's Sphere Foundation Drain Sump).

The unprocessed water may still contain trace levels of contamination (generally only tritium) and as such, is identified as liquid waste and included in total curie and dose summaries in the following tables, along with all other liquid effluent, continuous or batch, processed or not.

However, to prevent confusion with regard to measures undertaken to convert liquid to solid waste (resin cleanup), the volumes of processed and unprocessed waste are reported separately.

Docket No. 50-3, 50-247, & 50-286 Page 4 of 55

5. Batch Releases Airborne:

Unit 1 and 2 Airborne Releases . ' Qtr 1 Qtr 2' Qtr3 Qtr4**.**.*.' 2007.

Number of Batch Releases 39 40 47 38 164 Total Time Period (min) 3.45E+3 3.52E+3 3.90E+3 3.65E+3 1.46E+4 Maximum Time Period (min) 2.23E+2 1.38e+2 1.68E+2 1.68E+2 . 2.23E+2 Average Time Period (min) 9.07E+1 8.81E+1 8.29E+1 9.61E+1 8.91 E+1 Minimum Time Period (min) 1.00E+1 3.90E+1 2.00E+0 3.60E+1 2.00E+0 Unit 3 Airborne Releases Qtr .1 ,Qtr2 ,'Qtr 3 I Qtr4 ** 2007 Number of Batch Releases 23 26 19 18 86 Total Time Period (min) 4.85E+3 2.75E+3 1.94E+3 2.43E+3 1.20E+4 Maximum Time Period (min) 7.20E+2 2.09E+2 2.23E+2 1.96E+2 7.20E+2 Average Time Period (min) 2.11E+2 1.06E+2 1.02E+2 1.35E+2 1.39E+2 Minimum Time Period (min) 2.10E+1 3.00E+0 9.00E+0 8.00E+0 3.00E+0 Liquid:

Unit 1 and 2 Liquid Releases Qtr1 'Qtr2," ,Otr 3 Qtr4 2007 Number of Batch Releases 10 7 8 12 37 Total Time Period min) 9.85E+2 7.2SE+2 7.S0E+2 1.06E+2 3.S2E+3 Maximum Time Period min) 1.12E+2 1.43E+2 1.02E+2 1.1SE+2 1.43E+2 Average Time Period min) 9.8SE+1 1.04E+2 9.38E+1 8.80E+1 9.50E+1 Minimum Time Period min) 7.60E+1 8.40E+1 7.40E+1 2.S0E+1 2.50E+1 Unit 3 Liquid Releases Qtr 1 Qtr 2 Qtr3 Qtr4 2007 Number of Batch Releases 64 40 15 8 127 Total Time Period (min) 1.05E+4 4.5SE+3 1.64E+3 8.97E+2 1.76E+4 Maximum Time Period (min) 5.56E+2 1.57E+2 1,16E+2 1.20E+2 S,S6E+2 Average Time Period (min) 1.65E+2 1.14E+2 1.09E+2 1.12E+2 1.39E+2 Minimum Time Period (min) 1.90E+1 1.00E+2 1.02E+2 1.03E+2 1.90E+1 Average Stream Flow:

Hudson River flow information is obtained from the Department of the Interior, United States Geological Survey (USGS). These data are received after review from the USGS, approximately 18 months after initial data collection. This information is included in the effluents report as the data become available.

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

Year Quarter Flow (ets) 2005 Fourth 114400 2006 First 97900 2006 Second 95600 2006 Third 52700

Docket No. 50-3, 50-247, & 50-286 Page 5 of 55

6. Abnormal Releases a) Liquid Groundwater The effluent contribution via ground water and storm drain discharges (broken up into six zones across the site) is discussed in Section H. The computation of these effluent contributions is comprised of two parts: 1) computing the groundwater and storm water discharges (flux), and 2) multiplying these fluxes by the measured radionuclide activity in each zone.

Groundwater flux beneath the site is calculated using a calibrated Precipitation Mass Balance model. Storm water discharge rates are generally estimated based on the yearly volume of precipitation falling on storm drain catchment areas.

Groundwater radionuclide activity is based on a yearly rolling average of analytical results from groundwater samples collected from monitoring wells.

Storm drain activity is measured via water samples collected directly from the storm drains on site during the calendar year.

The average groundwater activity in each zone is multiplied by the groundwater flux in that portion of the site to obtain the effluent contribution via groundwater. The average activity in each storm water discharge point is multiplied by the estimated storm water flow rate to obtain the effluent contribution via surface water.

The resulting offsite dose from this modeling is identified in the summary of Section H, and is added to the site total summary in the opening discussion of Section E, the Dose To Man report.

Section H provides a summary of the recently completed groundwater investigation on site. Included in this section are 1) the conclusions from effluent dose modeling for 2007, 2) a conservative assessment of groundwater effluent dose from as early as 1994, and 3) per the aDeM and NEI 07-07, a summary table of all groundwater radio-analyses in 2007.

Underground pipe leak In March 2007, a small secondary fluid leak to environment was identified on an aux steam cross-connect line from unit 2 to unit 3. The part of the line that was found leaking was underground, and wisps of steam through asphalt were the first indicators. The cross connect line was isolated and samples obtained. Regional and federal officials were notified, per the emerging NEI groundwater initiative. This particular event occurred just as the NEI final document was being prepared, and details of underground pipe integrity were added to the guidance as a result. An offsite dose evaluation of this steam/water release to environment indicated doses well below 0.1 % of routine values, or less than 0.01 % of effluent limits, even with a very conservative flow rate assessment determined from secondary system loss rate. This evaluation was performed per IE Bulletin 80-10 and resulted in repair and replacement of the pipe over a 4 month period. The secondary system contamination included no gamma isotopes and only a trace amount of tritium. Nonetheless, per the new guidance in NEI 07-07, secondary fluid at PWRs is considered "contaminated", even if this fluid only contains trace levels of tritium. This evaluation was completed to demonstrate compliance with NEI guidelines and to document no significant impact from this event.

Docket No. 50-3, 50-247, & 50-286 Page 6 of 55 b) Gaseous There was an assumed trace airborne H-3 effluent as a result of the underground steam piping leak, discussed above. The actual airborne effluent contribution from the steam venting to atmosphere was assessed and determined to be well below 0.1 % of routine values, and less than 0.001 % of effluent limits.

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

ODCM Instrumentation:

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

Out of Service .Details Instrument*

Period*

The instrument failed its routine calibration and a replacement was deemed necessary. A new transmitter was ordered and Unit 1, Waste received. Upon receipt and installation, techniCians identified Distillate Storage Ju15,2007 that the output signal shifted with no signal input.

Tank Release to The vendor then suggested another replacement.

Flow Rate Aug 15,2007 Transmitter, The new instrument was tested and successfully placed in (40 days) service. During this interval, three batch releases were CT-971 performed, each with compensatory action completed, verifying release flow rate (by level change) at 4-hour intervals.

The instrument was originally taken out of service for troubleshooting. A new instrument was deemed necessary, Unit 1, Waste Oct 1,2007 and purchased from the vendor.

Distillate Storage to Tank #13 Level Upon arrival, the work package was delayed due to Nov 2,2007 administrative challenges involved in training and use of Transmitter, new work control software applied on site.

(32 days)

CT-968 During this interval, no releases were performed from this pathway.

Docket No. 50-3, 50-247, & 50-286 Page 7 of 55

7. ODCM Reporting Requirements (continued)

Other Reporting Criteria:

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.

The ODCMs were updated several times in 2007.

In January, 2007, independent, but similar ODCMs were effective at each operating unit. ODCM revision at both units (Revision 10 at unit 2, and Revision 18 at unit 3) were processed to include several significant additions and ongoing actions from the Ground Water investigation.

A month later, a revision at unit 2 followed, in February (Rev 11), to officially adopt the new 10CFR20 at unit 2, after Tech Spec approval from the NRC.

In December, the unit-specific versions of the ODCMs at IPEC were combined into Revision 0 of the IPEC ODCM, with the Controls arranged in NUREG 1431 format, identical to the previous revision for unit 2. No new controls or routine dose calculations were added in this merging and reformatting process. The necessary changes performed to complete this upgrade and some minor updates to the ground water offsite dose modeling are discussed in the justification packages.

ODCM update information is discussed in Section G. Full copies of the ODCMs and their justification packages are included as an addendum to this report.

Docket No. 50-3, 50-247, & 50-286 Page 8 of 55 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2007

Docket No. 50-3, 50-247, & 50-286 Page 9 of 55 TABLE lA INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A Rssion & .Activation Gases Units I Qtr1 Qtr2 Qr3 Qr4 2JX1T %8rcr

1. Total Release a 6.46E-01 2.22E-01 4.386-01 1.38E-01 1.44E+OO +/-25

2. AVffcqa release rate uO/sec 8.31E-02 2.83E-02 5.51E-02 1.73E-02 4.58E-02 B. Icx:lines It Tdallodire-131 +/-25 C. Partirulates

1. Total Release, Wth half-life> 8 days a - - - - 0.00800 +/-25

2. AVffcqa release rate uO/sec - - - - O.OOE+OO

3. Qoss,AJ~ a - - - - 0.00800 2:25 D. Tritium

1. Total release a 3.45800 4.75E+OO 4.48E+OO 1.83E+OO 1.45E+01 2:25

2. AVffcqa release rate uO/sec 4.43E-01 6.04E-01 5.63E-01 2.30E-01 4.60E-01

- Indicates < rvDA

Docket No. 50-3, 50-247, & 50-286 Page 10 of 55 TABLE IC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr2 Qtr3 Qtr4 2007 Xe-131m Ci - - - - O.OOE+OO Xe-133 Ci - - - - O.OOE+OO Xe-135 Ci - - - - O.OOE+OO l Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

2) lodines 1-131 Ci - - - O.OOE+OO 1-133 Ci - - - - O.OOE+OO 1-135 Ci - - - - O.OOE+OO I Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3) Particulates Co-58 Ci - - - - O.OOE+OO Cs-137 Ci - - - - O.OOE+OO Ni-63 Ci - - - - O.OOE+OO I Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 11 of 55 TABLE IC INDIAN POINT 1 and 2 - BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

Nuclides Released Year

1) Fission Gases 2007 Units Qtr 1 Qtr 2 Qtr3 Qtr4 Ar-41 Ci 5. 16E-02 3.22E-02 9.15E-02 2.30E-02 1.98E-01 Kr-85 Ci 3. 94E-01 1.13E-01 5.71E-02 1.24E-02 5. 77E-01 Kr-85m Ci 2.23E-03 9.81E-04 4.00E-03 1.05E-04 7. 32E-03 Kr-87 Ci 1.89E-03 3.52E-04 3.49E-03 2.96E-05 5.75E-03 Kr-88 Ci 4.06E-03 1.45E-03 7.32E-03 9.90E-05 1.29E-02 Xe-131m Ci - - 1.93E-03 3.80E-04 2.31E-03 Xe-133 Ci 1.49E-01 5.32E-02 1.96E-01 9.72E-02 4.95E-01 Xe-133m Ci 9.43E-04 6.26E-04 1.83E-03 3.76E-04 3.78E-03 Xe-135 Ci 3.61E-02 2.05E-02 6. 37E-02 4.00E-03 1.24E-01 Xe-135m Ci 4. 77E-03 7.12E-05 9.34E-03 - 1.42E-02 Xe-138 Ci 1.22E-03 - 2.33E-03 - 3.55E-03 l Total for Period Ci 6.46E-01 2.22E-01 4.38E-01 1.38E-01 1.44E+OO

2) lodines Not Applicable for Batch Releases

3) Particulates Not Applicable for Batch Releases

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 12 of 55 TABLE lA INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Tctal A Rssim & Adivatim Gases Ulits Qr1 Qr2 Qr3 Qr4 21XJ7 %Errcr

1. TctaI Release a 7.54E+OO 1.21E-01 1.39E-02 212E-02 7.70E+OO :!:25

2. Av~ release rate LCi/sec 9.70E-01 1.54E-02 1.75E-03 267E-03 2.44E-01 B. looines

1. Tctallooire-131 a 1.42E-04 - - - 1.42E-04 :!:25

2. Av~ release rate LCi/sec 1.82E-05 - - - 4.49E-C6 C. Parti ClJIates

1. Tctal Release, wth half-life> 8 davs a - - - - - :!:25

2. Av~ release rate LCi/sec - - - - -

3. Qa;sAlp,a a - - - - - :!:25 D. Triti lUT1

1. Tctal release a 2.17800 3.94E+OO 4.00E+OO 2.00E+00 1.34E+01 :!:25

2. Av~ release rate LCi/sec 2.~-O1 5.01E-01 5.79E-01 3.34E-01 4.24E-D1

- Irdicates < MD\

Docket No. 50-3, 50-247, & 50-286 Page 13 of 55 TABLE IC INDIAN POINT 3 - CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 2007 IXe-133 Ci 5.99E+00 - - - 5.99E+00 I

Total for Period Ci 5.99E+00 - - - 5.99E+00

2) lodines 1-131 Ci 1.42E-04 - - - 1.42E-04 1-133 Ci 1.49E-05 - - - 1.49E-05 1-135 Ci - - - - -

I Tota! for Period Ci 1.57E-04 - - - 1.57E-04

3) Particulates Total for Period Ci

- indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 14 of 55 TABLE IC INDIAN POINT 3 BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr2 Qtr3 Qtr4 2007 Ar-41 Ci 2.77E-02 1.73E-02 1.35E-02 2.02E-02 7.87E-02 Kr-85 Ci - 8. 96E-02 - - 8.96E-02 Kr-85m Ci - - - - O.OOE+OO Kr-87 Ci - - - - O.OOE+OO Kr-88 Ci - - - - O.OOE+OO Xe-131 m Ci - 2.65E-04 - - 2.65E-04 Xe-133 Ci 1.50E+00 1.40E-02 4.44E-04 1.07E-03 1.52E+00 Xe-133m Ci - - - - O.OOE+OO Xe-135 Ci 2.23E-02 2.70E-06 1.34E-05 - 2.23E-02 Xe-135m Ci - - - - O.OOE+OO I Total for Period Ci 1.55E+00 1.21 E-01 1.39E-02 2.12E-02 1.71E+OO

2) lodines Not Applicable for Batch Releases

3) Particulates Not Applicable for Batch Releases

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 15 of 55 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2007

Docket No. 50-3, 50-247, & 50-286 Page 16 of 55 TABLE 2A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission & Activation Products % Error Units Qtr1 Qtr2 Qtr3 Qtr4 2007

1. Total Release (not induding Tritium, Gr Alpha, & Gases)

Ci 9.20E-03 1.54E-02 4. 56E-03 1.32E-02 4.24E-02 :t 25

2. Average Diluted Cone uCi/ml 1.94E-11 2.20E-11 5:28E-12 1.76E-11 1.52E-11 B. Tritium

1. Total Release Ci 3.21E+01 9.01E+01 3. 55E+02 2. 17E+02 6. 94E+02 :t 25

2. Average Diluted Cone uCi/ml 6. 76E-08 1.28E-07 4.11E-07 2. 89E-07 2.49E-07 C. Dissolved & Entrained Gases

1. Total Release Ci - - - - O.OOE+OO :t 25

2. AverageDiluted Cone uCi/ml - - - - O.OOE+OO D. GrossAipha 1"1. Total Release Ci :t 25 E. Volume of Waste Released

1. Processed (LW, NCO) liters 2.02E+06 2.30E+06 1.33E+06 2.36E+06 8.02E+06 :t 10

2. Unprocessed (SGBD, SFDS) liters 4. 14E+07 4.25E+07 3.72E+07 3. 95E+07 1.61E+08 :t 10 F. Volume of Dilution Water

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page .17 of 55 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

CONTINUOUS RADIOACTIVE EFFLUENT Year Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr4 2007 Cs-137 Ci 9.97E-04 4.03E-03 1.78E-06 9.19E-05 5.12E-03 Ni-63 Ci - - - - O.OOE+OO Sr-B9 Ci - - "

- - O.OOE+OO Sr-90 Ci 1.21E-04 1.88E-04 8.45E-05 2.47E-04 6.41E-04 I Total for Period Ci 1.12E-03 4.22E-03 8.63E-05 3.39E-04 5.76E-03

- Indicates < MDA

Docket No. SO-3, SO-247, & SO-28S Page 18 of SS TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

BATCH RADIOACTIVE EFFLUENT Year Nuclides Released 2007 Units Qtr1 Qtr2 Qtr3 Qtr4 Ag-110m Ci - - - 9.42E-OS 9.42E-OS Co-S7 Ci 7. 44E-OS 3. 16E-OS - - 3.9~E-OS Co-S8 Ci 1.48E-03 7.91E-04 1.54E-OS - 2.28E-03 Co-60 Ci S.71E-04 S.10E-04 7.64E-OS 2.89E-04 1.4SE-03 Cr-S1 Ci - - - 6.36E-OS 6.36E-OS Cs-134 Ci - 2.1SE-OS 2.0SE-04 3.28E-04 S.SSE-04 Cs-137 Ci 7.21E-OS 2.88E-04 1.B4E-03 3.28E-03 S.48E-03 Mn-54 Ci - - - 3.S8E-06 3.S8E-06 Ni-63 Ci 2.43E-03 8. 14E-03 8.0SE-04 2. 18E-03 1.3SE-02 Sb-12S Ci 3.S2E-03 1.4SE-03 1.S3E-03 6.60E-03 1.31E-02 Sr-90 Ci - 8.66E-07 - - 8.SSE-07 I Total for Period Ci 8.08E-03 1.12E-02 4.47E-03 1.28E-02 3.S6E-02 Dissolved & Entrained Gas Total for Period Ci IO.OOE+OOI

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 19 of 55 TABLE 2A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission & Activation Products 2007 % Error Units Qtr1 Qtr2 Qtr3 Qtr4

1. Total Release (not including Ci 6. 59E-03 1.45E-03 2. 76E-03 7. 13E-04 1.15E-02 .:!:25 Tritium, Gr Alpha, & Gases)

2. Average Diluted Conc uCiiml 1.39E-11 2.06E-12 3.19E-12 9.53E-13 4.13E-12 B. Tritium

1. Total Release Ci 6. 55E+02 7.72E+01 2.46E+01 1.71E+01 7. 74E+02 .:!:25

2. Average Diluted Conc uCiiml 1.38E-06 1.10E-07 2.85E-08 2.28E-OS 2. 77E-07 C. Dissolved & Entrained Gases

1. Total Release Ci 3.S7E-02 9.50E-04 - - 3. 96E-02 .:!:25

2. AverageDiluted Conc uCiiml S.15E-11 1.35E-12 - - 1.42E-11 D. Gross Alpha

1. Total Release Ci .:!:25 I

E. Volume of Waste Released

1. Processed Fluids (Mon Tanks) liters 1. 18E+06 1.04E+06 3. 88E+05 2.06E+05 2.S1E+06 .:!: 10

2. Unprocessed Fluids (SGs) liters 7.43E+06 1.S2E+07 1.64E+06 1.64E+06 2.90E+07 :!:10 F. Volume of Dilution Water

'- indicates < MDA

Docket No. SO-3, SO-247, & SO-286 Page 20 ofSS TABLE 2B INDIAN POINT 3 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2007)

BATCH and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT Batch Fission/Activation Products Units Qtr1 Qtr2 Qtr3 Qtr4 2007 Ag-110m Ci 7. 33E-OS 1.29E-OS 8.62E-OS Co-S8 Ci 1.3SE-03 3.S8E-04 3. 78E-04 1.26E-04 2.21E-03 Co-60 Ci 2.00E-03 8. 12E-OS 2. 68E-04 1.44E-04 2.49E-03 Cr-S1 Ci 1. 14E-04 1. 14E-04 Cs-134 Ci S.22E-OS S.22E-OS Cs-137 Ci 1. 17E-04 1.54E-OS 2.09E-06 2.S2E-06 1.37E-04 Fe-SS Ci 1. 17E-03 - - - 1. 17E-03 1-131 Ci - 4. 72E-OS - - 4. 72E-OS 1-132 Ci 7.91E-OS - - - 7.91E-OS Mn-54 Ci 1.S8E-OS 8.4SE-07 4.05E-06 1.25E-06 2. 19E-05 Nb-9S Ci - 3. 27E-06 - 1.12E-OS 1.4SE-05 Ni-63 Ci 8. 35E-04 - 3.48E-05 2. 83E-04 1.15E-03 Sb-124 Ci - 4.41E-OS 2.80E-04 - 3. 24E-04 Sb-12S Ci 5.71E-04 6.44E-05 1.78E-03 1.29E-04 2.54E-03 Sn-113 Ci - - - 3.10E-06 3.10E-06 Te-123m Ci 1.39E-04 8. 33E-04 1.18E-OS - 9.B4E-04 Te-132 Ci 7.65E-OS - - - 7.65E-OS I Total for Period Ci 6. 59E-03 1.4SE-03 2. 76E-03 7. 13E-04 1.15E-02 Dissolved and Entrained Gas (Batch)

Kr-85 Ci 1. 66E-03 5.3SE-04 - - 2. 19E-03 Xe-133 Ci 3.70E-02 4.1SE-04 - - 3. 74E-02 Xe-133m Ci 2.41E-05 - - 2.41E-05 I Total for Period Ci 3. 87E-02 9.50E-04 O.OOE+OO O.OOE+OO 3. 96E-02 Continuous Releases (SG Blowdown)

H-3 (only) Ci I 7. 59E-03 I 11.68E-03 I 2. 62E-03 I 1. 19E-02 I

'- indicates < mda

Docket No. 50-3, 50-247, & 50-286 Page 21 of 55 Indian Point Energy Center (Units I, 2, and 3)

RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2007

Docket No. 50-3, 50-247, & 50-286 Page 22 of 55 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2007 to 12/31/2007 Percent Cutoff: 0 (all identified isotopes are included)

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

Class fe m3 Shipped A 2.00 E +02 S.66E+00 1.12 E -0 1 +/- 25%

B 1.31 E+02 3.71E+00 1.23E+01 +/- 25%

C 9.50E+01 2.69E+00 2.74E+02 +/- 25%

All 4.26E+02 1.21E+01 2.86E+02 +/- 25%

Waste Stream Dry Active Waste DAW 1 Equip DAW 10 irt;B-25 Box DAW 20' Sea Land Soil/Debris - Interm odal Waste Volume Curies % Error (C i)

Class fe m 3 Shipped A 2.29E+04 6.47E+02 2.09E-01 +/-25%

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

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

All 2.29E+04 6.47E+02 2.09E-01 +/-25%

Waste Stream Irradiated Components Waste Volume Curies % Error (C i)

Class fe m 3 Shipped A 0.00 E +00 O.OOE+OO O.OOE+OO +/-25%

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

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

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

Waste Stream Other Waste Com bined Packages Waste Volume Curies % Error (C i) 3 Class ft3 m Shipped A O.OOE+oo o.ooE+oo o.ooE+oo +/-25%

B o.ooE+oo O.ooE+oo o .00E +00 +/-25%

C 2.03E+01 S.75E-01 1.44E+01 +/-25%

All 2.03E+01 5.75E-01 1.44E+01 +/-25%

Waste Stream : Sum of All 4 Categories Com bined Packages:

DAW ID irt; B-25 Box DAW 20' Sea Land LWS Resin Soil/Debris - Intermodal DAW-/ Equip Plant Resin 8-120 Waste Volume Curies % Error (C i)

Class fe m 3 Shipped A 2.31E+04 5.66E+00 3.21 E-01 +/-25%

B 1.31 E+02 3.71 E+OO 1.23E+01 +/-25%

C 1.15E+02 3.27E+00 2.88E+02 +/-25%

All 2.33E+04 1.26E+01 3.01E+02 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

Docket No. 50-3, 50-247, & 50-286 Page 23 of 55 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2007 to 12/31/2007 Percent Cutoff: 0 Number of Mode of Shipments Transportation Destination 5 Hittman Transport Duratek, Inc. - GIC 2 Hittman Transport Energy Solution - Bear Creek 5 Hittman Transport Studsvik Processing Facility 35 Studsvik Logistics Studsvik RACE Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance Curies Co-60 0.215% 2.42E-04 Cs-137 99.785% 1.12E-01 Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance Curies H-3 4.440% 5.45E-01 Mn-54 0.177% 2.18E-02 Fe-55 20.133% 2.47E+00 Co-57 0.055% 6.69E-03 Co-58 1.202% 1.47E-01 Co-60 8.028% 9.85E-01 Ni-63 50.354% 6.18E+00 Sr-90 0.081% 9.97E-03 Ag-110m 0.126% 1.55E-02 Sb-125 0.112% 1.38E-02 Cs-134 1.172% 1.44E-01 Cs-137 14.120% 1.73E+00 Resins, Filters, and Evap Bottoms Waste Class C Nuclide Name Percent Abundance Curies Mn-54 0.353% 9.67E-01 Fe-55 3.981% 1.09E+01 Co-57 0.069% 1.88E-01 Co-58 0.302% 8.28E-01 Co-60 6.136% 1.68E+01 Ni-63 36.343% 9.95E+01 Sr-90 0.089% 2.44E-01 Cs-134 18.336% 5.02E+01 Cs-137 33.969% 9.30E+01 Ce-144 0.394% 1.08E+00 Pu-238 0.001% 2.58E-03 Pu-239 0.000% 7.53E-04 Pu-241 0.024% 6.66E-02 Am-241 0.000% 5.28E-04 Cm-242 0.000% 1.29E-04 Cm-243 0.001% 1.54E-03

Docket No. 50-3, 50-247, & 50-286 Page 24 of 55 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies H-3 0.190% 5.45E-01 Mn-54 0.345% 9.88E-01 Fe-55 4.678% 1.34E+01 Co-57 0.068% 1.95E-01 Co-58 0.340% 9.75E-01 Co-60 6.214% 1.78E+01 Ni-63 37.006% 1.06E+02 8r-90 0.089% 2.54E-01 Ag-110m 0.005% 1.55E-02 8b-125 0.005% 1.38E-02 Cs-134 17.560% 5.03E+01 Cs-137 33.096% 9.48E+01 Ce-144 0.377% 1.08E+00 Pu-238 0.001% 2.58E-03 Pu-239 0.000% 7.53E-04 Pu-241 0.023% 6.66E-02 Am-241 0.000% 5.28E-04 Cm-242 0.000% 1.29E-04 Cm-243 0.001% 1.54E-03 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies C-14 0.012% 2.60E-05 Mn-54 3.035% 6.34E-03 Fe-55 33.935% 7.09E-02 Co-58 15.603% 3.26E-02 Co-60 25.702% 5.37E-02 Ni-63 10.530% 2.20E-02 8r-90 0.114% 2.39E-04 Cs-137 10.673% 2.23E-02 Ce-144 0.171% 3.58E-04 Pu-238 0.005% 1.03E-05 Pu-239 0.001% 2.64E-06 Pu-241 0.198% 4.13E-04 Am-241 0.001% 2.33E-06 Cm-242 0.011% 2.40E-05 Cm-243 0.007% 1.48E-05 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies C-14 0.012% 2.60E-05 Mn-54 3.035% 6.34E-03 Fe-55 33.935% 7.09E-02 Co-58 15.603% 3.26E-02 Co-60 25.702% 5.37E-02 Ni-63 10.530% 2.20E-02 8r-90 0.114% 2.39E-04 CS-137 10.673% 2.23E-02 Ce-144 0.171% 3.58E-04

Docket No. 50-3, 50-247, & 50-286 Page 25 of 55 Pu-238 0.005% 1.03E-05 Pu-239 0.001% 2.64E-06 Pu-241 0.198% 4.13E-04 Am-241 0.001% 2.33E-06 Cm-242 0.011% 2.40E-05 Cm-243 0.007% 1.48E-05 Other Waste Waste Class C Nuclide Name Percent Abundance Curies H-3 1.177% 1.69E-01 Mn-54 0.669% 9.63E-02 Fe-55 5.308% 7.64E-01 Co-57 0.068% 9.75E-03 Co-58 0.568% 8.18E-02 Co-60 4.789% 6.89E-01 Ni-63 25.421% 3.66E+00 Sr-90 0.070% 1.00E-02 Ag-110m 0.009% 1.35E-03 Sb-125 1.825% 2.63E-01 Cs-134 24.743% 3.56E+00 Cs-137 34.880% 5.02E+00 Ce-144 0.445% 6.41E-02 Pu-238 0.001% 1.43E-04 Pu-239 0.000% 3.02E-05 Pu-241 0.027% 3.92E-03 Am-241 0.000% 2.30E-05 Cm-242 0.000% 8.33E-06 Cm-243 0.000% 4.88E-05 Other Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 1.177% 1.69E-01 Mn-54 0.669% 9.63E-02 Fe-55 5.308% 7.64E-01 Co-57 0.068% 9.75E-03 Co-58 0.568% 8.18E-02 Co-60 4.789% 6.89E-01 Ni-63 25.421% 3.66E+00 Sr-90 0.070% 1.00E-02 Ag-110m 0.009% 1.35E-03 Sb-125 1.825% 2.63E-01 Cs-134 24.743% 3.56E+00 Cs-137 34.880% 5.02E+00 Ce-144 0.445% 6.41E-02 Pu-238 0.001% 1.43E-04 Pu-239 0.000% 3.02E-05 Pu-241 0.027% 3.92E-03 Am-241 0.000% 2.30E-05 Cm-242 0.000% 8.33E-06 Cm-243 0.000% 4.88E-05

Docket No. 50-3, 50-247, & 50-286 Page 26 of 55 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies C-14 0.008% 2.60E-05 Mn-54 1.970% 6.34E-03 Fe-55 22.030% 7.09E-02 Co-58 10.130% 3.26E-02 Co-60 16.748% 5.39E-02 Ni-63 6.836% 2.20E-02 Sr-90 0.074% 2.39E-04 Cs-137 41.948% 1.35E-01 Ce-144 0.111% 3.58E-04 Pu-238 0.003% 1.03E-05 PU-239 0.001% 2.64E-06 Pu-241 0.128% 4.13E-04 Am-241 0.001% 2.33E-06 Cm-242 0.007% 2.40E-05 Cm-243 0.005% 1.48E-05 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 4.440% 5.45E-01 Mn-54 0.177% 2.18E-02 Fe-55 20.133% 2.47E+00 Co-57 0.055% 6.69E-03 Co-58 1.202% 1.47E-01 Co-60 8.028% 9.85E-01 Ni-63 50.354% 6.18E+00 Sr-90 0.081% 9.97E-03 Ag-110m 0.126% 1.55E-02 Sb-125 0.112% 1.38E-02 CS-134 1.172% 1.44E-01 CS-137 14.120% 1.73E+00 Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies H-3 0.059% 1.69E-01 Mn-54 0.368% 1.06E+00 Fe-55 4.063% 1.17E+01 Co-57 0.069% 1.98E-01 Co-58 0.316% 9.10E-01 Co-60 6.077% 1.75E+01 Ni-63 35.766% 1.03E+02 Sr-90 0.088% 2.54E-01 Ag-110m 0.000% 1.35E-03 Sb-125 0.091% 2.63E-01 CS-134* 18.647% 5.37E+01 CS-137 34.030% 9.80E+01 Ce-144 0.399% 1.15E+00 Pu-238 0.001% 2.73E-03

Docket No. 50-3, 50-247, & 50-286 Page 27 of 55 Pu-239 0.000% 7.83E-04 Pu-241 0.024% 7.05E-02 Am-241 0.000% 5.51E-04 Cm-242 0.000% 1.37E-04 Cm-243 0.001% 1.59E-03 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 0.238% 7.14E-01 C-14 0.000% 2.60E-05 Mn-54 0.363% 1.09E+00 Fe-55 4.726% 1.42E+01 Co-57 0.068% 2.05E-01 Co-58 0.363% 1.09E+00 Co-60 6.190% 1.86E+01 Ni-63 36.275% 1.09E+02 Sr-90 0.088% 2.65E-01 Ag-110m 0.006% 1.68E-02 Sb-125 0.092% 2.77E-01 Cs-134 17.938% 5.39E+01 Cs-137 33.246% 9.99E+01 Ce-144 0.383% 1.15E+00 Pu-238 0.001% 2.74E-03 Pu-239 0.000% 7.86E-04 Pu-241 0.024% 7.10E-02 Am-241 0.000% 5.53E-04 Cm-242 0.000% 1.61E-04 Cm-243 0.001% 1.61E-03

Docket No. 50-3, 50-247, & 50-286 Page 28 of 55 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class an.d Stream 01/01/2007 to 12/31/2007 Percent Cutoff: 0 (all identified isotopes are included) waste Stream: Resins, Filters, and Evap Bottoms LWS Resin 14-170 Waste Volume Curies % Error (Ci)

Class fe m3 Shipped A 1.10E+02 3.12E+00 1.66E+00 +/- 25%

B o.OOE +00 O.OOE+OO 0.00 E +00 +/- 25%

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

All 1.10E+02 3.12E+00 1.66E+00 +/- 25%

waste Stream : Dry Active Waste DAW 40' Sea Land Unit 3 DAW-20' Sealand Unit 3 DAW B-25 SoillDebris B-25 Waste Volume Curies % Error (Ci)

Class fe m3 Shipped A 3.85E+04 1.09E+03 2.14E+00 +/-25%

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

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

All 3.85E+04 1.09E+03 2.14E+00 +/-25%

waste Stream Irradiated Com ponents Waste Volume Curies % Error (Ci)

Class fe m3 Shipped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

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

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

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

Waste Stream Other Waste Com bined Packages Waste Volume Curies %. Error (Ci)

Class fe m 3 Shipped A 1.08E+03 3.06E+01 5.78E-01 +/-25%

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

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

All 1.08E+03 3.06E+01 5.78E-01 +/-25%

Waste Stream : Sum of All 4 Categories LWS Resin 14-170 Unit 3 DAW-20' Sealand Unit 3 DAW-B25 So il/D e b ris B-2 5 Com bined Packages DAW 40' Sea Land Waste Volume Curies % Error (Ci)

Class fe m 3 Shipped A 3.96E+04 1.12E+03 4.38E+00 +/-25%

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

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

All 3 .96E +04 1.12E+03 4.38E+00 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

Docket No. 50-3,50-247, & 50-286 Page 29 of 55 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2007 to 12/31/2007 Percent Cutoff: 0 Number of Mode of Transportation Destination Shipments 2 Hittman Transport Duratek Services Inc.

Hittman Transport Energy Solutions Gallaher Road 23 Hittman Transport Energy Solutions Bear Creek Hittman Transport Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance Curies H-3 6.203% 1.03E-01 Mn-54 0.551% 9.15E-03 Fe-55 11.442% 1.90E-01 Co-57 0.759% 1.26E-02 Co-58 10.839% 1.80E-01 Co-60 11.140% 1.85E-01 Ni-63 31.795% 5.28E-01 Sr-89 0.218% 3.62E-03 Sr-90 0.067% 1.12E-03 Ag-110m 0.129% 2.15E-03 Sb-124 4.047% 6.72E-02 Sb-125 3.908% 6.49E-02 Cs-134 5.588% 9.28E-02 Cs-137 9.996% 1.66E-01 Ce-144 3.312% 5.50E-02 Pu-238 0.001% 2.06E-05 Pu-239 0.000% 6.31 E-06 Am-241 0.001% 1.07E-05 Cm-242 0.000% 7.01E-06 Cm-243 0.002% 3.42E-05 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies H-3 6.203% 1.03E-01 Mn-54 0.551% 9.15E-03 Fe-55 11.442% 1.90E-01 Co-57 0.759% 1.26E-02 Co-58 10.839% 1.80E-01 Co-60 11.140% 1.85E-01 Ni-63 31.795% 5.28E-01 Sr-89 0.218% 3.62E-03 Sr-90 0.067% 1.12E-03 Ag-110m 0.129% 2.15E-03

Docket No. 50-3, 50-247, & 50-286 Page 30 of 55 Sb-124 4.047% 6.72E-02 Sb-125 3.908% 6.49E-02 Cs-134 5.588% 9.28E-02 Cs-137 9.996% 1.66E-01 Ce-144 3.312% 5.50E-02 Pu-238 0.001% 2.06E-05 Pu-239 0.000% 6.31E-06 Am-241 0.001% 1.07E-05 Cm-242 0.000% 7.01 E-06 Cm-243 0.002% 3.42E-05 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.005% 9.82E-05 C-14 0.005% 1.05E-04 Cr-51 4.913% 1.05E-01 Mn-54 0.195% 4.16E-03 Fe-55 9.218% 1.97E-01 Co-57 0.100% 2.13E-03 Co-58 35.797% 7.65E-01 Co-60 11.745% 2.51E-01 Ni-63 29.340% 6.27E-01 Sr-90 0.001% 1.13E-05 Zr-95 0.000% 3.89E-09 Nb-95 0.096% 2.06E-03 Ag-110m 0.003% 5.97E-05 Sb-124 2.232% 4.77E-02 Sb-125 2.611% 5.58E-02 Cs-134 0.505% 1.08E-02 Cs-137 3.233% 6.91 E-02 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 0.005% 9.82E-05 C-14 0.005% 1.05E-04 Cr-51 4.913% 1.05E-01 Mn-54 0.195% 4.16E-03 Fe-55 9.218% 1.97E-01 Co-57 0.100% 2.13E-03 Co-58 35.797% 7.65E-01 Co-60 11.745% 2.51E-01 Ni-63 29.340% 6.27E-01 Sr-90 0.001% 1.13E-05 Zr-95 0.000% 3.89E-09 Nb-95 0.096% 2.06E-03 Ag-110m 0.003% 5.97E-05 Sb-124 2.232% 4.77E-02 Sb-125 2.611% 5.58E-02 Cs-134 0.505% 1.08E-02 Cs-137 3.233% 6.91 E-02

Docket No. 50-3, 50-247, & 50-286 Page 31 of 55 Other Waste Waste Class A Nuclide Name Percent Abundance Curies Cr-51 10.608% 6.13E-02 Mn-54 0.385% 2.22E-03 Fe-55 2.665% 1.54E-02 Co-57 0.190% 1.09E-03 Co-58 68.953% 3.98E-01 Co-60 1.841% 1.06E-02 Ni-63 3.794% 2.19E-02 Nb-95 0.218% 1.26E-03 Sb-124 5.014% 2.90E-02 Sb-125 4.984% 2.88E-02 Cs-134 0.736% 4.25E-03 Cs-137 0.612% 3.54E-03 Other Waste Waste Class All Nuclide Name Percent Abundance Curies Cr-51 10.608% 6.13E-02 Mn-54 0.385% 2.22E-03 Fe-55 2.665% 1.54E-02 Co-57 0.190% 1.09E-03 Co-58 68.953% 3.98E-01 Co-60 1.841% 1.06E-02 Ni-63 3.794% 2.19E-02 Nb-95 0.218% 1.26E-03 Sb-124 5.014% 2.90E-02 Sb-125 4.984% 2.88E-02 Cs-134 0.736% 4.25E-03 Cs-137 0.612% 3.54E-03 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 2.366% 1.04E-01 C-14 0.002% 1.05E-04 Cr-51 3.805% 1.67E-01 Mn-54 0.355% 1.55E-02 Fe-55 9.188% 4.02E-01 Co-57 0.361% 1.58E-02 Co-58 30.695% 1.34E+00 Co-60 10.213% 4.47E-01 Ni-63 26.892% 1.18E+00 Sr-89 0.083% 3.62E-03 Sr-90 0.026% 1.13E-03 Zr-95 0.000% 3.89E-09 Nb-95 0.076% 3.32E-03 Ag-110m 0.051% 2.21 E-03 Sb-124 3.286% 1.44E-01

Docket No. 50-3, 50-247, & 50-286 Page 32 of 55 Sb-125 3.417% 1.50E-01 Cs-134 2.464% 1.08E-01 Cs-137 5.463% 2.39E-01 Ce-144 1.256% 5.50E-02 Pu-238 0.000% 2.06E-05 Pu-239 0.000% 6.31 E-06 Am-241 0.000% 1.07E-05 Cm-242 0.000% 7.01 E-06 Cm-243 0.001% 3.42E;-05 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 2.366% 1.04E-01 C-14 0.002% 1.05E-04 Cr-51 3.805% 1.67E-01 Mn-54 0.355% 1.55E-02 Fe-55 9.188% 4.02E-01 Co-57 0.361% 1.58E-02 Co-58 30.695% 1.34E+00 Co-60 10.213% 4.47E-01 Ni-63 26.892% 1.18E+00 Sr-89 0.083% 3.62E-03 Sr-90 0.026% 1.13E-03 Zr-95 0.000% 3.89E-09 Nb-95 0.076% 3.32E-03 Ag-110m 0.051% 2.21E-03 Sb-124 3.286% 1.44E-01 Sb-125 3.417% 1.50E-01 Cs-134 2.464% 1.08E-01 Cs-137 5.463% 2.39E-01 Ce-144 1.256% 5.50E-02 Pu-238 0.000% 2.06E-05 Pu-239 0.000% 6.31E-06 Am-241 0.000% 1.07E-05 Cm-242 0.000% 7.01 E-06 Cm-243 0.001% 3.42E-05

Docket No. 50-3, 50-247, & 50-286 Page 33 of 55 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2007 - Dec 31, 2007

Docket No. 50-3, 50-247, & 50-286 Page 34 of 55 RADIOLOGICAL IMPACT ON MAN Routine Effluent Dose Calculations:

The Radiological Impact on Man due to radioactive effluent from the site is determined from NRC approved modeling, per Reg Guide 1.109 and NUREG 0133. Calculations are divided into 3 categories: Noble Gases, Particulates and Iodine, and Liquid Releases (fish and invertebrate consumption). This modeling involves conservative dose calculations to Adult, Teen, Child, and Infant age groups. Furthermore, dose modeling is performed for six separate organs as well as the total bocjy dose. This well-established industry model provides doses (as a result of plant effluent) to a hypothetical maximally exposed individual offsite. While ALL age groups and organs are considered, it is this maximum value that is provided in the tables that follow.

An approved computer code is used to perform liquid and gaseous dose calculations according to the models and parameters presented in the Indian Point Offsite Dose Calculation Manual (ODCM). This information is stored in a database on site to enhance dose tracking information and management.

Site airborne effluent dose calculations include annual average dispersion and deposition factors, averaged from data collected over approxiniate ten year periods. When new data is averaged (approximately every ten years) the modeling is updated and used in subsequent airborne effluent calculations.

Liquid offsite dose calculations involve fish and invertebrate consumption pathways only, as determined in the ODCM. While the ODCM identified some site-specific dose factors, the bulk of this information is obtained directly from Regulatory Guide 1.109 and NUREG 0133. Details of the calculations, site-specific data, and their bases are presented in the ODCM.

Carbon-14 (C-14l:

Concentrations and offsite dose from C-14 have been estimated using data generated at IP3 from August 1980 to June 1982 after a study conducted by the NY State Department of Health.

These estimates are consistent with NUREG 0017, Rev. 1. The maximum expected annual dose from C-14 releases at IP2 and IP3 have been calculated using the maximum dependable gross electrical capacity, which is approximately 1000 MW(e) maintained for the entire year.

The resultant bounding doses are based upon site specific assumptions of source term released for an entire year at 1000 MW(e) output, as outlined in the ODCM.

The resulting annual dose to the maximally exposed individual (child) from gaseous releases of C-14 is 0.254 mRem to the critical organ (bone) and 0.0508 mRem to the total body. The annual dose to the maximally exposed individual (child) from liquid releases of C-14 is 0.00583 mRem to the critical organ (bone) and 0.00117 mRem to the total body. These curies and doses are reported in this section (and not in the earlier tables), specifically to avoid confusion.

The data is listed separately from other isotopes (in the familiar table format) to preserve consistency with the format of Reg Guide 1.21 and the listed isotopes of concern, which do NOT include C-14.

Groundwater:

Curies and dose contribution from activity discovered in onsite ground water and storm drain pathways during the year are discussed in detail in Section H. The offsite dose calculation involves multiple source term measurements, as well as determinations for release and dilution flow. A summary of the quantification methodology, and the resulting calculated doses, is provided at the end of Section H. The Total Dose table below provides a means to compare ground water doses with those of other components making up the site's total dose.

Docket No. 50-3, 50-247, & 50-286 Page 35 of 55 Members of the Public:

Members of the public visiting the site receive minimal dose as a result of airborne and liquid releases because of the relatively insignificant total amount of time they are on site, as well as the immeasurably low levels of dose at the critical receptors. Their doses can be calculated from standard ODCM methodology, with typical occupancy factors employed. These factors are determined by comparing a conservative assumption for their expected hours on site, to 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months (the number of hours in a year, used in calculations in the ODCM).

example 1: Several students visit the site for an 8-hour guided tour.

Their occupancy factor is: 8 / 8760 or .0009.

example 2: A man drives his wife to work and drops her off at the security gate each morning, with a total stay-time on site for 2 minutes per day. His occupancy factor is calculated as follows:

2 min/60 min per hour =.0333 hr; 0.0333 / 8760 = 3.8E-6 These factors, when multiplied by doses calculated per the ODCM, demonstrate that dose to MEMBERS OF THE PUBLIC within the site boundary is negligible, despite a potential reduction in the atmospheric dispersion.

Total Dose:

In compliance with 40CFR190, the following table indicates the Total Dose, including any measured direct shine component from the site property for 2007:

Routine Airborne Effluents Units 1 and 2 2.43E-03 2.43E-03 Routine Liquid Effluents Units 1 and 2 5.35E-04 1.30E-03 Routine Airborne Effluents Unit 3 3.88E-03 3.88E-03 Routine Liquid Effluents Unit 3 3.20E-04 2.14E-04 Carbon-14 Liquid & Airborne Totals IPEC 5.20E-02 2.60E-01 Ground.Water & Storm Drain Totals IPEC 1 .... 2.66E-04* 9.94E-04 Indian Point Energy Center Total Dose, per 40 CFR 190 IPEC < 7.06 < 7.27 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 the siting criteria and assumptions established for each area.

Docket No. 50-3, 50-247, & 50-286 Page 36 of 55 INDIAN POINT UNITS 1 and 2 NUCLEAR POWER PLANTS RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2007 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr4 ANNUAL Organ Dose (mrem) 2.74E-04 5.94E-04 1.31 E-04 3.11 E-04 1.30E-03 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 5.48E-03 1.19E-02 2.62E-03 6.22E-03 1.30E-02 A~e Group Child Child Adult Child Child Critical Organ Bone Bone Liver Bone Bone Adult Total Body (mrem) 7.86E-05 1.72E-04 1.12E-04 1.72E-04 5.35E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3 Percent of Limit (%) 5.24E-03 1.15E-02 7.47E-03 1.15E-02 1.78E-02 B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 3.14E-05 1.68E-05 5.39E-05 1.15E-05 1.14E-04 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 6.28E-04 3.36E-04 1.08E-03 2.30E-04 1.14E-03 Beta Air (mrad) 8.65E-05 3.11 E-05 6.06E-05 1.50E-05 1.93E-04 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 8.65E-04 3.11 E-04 6.06E-04 1.50E-04 9.66E-04 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Iodine/Part (mrem) 5. 77E-04 7.95E-04 7.50E-04 3.06E-04 2.43E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 7.69E-03 1.06E-02 1.00E-02 4.08E-03 1.62E-02 Child Child Total Body Total Body

Docket No. 50-3, 50-247, & 50-286 Page 37 of 55 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2007 Maximum exposed individual doses in mrem or mrad A. LIQUID DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Organ Dose (mrem) 2.68E-04 2.97E-05 1.46E-05 1.16E-05 3.20E-04 Applicable Limit (mrem) 5 5 5 5 10 Percent of Limit (%) 5.36E-03 5.94E-04 2.92E-04 2.32E-04 3.20E-03 Age Group Adult Adult Adult Child Adult Critical Organ GILLI GILLI GILLI Bone GILLI Adult Total Body (mrem) 1.91 E-04 1.49E-05 4.40E-06 3.57E-06 2.14E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3 Percent of Limit (%) 1.27E-02 9.93E-04 2.93E-04 2.38E-04 7.13E-03 B. AIRBORNE NOBLE GAS DOSES Qtr 1 Qtr 2 Qtr 3 Qtr 4 ANNUAL Gamma Air (mrad) 2.27E-04 5.39E-06 3.81E-06 5.72E-06 2.42E-04 Applicable Limit (mrad) 5 5 5 5 10 Percent of Limit (%) 4.54E-03 1.08E-04 7.62E-05 1.14E-04 2.42E-03 Beta Air (mrad) 1.14E-03 3.50E-05 6.33E-06 9.54E-06 1.19E-03 Applicable Limit (mrad) 10 10 10 10 20 Percent of Limit (%) 1.14E-02 3.50E-04 6.33E-05 9.54E-05 5.95E-03 C. AIRBORNE IODINE and PARTICULATE DOSES Qtr 1 Qtr 2 Qtr 3 Qtr4 ANNUAL Iodine/Part (mrem) 2.03E-03 6.51E-04 7.60E-04 4.39E-04 3.88E-03 Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of Limit (%) 2.71E-02 8.68E-03 1.01 E-02 5.85E-03 2.59E-02 Child Child Total Body Thyroid

Docket No. 50-3, 50-247, & 50-286 Page 38 of 55 Indian Point Energy Center (Units 1, 2, and 3)

. RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2007 - Dec 31, 2007 This data is stored onsite and is available in printed or electronic form.

Docket No. 50-3, 50-247, & 50-286 Page 39 of 55 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 2007 There was a minor change in REMP sampling locations in 2007.

(Monitoring Wells were added to the REMP in the South-West boundary locations, as discussed in the ODeM changes below.)

There were no changes to the Land Use Census in year 2007.

There were no changes to the Process Control Programs in year 2007.

There were four ODCM updates 2007.

1) Unit 2's ODCM (Rev 10, included Unit 1), for groundwater program updates, Jan 2007.

2) Unit 3's ODCM (Rev 18), for the same groundwater program updates, Jan 2007.

3) A month later, a revision at Unit 2 followed, in February (Rev 11), to officially adopt the new 10CFR20 at Unit 2 (this version of 10CFR20 had been adopted at Unit 3 in 2000). The update to Unit 2's ODCM was required for consistency with the updated Technical Specifications, Amendment 250 (TSTF-258).

4) In December 2007, the earlier unit-specific versions of the ODCMs at IPEC were combined into Rev 0 of the IPEC ODCM, with the Controls arranged in NUREG 1431 format, identical to the previous revision for unit 2. No new controls or routine dose calculations were added in this merging and reformatting process. However, some minor updates to the ground water offsite dose modeling were added to this new site ODCM (rev 0).

Details of these ODCM updates Uustification packages) are provided in an Addendum to this report. In addition, complete copies of the ODCM (for items 1,2, and 4 above) are included in this addendum. The February revision to Unit 2's ODCM (Rev 11) is essentially identical to Rev 10, and included only 2 administrative wording changes to ensure compliance with the Technical Specification update for new 10CFR20, as identified in the justification package.

Therefore, for Unit 2's ODCM Rev 11, the addendum includes the justification package, but does NOT include a full copy of the ODCM. All historical revisions to either unit's ODCM remain available on site.

Docket No. 50-3, 50-247, & 50-286 Page 40 of 55 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT H. GROUNDWATER and STORM WATER ACTIVITY ON SITE AND OFF SITE DOSE CALCULATION FOR THE PERIOD:

Jan 1, 2007 - Dec 31, 2007

Docket No. 50-3, 50-247, & 50-286 Page 41 of 55 Summary of IPEC Groundwater and Storm Water Activity and Offsite Dose Calculation, 2007 The precipitation mass balance model applied in 2005 through 2006 was enhanced and further validated for 2007. The original 3 groundwater flow zones established in 2005/2006 were split into 6 zones to better partition the distribution of flow across the site. Each zone was also further subdivided into a shallow flow regime and a deeper flow regime based on the depth-specific differences in formation hydraulic conductivity. In addition, the groundwater flow values before and after the Discharge Canal were computed and compared to estimate the amount of groundwater flowing into the canal as well as that discharging directly to the river. The overall precipitation mass balance model was also validated through calibration against a Darcy's Law model relative to groundwater flow through each zone. This calibration was also used to provide the basis for the depth specific and pre~canal/post-canal differentiation of flow values in each zone.

Additional data was also gathered in 2007 from the increased number of wells on site (as compared to the 2006 data). The concentrations at groundwater to surface water discharge points were updated using wells specifically drilled at these points for a more accurate assessment of the plume boundaries, limits and release concentrations. The average concentrations used were based on multiple samples, generally at least one per quarter per elevation per well. The additional wells, and the instrumentation installed therein, also provided further definition of groundwater elevations to enhance the Darcy's Law calibration of the precipitation mass balance model. The specific processes for release and dilution flow evaluation are defined in the following text. The hydrology portion of this assessment and the associated 2007 enhancements were performed by IPEC's consultant, GZA GeoEnvironmental, Inc. IPEC concurs with this methodology.

The precipitation mass balance model 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 which infiltrates but then moves back into the atmosphere via evaporation 1 transpiration and other processes, and water that flows off the surface as storm water (SW).

There are five parameters required by the precipitation mass balance method of computing radionuclide release rate to the Hudson River via the groundwater pathway. Enhancements or adjustments made in 2007 based on the Darcy's Law Model are noted.

1. Overall direction of groundwater flow - The surface topography shows that the IPEC facility is located in a significant depression in the eastern bank of the Hudson River. Given that groundwater elevations generally mirror ground surface topography and groundwater flow is from high elevations to lower elevations, the groundwater flows from the north, east and south towards the facility, with ultimate discharge to the .Hudson River to the west.

2. Facility-specific groundwater flow paths - To establish facility-specific groundwater flow paths relative to on-site release areas, facility ground surface topography mapping was used. These flow paths were refined based on groundwater contours developed from the groundwater elevations measured with transducers installed in groundwater monitoring installations. The groundwater flow in each zone was then proportioned into shallow flow and deeper flow regimes based on relative hydraulic conductivities measured for the geologic deposits in each zone.

3.

Docket No. 50-3, 50-247, & 50-286 Page 42 of 55 Rate of groundwater flow - The groundwater flow rates through the individual zones were computed using mass-balance relationships that begin with the overall average yearly precipitation for the watershed area and then subtract out precipitation volumes reflecting removal mechanisms such as:

Direct evaporation;

Vegetative transpiration;

Paved and roof surfaces - transport precipitation directly to the river via storm drains;

Footing drains.

The net precipitation infiltration rates resulting in groundwater flow were adopted from a USGS study performed specifically for the Westchester County area, the location in which the facility is sited. The total groundwater flow rate was initially proportioned relative to the catchment areas associated with individual groundwater flow zones. These groundwater flow values were subsequently refined using the relative flow values computed using the Darcy's Law model. The gradient was computed from the groundwater elevation contours. For this computation, each flow zone was segregated into two depth regimes; a higher hydraulic conductivity shallow regime and a lower conductivity deeper regime. Finally, the zone-specific flow rates before the Discharge Canal were compared to those after the canal to evaluate the groundwater flux to the river via the Discharge Canal as comp~red to that discharging directly to the river.

4. Groundwater radionuclide concentration - A number of multi-level groundwater monitoring installations are in place up-gradient of the Discharge Canal and along the waterfront, thus allowing the radionuclide concentrations to be measured for groundwater flowing into the canal as well as that near the groundwater/river interface.

5. Radionuclide release rate to river - Once the groundwater flow rates were established, the zone-specific radionuclide release rates to the Hudson River were computed by multiplying the area/depth-specific groundwater flow rates times the associated radionuclide concentrations; these individual zone-specific values were then summed to arrive at the total radionuclide release rate to the river.

Over the entire watershed catchment area of 3.2 million ft2, the GW and SW has been segmented relative to areas of the facility through which it flows (primarily established based on the relative concentrations and types of contaminants in the various facility areas). The bulk of the GW activity is identified down gradient of the Unit 2 transformer yard. While tritium is suspected to have originated at both Unit 2 and Unit 1 leaks, most of the offsite dose has been demonstrated to originate from Unit 1 contamination from Sr-90 and other radionuclides (tritium has little dose effect). Stream tubes have been drawn through the boundaries of these areas to define six individual groundwater flow zones.

The six zones are shown in the figure at the end of this section, and are defined as:

ZONES:

Northern Clean Zone, the area north of Unit 2;

Unit 2 North Zone, the northern areas of Unit 2, including some low levels of tritium;

Unit 1 and 2 Zone, the area encompassing most of the known plume, between units 1 and 2;

Unit 3 North Zone, the area between Unit 1 and Unit 3;

Unit 3 South Zone, the area that primarily includes operating areas of Unit 3;

Southern Clean Zone, south of Unit 3 to the edge of the property line.

Docket No. 50-3, 50-247, & 50-286 Page 43 of 55 Overall, the partitioning is established for groundwater and storm water, including recharge rates where storm drains and ground water communicate. hi each zone, the groundwater flow is further subdivided into a shallow flow regime and a deeper flow regime based on the depth-specific differences in formation hydraulic conductivity. In addition, the groundwater flow values before and after the Discharge Canal were computed and compared to estimate the amount of groundwater flowing into the canal as well as that discharging directly to the river.

Concentrations of identified radionuclides have been established for all Zones using the available 2007 quarterly groundwater sampling data from Monitoring Wells and the accumulated Storm Drain sample data. Analyses were conducted by gamma spectroscopy (all wells and drains) and liquid scintillation (for tritium), as well as specific analyses for beta emitters, such as Ni-63 and Sr-90.

The quarterly results from effected wells in the effluent locations were evaluated to compute an average source term for each area or zone. If a result was be/ow MOe (whether positive or negative) it was not included in the computed average, so as not to drive the computed average value down.

Therefore more conservative average values, based on only those results above MOC, were used to avoid averaging in zero and negative values (below MOC) for any location that had at least one identified value above MOC, for any quarterly sampling round within 2007. However, if all the sampling locations assigned to a given stream tube provided results below the MOC, then an average concentration value of zero was assigned to the effected portion of the stream tube. This mathematically allows the calculation to proceed in the absence of positive detections.

Using source term and flow data specific to each zone resulted in several improvements over earlier assessments of groundwater's offsite dose contribution:

More source term data points were available,

Flow distribution was validated and enhanced, and

These more precise inputs allowed for a more detailed integration of total measured effluent.

As a result of these improvements, there is greater confidence in the accuracy of the calculated dose.

The following table summarizes the source terms applied for the 2007 assessment, in uCilml:

Northern Unit 2 Units 1 Unit 3 Unit 3 Southern Clean Zone North and 2 North South Clean Zone Storm Drains None H-3) 1.26E-6 None None None None To Canal Storm Drains None H-3) 7.96E-7 H-3) 4.96E-7 H-3) 1.97E-6 None None To River H-3) 3.34E-6 GWto H-3) 5.28E-7 H-3) 1.40E-7 None None Ni-63) 249E-.9 H-3) 8.99E-7 Canal Sr-90) 1.03E-9 Cs-137) 9.56E-10 Sr-90) 1.58E-8 H-3) 4.41 E-6 Upper H-3) 3.11 E-7 H-3) 4.73E-7 Co-60) 2.35E-11 H-3) 8.99E-7 GWto H-3) 1.50E-7 Co-60) 1.77E-11 H-3) 1.39E-7 Sr-90) 1.22E-1 0 Sr-90) 1.62E-8 Co-60) 513E-11 River Sr-90) 1.31 E-9 Cs-137) 1.02E-8 H-3) 1.08E-6 Lower H-3) 4.63E-7 H-3) 4.07E-7 H-3) 183E-7 H-3) 5.76E-7 Co-60) 1.17E-11 GWto H-3) 1.50E-7 Co-50) 8.1 E-12 Co-50) 2.64E-11 Co-50) 3.38E-11 Co-60) 1.19E-11 Sr-90) 1.11 E-9 River Sr-90) 8.19E-1 0 Sr-90) 5.32E-9 Sr-90) 1.53E-1 0 Cs-137)608E-11

Docket No. 50-3,50-247, & 50-286 Page 44 of 55 Source terms, sample results, and documents relating to Monitoring Wells and Storm Drains sampled on site are available in plant records. No source term was applied to storm water from the Northern and Southern Clean Zones, as records indicate no contamination in these areas for 2007 and they include no known sources. Additionally, hydrological studies show that flow through these areas/zones is from up gradient, perimeter areas farther north and south which are unrelated to potential contamination from within the site boundary.

The infiltration rate in non-paved/building areas was computed at 0.87 feet/year which is within the range provided in 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 3.02 feet/year based on long-term onsite meteorological data averaging. All precipitation falling on paved/building areas was assumed to result in SW flow. Although some of this water actually evaporates directly to atmosphere from pavement and buildings, no credit for this evaporation is taken t6 ensure conservativism in the model.

The ODCMs were combined in 2007 (as one IPEC document), and updated to included details of the Ground Water Monitoring Program. These updates are discussed in Section G of this report. The ODCM updates reflect both the requirements of the Ground Water Monitoring Program, and specifics on calculating offsite dose.

Results of 2007 Groundwater and Storm water offsite dose evaluation:

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 0.052 Curies of Tritium migrated directly to the river via the GW flow path in 2007, resulting in an approximate total body dose of less than 0.1 mrem (2.6E-7 mrem). It is evident that tritium alone, whether from ground water or routine effluents, does not significantly add to offsite dose.

Strontium-90, Nickel-63, and Cesium-137, and Co-60 collectively contributed approximately 0.00008 curies from the groundwater pathway.

Combined groundwater releases from IPEC in 2007 (all radionuclides) resulted in a calculated annual dose of less than 0.1 mrem to the whole body and critical organ (0.000266 mrem - total body, and 0.000994 mrem to the critical organ, adult bone primarily from Strontium-90).

The annual dose from combined groundwater and storm water pathways at IPEC, remains well below the applicable limits. When combined with routine liquid effluents, the total dose remains significantly below the ALARA limits of 3 mrem total body and 10 mrem to the critical organ. This comparison is provided in the opening discussion of Section E, Radiological Impact on Man.

See the following groundwater/storm water annual offsite dose summary table.

Docket No. 50-3, 50-247, & 50-286 Page 45 of 55 IPEC Summary for Storm & Ground Water releases (H-3, Co-60, Ni-63,Sr,90, and Cs-137) 2007 year Northern Clean Zone AdultDoses.in mrem

.~Si?ZY(;l;J H-3 ".' O,OOE+OO 4:64E~09' 4.64E-09 . 4.64E-09 ." 464Ec09 4.64E-09;. :4.64E~09 4.15£+02 Co-60 ~ O.OOE+OO* O.OOE+OOO.OOE+OO O.OOE+OO ' O:OOE+OO O.OOE+OO: O.OOE+OO 0.00£+00; Ni-63 ,. *O.OOE+OO O.OOE+OO' . ;. O.OOE+OO<::, ,; O.OOE+OO. O:OOE+OO "O*OOE+OO,;:*. O.OOE+OO :0:00£+00 Sr-90 O.OOE+OO O,OOE+OO '. O.OOE+OO. O,OOE+OO" O.OOE+OO O.OOE+oO' 'i '~O,OOE+OO' ' 0.00£+00 Cs-137 .OiOOE+OO O:OOE+OO .. ' O,OOE+OO*: O:OOE+OO' O,OOE+.OO* . O:OOE+OO*: O.OOE+OO ' 0.00£+00 totals O.OOE+OO 4.64E-09 4.64E"09 4.64E-09 4.64E-09 4.64E-09 4,64E-09 r.m 5£+.02,;

Unit2 North r.:,~,:,;uCijJ'::

H-3,O:OOE+OO '.1.59E-08159Ec 08" * . 1,59E-08,' 1.59E~08: 1. 59E-08 . *159E"08' 3,22£+04 Co-60 O:OOE+OO.' 4.56E" 10 101 Ec09 :' O.OOE+OO O.OOE+OO 0.OOE+OOB.57E"09 711.£-03 Ni-63 If O:OOE+OO O,OOE+OO .*O.OOEfOO"; O.OOE+OO ,O:OOE+OO **O.OOE+OO" '. O.OOE+OO 0:00£+00.

Sr-90 :;: 5.55E':'07; O:OOE+OO,.' ,1 :36E-07', ,O.OOE+OOO.OOE+OO... . O:OOE+OO'" <. T60E~08*: 2.21£-02 Cs-137:'0.OOE+00** 'O,OOE+OO" O.OOE+OO " O.OOE+OO O,OOEfOO, , O:OOE+OO .'*.O.OOE+OO , 0.00£+00 totals 5.55Ec07 1,64E"OB 1.53Ec07 1.59E-08 . 1.59E-08 1.59E-08 4.05E-08 !G!22E+JJ4i Unit1/2 1":(:"ISQIQ~E'i> ;;,;;BPNEt'?:!2' 1f;:ji/frt!IVER(:~*j %:;i:~TOT;BOOY,:*!: f::::IHY,J~OIDi2!j <KIDNEY LUNG,<j?lf! 1:C;':l!1I,r.i H-3 : ' O.OOE+OO 1.27E':'07, 1.27E-07 .,' ,,1:27Ec07' '1.27Ec07L ' ' 1.27E-07 1.27E-07 1.54£+04' Co-60 O,OOE+OO" 4:00E.:.09. 'B:81 E~09 . O:OOE+OO O,OOE+OO O:OOEf{lO,,! 7,51E-08 6.8-1£-02 Ni-63 >:,9,68E"08* 6:72E-09" : '3,25E-09' .,O.OOE+OO ,O.OOE+OO. O.OOE+OO* 1AOE-09 . '3,10£+00, Sr-90 * :7.07E-04 . O,OOE+OO 1.73E-04" O.OOE+OO ' O,OOE+OO O:OOE+OO, : 2:04E.*05' 4.76£+.01 Cs-137 ':," '(3,32E~05,' 4:54E"05 298E~05 O,OOE+OO' 1,54Ec05 5. 12E-06 8:77E-07 1.58£+01 totals 7.41E-04 4.56E-05 2,03E-04 1. 27E-07 1.55E-05 5,25E-06 2. 14E-05 r,1155£+J)tll Unit3 North

~:~;~i.iCi."*.,**;:Lr H-3 'O.OOE+OO ,7.16E-08 " 7:16E~08, '7, 16E-OB ,,' 7. 16E-08' 7: 16E-08:: 716E-08 8:24E+03*

Co-60 O,OOE+OO ,. *.1:75Ec 09 I'" ,3.86E-09. O.OOE+OO O.OOE+OO *;',O.OOE+OO' 3,30E-08 2,99£-02 Ni.63 '*'O.OOE+OO O.OOE+OO O,OOE+OO "O:OOE+OO h O.OOE+OO, O.OOE+OO:". O:OOE+:OO 0.00£+00 Sr-90 "',' 6:77E-05,' O,OOE+OO '1.66E~05:, O,OOE+OO", O,OOE+OO,.*. * .O:OOE+OO '. 't95E"06' 6.30£tOO Cs-,137 O.OOE+OO O.OOHOO O:OOE+OO O.OOE+OO, Q,OOE+OO . O:OOE+OO' O,OOE+OO 0,00£+00 totals 6.77E-05 7.33E"08 1.67E-05 l.16E-08 7,16E-08 7. 16E-08 2,05E-06 ~8'j25£+03j Unit3 South

{ii{UC;:"~::,

H-3 ' 'O,OOE+OO 1.25E-08 1,25E-08 1. 25E-08 1.25E-08t25E-OB ,1.25E-08 5.64£+03' Go-60 O:OOE+OO 3.71 E-09 ' B.17Ec 09 O.OOE+OO O.OOE+OO O.OOE+OO' 6,97E-08' 6.32E-02 Ni-63 O:OOE+QOO:OOE+OO O,OOE+OO, , , O.OOE+OO O.OOE+OO ' I' O,OOE+OO:: OOOE+OO 0.00£+00 Sr-gO 1.58E':'04'O,OOE+OO "',' 3B7E-05, O,OOE+OO; O,OOE+OO O:OOE+OO 455E-06 6.30£+00.

Cs-137 O,OOE+OO O:OOE+OO ' O,OOE+OO O,OOE+OO O,OOE+OO O.OOE+OO* O.OOE+OO 0.00£+00 totals 1.58E-04 1.62E-OB 3,BBE-05 1. 25E-OB 1.25E-OB 1. 25E-OB 4,63E-06 ;5,65£+03; Southern Clean Zone H-3 O:OOE+OO 2,63E-OB 2,63E-08 2.63E-OB 2,63E-08 263E-OB" 2.35£+03 Co-60 .O.OOE+OO 1AOE-OB 3.09E-OB O.OOE+OO O.OOE+OO O,OOE+OO: 2.63E-07 2.39£-01 Ni-63 O.OOE+OO' O,OOE+OO O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO, O:OOE+OO O.OO£+CXJ Sr-gO 2.71 E':'05 O,OOE+OO 6,66E-06 O.OOE+OO ' O,OOE+OO O.OOE+OO 7,B1E-07 1.08£+00 Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO*. O.OOE+OO O.OOE+OO totals 2.71E-05 4.03E-OB 6.71E-06 2. 63E-OB 2.63E-OB 2,63E-08 1,07E-06 12!36E~l)3i Totals: Adult Doses. inmrem H-3 only O,OOE+OO 258E-07 2.58E-07 2.5BE-07 2,58E-07 2,5BE-07 25BEc07 T6taiuCiS 643£+04 H3 all isotopes 9.94E-04 4.57E-05 2.66E-042.58E-07 1.57E':'05 5:38E-06 2,92E-05 4:08£-0.1 Co 3.10£+00 Ni 6.13£+01 Sr

'1.58£+01 Cs

Docket No. 50-3, 50-247, & 50-286 Page 46 of 55 INDIAN POINT RADIOLOGICAL GROUNDWATER MONITORING PROGRAM 2007 Summary of Results The following pages represent a summary of isotopic radio-analytical data for all onsite groundwater testing performed at Indian Point in 2007, as required per the aDeM and NEI 07-07.

Docket No. 50-3, 50-247, & 50-286 Page 47 of 55 2007 RG 1.21 H-3 Summary Report

Positive

Samples Samples in Ave Pos Min Pos Max Pos Well Name in 2007 2007 Act Act Act B-1 3 .3; 9.98E+02 7.93E+02 1.10E+03 8...,6 3 1 4.03E+02 4.:03E+02 4,03E+02 MH-S 3 3 1.40E+03 1.17E+03 1.62E+03 MWt11 2 2 t.09E+OS 9.88E+04 1.19E+OS MW<30-69 13 1*3. 1'S9E+OS 8.17E+04 2.97E+OS MW30-84 S S S.84E+03 4.27E+03 7.79E+03 MW.;.~1-49: S S 6;07E+03 1.20E+03 1.19E+04 MW31-63' 5 S 2.66E+04. S.00E+03 4.06E+04 MW.31-8.S S S 3.10E+03 3.17E+02 S:S1E+03 MW,.32...;131 4 3 3.99E+03 3.02E+02 1.t3E+04 MW-32-149 4 4 3.62E+03 4.93E+02 1.0SE+04 MW.,.32.;.173 1 1 S.89E+03 S.89E+03 S.89E+03 MW32-190 4 4. 6.30E+03 1 :72E+03 1.13E+04 MW-32-48 3 3 1 ..S3E+04 7.67E+03 2AOE+04 MW-32-S9 1 1 1.11 E+04 1.11 E+04 1.11 E+04 MW32-8S 4. 4 8.73E+03 .S.42E+03 1.26E+04 MW33 2 2 S.68E+04 2.30E+04 9.06E+04 MW34 1 1 2~22E+04. 2.22E+04 2.22E+04 MW-35 2 2 3.99E+03 2.03E+03 S.9SE+03 MW-36-24 3 1 2.86E+02 2.86E+02 2.86E+02 MW36...;41 1 1 6.11 E+03 6.11 E+03 6.11 E+03 MW-36-S2 2 2 1.13E+04 1 :01 E+04 1.2SE+04 MW37-22 3 3 3.03E+03 2.26E+03 4~OSE+03 MW-37-32 3 3. 3.14E+03 2A9E+03 3.81 E+03 MW-37-40 3 3 S~96E+03 S.69E+03 6~3SE+03 MW-37-S7 3 3 S.82E+03 4.88E+03 6.68E+03 MW38 2 2 1.42E+03 6.04E+02 2.24E+03 MW-39-102 2 2 S.63E+02 3.21 E+02 8.0SE+02 MW39-124 2 2 2.27E+02 1.92E+02 2.61E+02 MW-39-183 2 1 2.47E+02 2A7E+02 2A7E+02 MW-39.;.19S 2 2 2.28E+02 2.00E+02 2.SSE+02 MW39-67 2 2 3.99E+02 3.2SE+02 4.73E+02 M W.:. 39-84 2 2 4.22E+02 2.S2E+02 S.91E+02 MW-40-100 3 1 1.76E+02 1.76E+02 1.76E+02 MW4Q-127 3 1 1.87E+02 1.87E+02 1.87E+02 MW-41-40 2 2 2.1SE+03 3.80E+02 3.91 E+03 MW41-63 2 2 S.SOE+02 S.47E+02 S.S2E+02 MW42-49 4 4 1.73E+03 1.34E+03 2.46E+03 MW-42-78 4 4 3.98E+02 3.19E+02 4.61 E+02 MW-43-28 2 1 2.78E+02 2.78E+02 2.78E+02 MW44.;.102 3 3 3.12E+02 2.84E+02 3.S4E+02 MW-44-67 3 3 3.99E+02 2.68E+02 S.13E+02 MW45-42 3 3 1.90E+03 1.16E+03 2.32E+03 MW-45-61 3 3 1.71 E+03 1.47E+03 2.1SE+03 Page 1 of 3

Docket No. 50-3, 50-247, & 50-286 Page 48 of 55 2007 RG 1.21 H,-3Summary Report

Positive

Samples Samples in Ave Pos Min Pos Max Pos Well Name in 2007 2007 Act Act Act MW-c46 3 3 1.92E+03 6.62E:+-02 3.43E+03 MW-47...:56 2 2 4.00E+02 2.70E+02 5.29E+02 MW-47-80 2 2 2.94E+03 2.36E+03 3.51 E+03 MW-48-23 2 2 3.33E+02 2.72E+02 3.93E+02 MW-49"26 2 2 7.24E+03 6.72E+03 7.76E+03 MW-49-42 2 2 4.37E+03 4.30E+03 4.44E+03 MW-49-65 2 2 2.52E+03 2,41 E+03 2.62E+03 MW-50-42 3 1 2.15E+02 2.15E+02 .2.15E+02 MW-50-66 3 3 4.19E+03 3.85E+03 4.50E+03 MW-51-189 4 1 1.87E+02 1.87E+02 1.87E+02 MW-51-40 4 2 2.11E+02 1.98E+02 2.23E+02 MW..:52-162 2 2 2.47E+02 2.11E+02 2.82E+02 MW-52-181 2 1 2.48E+02 2048E+02 2.48E+02 MW.,.53-120 3 3 8.35E+03 7.40E+03 9.61 E+03 MW-53-82 3 3 3.52E+03 7.76E+02 8.68E+03 MW-54-123 3 3 9.25E+02 7.01 E+02 1.11E+03 MW-54..:144 3 .3 1 ..59E+03 1.34E+03 1.89E+03 MW-c54-173 3 3 1.96E+03 1.90E+03 2.08E+03 MW-54-190 3 3 2.08E+03 1.87E+03 2.25E+03 MW.:.54-37 3 3 9:10E+02 8.01 E+02 1.04E+03 MW-54-58 3 3 6.71 E+02 5.61 E+02 7.60E+02 MW-S5-24 3 3 2.66E+03 2:20E+03 3.08E+03 MW-55:..35 3 3 3.95E+03 3.09E+03 5.09E+03 MW-55-54 3 3 1.02E+04 9.91 E+03 1.04E+04 MW-56-53 3 3 4.28E+02 2.16E+02 7.80E+02 MW-56-83 3 3 1.54E+03 1.28E+03 1.851=+03 MW-57-11 2 2 4.35E+03 4.09E+03 4.616+03 MW-57-20 2 2 1.31 E+03 9.66E+02 1.65E+03 MW,..57-45 2 2 8.48E+02 7.40E+02 9.55E+02 MW-c58-26 3 3 5.71 E+02 2.60E+02 8.56E+02 MW-58-65 3 3 4.02E+02 3.15E+02 5 ..50E+02 MW-59-32 3 2 3.18E+02 1.69E+02 4.67E+02 MW-59-45 3 2 5.02E+02 2.49E+02 7.54E+02 MW-59-68 3 2 7.05E+02 5.90E+02 8.19E+02 MW-60-135 3 2 4.56E+02 3.92E+02 5.20E+02 MW-60-154 3 2 5.21 E+02 4.62E+02 5.80E+02 MW-60-176 3 3 6.94E+02 5.30E+02 8.49E+02 MW-60-35 3 2 4.73E+02 1.84E+02 7.61 E+02 MW-62-138 3 3 5.90E+02 4.55E+02 7.78E+02 MW-62-18 3 3 4.45E+02 3.76E+02 5.08E+02 MW-c62-182 3 3 4.84E+02 4.17E+02 5.41 E+02 MW-62-200 1 1 6.40E+02 6.40E+02 6.40E+02 MW-62-37 3 3 2.83E+02 2.50E+02 3.02E+02 MW-62-53 2 2 3.69E+02 3.45E+02 3.93E+02 Page 2 of 3

Docket No. 50-3, 50-247, & 50-286 Page 49 of 55 2007 RG 1.21 H ..3 Summary Report

Positive

Samples Samples iri Ave Pos MinPos Max Pos Well Name in 2007 2007 Act Acf Act MW-62-71 3 2 3.86E+02 2.69E+02 5.02E+02 MW62-92 3 3. 5.22E+02 428E+02 7,00E+02 MW-6.3-112 3 3 *3.24E+02 2.69E+02 4.24E+02 MW63-121 3 3 3.56E+02 2.96E+02 4.62E+02 MW-63-163. 3 3 4.69E+02 3.49E+02 5.78E+02 MW-63-174 3 3 4.9.7E+02 3]OE+02 5.93E+02 MW-63-18 3 2 2.15E+02 2.00E+02 2.30E+02 MW-63-191 1 1 3.44E+02 3.44E+02 3A4E+02 MW-63-34 3 3 2.46E+02 2.28E+02 2.80E+02 MW-,63..;50 3 3 2.80E+02 2.25E+02 3.26E+02 MW-63-93 3 2 2.59E+02 2.37E+02 2.81 E+02 MW-65-48 1 1 2.08E+.02 2.08E+02 2.08E+02 MW-65""?0 1 1 1.83E+02 1.83E+02 1.83E+02 MW-66-21 2 2 2.31 E+03 1.04E+03 3.57E+03 MW-'66-36 2 2 9.03E+03 8.95E+03 9.10E+03 MW-67-105 2 2 2.25E+03 1.86E+03 2.64E+03 MW-67-173. 2 2 1.03E+03 1.01 E+03 1.05E+03.

MW-67-219 2 2 1.10E+03 9.46E+02 1.25E+03 MW-6.7-276 2 2 8.95E+02 6.79E+02 1.11 E+03 MW-67-323 2 2 8.02E+02 3.13E+02 1.29E+03 MW-67-340 2 2 3.80E+02 3.69E+02 3.90E+02 MW-67-39 2 2 4.97E+03 4.86E+03 5;07E+03 U1-CSS 4 4 2.60E+03 1.53E+03 4.32E+03 U3-'T1 3 3 5.09E+02 4.90E+02 5.30E+02 U3-'T2 3 3 1.29E+03 1.17E+03 1.45E+03 Note 1: All results are in pCi/L Note 2: A total of 377 samples were analyzed for H-3 in 2007 with 287 positive results. This total includes samples from REMP wells MW-40 and MW-51. See the AREOR for additional data.

Note 3: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC. The target MOC is 200 pCi/L.

Page 3 of3

Docket No. 50-3, 50-247, & 50-286 Page 50 of 55 2007 RG 1.21 Sr-90 Summary Report

Positive

Samples Samples in Ave Pas, Min Pos Max Pos Well Name in 2007 2007 Act Act Act LAF-001 3 1 1.08E+00 1.08E+OO 1.08E+00 MW-111 2 2 9.74E-01 9:74E-;Q1 9.74E-01 MW-30:"84 4 1 5.95E-01 5.95E..:01 5.95E-01 MW:"36-41 1 1 2.18E+00 2.18E+OO 2.18E+00 MW-36:-52 2" 2 2.44E+00 2.26E+00 2.62E+00 MW-37:"22 3 3 1.87E'+01 1.49E+01 2.29E+01 MW":37-32 3 3 1.96E+01 1.85E+01 2.13E+01 MW-37.,.40 3 3 6.81 E+OO 4.69E+00- 9.76E+00 MW-37-57 3 3 2.51 E+01 2.33E+01 2.78E+01 MW-39:..102 2 1 1.32E+00 1.32E+00 1.32E+00 MW-39-195 2 1 1.30E+00 1.30E+00 1.30E+00 MW39-67 2 2 3.77E+00 2]6E+00 4.78E+00 MW-39-84 2" 2 1.26E+00 7.97E-01 1.72E+00 MW-41-40 2* 2 5.98E+00 5.96E+00 5.99E+00 MW-41-63 2 2 5.32E+00 3.55E+OO 7.08E+00 MW-42:..49 4 4 4.85E+01 2.01 E+01 7.73E+01 MW-43-28 2 1 1.07E+00 1.07E+00 1.07E+00 MW-43:..62 2 1 8.55E-01 8.55E-01 8.55E-01 MW-47-56 2 1 5.93E-01 5.93E:..01 5.93E-01 MW-47-80 2 2 3.41 E+OO 3.27E+00 3.55E+OO MW-49-26 2 2 1.35E+01 1.27E+01 1.43E+01 MW-49-42 2 2 2.32E+01 2.08E+01 2.56E+01 MW-49-65 2 2 1.83E+01 1.58E+01 2.08E+01 MW-50-42 3 3 1.85.E+01 1.16E+01 2.45E+01 MW-50-6,6 3 3 3.59E+01 2.93E+01 4.74E+01 MW-!53:..120 3 3 3.3,6E+01 2.81 E+01 3.70E+01 MW53-82 3 1 3.98E+00 3.98E+00 3.98E+00 MW-54-123 3 3 1.57E+01 1.16E+01 2.19E+01 MW-54-144 3 3 1.70E+01 1.58E+01 1.92E+01 MW-54-173 3 3 1.68E+01 1.45E+01 2.09E+01 MW-54-190 3 3 1.93E+Q1 1.79E+01 2.04E+01 MW-54-37 3 3 8.00E+00 5.30E+00 1.25E+01 MW-54-58 3 2 1.99E+00 1.76E+00 2.22E+00 MW-55-24 3 3 2.626+01 2.29E+01 3.25E+01 MW-55-35 3 3 3.27E+01 3.16E+01 3.40E+.o1 MW-55-54 3 3 2.31 E+01 2.22E+01 2.47E+01 MW-56-83 3 3 2.20E+00 1.87E+()0 2.43E+00 MW-57-11 2 2 4.17E+01 3.79E+01 4.55E+01 MW-57-20 2 2 1.60E+00 1.23E+00 1.96E+00 MW-57-45 2 2 2.23E+00 1.90E+00 2.55E+00 MW-58-26 3 2 1.03E+00 1.02E+00 1,.04E+00 MW-62-138 3 1 8.19E-01 8.19E-01 8.19E-01 MW-62-18 3 1 1.80E+00 1.80E+00 1.80E+00 MW-66-21 2 2 2.11E+00 1.79E+00 2.42E+00 Page 1 of 2

Docket No. 50-3, 50-247, & 50-286 Page 51 of 55 2007 RG 1.21 Sr-90 Summary Report

Positive

- Samples Samples in AvePos Min Pos Max Pos Well Name in 2007 2007 Act Act Act MW66-36 2 2 8.70E+00 6.20E+00 1.12E+01 MW-67-105 2 1 1.11 E+OO 1.11 E+OO 1.11E+00 MW-6.7-39 2 2 2.29E+01 1.86E+01 2.7tE+01 U1-CSS 4 4 1.87E+01 1.38E+01 2.68E+01 Note 1: All results an;:! in pCi/L Note 2: A total of.364 samples .wereanalyzed for Sr-90 in 2007 with 104 positive results. This total includes samples from REM P wells MW-40 and MW-51. See the AREOR for additional data.

Note 3: A sample is positive if the result is both greater than 3 standard deviations and gre"ater than the MOC. The target MOC is 1 pCi/L.

2007 RG.1.21 Co-60 Summary Report*

Positive

Samples Samples in Ave Pos Min Pos Max Pos Well Name in 2007 2007 Act Act Act MW42-49 4 1.59E+01 1.59E+01 1.59E+01 Note 1: All results are in pCi/L Note 2: A total of 367 samples were analyzed for Co-60 in 2007 with only 1 positive result. This total includes samples from REMP wells MW-40 and MW-51. See the AREOR for additional data.

Note 3: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC. The targetMOC is 15 pCijL.

2007 RG 1.21 Ni-63 Summary Report

Positive

Samples in Samples in Ave Pos Min Pos Max Pos Well Name 2007 2007 Act Act Act MW-42-49 4 4 8.83E+02 5.26E+02 1.17E+03

. MW-53-120 3 1 1.73E+01 1.73E+01 1.73E+01 MW-57-11 2 1 2.24E+01 2.24E+01 2.24E+01 Note 1: All results are in pCi/L Note 2: A total of 140 samples were analyzed for Ni-63 in 2007 with only 6 positive results.

Note 3: Asample is positive if the result is both greater than 3 standard deviations and greater than the MOC. The target MOC is 30 pCi/L.

Docket No. 50-3, 50-247, & 50-286

. Page 52 of 55 2007 RG 1.21 Cs-137 Summary Report

Positive

Samples Samples in AvePos Min Pos Max Pos Well Name in2007 2007 Act Act Act 8-1 3 1 1.68E+01 1.68E+01 1.68E+01 MW-31-4.9 !5 1 e.83E+Q1 8.83E+01 8.83E+01 MW~35 2 1 4.66E+01 4.66E+01 4.66E+01 MW-38 2 1 2.73E+00 2.73E+00 2.73E+OO MW-42~49 4 4 2.51 E+04 1.90E+04 3.69E+04 MW"42-78 4 3 1.37E+02 4.51E+01 3.04E+02 MW-51-t35 4 1 2.1.6E+01 2.16E+01 2.16E+01 MW-51;.163 4 1 1.16E+01 1.16E+01 1.16E+01 MW-51-189 4 1 1.38E+01 1.38E+01 1.38E+01 MW-51-40 4 1 5.1SE+00 S.15E+00 5.15E+00 MW-51-79 4 1 5.37E+00 5.37E+00 5.37E+00 MW-53-120 3 1 7.93E+00 7.93E+00 7.93E+00 MW-54'-:123 3 1 4.21 E+OO 4.21E+00 4.21 E+OO MW-56-53 3 1 1.36E+01 1.36E+01 1.36E+01 MW-56-83 3 1 1.18E+01 1.18E+01 1.18E+01 MW-59..45 3 1 1.49E+02 1.49E+02 1.49E+02 MW-S9-68 3 1 6.76E+01 6.76E+01 6.76E+01 MW-62-200 1 1 1.56E+00 1.56E+00 1.S6E+00 MW-63-191 1 1 2.4SE+01 2.45E+01 2.4SE+D1 MW~67-39 2 1 1.02E+01 1.02E+01 1.02E+01 Note 1: All results are in pCi/L Note 2: A total of 367 samples were analyzed for Cs-137 in 2007 with 25 positive results. This total includes s~mples from REMP wells MW-40 and MW-51. See the AREOR for additional data.

Note 3: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC. The target MDC is 18 pCilL.

Indian Point Energy Center Groundwater .Flow Zones Northern (Jellll

"-"-"-"-',. ~.~

~.(9) UnitJ L nits 1 mId 2 N0I1b r"-'-o""'" , """

. [nit3" IRW~O!I South OMli41 " "'.

Sfmthem

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Docket No. 50-3, 50-247, & 50-286 Page 54 of 55 An Assessment of Potential Historical Offsite Dose from Ground Water at Indian Point 1994 - 2007 An assessment of groundwater dose was included in 2005-2007's report, along with the dose assessment for routine effluents typically provided.

Since the groundwater dose was not considered a pathway previous to 2005, there were no groundwater dose assessments in 2004 and earlier. In retrospect, the first identification of groundwater contamination was in the Unit 1 North Curtain Drain in mid 1994.

The following data provides an assessment of potential additional offsite dose, over that which was reported in earlier annual effluent reports, for the period 1994 to 2004. This evaluation provides a reasonable yet conservatively high annual calculation for determining an additional potential contribution from groundwater. Groundwater dose assessments for 2005 and later were included in their respective annual effluent reports.

Docket No. 50-3, 50-247, & 50-286 Page 55 of 55 Groundwater Dose Assessment 1994-2004 In order to conservatively determine the ground water effluent dose impact from 1994 to current, a ratio was established between Unit 1 North Curtain Drain (NCO) Sr-90 annual microcuries released and effluent dose, for the periods in which detailed assessment had already been completed (2005-2007). This ratio was then used for the previous time periods (1994 - 2004) for which no groundwater dose assessments were performed. This ratio appears to be a justifiable method to determine offsite dose, as the Sr-90 in this pathway since 2005 was responsible for greater than 95% of the total groundwater dose.

The ratios for 2005 - 2007 are developed in the table below:

GW Critical Ratio - CO Dose GWWhole Ratio - Whole Body NCO annual

~

Year Organ (CO) Dose per uCi Sr-90 Body Dose Dose per uCi Sr-90 Sr-90 uCi (mrem) (mrem/uCi) (mrem) (mrem/uCi) 2005 2006 511 664 9.72E-03 7.21E-03 1.90E-05 1:09E-05

=

,~{~

2.12E-03 1.78E-03 4.15E-06 2.68E-06

.~

2007 481 9.94E-04 2.07E-06 2.66E-04 5.53E-07 Avg 552 5.97E-03 1.07E-05 <: 1.39E-03 2.4SE-OS Records of NCO Sr-90 and integrated curies were compiled from earliest records with identified contamination in the system, which was July 1994. From 1994 to the end of 1996, the NCO was directed to routine liquid waste (and specific curies from this system were unavailable). From 1997 to 2007, the NCO was directed, in one fashion or another, to the discharge canal as its own effluent pathway. The following table was generated by applying this ratio back to 1997, and using 1997's ratio back to 1994 (when contamination in the NCO was first discovered). These ratios are used to estimate the dose for the years 1994 - 2004, as follows:

NCO annual GW Critical Organ GW Whole Body Year Sr-90 uCi (CO) Dose (mrem) Dose (mrem) 1994-1997 (each) 1373 1.5E-02 3.4E-03 1998 1790 1.9E-02 4.4E-03 1999 1774 1.9E-02 4.4E-03 2000 1646 1.8E-02 4.1E-03 2001 1952 2.1E-02 4.8E-03 2002 1639 1.7E-02 4.0E-03 2003 952 1.0E-02 2.3E-03 2004 475 5.1E~03 1.2E-03 The table above represents conservative additional liquid effluent dose, potentially attributable to ground water from IPEC (principally Unit 1) since 1994. These values represent a conservative assessment of potential additional offsite dose, beyond that which was reported in routine effluent reports from 1994 to 2004, due to the potential for undetected groundwater contamination during these years. The basis (from NCO activity) does not suggest a verified groundwater component, but an assessment to provide a conservative estimate of what may have been released.

Unit 3 aDeM Revision 18 Justification 8ackage Prepared by: Steven Sandike Brief Summary of Changes January, 2007 ODCM Part I Corrected typo for Action 11 on Table 2.2-1 regarding "a" radwaste tank.

2 Clarified Table 3.3.1-1 to more clearly comply with NUREG 1301 requirements (31 days used in lieu of monthly, etc).

3 Added clarification to Note" f" following Table 3.3.1-1 for analyses on SG Feedwater and Turbine Hall drains.

4 Clarified VCPR sampling requirements in Note "i" following Table 3.4.1-1, when no rad monitor is available.

5 Added Sr-90 requirements to the REMP in Table 2.7-1, Sections 3c (sediment) and 4b (Fish / Inv) per NL-06-033, #7 & #8.

6 Added Site Boundary Man Well sample requirements to Table 2.7-1 (as Sec 5) per the GWMP per NL-06-033, #2 &.#3.

7 Added Sr-90 to Tables 2.7-2 and 3.7-1, with note identifying the GWMP interface with the REMP per NL-06-033, #6.

8 Reworded SR 3.10 to reference ODCM (as the gas tank section does) for methodologies of verifying < 10 curies per tank.

9 Added Section 5.8 to identify the Ground Water Monitoring Program and its key components per NL-06-033, #4 & #5.

ODCM Part II 10 Expanded and updated Figure 1-1 into two figures (adding 1-2), to show greater detail with release points and site boundary.

11 Clarified the requirement for having a permit for batch liquid releases in Section 2. 1.2.

12 Added clarification to Section 2. 1. 10 regarding the use of variable speed Circulating pumps.

13 Expanded Section 2. 1. 11 to add the option to verifying tank curie levels by tracking curies added to idle tanks.

14 Added Section 2.1.21 to identify potentially necessary additional release quantification from the GWMP per NL-06-033, #1.

15 Added ground and storm water representation to Figure 2~1.

16 Modified Section 4.0 to identify Figure 4-3 as "additional" sample points, rather than "non-RECS".

17 Identified in Section 4.0 that distances in Table 4-1 were measured from the unit 1 stack.

18 Added a paragraph in Section 4.0 describing the interface between the REMP and the GWMP.

19 Removed "RECS" from the title of Figures 4-1, 4-2, 4-3, and Table 4-1.

20 Identified Roseton as a control sample location without use of a footnote on Table 4-1, page 1.

21 Denoted samples that are NOT required by RECS on Table 4-1 (pages 3 and 4).

22 Added Boundary Wells (MW-40/51) in Table 4-1, page 4 & explained note 13, supporting GWMP, per NL-06-033, #2 & #3.

Each change is discussed in detail on the following pages. This information is to be included in the OSRC presentation, the 50.59 package, and the next Annual Effluent Release Report sent to the Commission per Reg Guide 1.21

Unit 3 aDeM Revision 18 Justification Package item # 1 of 22 Jan, 2007 OBJECTIVE:

Correct typo for Action 11 on Table 2.2-1 regarding "a" radwaste tank.

DESCRIPTION OF CHANGES:

Changed "... contents of the radwaste gas decay tanks ..."

to

" ... contents of a radwaste gas decay tank ... "

IMPACT:

None JUSTIFICATION:

Typographical improvement

Unit 3 aDeM Revision 18 Justification Package item # 2 of 22 Jan,2007 OBJECTIVE:

Clarify Table 3.3.1.-1 to more readily apply to NUREG 1431 format, while maintaining compliance with NUREG 1301 requirements (31 days used in lieu of monthly, etc).

DESCRIPTION OF CHANGES:

Sample frequencies were identified as "composite" and the ANALYSIS FREQUENCY was clarified as is specified in NUREG 1301, but using NUREG 1431 format of # of days in lieu of words like "monthly" or quarterly.

IMPACT:

None JUSTIFICATION:

In an effort to standardize the ODCMs for both operating units at IPEC, the format of the RECS is targeted to be that of NUREG 1431, like the Technical Specifications. This improvement drives the unit 3 ODCM one step closer to that goal, prior to actually merging the ODCMs into one document for the site in a future revision. The use of # of days in lieu of "monthly" or "quarterly" is standard practice for experienced readers of licensing basis documents after ITS. This methodology, aside from the improvements of standardization, also allows for a less complicated and more universally understood determination of the 25% grace period for required analyses or surveillances.

Although the format of the verbiage has been upgraded to NUREG 1431 format (ITS), the periodicities of samples, analyses, and surveillances have not changed from the requirements of NUREG 1301.

Unit 3 aDeM Revision 18 Justification Package item # 3 of 22 Jan, 2007 OBJECTIVE:

Add clarification to Note "f" following Table 3.3.1-1 for analyses on Steam Generator Feedwater and Turbine Hall drains.

DESCRIPTION OF CHANGES:

Identify that these pathways are adequately monitored from SG Slowdown, clarifying that increased monitoring is only required when the conditions of a "Primary to Secondary Leak" have been met, per RECS definition of this term.

IMPACT:

None.

JUSTIFICATION:

Station procedures have assumed this understanding and the aDCM was clarified to ensure compliance.

These sample descriptions are in excess of NUREG 1301 and are listed in the station ODCMs for clarify and completeness for "continuous" pathways that do NOT involve SG Slowdown.

Unit 3 aDeM Revision 18 Justification Package item # 4 of 22 Jan,2007 OBJECTIVE:

Clarify VCPR sampling requirements in Note "i" following Table 3.4.1-1, when neither the VC Noble Gas, nor the particulate radiation monitor is available.

DESCRIPTION OF CHANGES:

Identified a required noble gas grab sample prior to a pressure relief if the noble gas rad monitor is out of service. Also identified the condition and necessary compensatory actions for periods when both the VC Noble Gas and Particulate monitors are out of service.

IMPACT:

None.

JUSTIFICATION:

Station procedures have been used to clarify these requirements because VCPR requirements are generally incomplete in NUREG 1301, and its predecessor, NUREG 0472. To .!3nsure licensing basis documents cover the necessary requirements for conditions involving out of serVice rad monitors, as well as the effluent concern of properly quantifying the impact of VC Pressure Reliefs, this verbiage is added to the aDeM for clarity and completeness. These criteria are in excess of NU REG 1301.

Unit 3 aDeM Revision 18 Justification Package item # 5 of 22 Jan, 2007 OBJECTIVE:

Add Sr-90 requirements to the REMP in Table 2.7-1, Sections 3c (sediment) and '4b (Fish / Inv).

DESCRIPTION OF CHANGES:

Added Sr-90 analysis for sediment and "edible portions" of fish/invertebrates in REMP as a result of ground water investigation and commitments, per NL-06-033 , # 7 and #8.

IMPACT:

Increased annual operating cost and new procedural requirements for the REMP.

JUSTIFICATION:

The presence of trace levels of Sr-90 in some Monitoring Wells (defining the U1 ground water plume) suggests a specific effort to detect Sr-90 in REMP samples, in addition to the existing Gross Beta requirements. This effort will determine the significance of any movement of Sr-90 into the Hudson or the human food chain through fish or invertebrate consumption.

Identified specific effluent concerns and an association, such as this effort between the EFFLUENTS program and the REMP, are required per NUREG 1301 and other effluent and environmental regulations.

Unit 3 aDeM Revision 18 Justification Package item # 6 of 22 Jan, 2007 OBJECTIVE:

Add Site Boundary Monitoring Well sample requirements to Table 2.7-1 (as Section 5) per the GW Monitoring Program.

DESCRIPTION OF CHANGES:

Added the Site Boundary Monitoring Wells and sample requirements to Table 2.7-1, per the Ground Water Monitoring Program. Included in these requirements are analyses for gamma spectroscopy, Tritium, and Strontium-gO, per NRC commitments NL-06-033 , # 2 and # 3.

IMPACT:

Increased annual operating cost and new procedural requirements for the REMP.

JUSTIFICATION:

Analyzing for these isotopes at or on the way to the site boundary will help define the extent of any potential plume. It will give an early warning of possible movement toward the actual site boundary in these directions. This effort is required per the NEI initiative on ground water.

Unit 3 aDeM Revision 18 Justification Package item # 7 of 22 Jan, 2007 OBJECTIVE:

Add Sr-90 to Tables 2.7-2 and 3.7-1, with note identifying the GWMP interface with the REMP.

DESCRIPTION OF CHANGES:

Reporting Levels and LLDs for Sr-90 were reinstated into these tables, as a result of adding the requirement to analyze for this isotope. Added a note to ensure there is a clear understanding of the interface between the GWMP and the REMP (such that LLDs and Reporting Levels are understood to be potentially different between the two).

IMPACT:

None. Vendor labs have verified ability to meet LLDs.

JUSTIFICATION:

Sr-90 was added to these tables as a commitment from the Ground Water investigation. While the old values of ETSR in 1977 were evaluated for application, a new dose basis for the values selected was performed per IPEC-CHM-06-026. This memo establishes LLDs and Reporting Levels by comparisons to ratios of other isotopes and EPA drinking water standards, as well as a determination of ensuring the LLD represents 10% or less of the annual critical organ dose contribution for Sr-90 in both water and fish.

The resulting LLDs dropped slightly from those in practice when Sr-90 was last required in the REMP.

Reporting levels were then extrapolated from comparisons to other nuclides and to the drinking water guidelines.

The memo also made clear the distinction between these values (applying solely to the REMP) and values determined for use in the Ground Water Monitoring Program (GWMP), which may involve other criteria. Reporting levels and LLDs for ground water are included in the GWMP and station procedures.

Unit 3 aDeM Revision 18 Justification Package item # 8 of 22 Jan, 2007 OBJECTIVE:

Reword SR 3.10 to reference the ODCM (as the gas tank section does) for methodologies of verifying that curies in the tank remain less than 10 curies.

DESCRIPTION OF CHANGES:

Reworded this section to place the conditional phrase first, add added a phrase at the* end that this determination will be performed in accordance with the methodology and parameters of the ODCM.

IMPACT:

. None.

JUSTIFICATION:

Placing the conditional phrase first is in keeping with station procedural policy and improves clarity for understanding this condition and required surveillances. The methods of determining compliance with the ten curie limit are defined in the applicable section of ODCM Part II, Calculational Methodologies.

Unit 3 aDeM Revision 18 Justification Package item # 9 of 22 Jan, 2007 OBJECTIVE:

Add Section 5.8 to identify the Ground Water Monitoring Program and its key components ..

DESCRIPTION OF CHANGES:

Add a section to the Admin portion of the REGS to ensure licensing basis inclusion of tlw GWMP and comply with commitments NL-06-033, #4 and #5.

IMPACT:

Lower tier procedures as well as an SMM are drafted for implementing the GWMP.

JUSTIFICATION:

This new section is added to the REGS Admin Requirements to ensure the GWMP maintains a 'tie to the licensing basis requirements and NRG commitments, as well as,the NEI initiative. Placing the overview and general requirements of the program (defined in the SMM for GWMP) here in the REGS ensures continued connection with the licensing basis, in a similar fashion as the effluents and environmental monitoring programs.

Unit 3 aDeM Revision 18 Justification Package item # 10 of 22 Jan,2007 OBJECTIVE:

Expand / update Figure 1-1 into two figures (adding 1-2), to show greater detail with regard to the release points and site boundary.

DESCRIPTION OF CHANGES:

Indicated the GWMP Boundary Wells (MW-40 and MW-51 on the site boundary map, and removed the confusing complexity of identifying release points on this map. Included a second, more detailed map of the power block area, specifically for identifying release pOints. Section 1.3 description of the maps included in the aDeM was updated to identify their purpose.

IMPACT:

None.

JUSTIFICATION:

A map showing the unrestricted area and effluent release pOints is required by NUREG 1301.

Using 2 maps more clearly complies with these requirements. . The maps include all the desired functionality, and allow for the addition of locating the GWMP boundary wells. The location of these wells cannot be shown on other REMP maps, due to their location WITHIN the site boundary.

Unit 3 aDeM Revision 18 Justification Package item # 11 of 22 Jan, 2007 OBJECTIVE:

Clarify the requirement for having a permit for batch liquid releases in Section 2.1.2.

DESCRIPTION OF CHANGES:

All batch liquid releases require a permit prior to release. Reworded this section to more accurately state the requirements by replacing the word "should" with more appropriate verbiage.

IMPACT:

None.

JUSTIFICATION:

The requirements of NUREG 1301 were being met in station procedures, but this verbiage in the ODCM was not as clear as it should have been to reflect the absolute requirement for permitting batch liquid releases. The improved wording more precisely ensures compliance verbiage for NUREG 1301 is captured in the ODCM, not just station procedures.

Unit 3 aDeM Revision 18 Justification Package item # 12 of 22 Jan, 2007 OBJECTIVE:

Add Clarification to Section 2.1.10 regarding the use of variable speed circulating pumps.

DESCRIPTION OF CHANGES:

Changed "reduced speed" to verbiage clarifying the application of variable speed pumps at unit 3.

Circulators can operate at any speed between typical low and high end values.

IMPACT:

None.

JUSTIFICATION:

This update more accurately describes operation of unit 3's circulating pumps and provides reasoning for using actual Circ Pump flow rate for quantification, rather than a default low or high speed value. (Unit 3 circulators operate at variable speeds between 64,qOO gpm and 140,000 gpm).

Unit 3 aDeM Revision 18 Justification Package item # 13 of 22 Jan,2007 OBJECTIVE:

Expand Section 2.1.11 to identify the means of curie tracking in idle liquid tanks.

DESCRIPTION OF CHANGES:

Added the explanation at end of this section for the option of determining that curies remain below the ten curie limit in outdoor unprotected tanks.

IMPACT:

None.

JUSTIFICATION:

Adding this explanation ensures that a grab sample of an idle tank is not automatically required to demonstrate compliance with this surveillance. While isolating, reCirculating, and sampling are always an option, "determining" that the curie level of an outdoor tank can also be accomplished by tracking the curie contents from inlet concentrations and volume added, which in many case, is zero.

Station procedures, as well as this section of the ODeM, limit the concentration in these tanks such that ten curies cannot be approached at any time. This improvement will ensure there is a means of determining the curie content, while precluding mandated significant resource expenditure for idle tanks which can otherwise be proven well below the ten curie limit.

Unit 3 aDeM Revision 18 Justification Package item # 14 of 22 Jan,2007 OBJECTIVE:

Add Section 2.1.21 to identify potentially necessary additional release quantification from the GWMP.

DESCRIPTION OF CHANGES:

Summarize the inputs to the process of quantifying groundwater's contribution to offsite dose, in a similar fashion to the discussion of inputs to other quantification methodologies, per NL-06-033, #1. These inputs include source term, release rate, and the dilution factor, per new References 32 and 33.

IMPACT:

None.

JUSTIFICATION:

Quantification methodologies for all effluent calculations are discussed in this section of the ODCM (Calculational Methodologies). Hence, an oveNiew of the Ground Water calculational inputs is added to this section of the ODCM. Release rate and dilution flow quantification bases are provided in References 32 and 33 for this purpose. Once these inputs are gathered, this step refers to Reg Guide 1.109 processes like other liquid effluent, for determining the offsite dose. Beyond the basic tenants of quantifying ground water effluent, the details of this quantification process, like other liquid and airborne pathways, are provided in station procedures.

Unit 3 aDeM Revision 18 Justification Package item # 15 of 22 Jan, 2007 OBJECTIVE:

Add ground and storm water representation to Figure 2-1.

DESCRIPTION OF CHANGES:

Add the representation of-ground and storm water pathways to the figure of liquid effluent pathways.

IMPACT:

None.

JUSTIFICATION:

This effort results in a more complete representation of all liquid effluent.

Unit 3 aDeM Revision 18 Justification Package item # 16 of 22 Jan,2007 OBJECTIVE:

Modify Section 4.0 to identify Figure 4-3 as "additional" sample pOints, rather than "non-REGS".

DESCRIPTION OF CHANGES:

Discontinue the differentiation of REGS and NON-REGS atop the pages of sample locations. Instead,

. samples that are in excess of REGS requirements are denoted in the list of locations.

IMPACT:

None.

JUSTIFICATION:

Data from extra sample locations will continue to be collected for historical purposes. The attempt to differentiate REGS and NON-REGS locations generated confusion with regard to the fact that all locations listed in the ODGM are required by the "ODGM", if not the "REGS". This effort was a hold-over from pre-89-01 implementation and has no purpose in our more modern ODGMs, all of which is governed by the 50.59 process.

Simplifying, all samples listed are required due to their presence in the ODGM, and those in excess of the REGS are so designated.

Unit 3 aDeM Revision 18 Justification Package item # 17 of 22 Jan, 2007 OBJECTIVE:

Identify in Section 4.0 that distances in Table 4-1 were measured from the unit 1 stack.

DESCRIPTION OF CHANGES:

Added to Section 4.0 the already completed work to standardize the measured distances in the REMP from a central starting point at IPEC.

IMPACT:

None.

JUSTIFICATION:

The distances are quoted as one value for both operating units at IPEG per NUREG 1301. Therefore, a common central starting point is inferred. This addition to the aDCM clarifies that point, as it was not included in the earlier revisions where common distances were determined. This common application of the REMP for a multi-unit site is conducted per guidance in NUREG 1301.

Unit 3 aDeM Revision 18 Justification Package item # 18 of 22 Jan, 2007 OBJECTIVE:

" Add a paragraph in Section 4.0 describing the interface between the REMP and the GWMP.

DESCRIPTION OF CHANGES:

A paragraph was added at the end of this section to ensure clarity regarding the boundary and interface between the REMP and the Ground Water Monitoring Program. This added verbiage identifies that the GWMP is defined on site with station procedures and program documents (SMM), in a similar fashion to NEM procedures that implement the REMP.

IMPACT:

None.

JUSTIFICATION:

This paragraph is added to ensure clarity and avoid what was considered to be a possible opportunity for confusion regarding the interface of these two similar programs. The REMP improvements and the GWPM are added to the ODeM and defined per NUREG 1301 and the NEI initiative for ground water investigation.

Unit 3 aDeM Revision 18 Justification Package item # 19 of 22 Jan, 2007 OBJECTIVE:

Remove "RECS" from the title of Figures 4-1, 4-2, 4-3, and Table 4-1.

DESCRIPTION OF CHANGES:

Removed the word "REGS" from the title of these tables, leaving simply "sampling locations".

IMPACT:

None.

JUSTIFICATION:

This simplification was performed in light of the fact that all listed locations are required due to their inclusion in the ODGM. Sample locations in excess of the REGS are so designated within the tables.

Unit 3 aDeM Revision 18 Justification Package item # 20 of 22 Jan, 2007 OBJECTIVE:

Identify Roseton as a control sample location without use of a footnote on Table 4-1, page 1.

DESCRIPTION OF CHANGES:

Removed the previous footnote and simply included this information on the effected line of the table.

IMPACT:

None JUSTIFICATION:

Typographical improvement.

Unit 3 aDeM Revision 18 Justification Package item # 21 of 22 Jan, 2007 OBJECTIVE:

Denote samples that are NOT required by RECS on Table 4-1 (pages 3 and 4).

DESCRIPTION OF CHANGES:

.In place of identifying sample locations as RECS or NON-RECS, this verbiage was replaced by a notation for each effected sample location as being in excess of RECS requirements.

IMPACT:

None JUSTIFICATION:

This improvement clarifies that although all samples are required by the ODCM, some are in excess of RECS requirements. Samples listed are continued for historical purposes. This update reduces confusion with regard to RECS and NON-RECS sampling by eliminating those terms in favor of notation identifying effected sample location as being "in excess of RECS requirements".

Unit 3 aDeM Revision 18 Justification Package item # 22 of 22 Jan,2007 OBJECTIVE:

Add" Boundary Wells (MW-40 and MW-51) at end of Table 4-1, page 4, and explain note 13 as supporting the GWMP.

DESCRIPTION OF CHANGES:

Added boundary well sample requirements to the REMP per NL-06-033, #2, and #3.

IMPACT:

Increased annual operating cost and new procedural requirements for the REMP.

NEM procedures are updated for this inclusion.

References of this interface are drafted in the GWMP implementing procedures.

JUSTIFICATION:

The commitment to add these boundary wells to the REMP was driven from the NEI ground water initiative. The interface between the REMP and the GWMP is identified as these boundary wells in the REMP, and are added to the aDeM in excess of the requirements of NUREG 1301.

Entergy Nuclear Northeast Indian Point 3 TITLE: OFFSITE DOSE CALCULATION MANUAL "

(ODCM)

Rev. 18 WRITTEN BY:

REVIEWED BY:

OSRC REVIEW:

APPROVED BY:

EFFECTIVE DATE:

Unit 3 ODCM Table of Contents TABLE OF CONTENTS Table of Contents List of Tables iv List of Figures vi References vii PART -I RADIOLOGICAL EFFLUENT CONTROLS Chapter 1.0. DEFINITIONS 1-1 Chapter 2/3.0 RADIOLOGICAL EFFLUENT CONTROLS AND SURVEILLANCE REQUIREMENTS 2/3.1 Radioactive Liquid Effluent Monitoring Instrumentation 2/3-1 2/3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 2/3-7 2/3.3 Radioactive Liquid Effluents 2/3-12 2/3.3.1 Liquid Effluent Concentration 2/3-12 2/3.3.2 Dose From Liquid Effluents 2/3-15 2/3.3.3 Liquid Radwaste Treatment System 2/3-16 2/3.4 Radioactive Gaseous Effluents 2/3-17 2/3.4.1 Gaseous Effluent Dose Rates 2/3-17 2/3.4.2 Dose From Noble Gases 2/3-21 2/3.4.3 Dose From lodine-131, Tritium, and 2/3-22 Radionuclides in Particulate Form 213.4.4 Gaseous Radwaste Treatment System 213-23 2/3.5 NOT USED (PCP) 2/3.6 Total Dose 2/3-24 213.7 Radiological Environmental Monitoring Program 2/~-26 2/3.8 Land Use Census 2/3-37 2/3.9 Interlaboratory Comparison Program 2/3-38 2/3.10 Radioactive Liquid Effluent Holdup Tanks 2/3-39*

2/3.11 Gas Storage Tanks 2/3-40 Indian Point 3 Revision 18

Unit 3 ODCM Table of Contents TABLE OF CONTENTS PAGE Chapter 4.0 BASES 4-1 Chapter 5.0 ADMINISTRATIVE REQUIREMENTS 5.1 Records Retention 5-1 5.2 Annual Radioactive Effluent Release Report 5-1 5.3 Annual Radiological Environmental Operating Report 5-3 5.4 Major Changes To Radioactive Liquid, Gaseous and 5-4 Solid Waste Treatment Systems 5.5 Process Control Program 5-5 5.6 Offsite Dose Calculation Manual (ODCM) 5-6 5.7 Special Reports 5-6 5.8 Ground Water Monitoring Program 5-7 PART-II CALCULATIONAL METHODOLOGIES

/

(

" Chapter 1.0 INSTRUMENTATION AND SYSTEMS 1.1 Effluent Monitoring System Description 1-1 1.2 Setpoints 1-1 1.2.1 Setpoints for Gaseous Effluent Monitors 1-1 1.2.2Setpoints for Liquid Effluent Monitors 1-2 1.3 Maps Defining Unrestricted Areas for Radioactive Gaseous 1-3 and Liquid Effluents Chapter 2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Information 2-1 2.2 Liquid Effluent Concentrations 2-5 2.3 Liquid Effluent Dose Calculation Requirements 2-8 2.4 Dose Methodology (Computer Calculation) 2-9 2.5 Backup Dose Methodologies 2-12 2.6 Site Specific Bioaccumulation and Dose Factors 2-12 Indian Point 3 ii Revision 18

Unit 3 ODCM Table of Contents TABLE OF CONTENTS Chapter 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluents Releases-General Information 3-1 3.2 Gaseous Effluent Dose Calculation Requirements 3-5 3.3 Dose Calculations Methodology (Computer Calculation) 3-6 3.3.1 Instantaneous Dose Rates - Noble Gas Releases 3-6 3.3.2 Instantaneous Dose Rates - 3-8 Radioiodine 131 and Particulate Releases 3.3.3 Time Average Dose - Noble Gas Releases 3-9 3.3.4 Time Average Dose - Radioiodines and Particulates 3-11 3.4 Backup Dose Methodologies 3-19 3.4.1 Instantaneous Dose Rates - Noble Gas Releases 3-19 3.4.2 Instantaneous Dose Rates - 3-20 Radioiodine 131 and Particulate Release 3.4.3 Time Average Dose - Noble Gas Releases 3-20 3.4.4 Time Average Dose - Radioiodine 131 3-22 and Particulate Releases 3.5 Calculation of Meteorological Dispersion Factors 3-22 3.6 Justification for the Use of the Finite Cloud 3-26 Assumption for Assessing Site Boundary Dose 3.7 Direct Radiation Measurements and Total Dose 3-27 Calculations (40CFR190) 3.8 Gaseous Effluent Dose to MEMBERS OF THE PUBLIC 3-27 Visiting the Site Appendix A Calculation of Allowable Release Rates for Indian Point Units 2 and 3 3-68 4.0 SAMPLE LOCATIONS 4-1 Appendix B Detection Capabilities 4-9 Indian Point 3 iii Revision 18

Unit 3 ODCM - List of Tables LIST OF TABLES PART-I RADIOLOGICAL EFFLUENT CONTROLS 2.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 2/3-2 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 2/3-5 Surveillance Requirements 2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 213-8 3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 2/3-10 Surveillance Requirements 3.3.1-1 Radioactive Liquid Waste Sampling and Analysis Program 2/3-13 3.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program 213-18 2.7-1 Radiological Environmental Monitoring Program 213-28 2.7-2 Reporting Levels For Radioactivity Concentrations In 213-34 Environmental Samples 3.7-1 Detection Capabilities For Environmental Sample Analysis 2/3-35 PART-II CALCULATIONAL METHODOLOGIES 1-1 Effluent Monitoring System Data 1-6 2-1 Adult Liquid Effluent Dose Factors 2-15 2-2 Teen Liquid Effluent Dose Factors 2":17 2-3 Child Liquid Effluent Dose Factors 2-19 2-4 Liquid Effluent Bioaccumulation Factors 2-21 3-1a Inhalation Dose Factors for Adult 3-28 3-1b Inhalation Dose Factors for Teen 3-30 3-1c Inhalation Dose Factors for Child 3-32 3-1d Inhalation Dose Factors for Infant 3-34

, i~'

Indian Point 3 iv Revision 18

Unit 3 aDCM - List of Tables LIST OF TABLES 3-2 Ground Plan Dose Factors 3-36 3-3a Ingestion Dose Factors for Adult 3-38 3-3b Ingestion Dose Factors for Teen 3-40 3-3c Ingestion Dose Factors for Child 3-42 3-3d Ingestion Dose Factors for Infant 3-44 3-4 Total Body Dose Factors (Ki) from Noble Gases (Gamma) 3-46 3-5 Skin Dose Factors (Li) from Noble Gases (Beta) 3-47 3-6 Air Dose Factors (Mi) from Noble Gases (Gamma) 3-48 3-7 Air Dose Factors (Ni) from Noble Gases (Beta) 3-49 3-8 Noble Gas Dose Factors for Instantaneous and Time Average Mixtures at the SB 3-50 3-9 Locations of Site Boundary and Nearest Residence 3-51

(

\.

-**.... :. 3-10a .Adult Inhalation Ri(I) 3-52 3-10b Teen Inhalation Ri(l) 3-54 3-10c Child Inhalation Ri(l) 3-56 3-10d Infant Inhalation Ri(l) 3-58 3-11a Adult Ingestion Ri(V} 3-60 3-11b Teen Ingestion Ri(V} 3-62 3-11c Child Ingestion Ri(V) 3-64 3-12 Ground Plane Dose Factors Ri(G) and Ri(S) 3-66 4-1 Indian Point Station - Environmental Sampling Station Points 4-5 Indian Point 3 v Revision 18

Unit 3 ODeM - List of Figures LIST OF FIGURES PART-II CALCULATIONAL METHODOLOGIES Figure 1-1 Map Defining Unrestricted Areas (Site Boundary) 1-4 Figure 1-2 Map Defining Gaseous and Liquid Release Points 1-5 Figure 2-1 Radioactive Liquid Waste Effluent System Flow 2-22 Diagram Figure 3-1 Gaseous Radioactive Waste Effluent System Flow 3-76 Diagram Figure 4-1 Radiological Environmental Monitoring Sampling 4-2 Points within 2 miles from site Figure 4-2 Radiological Environmental Monitoring Sampling 4-3 Points within 10 miles from site Figure 4-3 Radiological Environmental Monitoring Sampling 4-3 Additional Sampling Locations

(

Indian Point 3 vi Revision 18

Unit 3 ODCM - References REFERENCES

1. U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", USNRC Report NUREG-0133, Washington D.C. 20555, October 1978. .

2. M.E. Wrenn and J. W. Lentsch, "The Fate of Gamma-Emitting Radionuclides Released into the Hudson River Estuary and an Evaluation of Their Environmental Significance", New York University Medical Center, Institute of Environmental Medicine, 1974.

3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Revisions 1 and 0 (original draft for information only), USNRC Washington D.C. 20555, October 1977.

4. "An Evaluation to Demonstrate the Compliance of the Indian Point Reactors with the Design Objectives of 10CFR50, Appendix I", Consolidated Edison Company of New York, Inc. and Power Authority of the State of New York, February 1977.

5. U.S. Nuclear Regulatory Commission, "XOQDOQ Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC Report NUREG-0324, Washington D.C. 10555, September 1977. (Later updated by NUREG CR 2919).

6. "Semi-Annual Report of Radioactivity in Solid Wastes and Releases of Radioactive Materials in liquid and Gaseous Effluents for Indian Point Three", Power Authority of the State of New York, January 1, 1978 to June 30, 1980.

7. "Environmental Technical Specification Requirements for Indian Point Nuclear Generating Unit Number 3", Power Authority of the State of New York, December 12,1975 (original ETSR).

8. U.S. Nuclear Regulatory Commission, "Radiological Effluent Technical Specification for PWR's",

USNRC Report NUREG-0472, Washington D.C. 20555.

9. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix ", Revision 1, USNRC, Washington D.C. 10555, October 1977.

10. IP-SM M-CY-OO 1, "Radioactive Effluents Control Program" (formerly AP-11 for unit 3).

11. NUREG/CR-4007, 1984, "Lower limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements".

12. New York University Medical Center, "Radioecological Studies of the Hudson River Progress Report (1986-1987}", N.Y.U. New York, New York 10016, March 1988.

13. IPI-DM-153, "Antimony Dose Factors", IPS Memorandum to M. Kems from D. Mayer, August 8, 1988.

14. New York University Medical Center, "Radiological Studies of the Hudson River Progress Report

{1987-1988)"., N.Y.U. New York, New York 10016, September 1988.

15. USNRC Regulatory Guide 1.111, "Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. Nuclear Regulatory Commission (October 1977, Rev. 1).

Indian Point 3 vii Revision 18

Unit 3 ODCM - References REFERENCES

16. CRE Computer Code AEOLUS-3, "A Computer Code for the Determination of Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents During Continuous, Intermittent and Accident Conditions in Open-Terrain Sites, Coastal Sites and Deep-River Valleys," RAD-004, Version 1, Level 2 (June 1991).

17. CRE Engineering Calculation IP3-CALC-RAD-00001, "IP3 - Revised ODCM Atmospheric Dispersion Parameters (Multi-Year Hourly Data, Mixed-Mode Releases and Valley Effects, July 1991 )," and updated reports from Entech Engineering (March 2005), by John N. Hamawi.

18. USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs," U.S. Nuclear Regulatory Commission (2117172) (and proposed revisions).

19. USNRC Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants," U.S. Nuclear Regulatory Commission (August 1979).

\

20. D. H. Slade, Ed., "Meteorology and Atomic Energy - 1968," USAEC, TID-24190 (1968).

21. WCRE-93-157, "JP3-Annual Average AtmospheriC Dispersion and Deposition factors for Ground-Level Release, December, 1993 Memorandum Hamawi to Mayer.

22 NRC Generic Letter 89-01 (Technical Specification Amendment 199) with NUREG 1301.

23. Improved Technical Specifications from NUREG 1431, Amendment 205, Feb 2001.

24. ERDA 660 (ORNL-4992), "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment ".

25. Intemational Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases: Exposures of Critical Groups, Safety Series No. 57, IAEA, Vienna (1978).

26. IP3-CALC-RAD-00013, "Radiological Analysis of Site Boundary Gamma Dose from Onsite Radioactive Material Holding Areas".

27. MicroShield Manual and Calculations, Grove Engineering.

28. M020.02, Calculations for Steam Generator Storage Facility Site Boundary Dose.

29. NYPA 3899.001, Calculations for Direct Shine Dose from the Interim Radioactive Waste Storage Facility.

30. IPEC CHM-04-035, "Nuclide Mixtures for Instantaneous and Time Average Releases".

31. IPEC CHM-05-003, "Site Specific Distances to Site Boundary and Nearest Resident".

32. IPEC CHM-06-012, "Updated Ground Water Dose Evaluations", Apr 2006.

33. IPEC CHM-05-042, "Update to Initial Monitoring Well Offsite Dose Calculation", Dec 2005.

Indian Point 3 viii Revision 18

INDIAN POINT 3 OFFSITE DOSE CALCULATION MANUAL PART I RADIOLOGICAL EFFLUENT CONTROLS (RECS)

Revision 18 I

ODCM Part I - RECS 1.0 DEFINITIONS NOTE:

Common definitions are found in Technical Specifications Section 1.1.

In addition, the following specific terms are defined below.

1.1 GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.2 MAXIMUM PERMISSIBLE CONCENTRATION WATER (MPCW)

MPCW is that concentration of a radionuclide equal to 10 times the liquid EFFLUENT CONCENTRATION(s) specified in column 2, Table 2 of Appendix B to 10CFR20.

1.3 MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC means any individual who is not occupationally associated with the plant. Excluded from this category are utility employees, its contractors or vendors, and delivery or service personnel. Included in this category are persons using the site for recreation or occupation not associated with the plant.

1.4 OFFSITE DOSE CALCULATION MANUAL (ODCM)

The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and 5.5.4 and (2) descriptions of the information that should be included in the Annual Radioiogical Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.

1.6 PRIMARY TO SECONDARY LEAK A PRIMARY TO SECONDARY LEAK is defined by a quantifiable leak rate equal to or greater than 0.5 gpd, AND a) The presence of fission or activation products in the secondary fluid; verified as Steam Generator U-tube leaks (and not from other known contamination, such as IVSWS leaks), OR b) Tritium activity in the secondary fluid indicating an increase above historical baseline (normal diffusion) of 5.00E-6 uCi/ml or greater.

Indian Point 3 ODCM Page 1-1 Revision 18

ODCM Part I - RECS 1.6 PROCESS CONTROL PROGRAM (PCP)

The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling.

analyses. tests. and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61 and 71 and Federal and State regulations and other requirements governing the disposal of solid radioactive waste., The PCP is further described in RECS 5.5.

1.7 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement in such a manner that replacement air or gas is required to purify the confinement.

1.8 SITE BOUNDARY The SITE BOUNDARY (ODCM Part II, Figure 1-1) means that line beyond which the land or property is not owned, leased, or otherwise controlled by either site licensee.

1.9 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

1.10 UNRESTRICTED AREA An UNRESTRICTED AREA (ODCM Part II, Figure 1-1) means an area at or beyond the SITE BOUNDARY, access to which is neither limited nor controlled by the licensee for purposes of radiation protection. or a similarly uncontrolled area within the SITE BOUNDARY that is used for residential quarters or for industrial. commercial, institutional, and/or recreational purposes.

1.11 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

Indian Point 3 ODCM Page 1-2 Revision 18

ODCM Part I - RECS 2/3.0 RADIOLOGICAL EFFLUENT CONTROLS AND SURVEILLANCE REQUIREMENTS 2.1 Radioactive Liguid Effluent Monitoring Instrumentation CONTROL:

In accordance with Technical Specification 5.5.4, the radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.3.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-1.

ACTION:

A. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected.

channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

B. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1.

Exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to RECS 5.2, why the inoperability was not corrected within this time frame.

C. Report all deviations in the Annual Radioactive Effluent Release Report.

3.1 SURVEILLANCE REQUIREMENTS:

Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 3.1-1.

Indian Point 3 ODCM Page 2/3-1 Revision 18

ODCM Part I - RECS TABLE 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM INSTRUMENT CHANNELS ACTION OPERABLE a

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE C

a. Liquid Radwaste Processing Effluent Line (R-18) (1 ) 1

b. Condensate Polisher Facility (CPF) Waste Line (R-61) b (1 ) 1

c. Steam Generator Slowdown (R-19) e (1 ) 2

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM SUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Line (R-16A, R-16S) (1) 3

b. Service Water System Effluent Line (R-23)

(1 ) 3

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (1 ) 4

b. CPF Effluent Line b (1 ) 4

c. Steam Generator Slowdown Effluent Line (1 ) 4

4. TANK LEVEL INDICATING DEVICES d

a. Refueling Water Storage Tank (1) 5

b. Primary Water Storage Tank (1) 5

c. Monitor Tank #31 (1 ) 5

d. Monitor Tank #32 (1) 5

e. CPF High Total Dissolved Solids Tank b (1) 5

f. CPF Low Total Dissolved Solids Tank b (1) 5

. Indian Point 3 ODCM Page 2/3-2 Revision 18

ODCM Part I - RECS TABLE 2.1-1 (Continued)

TABLE NOTATION a) During releases via this pathway, channels shall be OPERABLE and in service during such release on a continuous, uninterrupted basis, except that outages are permitted, within the time frame and limitations of the specified action, for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION or CHANNEL OPERATIONAL TEST.

b) The Condensate Polisher Facility (CPF) instrumentation requirements apply only when a primary to secondary leak is present (R-61 , the effluent flow rate meter, and the TDS level instruments). Primary to Secondary Leak is defined in RECS Section 1.

c) Recorders are only required if alarm/trip setpoints are based on recorder-controller.

d) Tanks included in this Control are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

e) Applicable for Continuous Steam Generator Slowdown to the environment only. Not applicable for Steam Generator Draindowns in Mode 5 or 6.

Indian Point 3 ODCM Page 2/3-3 Revision 18

ODCM Part I - RECS

( TABLE 2.1-1 (Continued}

TABLE NOTATION ACTION 1- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Radiological Effluent Control Surveillance Requirement 3.3.1.A, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving:

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed either for principal gamma emitters or for gross radioactivity (beta or gamma) at a lower limit of detection of at least 5E-7 microcurie/ml (as Cs-137):

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie/gram Dose Equivalent 1-131.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie/gram Dose Equivalent 1-131.

ACTION 3- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE reqUirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 5E-7 microcurie/ml (as CS-137).

ACTION 4- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.

ACTION 5- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank.

Indian Point 3 ODCM Page 2/3-4 Revision 18

ODCM Part I - RECS

( TABLE 3.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL SOURCE

-INSTRUMENT CALIBRA- OPERATIONAL CHECK CHECK TION TEST

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE d

a. Liquid Radwaste Effluent Line (R-18) Daily a Daily a 24Mi Quarterly a.g

b. CPF Effluent Line (R-61) Dailya.e Monthlt*e 24Mi Quarterly a.g

c. Steam Generator Blowdown (R-19) f Daily a Monthlt 24Mi Quarterly a.g

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Daily a Monthlt 24Mi Quarterly a.h Line (R-16A and R-16B)

b. Service Water System Effluent Daily a Monthlt 24Mi Quarterly a.h Line (R-23)

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line Daily] N.A. 24M Quarterly

b. CPF Effluent Line Daily I.e N.A. 24M Quarterly

c. Steam Generator Blowdown Daily]

N.A. 24M Quarterly Effluent Line

4. TANK LEVEL INDICATING DEVICES C

a. Refueling Water Storage Tank Dailyb N.A. 24M 24M

b. Primary Water Storage Tank Daily b N.A 24M 24M

c. Monitor Tank #31 Dailyb N.A. 24M 24M

d. Monitor Tank #32 Dailyb N.A. 24M 24M

e. CPF High Total Dissolved Solids Tank e Daily b N.A. 24M 24M

f. CPF Low Total Dissolved Solids Tank e Dailyb N.A. 24M 24M Indian Point 3 ODCM Page 2/3-5 Revision 18

ODCM Part I - RECS

( TABLE 3.1-1 (Continued)

TABLE NOTATION a) When this pathway is utilized for releases, with frequency no more than indicated.

b) During liquid additions to the tank.

c) Tanks included in this Control are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

d) Recorders are only required if alarm/trip setpoints are based on recorder-controller.

e) CHANNEL and SOURCE CHECKS on the CPF instrumentation are required only when a primary to secondary leak exists, per RECS Section 1. The tank level indicator calibrations are also required by the SPDES permit.

f) Applicable for Steam Generator Blowdown to the river only. Not applicable for Steam Generator Draindowns in Mode 5 or 6.

g) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if the following condition exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

h) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Instrument controls not set in operate mode.

i) Radioactive calibration standards used for CHANNEL CALIBRATIONS shall be traceable to the National Institute of Standards and Technology (NIST) or an aliquot of calibration solution shall be analyzed with instrumentation which is calibrated with NIST traceable standards.

(Standards from suppliers who partiCipate in measurement assurance activities with NIST are acceptable). .

j) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

Periodicity Abbreviations N.A. Not Applicable 24M At least once per 24 months Indian Point 3 ODCM . Page 2/3-6 Revision 18

ODCM Part I - RECS

( ....

'0.,;..

2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROL:

In accordance with Technical Specification 5.5.4, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 2.2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.4.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 2.2-1.

ACTION:

A. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

B. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.2-1. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to RECS 5.2, why the inoperability was not corrected within this time frame.

C. Report all deviations in the Annual Radioactive Effluent Release Report.

3.2 SURVEILLANCE REQUIREMENTS:

Radioactive gaseous effluent monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 3.2-1.

Indian Point 3 ODCM Page 2/3-7 Revision 18

ODCM Part I - RECS TABLE 2.2-1

(

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM INSTRUMENT CHANNELS APPLICABILITY ACTION OPERABLE

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor Providing Alarm (R-20) (1 ) (b) 6

2. CONDENSER AIR EJECTOR

a. Noble Gas Activity Monitor (R-15) (1 ) (a) 8

3. ENVIRONMENTAL RELEASE POINTS:

(PLANT VENT c, ADMIN BUILDING CONTROLLED AREA, RAD MACHINE SHOP)

a. Noble Gas Activity Monitors:

(1 ) (a) 8, 11

PV (R-14 or R-27) (1 ) (a) 8

Admin Bldg (R-46) (1 ) (a) 8

Rams Bldg (R-59)

(1 ) (a) 10

b. Iodine Sampler (1 ) (a) 10

c. Particulate Sampler (1) d (a) 7

d. Flow Rate Monitor (1 ) (a) 7

e. Sampler Flow Rate Monitor

4. CONTAINMENT PURGE SYSTEM

a. Containment Noble Gas Activity Monitor (1 ) (a) 9 (R-12), Providing Alarm and Automatic Termination of Release TABLE NOTATION (a) Channels shall be OPERABLE and in service on a continuous basis during release via this pathway, except that outages are permitted, within the time framebf the specified action for the purpose of maintenance and performance of required tests, checks and calibrations. .

(b) During waste gas holdup system operation (treatment for primary system offgases).

(c) The Plant Vent will also monitor releases from the Vent Header, Auxiliary Building Vents, Fuel Storage Building Vents, and the Rad Waste Area Vent.

(d) The Admin Bldg Controlled Area ventilation system uses default fan flow rate in lieu of a Process Flow Rate Monitor, per ODCM Part II, Section 3.1.13.

Indian Point 3 ODCM Page 2/3-8 Revision 18

ODCM Part I - RECS TABLE 2.2-1 (Continued)

ACTION 6 - With the number of channels OPERABLE less than that required by the Minimum Channels OPERABLE requirement, the radioactive content of the receiving gas decay tank shall be determined daily to ensure compliance with RECS 2.11.

ACTION 7 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 8 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 9 - With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

During containment building ventilation in Modes 5 or 6, continuous monitoring and automatic termination of release is not required. One continuous monitor at the final release point (Plant Vent) is sufficient.

ACTION 10 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 3.4-1.

ACTION 11 - With the number of channels OPERABLE less than that required by the Minimum Channels OPERABLE requirement for the plant vent, the contents of a radwaste gas I Yo' decay tank may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank contents are analyzed, AND,

b. At least two technically qualified members of the facilities staff independently verify the release rate calculations and discharge valve lineup.

Indian Point 3 ODeM Page 2/3-9 Revision 18

aDCM Part I - RECS TABLE 3.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT a CHANNEL SOURCE CHANNEL OPERATIONAL CHECK CHECK CALIBRATION TEST 1.WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor Daily Monthly 24M e Quarterly b.d Providing Alarm (R-20)

2. CONDENSER AIR EJECTOR e Quarterly b,d

a. Noble Gas Activity Daily Monthly 24M Monitor (R-15)

3. ENVIRONMENTAL RELEASE POINTS:

(PLANT VENT. ADMIN BUILDING CONTROLLED AREA. RAD MACHINE SHOP VENT)

a. Noble Gas Activity Monitors:

PV (R-14 or R-27) Daily Monthly 24M e Quarterly b.d

Admin Bldg (R-46) Daily Monthly 24M e Quarterly b,d

Rams Bldg (R-59) Daily Monthly 24M e Quarterly b.d

b. Iodine Sampler Weekly N.A. N.A. N.A.

c. Particulate Sampler Weekly N.A. N.A. N.A.

d. Flow Rate Monitor Daily N.A. 24M QuarterlyC

e. Sampler Flow Rate Monitor Daily N.A. 24M N.A.

4. CONTAINMENT PURGE SYSTEM

a. Containment Noble Gas Daily Monthly 24M e Quarterly b.d Activity Monitor (R12) providing Alarm and Automatic Termination of Release Indian Point 3 aDCM Page 2/3-10 Revision 18

ODCM Part I - RECS TABLE 3.2*1 (Continued)

TABLE NOTATION a) Surveillances are required at all times except when monitor has been removed from service in accordance with Table 2.2-1.

b) Will not include operation of automatic control functions.

c) Environmental Release Point flow rate meters are normally associated with the corresponding noble gas radiation monitor. The Administration Building Controlled Area Vent system does NOT have an installed process flow meter and uses default fan flow rate instead. per ODCM Part fl. Section 3.1.13.

d) The CHANNEL OPERATIONAL TEST shaff also demonstrate that control room alarm annunciation occurs if any of the foffowing conditions exists:

Instrument indicates measured levels above the alarm setpoint.

Instrument controls not set in operate mode.

e) Radioactive Calibration Standards used for CHANNEL CALIBRATIONS shall be traceable to the National Institute of Standards and Technology (NIST) or an aliquot of calibration gas shall be analyzed with instrumentation which is calibrated with NIST traceable standards (standards from suppliers which participate in measurement assurance activities with NIST are acceptable).

Periodicity Abbreviations N.A. Not Applicable 24M At least once per 24 months.

Indian Point 3 ODCM Page 2/3-11 Revision 18

ODCM Part I - RECS 2.3 RADIOACTIVE LIQUID EFFLUENTS 2.3.1 LIQUID EFFLUENT CONCENTRATION CONTROL:

In accordance with Technical Specifications 5.5.4, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 of 10CFR20 in accordance with 10CFR20.1302(2)(i) for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 uCi/ml.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within these limits.

3.3.1 SURVEILLANCE REQUIREMENTS:

A. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 3.3.1-1.

B. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 2.3.1. )

i

\

Indian Point 3 ODCM Page 2/3-12 Revision 18

aDCM Part I - RECS TABLE 3.3.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Liquid Sampling Type of Activity Analysis Detection Release Type Frequency Analysis Frequency (LLD)a (uCilml)

Each Batch Each Batch Principal 5E-7 A. Batch Gamma Emitters C Releases b (completed (completed Mo-99, Ce-144 5E-6 prior to prior to (Waste Tanks, release) release) 1-131 1E-6 Steam

. Generator One Batch 31 days per 31 days Dissolved & Entrained Draindowns to (completed prior Gases (Gamma 1E-5 the River, (completed prior to release) Emitters) to release) etc) 31 days H-3 1E-5 Each Batch (Composite d) Gross Alpha 1E-7 Sr-89, Sr-90 5E-8 Each Batch 92 days (Composite d) 1/

Fe-5S 1E-6 B. Continuous Principal SE-7 Releases e Gamma Emitters d 7 days Composite (Composite d) Mo-99, Ce-144 SE-6 1-131 1E-6 (Steam Generator 31 days Dissolved & Entrained Blowdown 31 days Gases (Gamma 1E-S (grab sample) to River, etc) Emitters)

H-3 1 E-S 31 days (Composite d) Gross Alpha 1E-7 Composite d 92 days Sr-89, Sr-90 SE-8 (Composite d)

Fe-55 1E-6 C. Service Water Gamma and Beta per Section A, (in Radiologically 31 days 31 days emitters 9 Liquid Batch Releases Controlled Areas)

D. Turbine Hall d 7 days Gamma and Beta per Section A, Drains, SG Composite (Composite d) emitters 9 Liquid Batch Releases Feedwater f Indian Point 3 aDCM Page 2/3-13 Revision 18

ODCM Part I - RECS TABLE 3.3.1-1 (Continued)

TABLE NOTATION a) The LLD is defined, for purposes of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" Signal. Equations used in the calculation of the LLD for a particular measurement system are presented in the ODCM.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to samplings for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

c) The principal gamma emitters for which the LLD Control applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137; and Ce-141. This list does not mean that only these nuclides are to be monitored. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuantI to Reporting Requirement 5.2.

d) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged for each pathway. The method of sampling employed results in a specimen ,

that is representative of the liquids released.

e) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

f) Steam Generator Feedwater and Turbine Hall Drains are adequately monitored from Steam I I/O' Generator Blowdown composites. Increased monitoring need only be performed when a Primary to Secondary leak exists, as defined in RECS Section 1.

g) Beta emitters need only be analyzed if gamma emitters have been positively identified.

Indian Point 3 ODCM Page 2/3-14 Revision 18

ODCM Part I - RECS 2.3.2 DOSE FROM LIQUID EFFLUENTS CONTROLS:

In accordance with Technical Specifications 5.5.4, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

2. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

(-

ACTION:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective action(s) that have been taken to reduce the release(s) and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

If drinking water supply is taken from the receiving water body within 3 miles of the plant discharge (3 miles downstream for river sited plants), this Special Report shall also include:

1) the results of radiological analyses of the drinking water source; and

2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.

3.3.2 SURVEILLANCE REQUIREMENTS:

Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined -in accordance with the methodology and parameters in the ODCM at least once per month.

Indian Point 3 ODCM Page 2/3-15 Revision 18

ODCM Part I - RECS 2.3.3 LIQUID RADWASTE TREATMENT SYSTEM CONTROL:

In accordance with Technical Specification 5.5.4, the liquid radwaste treatment system shall be used when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged without treatment-and in excess of the above limits, in lieu of a licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that includes the following information:

A. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, B. Action(s) taken to restore the inoperable equipment to OPERABLE status, and C. Summary description of action(s) taken to prevent a recurrence.

3.3.3 SURVEILLANCE REQUIREMENTS:

Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per month in accordance with the methodology and parameters in the ODCM when the liquid radwaste treatment systems are not being fully utilized.

Indian Point 3 ODCM Page 2/3-16 Revision 18

ODCM Part I - RECS 2.4 RADIOACTIVE GASEOUS EFFLUENTS 2.4.1 GASEOUS EFFLUENT DOSE RATES CONTROL:

hi accordance with Technical Specification 5.5.4, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

A. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and B. For iOdine-131, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

3.4.1 SURVEILLANCE REqUIREMENTS:

A. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODeM.

B. The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.4.1-1.

Indian Point 3 ODCM Page 2/3-17 Revision 18

aDCM Part I - RECS TABLE 3.4.1-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit Sampling Release Analysis Activity of Detection Frequency Type Frequency Analysis (LLD)8 , uCi/cc Batch Grab Batch Grab Principal A. Waste Gas Noble Gas Sample Prior to Sample Prior to 1E-4 Storage (NG)Gamma Each Release Each Release Emitters b Batch Grab Batch Grab B.

Purge Sample Prior to Sample Prior to Principal Vapor Each Purge Each Purge NG Gamma 1E-4 Containment Press Emitters b Monthly i Monthly i Relief C. Condenser Air Principal NG Ejector Grab Sample Monthly Gamma 1E-4 Emitters b.h D. Environmental Monthly Principal Release Monthly C Grab c NG Gamma 1E-4 Points Sample Emitters b Monthly Grab Sample d,e Monthly d,e H-3 1E-6 (Plant Vent, Weekly 9 Admin Bldg Charcoal Continuous f 1-131 1E-12 Control/ed Sample Area Vent, Weekly 9 Principal b Radioactive Continuous f Particulate Gamma 1E-11 Machine Shop Sample Emitters Vent)

Monthly Composite Gross Continuous f 1E-11 Particulate Alpha Sample Quarterly Composite Sr-89, Continuous f 1E-11 Particulate Sr-90 Sample Noble Gases Noble Gas Continuous f Gross Beta 1E-6 Monitor or Gamma Indian Point 3 aDCM Page 2/3-18 Revision 18

ODCM Part I - RECS TABLE 3.4.1-1 (Continued)

TABLE NOTATION a) The LLD is defined, for purposes of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. Equations used in the calculation of the LLD for a particular measurement system are presented in the ODCM.

It should be recognized that the LLD is defined as an g priori (before the fact) limit representing the capability of a measurement system and not as an g posteriori (after the fact) limit for a particular measurement.

b) The principal gamma emitters for which the LLD Control applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be monitored. Other identifiable gamma peaks (1-131 in particulate form, for example), together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to RECS 5.2.

c) IF following a shutdown, startup, or thermal power change (within one hour) exceeding 15% of RATED THERMAL POWER, analyses indicate that the DOSE EQUIVALENT IODINE-131 concentration in the primary coolant AND the plant vent noble gas activity (as indicated on a radiation monitor) have increased by a factor of 3 or more THEN:

1) Sample the Plant Vent for noble gases within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , AND

2) Sample the Plant Vent for Iodine and Particulate once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days with analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of sample changeout. The LLDs of these samples may be increased by a factor of 10.

d) Plant vent Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded unless continuous sampling equipment is in use.

e) Plant vent tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool unless continuous sampling equipment is in use.

Indian Point 3 ODCM . Page 2/3-19 Revision 18

ODCM Part I - RECS TABLE 3.4.1-1 (Continued)

TABLE NOTATION f) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 2.4.1, 2.4.2 and 2.4.3.

g) Continuous samples shall be changed at least once, per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

Additionally, IF routine Iodine sampling indicates 1-131 in a continuous ventilation pathway, THEN, collect a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sample (within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) for short-lived Iodine isotope quantification, on a periodicity not to exceed once per 31 days. The lLDs of these samples may be increased by a factor of 10.

h) The air ejector shall be sampled for Iodine and Tritium when a Primary to Secondary Leak exists. This leak is defined in RECS Section 1.

i) Vapor Containment (VC) noble gas shall be sampled at least monthly to ensure Pressure Reliefs are quantified with an accurate isotopic mixture. Containment noble gas radiation monitor readings can be used for quantification of Pressure Reliefs, provided the monitor readings are consistent with those observed during recent (at least monthly) grab samples. Sample data is routinely adjusted by the noble gas radiation monitor reading for purposes of quantification of each release. '

Should the VC Noble Gas Radiation Monitor be inoperable, a containment noble gas grab sample is required within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the Pressure Relief.

Should BOTH the VC and Plant Vent (PV) noble gas radiation monitors be inoperable (no auto-termination), two independent samples of the VC are required prior to the Pressure Relief.

Indian Point 3 ODCM Page 2/3-20 Revision 18

ODCM Part I - RECS 2.4.2 DOSE FROM NOBLE GASES CONTROLS:

In accordance with Technical Specification 5.5.4. the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

1. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation.

and,

2. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report. prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that identifies the cause(s} for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

3.4.2 SURVEILLANCE REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the ODCM at least once per month.

Indian Point 3 ODCM Page 213-21 Revision 18

ODCM Part I - RECS 2.4.3 DOSE FROM IODINE-131. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS:

In accordance with Technical Specification 5.5.4, the dose to a MEMBER OF THE PUBLIC from lodine-131, Tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

t. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

2. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

3.4.3 SURVEILLANCE REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per month.

Indian Point 3 ODCM Page 2/3-22 Revision 18

ODCM Part I - RECS 2.4.4 GASEOUS RADWASTE TREATMENT SYSTEM CONTROL:

In accordance with Technical Specification 5.5.4, the appropriate GASEOUS RADWASTE TREATMENT SYSTEM and the appropriate VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation in a 31 day period. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC in a 31 day period.

APPLICABILITY: At all times.

ACTION:

With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that includes the following information: .

A. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, B. Action(s) taken to restore the inoperable equipment to OPERABLE status, and C. Summary description of action(s) taken to prevent a recurrence.

3.4.4 SURVEILLANCE REQUIREMENTS:

Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per month in accordance with the methodology and parameters in the ODCM when the GASEOUS RADWASTE TREATMENT SYSTEMS are not being fully utilized.

Indian Point 3 ODeM Page 2/3-23 Revision 18

ODCM Part I - RECS 2.5/3.5 SOLID RADIOACTIVE WASTE CONTROLS AND SURVEILLANCE REQUIREMENTS:

These sections are contained in the PCP.

2.6 TOTAL DOSE CONTROL:

In accordance with Technical Specification 5.5.4, limit the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to direct radiation from uranium fuel cycle sources to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

A. With calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 2.3.2.1, 2.4.2.1 or 2.4.3.1, calculations should be made, including direct radiation contributions from the reactor units and from outside storage tanks, etc., to determine whether the above limits have been exceeded.

B. If such is the case, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the .

above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release( s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report within 30 days is considered a timely request, and a variance is granted until staff action on the request is complete.

Indian Point 3 ODCM Page 2/3-24 Revision 18

ODCM Part I - RECS 3.6 SURVEILLANCE REQUIREMENTS:

A. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillance Requirements 3.3.2, 3.4.2, 3.4.3 and in accordance with the methodology and parameters in the ODCM.

B. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks, etc., shall be determined in accordance with the methodology and parameters in the ODCM.

This requirement is applicable only under conditions set forth in Control 2.6.

( ..

Indian Point 3 ODCM Page 213-25 Revision 18

ODCM Part 1.- RECS 2.7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL:

Pursuant to Technical Specifications 5.5.1.b, a program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of the environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of 10CFR50, Appendix I, and (3) include the following:

A. Monitoring, sampling, analysis, and reporting of radiation and, radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

B. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census.

C. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in the environmental sample matrices are performed as pa,rt of the quality assurance program for environmental monitoring.

The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 2.7-1.

APPLICABILITY: At all times.

ACTION:

A. With the Radiologica~ Environmental Monitoring Program not being conducted as specified in Table 2.7-1, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by RECS 5.3, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Indian Point 3 ODCM Page 2/3-26 Revision 18

ODCM Part I - RECS B. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 2.7-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to RECS 5.7, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to A MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 2.3.2, 2.4.2, and 2.4.3.

When more than one of the radionuclides in Table 2.7-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) +... ~ 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 2.7-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Controls 2.3.2, 2.4.2, and 2.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

C. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.7-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. In lieu of a Licensee Event Report and pursuant to RECS 5.2, identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

3.7 SURVEILLANCE REQUIREMENTS:

The radiological environmental monitoring samples shall be collected pursuant to Table 2.7-1 from the specific locations given in the table and figure(s) in the ODCM and the detection capabilities required by Table 3.7-1.

Indian Point 3 ODCM Page 2/3-27 Revision 18

aDCM Part I - RECS TABLE 2.7-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling Number of and Type and Exposure Pathway Representative Samples Collection Frequency and/or Sample and Sample Locationsa Frequency of Analysis

1. Direct Radiation b 41 routine monitoring Quarterly Gamma dose stations (DR1-DR41) with quarterly two or more dosimeters for measuring and recording integrated dose continuously placed as follows:

an inner ring of stations, one in each meteorological sector in the general area of the site boundary (DR1-DR16) an outer ring of stations, one in each meteorological sector in the 6 to 8 km range from the site (DR17- DR32) the balance of the stations (DR33-DR41) to be placed in special interest areas and in one area to serve as a control station.

Indian Point 3 aDCM Page 2/3-28 Revision 18

aDCM Part I - RECS TABLE 2.7-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling Number of and Type and Exposure Pathway Representative Samples Collection Frequency and/or Sample and Sample Locations a Frequency of Analysis

2. Airborne Samples from S Continuous Radioiodine Radioiodine and locations (A 1-AS): sampler Canister:

Particulates operation 3 samples (A1-A3) from close with col- 1-131 analysis to the 3 site boundary lection weekly.

locations in different sectors, weekly, or of the highest calculated more fre- Particulate annual average ground level quently if Sampler:

0/0. required by dust loading Gross beta 1 sample (A4) from the radioactivity vicinity of a community analysis having the highest calculated following filter annual average ground level change d 0/0.

Gamma isotopic 1 sample (AS) from a control analysis e of location approximately 1S-30 composite (by km distant and in the least location) prevalent wind direction. C quarterly

3. Waterborne Gamma isotopic 1 sample upstream (Wa1) Composite analysis e

a. Surface f 1 sample downstream (Wa2) sample over monthly.

1 month Composite for period 9 tritium analysis quarterly.

b. Drinking Gross beta and 1 sample (Wb1 ) of the Grab monthly gamma isotopic nearest surface drinking analysis monthly.

supply Composite for tritium analysis quarterly. e Indian Point 3 aDCM Page 2/3-29 Revision 18

aDCM Part I - RECS TABLE 2.7-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling Number of and Type and Exposure Pathway Representative Samples Collection Frequency and/or Sample and Sample Locations a Frequency of Analysis

3. Waterborne (cont) I

c. Sediment from 2 samples (Wc1-Wc2)

Shoreline 1 sample (Wc1) from 2 annually at Gamma isotopic downstream area with least 90 days analysis e, existing or potential recreational value.

apart and Sr-90 I I/O 1 control sample (Wc2) from an upstream area.

d. Ground Water Site Boundary samples Quarterly Gamma isotopic (2 Monitoring Wells, analysis e, H-3, drilled near the south- and Sr-90 western site boundary.)

Samples from milking

4. Ingestion animals in 3 locations (la1- Semimonthly Gamma isotopic e la3) within 5 km distance when animals and 1-131

a. Milk i (for human consumption) are on analysis having the highest dose pasture; semimonthly potential. If there are none, monthly at when animals are then 1 sample from milking other times. on pasture; animals in each of 3 areas monthly at other (la1-la3) between 5 to 8 km times.

distant if available where doses are calculated to be greater than 1 mrem per y~.

1 sample from milking animals at a control location Concurrently (la4), 15-30 km distant and with indicator in the least prevalent wind locations.

direction.

Indian Point 3 aDCM Page 2/3-30 Revision 18

aDCM Part I - RECS TABLE 2.7-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling Number of and Type and Exposure Pathway Representative Samples Collection Frequency and/or Sample and Sample Locationsa Frequency of Analysis

4. Ingestion

b. Fish and 2 samples (lb1, Ib2) Sample in Gamma isotopic Invertebrates season, or analysis e 1 sample (lb1) from edible semi- and Sr-90 portions of 2 commercially annually if and/or recreationally they are not important species of fish or seasonal invertebrate, in the vicinity of the discharge, when available.

1 sample (lb2) from edible 1'/01 portions of each of 2 commercially and/ or recreationally important species (the same species as in Ib1 if available) from an area not influenced by plant discharge.

c. Food Products Samples of 3 different kinds Monthly Gamma isotopic e of broad leaf vegetation when and 1-131 analysis (edible or inedible) grown available nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed (lc1-lc2). j 1 sample of each of the similar broad leaf vegetation Monthly Gamma isotopic e grown 15-30 km distant in when and 1-131 analysis the least prevalent wind available direction if milk sampling is not performed (lc3).

Indian Point 3 aDeM Page 2/3-31 Revision 18

ODCM Part I - RECS to TABLE 2.7-1 (Continued)

\

o TABLE NOTATION aThe code letters in parenthesis (e.g., DR1, A1,oetc.) refer to sample locations as specified in the ODCM. Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 2.7-1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plant," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to RECS 5.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. In lieu of a licensee Event Report and pursuant to RECS 5.2, identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

( b One or more instruments, such as a pressurized ion chamber, for measuring and recording

\ .*..... '

dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermo luminescent dosimeter (TlD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

C The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean, of the previous calendar year, of control samples, gamma isotopic analysis shall be performed on the individual samples.

Indian Point 3 ODCM Page 2/3-32 Revision 18

aDCM Part I "" RECS TABLE 2.7-1 (Continued)

TABLE NOTATION e Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.

f The "upstream" sample shall be taken near the intake structures as described in the ODCM.

The "downstream" sample shall be taken from the mixing zone at the diffuser to the discharge canal.

9 A composite sample is one in which the quantity (aliquot) of liquid sampled shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g.,

monthly) in order to assure obtaining a representative sample.

h The dose shall be calculated for the maximum organ and age group using the methodology and parameters in the ODCM.

I The requirement to obtain and analyze samples from milch animals within 8 km of the site is intended to ensure monitoring of the "cow-milk" and vegetation pathways. Thus, only milch animals whose milk is used for human consumption are considered in the pathway and sample evaluation.

j Broad lead vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different sectors with the highest predicted D/Q in lieu of the garden census.

Indian Point 3 ODCM Page 2/3-33 Revision 18

aDCM Part I - RECS

/, ..... TABLE 2.7-2 t,

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES **

Airborne Fish Food Products Milk Analysis Water (pCi/L) Particulate or (pCi/kg, (pCi/L) (pCi/kg,wet)

Gases (pCi/m3) wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 *** 8* 40 Zr-Nb-95 400 1-131 2* 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 TABLE NOTATION

Values provided are for drinking water samples. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCi/L (This is a 40 CFR Part 141 value)

Sr-90 12 pCi/L 1-131 20 pCi/L

- These reporting levels are associated only with the REMP requirements. The Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

- - Sr-90 is added to this table due to its potential pathway via ground water.

Indian Point 3 aDCM Page 2/3-34 Revision 18

ODCM Part I - RECS TABLE 3.7-1

- DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a LOWER LIMIT OF DETECTION (LLD) b ,C Airborne Food Fish Water Particulate Products Sediment Analysis (pCi/kg, Milk (pCill)

(pCill) or Gases (pCi/kg, (pCi/kg,dry) wet)

(pCi/m3) wet)

Gross beta 4 0.01 H-3 2,000*

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Sr-90 *** 1 5 5000 1'/0 Zr-Nb-95 15 1-131 1* 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 TABLE NOTATION

If no drinking water pathway exists, higher detection capability values may be used, as follows:

H-3 3,000 pCiIl 1-131 15 pCi/1

- These required lower limits of detection are associated only with the REMP. The Ground Water Monitoring Program may involve unique requirements, independent of the REMP, and defined in station procedures.

H Sr-90 is added to this table due to its potential pathway via ground water.

Indian Point 3 ODCM Page 2/3-35 Revision 18

ODCM Part I - RECS TABLE 3.7*1 (Continued) a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to RECS 5.3.

b Required detection capabilities for thermo luminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

C The LLD is defined, for purposes of these Controls as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. Equations used in the calculation of the LLD for a particular measurement system are presented in the ODCM, Part II, Appendix B. .

It should be recognized that the LLD is defined as an g priori (before the fact) limit representing the capability of a measurement system and not as an g posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to RECS 5.3.

Indian Point 3 ODCM Page 2/3-36 Revision 18

ODCM Part I - RECS 2.8 LAND USE CENSUS CONTROl:

In accordance with Technical Specification 5.5.1.b and RECS 2.7. conduct a land use census which identifies within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50m 2 (500 tf) producing broad leaf vegetation. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. The Controls for broad leaf vegetation sampling in Table 2.7-1.4c shall be followed. including analysis of control samples.

APPLICABILITY: At all times.

ACTION:

A. With a land use census identifying a location(s} that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 3.4.3. in lieu of a Licensee Event Report. identify the new location( s) in the next Annual Radioactive Effluent Release Report. pursuant to RECS 5.2.

B. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) two times greater than at a location from which samples are currently being obtained in accordance with Control 2.7. add

/'. the new location(s} to the Radiological Environmental Monitoring Program within 30

'\~.".' .

days. The sampling location(s). excluding the control station location. having the lowest calculated dose or dose commitment(s). via the same exposure pathway. may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted. In lieu of a Licensee Event Report and pursuant to RECS 5.2. identify the new location(s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the aDeM reflecting the new location( s).

3.8 SURVEILLANCE REQUIREMENTS:

The land use census shall be conducted during the growing season at least once per calendar year using that information that will provide the best results, such as by a door-to-door survey. aerial surveyor by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to RECS 5.3.

\

Indian Point 3 ODCM Page 2/3-37 Revision 1~

ODCM Part I - RECS 2.9 INTERLABORATORY COMPARISON PROGRAM CONTROL:

In accordance with Technical Specification 5.5.1.b and RECS 2.7, perform analyses on radioactive materials supplied as part of an Interlaboratory Comparison Program.

APPLICABILITY: At all times.

ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to RECS 5.3.

3.9 SURVEILLANCE REQUIREMENTS:

A summary of the results obtained as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operation Report pursuant to RECS 5.3. '

Indian Point 3 ODCM Page 2/3-38 Revision 18

ODCM Part I - RECS 2.10 RADIOACTIVE LIQUID EFFLUENT HOLDUP TANKS CONTROL:

The quantity of radioactive material contained in each of the following unprotected outdoor tanks a shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

1. Refueling Water Storage Tank b

2. Primary Water Storage Tank

3. 31 Monitor Tank

4. 32 Monitor Tank

5. CPF High Total Dissolved Solids Tank C

6. CPF Low Total Dissolved Solids Tank C

7. Outside Temporary Tank d APPLICABILITY: At all times C ACTION:

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank. Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive

/ Effluent Release Report, per RECS 5.2.

\"

3.10 SURVEILLANCE REQUIREMENTS:

When radioactive materials are being added to any of the listed tanks C, the quantity of radioactive material in the tanks shall be determined to be less than or 'In equal to 10 curies, excluding tritium and noble gas, once per 31 days, in 01 accor~ance with the methodology and parameters in the ODCM.

NOTES:

a) Tanks included in the specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

b) After refueling operations, liquid from the reactor cavity will be sampled for radioactive material content prior to pumping into the tank.

c) The Condensate Polisher Facility (CPF) Total Dissolved Solids Tanks require controls and surveillances only when a primary to secondary leak exists.

d) Liquid will be sampled for radioactive content prior to being pumped into the tank.

Indian Point 3 ODCM Page 2/3-39 Revision 18

ODCM Part I - RECS 2.11 GAS STORAGE TANKS CONTROL:

The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 50,000 curies of noble gas (considered as Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank.

Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the tank contents to within the limit and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, per RECS 5.2.

3.11 SURVEILLANCE REQUIREMENTS:

The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank in accordance with the methodology and parameters in the ODCM.

Indian Point 3 ODCM Page 2/3-40 Revision 18

ODCM Part I - RECS 4.0 BASES RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (213.1)

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 to 10 CFR 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (2/3.2)

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General DeSign Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

LIQUID EFFLUENTS CONCENTRATION (2/3.3.1)

This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the EFFLUENT CONCENTRATION values specified in Appendix B, Table 2, Column 2 to 10 CFR 20. The Control provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the restrictions authorized by 10 CFR Part 20.1301(e). The concentration limit for the dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its EFFLUENT CONCENTRATION in air (submersion) was converted to an equivalent concentration in water.

This control does not affect the requirement to comply with the annual limitations of 10 CFR Part 20.1301(a).

This Control applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLDI and other detection limits can be found in Currie, L.A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

Indian Point 3 ODCM 4-1 Revision 18

ODCM Part I - RECS

/.... DOSE FROM LIQUID EFFLUENTS (2/3.3.2)

This Control is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I, 10 CFR Part 50. The Control statement implements the guides set forth in Section II.A of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the aDCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER aF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the aDCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision t, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that systen;l.

LIQUID RADWASTE TREATMENT SYSTEM (2/3.3.3)

The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

Indian Point 3 OOCM 4-2 Revision 18

ODCM Part I - RECS GASEOUS EFFLUENTS DOSE RATE (2/3.4.1 )

This Control provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10 CFR Part 50. This Control is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section ILA and II.C design objectives of Appendix I to 10 CFR Part 50.

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmospheric dispersion of gaseous effluents relative to that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding -dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mremlyear to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. This Control does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

This Control applies to the release of gaseous effluents from all units at the site.

DOSE FROM NOBLE GASES (2/3.4.2)

This Control is provided to implement the requirements of Sections II.B, liLA and IV.A of Appendix I, 10 CFR Part 50. The Control statements implement the guides set forth in Section II.B of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept nas low as is reasonably achievable. The II Surveillance Requirements implement the requirements in Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. .

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

Indian Point 3 ODCM 4-3 Revision 18

ODCM Part I - RECS DOSE FROM IODINE-131. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM (2/3.4.3)

This Control is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section II.C of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of AppendiX I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for lodine-131, Tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man (determined to be not applicable at Indian Point), and 4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from each reactor at the* site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

GASEOUS RADWASTE TREATMENT SYSTEM (2/3.4.4)

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Control applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

i

\..,

Indian Point 3 ODCM 4-4 Revision 18

ODCM Part I - RECS TOTAL DOSE (213.6)

This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301 (d). The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks, etc., are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, submittal of the Special Report within 30 days with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4), is considered to bea timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Parts 20, as addressed in Controls 2.3.1 and 2.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the I nuclear fuel cycle.

Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (2/3.7)

The Radiological Environmental MonitOring Program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

This monitOring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Isotopes identified in REMP are compared to those identified in the applicable Annual Effluent Report. Program changes may be initiated based on these operational experiences.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 3.7-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an g priori (before the fact) limit representing the capability of a measurement system and not as an g posteriori (after the fact) limit for a particular measurement.

(

Indian Point 3 ODCM 4-5 Revision 18

ODCM Part I - RECS LAND USE CENSUS (213.8)

This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to-door survey, from aerial surveyor from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than* 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2 .

INTERLABORATORY COMPARISON PROGRAM (2/3.9)

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the preciSion and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

LIQUID HOLDUP TANKS (2/3.10)

Pursuant to Technical Specification 5.5.11.c, the tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits identified in Appendix B, Table 2, Column 2 of 10CFR20, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICED AREA.

GAS STORAGE TANKS (2/3.11 )

Pursuant to Technical Specification 5.5.11.b, the tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another specification to a quantity that is less than the quantity that provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months duration.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with NUREG-0133.

Indian Point 3 aDCM 4-6 Revision 18

ODCM Part I - RECS 5.0 ADMINISTRATIVE REQUIREMENTS 5.1 RECORDS RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, records shall be retained in accordance with the retention schedule of TRM 5. 5.

The following specific Effluent and Environmental records shall be retained for the duration of the unit operating license:

Records of any drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

Records of gaseous or liquid radioactive material released to the environs.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and records showing that these procedures were followed.

Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.

5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT A Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. A single sUbrnittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station. However, for units with separate radwaste systems, the. submittal shall specify the releases of radioactive material from each unit.

The Annual Radioactive Effluent Release Report shall include the following information:

A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof or as modified in the RECS.

Indian Point 3 ODCM Page 5-1 Revision 18

ODCM Part I - RECS

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For solid wastes, the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period will be presented in tabular form similar to that of Table 3 of Regulatory Guide 1.21:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate,

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on electronic media of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments, i.e., specific actiVity, exposure time and location, shall be included in the report. Approximate and conservative approximate methods for determining the meteorological conditions shall be used for determining gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). .

An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, when required by Sections 2.6 and 3.6, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose* contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109 Rev. 1, October, 1977.

A list and deSCription of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

Indian Point 3 ODCM Page 5-2 Revision 18

ODCM Part I - RECS

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Pursuant to Controls 2.1 and 2.2, an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified.

Pursuant to Controls 2.1 and 2.2, a discussion of all deviations from the provisions of these Controls.

Pursuant to Control 2.7 and Table 2.7-1, Notation (a), identify the causes of' the unavailability of samples for pathway analysis and identify the new locations for obtaining replacement samples. Include revised figure(s) and table for the ODCM reflecting the new locations.

Pursuant to Table 3.3.1-1, Notation (c) and Table 3.4.1-1, Notation (b), a discussion of identifiable gamma peaks, including those of nuclides specified in Tables 3.3.1-1 and 3.4.1-1.

Pursuant to Control 2.8, a listing of new location(s) for dose calculations and/or

. environmental monitoring identified by the land use census. Include revised figure(s) and table for the ODCM reflecting the new location( s).

Pursuant to Controls 2.10 and 2.11, a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the Control limits.

Pursuant to RECS 5.4, a discussion of the major changes to radioactive liquid, gaseous, and solid waste treatment systems.

Pursuant to RECS 5.5 and 5.6, any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), respectively.

5.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT An annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15th of each year, according to Technical Specification 5.6.2. A single submittal may be made for a multiple unit station.

The Annual Radiological Environmental Operating Report shall include:

Summaries, interpretations, and an analysis of trends of the results of the Radiological Environmental Monitoring Program for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

At least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary and the second shall include the more distant stations.

Indian Point 3 ODCM Page 5-3 Revision 18

ODCM Part I - RECS

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The results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

A summary description of the Radiological Environmental Monitoring Program.

A discussion of the reasons for not conducting the Radiological Environmental Monitoring Program as specified by Control.2.7 and the plans for preventing recurrence.

Pursuant to Control 2.7, a discussion of environmental sample measurements that exceed the reporting levels of Table 2.7-2 but are not the result of plant effluents.

Pursuant to Table 2.7-1, Notation (a), a discussion of all deviations from the sampling schedule of Table 2.7-1.

Pursuant to Table 3.7-1, Notation (c), a discussion of the contributing factors for cases in which the LLD required by Table 3.7-1 was not achievable.

Pursuant to Table 3.7-1, Notation (a), a discussion of identifiable nuclide peaks, including

. those cif nuclides specified in Table 3.7-1.

Pursuant to Control 3.8, the results of the land use census.

Pursuant to Control 2.9, the corrective actions taken to prevent a recurrence if the Interlaboratory Comparison Program is not being performed as required.

Pursuant to Control 3.9, the results of licensee participation in the Interlaboratory Comparison Program.

5.4 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the OSRC. The discussion of each shall contain: .

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems Indian Point 3 ODCM Page 5-4 Revision 18

ODCM Part I - RECS f

An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto

An evaluation of the change, which shows the expected maximum exposures to an individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made .

An estimate of the exposure to plant operating personnel as a result of the change

Documentation of the fact that the change was reviewed and found acceptable by the OSRC.

A single submittal may be made fora multiple unit station

The information called for in this Specification will be submitted as part of the annual FSAR update 5.5 PROCESS CONTROL PROGRAM (PCP) 5.5.1 The PCP shall be approved by the Commission prior to implementation.

5.5.2 Licensee initiated changes to the PCP:

5.5.2.1 Shall be documented and records of reviews performed shall be retained as required by RECS 5.1. This documentation shall contain:

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s); and

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

5.5.2.2 Shall become effective upon review and acceptance by the OSRC and the approval of the Site Executive Officer.

5.5.2.3 Shall be submitted to the Commission as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the PCP was made. Each change shall be identified by marking in the margin. of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

Indian Point 3 ODCM Page 5-5 Revision 18

ODCM Part I - RECS 5.6 OFFSITE DOSE CALCULATION MANUAL (ODCM) 5.6.1 The ODCM shall be approved by the Commission prior to implementation.

5.6.2 Licensee initIated changes to the ODCM:

5.6.2.1 Shall be documented and records of reviews performed shall be retained as required by RECS 5.1. This documentation shall contain:

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes(s); and

A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations; 5.6.2.2 Shall become effective upon review and acceptance by the OSRC and the approval of the Site Executive Officer.

5.6.2.3 Shall be submitted to the Commission as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by marking in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

5.7 SPECIAL REPORTS In lieu of a Licensee Event Report (LER), the following special reports must be generated within 30 days:

Pursuant to Control 2.3.2, identify the cause(s} for exceeding the specified limits for dose or dose commitment to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents to UNRESTRICTED AREAS. Define the corrective action(s) taken to reduce the releases and the proposed corrective action(s) to be taken to assure subsequent releases will be in compliance with limits.

Include the results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.

Pursuant to Control 2.3.3, explain why liquid radwaste was discharged without treatment and identify any inoperable liquid radwaste treatment system equipment or subsystems and the reason for the inoperability. Include the action(s) taken to restore the inoperable equipment to OPERABLE status and a summary description of the action(s) taken to prevent a recurrence.

Pursuant to Control 2.4.2, identify the cause(s) for exceeding the specified limit(s) for the air dose due to radioactive noble gases released in gaseous effluents. Define the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure subsequent releases will be in compliance with Control limits.

Indian Point 3 ODCM Page 5-6 Revision 18

ODCM Part I - RECS

Pursuant to Control 2.4.3, identify the cause(s) for exceeding the specified limits for

( the dose to a MEMBER OF THE PUBLIC from the release of iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days in gaseous effluents. Define the corrective actions taken to reduce the releases and define the proposed corrective actions to be taken to assure subsequent releases will be in compliance with limits.specified in the Control.

Pursuant to Control 2.4.4, explain why gaseous radwaste was discharged without treatment and identify inoperable gaseous radwaste treatment system equipment or subsystems and the reason for the inoperability. Include the action(s) taken to restore the inoperable equipment to OPERABLE status and a summary description of the action(s) taken to prevent a recurrence.

Pursuant to Control 2.6 and 10 CFR Part 20.2203(a)(4), define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified total dose limits. Include a schedule for achieving conformance with the limits and describe the course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by this report.

Also describe the levels of radiation and the concentrations of radioactive material involved as well as the cause of the exposure levels or concentrations. Include a request, if required by the provisions of the Control, for a variance in accordance with the provisions of 40 CFR Part 190.

Pursuant to Control 2.7, identify the cause(s) for exceeding the reporting levels of Table 2.7-2 and define the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 2.3.2, 2.4.2, and 2.4.3. Report when more than one radionuclide in Table 2.7-2 is detected and Concentration (1) + Concentration (21 +... ~ 1.0 Reporting Level (1) Reporting Level (2)

Report when radionuclides other than those in Table 2.7-2 are detected and are the result of plant effluents and the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Controls 2.3.2, 2.4.2, and 2.4.3.

5.8 GROUND WATER MONITORING PROGRAM (GWMP)

. The GWMP shall be defined in station procedures and shall include detailed information regarding the following:

Purpose and scope of the program

Sample locations, types, and species analyzed

Methods of archiving and retrieving historical records of analytical results

Reporting instructions, including limits of detection

Summary information characterizing the condition of site ground water

An annual summary report for submittal to the NRC and/or general publication Indian Point 3 ODCM Page 5-7 Revision 18

INDIAN POINT 3 OFFSITE DOSE CALCULATION MANUAL ODCM PART 11- CALCULATIONAL METHODOLOGIES REVISION 18

aDCM Part II - Calculational Methodologies 1.0 INSTRUMENTATION AND SYSTEMS 1.1 Effluent Monitoring System Description Effluent monitor information is provided in Table 1-1, including an indication of which monitors use effluent setpoints. Figures 2-1 and 3-1 show a schematic of the possible radioactive release points which monitor locations for liquid and gaseous pathways, respectively.

1.2 Setpoints This section provides equations and methodology used for each alarm and trip setpoint on each effluent release point according to Sections 2.1 and 2.2 of the RECS.

1.2.1 Setpoints for Gaseous Effluent Monitors Setpoints for gaseous monitors are based on the permissible discharge rate as calculated in Section 3 of the aDCM. These setpoints are inherently conservative due to the assumed mixture (Table 3-8) and the use of the most restrictive setpoints (annual average dose limit), which are used whenever practical. Higher release rates may be authorized with the proper concurrence, as delineated in Section 3.1.8. The methodology identified in Section 3, along with an isotopic mix described in Table 3-8, are used to generate the following noble gas discharge rates (normally utilized for alarm setpoints):

Indian Point Unit 3 Conservative Permissible Discharge Rates (uCi/sec)

Basis of Limit 10dine/Particulate* Noble Gases Annual Average ** 4.0SE-2 3.S7E+3 Quarterly Average ** 8.10E-2 7.14E+3 Instantaneous *** 1.38E+1 7.00E+4

Half-lives greater than 8 days

- These limits are not part of Section 2.4.1 of the RECS, but are included for information, as these limits are used for operational control of releases.

- - Derived from Section 2.4.1 of the RECS.

1.2.1.1 The Plant Vent Wide Range Gas Monitor (R-27) reads and alarms in

!-lCi/sec, hence, the alarm setpoints are set directly in !-lCi/sec.

1.2.1.2 If the monitor reads and alarms in J,lCi/cc, the maximum alarm set point is calculated as follows:

S = D / [(F) * (4. 72E+2)}

where: S =Maximum alarm setpoint in jlCi/cc Indian Point 3 aDCM Page 1-1 Revision 18

aDCM Part II - Calculational Methodologies D = Permissible discharge rate in J..lCi/sec .

F = Vent duct flow in fe/min

( 4.72E+2.= unit conversion factor (28317 ccemin/fee60sec) 1.2.1.3 If the monitor reads and alarms in cpm, then the maximum alarm setpoint is calculated as follows:

S = D / [(F) * (4.72E+2)* (CF)]

where:

S, D, F, and 4.72E+2 are defined in the previous step CF = Rad Monitor Conversion Factor (J..lCi/cc per net cpm) 1.2.1.4 Normally, maximum allowable limits are calculated using a standard nuclide mix. However, setpoints may be determined based on the actual mix, on a case by case basis. This method is usually performed when the instantaneous release rate is applied. Should this method be applied, extra care should be applied to setpoint partitioning (for all release points) to ensure site dose rate limits are not approached.

1.2.1.5 During normal operation, the Unit 3 main plant vent is the only significant release point. Hence, monitors on the plant vent are routinely set at the annual limit. which is approximately 10% of the conservative instantaneous limit.

Monitor setpoints on other pathways are routinely set to 1% of the instantaneous limit. If multiple pathways become significant, each pathway's permissible release rate is apportioned with the Plant Vent's to ensure the total discharge rate for all release pOints remains less than the maximum permissible discharge rate.

1.2.2 Setpoints for Liquid Effluent Monitors 1.2.2.1 Liquid Effluent Monitors have setpoints based on limiting the concentrations in the discharge canal to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20 in accordance with 10CFR20.1302(2)(i). Monitor setpoints are inherently conservative due to the routine use of Circulating Water Pumps for liquid waste releases, and Service Water for continuous releases.

In actuality, both Circulating and Service Water systems contribute to site dilution.

1.2.2.2 For monitors that read and alarm in IlCi/ml, such as the liquid waste disposal monitor (R-18), the service water monitors (R-16 A and B and R-23), and the steam generator blowdown monitor (R-19) the alarm setpoint is calculated as follows:

S = [(ADC) (F)]/[ij = Maximum alarm setpoint in J..lCi/ml Indian Point 3 aDCM Page 1-2 Revision 18

ODCM Part II - Calculational Methodologies where:

F= Available discharge canal dilution flow for this release in gal/min f= calculated allowable release rate in gal/min (Section 2.2.6)

ADC = Allowed diluted concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (beta and gamma emitters). This parameter is further clarified in Section 2.2.

NOTE: The gamma equivalent MPCW or ADC must be used due to the insensitivity of the radiation monitor to beta emitters and the time necessary to analyze liquid releases for these beta emitters.

1.2.2.3 Alert setpoints should be used on batch liquid release monitors to ensure the contents of the batch tank have not changed since sampling. The alert setpoint is calculated as follows:

AS = (C) * (M) where:

AS = Alert setpoint in J-lCi/ml C = Average monitor reading at time of sample M = A conservative factor based upon the mixing ratio of two tank volumes and an

. expected monitor response error term (typically 1.25, coinciding with 25%).

NOTE: Liquid Monitor alert setpoints do not control any auto functions but simply provide indication to the operators.

1.3 MAPS DEFINING UNRESTRICTED AREAS AND RADIOACTIVE GASEOUS AND I '/01 LIQUID EFFLUENTS Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE I '/01 PUBLIC, are shown in Figures 1-1 and 1-2.

The definition of UNRESTRICED AREA used in implementing the Radiological Effluent Controls (RECS or ODCM Part I) has been expanded over that in 10 CFR 20.1003. For calculations performed pursuant to 10 CFR 50.36a, the concept of UNRESTRICTED AREAS refers to areas at or beyond the SITE BOUNDARY and does not include areas over water bodies. This definition is utilized in the RECS to keep levels of radioactive materials in liquid and gaseous effluents as low as reasonably achievable.

Indian Point 3 ODCM Page 1-3 Revision 18

ODCM Part 11- Calculah,- .* ~I Methodologies Figure 1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS Showing Locations of Site Boundary Wells (MW-40 and MW-S1)

~ Ii 1-----:::::lL~ _______ h . . . . . .-

Il,---::--:--_

I Area Site Map I

I I ( ...... _.....\

I I \... .. - ..?)

I RESTRlCla> AREAS within F:::;::;'::'?)

the SITE BOUNDARY are I Identified with flO$ting& and do NOT apply over water.

H j:

o I

I I

I

.\

I II I

t I

\

\ ----.....- -

\

MW-40 HuO,son Ri\<er Indian Point 3 ODCM Page 1-4 Revision 18

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aDCM Part II - Calculatl.: .jl Methodologies Figure 1-2 MAP DEFINING RELEASE POINTS

GASEOUS EFFLUENT RELEASE POINT A RWsrO I'

N 1

DISCHARGE CANAL U-3 TURBINE BLDG.

U-l TURBINE BLDG.

Indian Point 3 aDCM Page 1-5 Revision 18

ODCM Part II - Calculational Methodologies TABLE 1 -1 (Page 1 of 2)

EFFLUENT MONITORING SYSTEM DATA ALARM MONITOR EFFLUENT CONTROL CHANNEL SAMPLING LOCATIONS RANGE SETPOINT DESCRIPTION- - FUNCTIONS USED Samples drawn from 32 and R-12 G Containment Gas 1E-7 to 1E-1 /lCilcc Containment Ventilation Isolation Note 1 35 Containment Fan Coolers Monitor Secures waste gas tank release Plant Vent Radiogas In Plant Vent at R-14 G 1E-6 to 1E-1 /lCi/cc and Containment Ventilation Note 1 Monitor approximately 105' elevation Isolation On alarm diverts air ejector flow to Condenser Air Ejector In-line detector on the air R-15 G 1E-6 to 1E+O IlCi/cc VC, steam to condenser priming Note 1 Monitor ejector exhaust header air ejector stopped and steam to reheater secured Waste Gas Disposal Adjacent to line monitor on R-20 G suction to waste gas 1E-2 to 1E+3 IlCi/cc None Note 3 System Monitor compressors Secure waste gas tank release Plant Vent Wide-Range Sample drawn from inside R-27 G 1E-7 to 1E+5llCi/cc and Containment Ventilation Note 1 Monitor Plant Vent Isolation Administration Building 4th Floor Administration 1E+1 to 1E+6 cpm R-46 G Building Monitor Exhaust (typically 5E-8 to 5E- None Note 1 Vent Radiogas Monitor Plenum for Controlled Areas 2uCi/cc)

R-59 G RAMS Building Vent 55' RAMS Building Monitor 1E-6 to 1E+2 /lCi/cc None Note 1 RadioQas Monitor Exhaust Plenum Indian Point 3 ODCM Page 1-6 Revision 18

ODCM Part /I - Calculational Methodologies TABLE 1 -1 (Page 2 of 2)

EFFLUENT MONITORING SYSTEM DATA ALARM MONITOR DESCRIPTION EFFLUENT CONTROL CHANNEL SAMPLING LOCATIONS RANGE SETPOINT FUNCTIONS USED Fan Cooler and Motor Adjacent to service water return line from 1E-7 to 1E-1 R-16,AlB L Cooler Service Water Return V.C. fan cooler units and motor coolers J.tCi/cc , None Note 1 Component Cooling System Adjacent to line monitors on each pump 1E-6 to 1E-1 R-17A1BL pump outlet outlet None Note 2

/J.Cilml Component Cooling Heat Adjacent to line monitor mounted on R-23 L 1E-7 to 1E-1 Exchanger Service Water service water return line from Component None Note 1 Monitor _ Cooling Heat Exchanger J.tCi/cc Waste Disposal Liquid In-line monitor on monitor tank recirc 1E-7 to 1E-1 Terminates monitor R-18 L tank release on alarm Note 1 I Effluent Monitor pump discharge /J.Ci/cc Closes blowdown PAB blowdown room monitors steam 1E-6 to 1E+2 R:'19 L SG Blowdown Monitor isolation valves and SG Note 1 generator blown J.tCi/cc I sample valves Monitor recirculation of HTDS and LTDS CPF Regen Waste Release 1E-7 to 1E-1 Terminates HTDS or ,

tanks in condensate polisher (used when Note 4 I

R-61 L Monitor I!Ci/cc LTDS tank release primary to secondary leakage exists).

Note 1 Alarm setpoint used for effluent considerations. G =Gaseous L =Liquid Note 2 Alarm setpoint NOT used for effluent considerations, used for information only.

Note 3 Ensures 50000 Ci limit in gas decay tanks is not exceeded.

Note 4 Alarm setpoint based on effluent considerations ONLY if a Primary to Secondary Leak exists, per RECS Section 1.

Indian Point 3 ODCM Page 1-7 Revision 18

ODCM Part II - Calculational Methodologies 2.0 LIQUID EFFLUENTS 2.1 liquid Effluent Releases - General Information 2.1.1 The surveillance and lower limit of detection requirements for liquid radioactive effluents are contained in Section 3.3.1 of the Radiological Effluent Controls (RECS). Lower limit of detection calculations are listed in ODCM Part II, Appendix B.

2.1.2 A completed and properly authorized liquid Radioactive Waste Permit is required prior to the release of any radioactive waste from an isolated tank to the discharge canal.

2.1.3 All activity determinations for liquid radioactive effluents are performed in such a manner as to be representative of the activity released to the river.

2.1.4 The radioactivity in liquid waste tanks shall be continuously monitored during release except as allowed by Section 2.1 of the RECS. If the flowmeter is inoperable, the flow shall be estimated every four hours by difference in tank level or by discharge pump curves.

2.1.5 Prior to discharge, the radioactive waste tank contents shall be recirculated for at least two tank volumes. After this recirculation, and prior to discharge, a sample shall be taken and analyzed for activity with a portion of the sample set aside for composite analysis. The measured activity shall be used for calculating allowable discharge rate and the alarm setpoint for the liquid waste discharge monitor.

2.1.6 Radioactive releases of steam generator blowdown during primary to secondary leaks when released to the river should be documented on liquid Radioactive Waste Release Permits using data supplied by the Chemistry Technician.

2.1. 7 As~urance that combined liquid releases from Units 2 and 3 do not exceed the requirement of the RECS, Section 2.3 (10CFR20 requirements) are provided by administrative controls which include routine use of unit-specific dilution flow for each permitted release. In order to facilitate two-unit operation, however, upon agreement between shift managers, one unit can reduce or eliminate radioactive liquid waste discharges for a period of time to allow the other unit to use the full site dilution flow, or a specified portion thereof, for a limited time.

2.1.8 Steam Generator Blowdown activity is determined by samples taken at least three times per week. These "grab" samples of the steam generators are collected in a manner to be proportional to the rate of flow of individual steam generator to total steam generator blowdown. These samples are then analyzed for the various radionuclides at frequencies specified in Table 3.3.1-1 of the RECS. Further flow proportional composites are made where appropriate.

Indian Point 3 ODCM Page 2-1 Revision 18

ODCM Part II - Calculational Methodologies

( 2.1.9 Time average dose calculations (10CFR50) may use total site dilution flow for both units, with the determined dose contributions additive for a site report over any specified period.

2.1.10 The discharge canal flow rate is determined by the use of pump flow characteristics curves. Nominal maximum flow for condenser cooling pumps is 140,000 gpm. During the cold weather months, the condenser cooling pumps are operated at reduced speed, nominally 64,000 gpm or greater, depending on the variable speed selected.

2.1.11 Radioactivity content in outdoor tanks is to be limited to less than 10 curies, excluding tritium and noble gas, as per Section 2.10 of the RECS.

Compliance with this requirement is demonstrated by limiting the radioactive concentration in these tanks to the value which results in 10 curies when the tank is at full liquid capacity, except as modified below.

The radioactive concentration limits for these tanks are:

6 RWST: 10 curies x 10 fJCi / curie = 7.3 x 10-3 fJCi I ml 358,500gal x 3785ml / gal 6

PWST: 10 curies x 10 fJCiI curie = 1.6x 10- 2 fJ Cil ml 165,000gals x 3785ml I gal

(

31 & 32 MT:

10 curies x 106 fJCi / curie I

- - - - - - - - : : : 2.2 x 10- fJCi I ml 11,750gals x 3785mll gal Condensate Polisher High and Low Total Dissolved Solids Tanks:

6 10 curies x 10 JiCi I curie 2

- - - - - - - - - = 4.4 xl 0- fJCi I ml 60,000gals x 3785ml I gal Outside Temporarv Tanks:

10 curies x 10-6 fJCi / curie

- - - - - - - - - - = fJCi/ ml /

Volume (gal) x 3785ml / gal Integrated curies in a tank can similarly be determined by calculating the I VOl curies added from known inlet concentrations and volumes, which would then be combined with previously determined tank curie levels.

Indian Point 3 ODCM Page 2-2 Revision 18

ODCM Part 1\ - Calculational Methodologies The refueling water storage tank has the potential to be filled from the reactor cavity with liquid which exceeds the limits stated. Therefore, prior to filling the RWST from the reactor cavity after refueling operations, the reactor cavity (or residual heat removal system) must be sampled for radioactivity and action taken to ensure that the total activity in the tank does not exceed 10 curies.

Outside temporary tanks should not be filled with liquid which could exceed the concentration limit calculated. Therefore, prior to transfer to outside temporary tanks, the source of liquid shall be sampled for radioactivity. If it exceeds the concentration limit calculated, action shall be taken to ensure that the total activity in the tank does not exceed 10 curies.

2.1.12 Although R-19 continuously monitors steam generator blowdown to the river, there are no continuous composite samples for steam generator blowdown. The niethod of determining release concentration is as follows:

Individual blowdown Sample Composite flow rate to river x Slowdown = aCtivity being (by flowmeter or curves) Concentration released 2.1.13 The service water radioactivity monitors listed in Table 2.1-1 of the RECS are defined as the process radiation monitors which monitor components discharging into or are cooled by the service water system. These and other liquid effluent process radiation monitors are:

Service Water:

R-16 A or B: Fan Cooler and Motor Cooler unit service water return monitors R-23: Component cooling service water return Liquid Waste (separate release points):

R-18: Liquid waste release monitor R-19: Steam generator blowdown radioactivity monitor R-61: Condensate Polisher waste monitor. Applicable only after a Primary to Secondary Leak, per RECS Section 1.6 and ODCM Part II, Sec 1, Table 1-1, Note 4.

If all monitors on the effected release path are taken out of service and the removal of that monitor from service is not specifically addressed in the RECS, releases may continue via this pathway provided that samples are taken on the effected stream every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Indian Point 3 ODCM Page 2-3 Revision 18

aDCM Part II - Calculational Methodologies 2.1.14 Liquid effluent concentrations must be within the limitations of 2.3.1 of the RECS. The total dose per quarter and per year must be within the limitations of 2.3.2 of the RECS.

2.1.15 There are no drinking water intakes within 3 miles downstream of the site on the Hudson River (see Section 2.4.1 for further details).

2.1.16 A turbine hall drain system which would collect leakage of contaminated secondary plant waters during operation does not exist at IP3. The sumps present in the turbine hall (five foot elevation) receive drains from areas containing secondary plant components at sub-atmospheric pressures.

These sumps do not meet the intent of a turbine hall drain system as defined in NUREG 0472.

Quantification of effluents is performed on this pathway during a Primary to Secondary leak, as defined by aDCM Part II, Section 1, Table 1-1, Note 4.

In these cases, releases from this pathway would be quantified by periodic sampling and determination of the release rate to the river.

At elevated Steam Generator activity levels (approximately 1.0E-4 or above), turbine hall drains may require temporary processing, should effluents via this pathway approach the 31-day dose projection limits per RECS 2.3.2. In this case, water is directed to the Condensate Polishing Facility or otherwise processed prior to release. Activity released via this pathway is determined as follows: '

Turbine Hall ) (F eedwater) (S team Plant SG BlOWdown)

Drain

( Effluent Activity

= Specific

Makeup - Rate to the Activity Rate River 2.1.17 Carbon 14 is released at a rate of .07 curies per GW(e)/yr with an average make up rate of 0.5 gal/min based upon studies performed by the New York State Department of Health. The estimate of Carbon 14 releases are included in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. These estimates are not included in dose calculations for routine releases.

2.1.18 Several normally non-radioactive systems are periodically analyzed for radioactivity. Examples include the condensate polisher regenerant waste tank, the Spent Fuel Pool Auxiliary Heat Exchanger Secondary Cooling System (when in use), and Site Storm Drains, etc. The monitoring program for these type of release points is consistent with the direction set forth in NRC IE Bulletin 80-10 "Contamination of Non-radioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment". Should a system become contaminated, releases will be evaluated and quantified (as either batch or continuous) in accordance with the requirements listed in the RECS and the IPEC 80-10 program, or as defined in Section 2.1.21.

Indian Point 3 aDCM Page 2-4 Revision 18

aDCM Part II - Calculational Methodologies 2.1.19 The liquid waste monitor tanks have an airborne release pathway. The original plant design limited the gases through this pathway by reducing the entrained gases to less than 2E-3 !lCi/ml. When the entrained gas concentration in the monitor tank inlet exceeds 2E-3 !lCi/ml, the noble gas release will be quantified by calculating the difference (in !lCi's) between the gaseous activity added to the tank and the gaseous activity present in the effluent release sample. This difference will be the activity released through the tank vents and is quantified as an airborne release.

2.1.20 Due to the addition of Hafnium control rods in fuel cycle 11, an offsite dose may need to be calculated for Hafnium isotopes in waste pathways. In the absence of site-specific bioaccumulation and dose factors for Hafnium, factors for Zirconium will be used, as suggested in ICRP 30. Should these calculations become necessary, they will be performed per Sections 2.4 and 2.5, and manually added to other totals.

2.1.21 Investigations from the Ground Water Monitoring Program (GWMP) may result in a determination of liquid effluent. A quantification and dose assessment of radioactive groundwater or storm water leaving the site shall be performed at least annually.

This quantification shall include, as a minimum, the source term from samples obtained near the effluent points of each applicable pathway (eg, ground water wells nearest the site boundary), and a determination of release rate and dilution flow. .

Release rates to the river from both the bedrock pathways and collective storm drain pathways are provided from modeling by hydrologists, as determined from 'annual average rainfall, the condition of the surface area over the effected zones, and other studies of ground water movement, per Reference 32.

Dilution flow is directly measured in the Discharge Canal for the Storm Drain component. For groundwater reaching the Hudson via a direct path under the canal, a dilution factor equivalent to a 6-hour half-tidal surge in the effected area of the Hudson applies, as discussed in Reference 33.

Dose calculations are otherwise then completed per Section 2.4, with results included in the annual effluent report, as defined in the GWMP.

2.2 Liquid Effluent Concentrations 2,2.1 This section provides a description of the means that will be used to demonstrate compliance with the RECS, Section 2.3.1.

2.2.2 Compliance with the instantaneous limits of 10CFR20 is achieved by allocating dilution per Section 2.1.7, on a per unit basis. Compliance with 10CFR50 (quarterly and annual limitations) is assured by completing a monthly report which summarizes the time-average releases from the site.

Indian Point 3 aDCM Page 2-5 Revision 18

ODCM Part II - Calculational Methodologies 2.2.3 Each isolated liquid waste tank must be recirculated for at least two tank volumes prior to sampling in order to ensure a representative sample is obtained. A default minimum recirculation time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months may be used for 31 and 32 monitor tank in lieu of the actual calculation:

11750 gals

2 Tank Volumes 39 lJ 4 lJ

. llours ~. llours 100 gal/min Note: Nominal monitor tank pump flow rate is approximately 135 gpm. For conservativism however, 100 gpm is used for the recirculation flow rate, while 150 gpm is used for the discharge flow rate in all release calculations.

2.2.4 For batch releases, the concentration in liquid effluents prior to dilution in the discharge canal is determined by sampling prior to release.

For continuous releases, the concentrations can be determined by either grab sampling (like the batch method), or by direct reading radiation monitor. If the process radiation monitor is utilized, the conversion factor should be verified as appropriate for the mixture being released.

For non-direct reading monitors, the following calculation is used:

C = CF*CR C = Concentration of liquid effluent (uCi/ml) prior to dilution CF = Conversion factor of monitor (uCi/ml per net cpm)

CR = Count rate of monitor (in net cpm) 2.2.5 The final diluted concentration in the canal is determined as follows:

CD = (C) >I< (f)/(F)

Where: CD = Diluted concentration in the discharge canal in uCi/ml C = Pre-dilution liquid concentration in uCi/ml F = Dilution flow in the discharge canal in gal/min f = Release rate of liquid effluent in gal/min 2.2.6 Calculation of Maximum Permissible Concentration in Liquid Effluents

a. This section describes the methodology used to ensure the requirements of section 2.3.1 of the RECS are satisfied. The total discharge canal concentration of radionuclides must be maintained less than those identified by section 2.3.1 of the RECS. The noble gases will be included using the limit 2E-4 uCi/ml as specified in section 2.3.1 of the RECS .

.,;~

Indian Point 3 ODCM Page 2-6 Revision 18

ODCM Part II - Calculational Methodologies These criteria are normally assured by using an Allowed Dilution Concentration (ADC) on each discrete release. This differs from the ECs given in 10CFR20 Appendix B in that, for radioisotopes that do not have gammas greater than 60 kev emitted during decay, default values are included to estimate their contribution. The Allowed Diluted Concentration is derived and calculated as follows:

ADC = MPCWt '" CG or ADO:: MPCWt "'CG or ADO:: MPCWt Totalactivity CG+CB Crr 1+ ICG where: ADC = Allowed diluted concentration in uCilml MPCWt = Maximum permissible concentration in water for all isotopes (beta & gamma), in uCi/ml, as defined in RECS, Section 1.2, as follows:

MPCWt L(C~PCWi i

)

Ci and MPCWi = Concentration and MPCW for each isotope CB = The concentration of the non gamma emitters, in uCi/ml CG = The concentration of the gamma emitters, in uCi/ml

b. A representative sample must be obtained. For batch releases, at least two tank volumes are recirculated after the tank has been isolated to meet these requirements. The minimum recirculation time is determined as follows:

T = 2 (V) / (G) where; T = Minimum recirculation time in min V = Volumes in the tank to be discharged, in gal G = Recirculation rate in gal/min NOTE: As stated in Section 2.2.3, a default recirculation time for 31 and 32 Monitor tanks of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months may be used to simplify routine calculations.

c. After the tank has been sampled, determine the Allowed Diluted Concentration as per step 2.2.6a.

d. Determine if other liquid radioactive discharges are being made from this unit and obtain the radioactive concentration and discharge rate. If another release is occurring, the available dilution flow must be adjusted. This may be performed by allocation or by calculation.

Indian Point 3 ODCM Page 2-7 Revision 18

ODCM Part II - Calculational Methodologies The required dilution flow is calculated as follows:

E= Dr*CG where; ADC Dr =Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm CG and ADC are defined in Section 2.2.6.a

e. Calculate the permissible discharge rate as follows:

ADC*B D Where:

CG D = Permissible discharge rate in gal/min ADC = Calculated and described in Step 2.2.6.a CG = Gamma emitter concentration in )lCi/ml B = Adjusted dilution flow from the unit, in gpm, from Step 2.2.6.d, above, as follows:

B = [ AvailableDilution Flow] - [ Required Dilution Flow for other releases (E)]

Note: With no "other" releases, B simply becomes the Available Dilution Flow.

2.3 Liquid Effluent Dose Calculation Requirements 2.3.1 Section 2.3.2 of the RECS requires that the dose or dose commitment above background to an individual in an unrestricted area from radioactive materials in liquid effluents released from each reactor unit shall be limited:

a) During any calendar quarter: Less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b) During any calendar year: Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

NOTE: If either of the above limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per Section 2.6.A of the RECS.

2.3.2 Section 2.3.3 of the RECS requires that appropriate portions of the radwaste treatment system be used to reduce the radioactive material in liquid waste prior to their discharge when the projected dose due to liquid effluent from each reactor unit when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

Indian Point 3 ODCM Page 2-8 Revision 18

ODCM Part II -' Calculational Methodologies Doses due to liquid release shall be projected at least once per 31 days.

These doses are projected based on the dose methodology in Section 2.4.

or 2.5. The average of previous months' doses is used to project future dose, as follows:

Dose

[ Projection 1= Current Month Dose + Previous months' Dose +/- major I

paMe d

]

number of months used [ I .

evo utlOns The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

2.3.3 Section 2.3.1 of the RECS requires that the concentration of radioactive material released from the site shall be limited to 10 times the concentration values specified in 10 CFR Part 20, Appendix 8, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases the concentration shall be limited to 2E-4 uCi/ml total activity.

2.4 Dose Methodology (Computer Calculation) 2.4.1 NUREG 0133 (Ref. 1, Section 4.3, Pg. 14) states that cumulative dose contributions should consider the dose contribution from the maximum exposed individual's consumption of fish, invertebrates, and potable water as appropriate. The river at IP3NPP is considered to be fresh water when in reality it is a tidal estuary and never completely fresh. Observed average chlorosity at IP3NPP has ranged as high as 2.5 gm/liter or about 13% sea water and 87% fresh water.

Hence, use of the Hudson River for water supply purposes is precluded south of Chelsea (mile point 65) which is the nearest point of potable water supply (approximately 15 miles upstream of IP3NPP). Radionuclide concentrations in the nearest water supply have been calculated (Ref. 2) to be a factor of at least 500 lower than the river water in the Indian Point area.

Due to the absence of a potable water pathway downstream of IP3NPP, RECS 2.3.2 reporting regulations for a 3 mile downstream limit do not apply. Exposures from ingestion of drinking water is therefore negligible.

Based on these factors, potable water consumption is not considered to be a pathway at IP3NPP. Thus, at IP3NPP, the cumulative dose considers only the dose contributions from the maximum exposed individuals consumption of fish and invertebrates. Tables of dose factors for three age groups were developed as per Section 2.4.3 and are included as Tables 2-1,2-2, and 2-3. (Infant dose factors are 0 and are not included).

Indian Point 3 ODCM Page 2-9 Revision 18

aDCM Part II - Calculational Methodologies 2.4.2 The relationships and methods that form the calculational base for dose accounting for the liquid effluent pathway are described in this section.

These relationships can be used to meet the calculational requirements of Section 2.3.1. The cumulative dose factors (AiT) are calculated in Section 2.4.3. The following equation is generally applicable and can be used for any number of isotopes released over any time period.

m n D(T) =I [Air *I (dtk)(Cik)(Fk )]

i=! k=!

Where:

m = The total number of isotopes released.

O(T) = The liquid effluent cumulative dose commitment from nuclides to the total body or any organ, T, for the time period k, in mrem.

dtk = The length of the time period, k over which Cik and Fk are averaged for all liquid releases, in hours. (This can be individual release durations summed, or an entire period duration, defined with each application of this equation.)

Cik = The undiluted liquid effluent average concentration of nuclide, i, in uCi/ml, during time period dtk from any liquid release.

n = The total number of releases considered.

AT = The site related ingestion dose commitment factor to the total body or any organ for each IP3NPP identified principal gamma and beta emitter listed in Table 2-1, 2-2, and 2-3, in mrem-ml per hr-uCi.

Fk = The total dilution factor for Clk during any liquid effluent releases; defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters, times an applicable factor.

The term C ik represents the total undiluted concentration of radioactive material in liquid waste at the release point as determined by the radioactive liquid waste sampling and analysis program as contained in the RECS. All dilution factors beyond the sample point are included in the Fk and AT terms.

The term Fk is a total dilution factor and is determined as folfows:

F = Liquid Radioact ive Waste Flow k [Discharge Structure Exit Flow

Applicable Factor]

Indian Point 3 aDCM Page 2-10 Revision 18

aDCM Part II - Calculational Methodologies The liquid radioactive waste flow is the flow from all continuous and batch radioactive effluent releases specified in the RECS from all liquid radioactive waste management systems. The discharge structure exit flow is the average flow during disposal from the discharge structure release point into the receiving body of water. Based on studies by New York University Medical Center (ref. 14 page 7), the appropriate "Applicable Factor" (also known as the "near field dilution factor") is 5.

Fk is first determined with dilution flow concurrent with applicable releases, for permitting requirements (see Section 2.2). Doses are later recalculated (for the entire site) on a quarterly basis to determine actual doses from quarterly total site dilution volume. This method allows both an immediate and accurate long-term assessment of radiation dose resulting from liquid effluent releases at Indian Point.

2.4.3 Dose Factor for Liquid Effluent Calculations The equation for dose from liquid effluents requires the use of a dose factor AiTfor each nuclide, i, which embodies the dose factors, pathway transfer factor, pathway usage factors, and dilution factors for the points of pathway origin.

IPEC follows the guidance of NUREG 0133 and has calculated Air for the total body and critical organ of the maximum exposed individual (e.g. the adult). All the factors needed in the equation were obtained from Regulatory Guide 1.109 with the exception of the fish and invertebrate bioaccumulation factors (BFi and Bl i) for Cesium, Niobium, Silver, and Antimony, which were determined locally (References 2, 12, 13, and 25).

For Cesium, a site specific factor of 224 was used instead of the 2,000 presented in Table A-1 of the Regulatory Guide for fish. Similarly, a factor of 224 was used for invertebrates instead of the Regulatory Guide value of 1000. For Silver, the fish and invertebrate factors are 2.3 and 3300, respectively. For Niobium. the fish and invertebrate factors are 300 and 100 respectively. For Antimony, the fish and invertebrate factors are 1 and 300 respectively. The justification for these substitutions is discussed in Section 2.6. The summary dose factor is as follows:

AiT = K[(UF)BF; + (UI)BI;lDJ Where:

Air = Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, mrem/hr per J.1Ci/ml.

K = Units conversion factor, 114155 = (1 E6pCi/uCi) * (1 E3mllkg) 8760 hr/yr Indian Point 3 aDCM Page 2-11 Revision 18

ODCM Part \I - Calculational Methodologies UF = kg/yr fish consumption from Table E-5 of Reg Guide 1.109:

(

21 Adult 6.9 Child 16 Teen 0 Infant BFi = Fresh Water Fish Bioaccumulation factor for nuclide, i, in pCi/kg per pCill from Table A-1 of Regulatory Guide 1.109.

UI = kg/yr invertebrate consumption from Table E-S of Regulatory Guide 1.109:

S.O Adult 1.7 Child 3.8 Teen o Infant Bli = Salt Water Invertebrates Bioaccumulation factor for nuclide, i, in pCi/kg per pCill from Table A-1 of Regulatory Guide 1.109.

DFi = Dose conversion factor for nuclide i, for age groups in pre-selected organs, T, in mrem/pCi. from Tables E-11, 12 & 13 of Regulatory Guide 1.109.

IP3NPP has compiled Arr factors for 3 age groups and various organs for the maximum exposed individual. These are included as Table 2-1, 2-2, and 2-3. For completeness, this table includes all isotopes found in Reg Guide 1.109, however. several isotopes listed are not routinely

( identified at IP-3. In addition, the values for Antimony, Silver, Cesium,

'. and Niobium are site specific as previously discussed.

2.S Backup Calculation Methodology Note: These methods provide backup calculations identical to those in Section 2.4.

2.S.1 An alternate computer method which completely complies with Section 2.4 should be used when the primary computer system is inoperable.

2.S.2 Hand Calculations which completely comply with Section 2.4 can be employed if the primary and secondary computer codes are inoperable.

Because they are time consuming and subject to calculational errors.

procedural guidance in the actual flow of calculations should be used to maintain a standard format. These procedures are also used for periodic benchmark tests of the computer codes.

2.6 Site Specific Bio-Accumulation & Dose Factors 2.6.1 As stated in Section 2.4.3 the bioaccumulation factor (BFi) for Cesium in fish is assumed to be 224 instead of the 2000 listed in Regulatory Guide 1.109 (Ref. 3). Similarly, the bioaccumulation factor for invertebrates is 224. This is based on the fact that the Hudson River at IP3NPP is not completely fresh, the Bioaccumulation Factor for salt water is 40 (Ref. 2),

and that the behavior of Cesium in the Hudson is a complex phenomenon.

Indian Point 3 aDCM Page 2-12 Revision 18

ODCM Partdl-Calculational Methodologies The NYU Study (Ref. 2) shows that Cesium concentrations in fish are

( regulated at a relatively constant value independent of the concentration of Cesium in water, and the bioaccumulation factors are thus inversely proportional to the water concentration of Cesium. This explains the lower bioaccumulation factor for Cesium reported by numerous investigators for salt water fish as opposed to fresh water fish because of the higher stable Cesium content of sea water. The NYU Report states that water at Indian Point has a dissolved Cesium concentration which is much higher than would be expected from simple mixing between sea.water and fresh water and postulates that these higher concentrations result from leaching of Cesium from bottom sediment by saline water.

Use of the bioaccumulation factors of Regulatory Guide 1.109 for,a fresh water site will thus substantially overestimate fish ingestion doses because no account is taken of the phenomena just discussed. However, radio-cesium concentrations in fish may still be estimated through the use of a bioaccumulation factor, provided that this factor is determined from the body of water of interest. This factor has been estimated (Ref. 12, page

33) to be about 224 for the flesh of indigenous fish caught in the Indian Point area. In contrast, the Cesium fresh water bioaccumulation factor presented by Regulatory Guide 1.109 for fish is 2000.

Fish ingestion doses would therefore be overestimated by a factor of 13 if the Regulatory Guide values were used.

r"...*.. Similarly for invertebrates, the site specific bioaccumulation factor of 224 is used. This is larger than the value of 25 given in Reg Guide 1.109 for salt water invertebrates.

A second conservatism in the NRC model concerns the location at which the concentrations in the river of the discharged Cesium are evaluated.

Use of this model implies that these fish have grown directly in such a location prior to being caught, which is unrealistic and adds about a factor of five in conservation. This conservatism remains in the calculation, thus the use of the NYU (Ref. 12) bioaccumulation factor is justifiable since this remains as a conservative calculation.

2.6.2 No bioaccumulation factor for Silver is listed in Rev. 1 of Regulatory Guide 1.109, Table A-1. The values of 2.3 and 5000 for fish and invertebrates were obtained from ORNL-4992 (sponsored by ERDA 660, Ref. 25) and are included in the ODCM in the interests of increased accuracy since Ag-110m is a potential component of IP3NPP liquid releases.

2.6.3 International Atomic Energy Agency Report No. 57 provides data more recent than that presented in Regulatory Guide 1.109 for niobium bioaccumulation factors. The factor in the Regulatory Guide appears to be substantially over-conservative and, therefore, the more recent IAEA information is incorporated into the dose calculation methodology for liquid releases of radio-niobium. The values from Table XVII of IAEA No. 57 are 300 and 100 for freshwater fish and marine invertebrates respectively and are incorporated into this ODCM.

Indian Point 3 ODCM Page 2-13 Revision 18

aDeM part II - Calculational Methodologies 2.6.4 Antimony isotopes are not listed in Reg. Guide 1.109. As for Niobium above, IAEA Report No. 57 was used to provide bioaccumulation factors for the Antimony isotopes in Table 2-1. Dose factors were calculated for Antimony as per Reference #13.

2.6.5 In summary, with the exception of the bioaccumulation factors discussed above, all remaining factors are as follows: fish factors are for fresh water and invertebrate factors are for salt water.

Indian Point 3 aDCM Page 2-14 Revision 18

aDCM Part II - Calculational Methodologies

/.

Table 2 - 1 Site. Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.82E-01 2.82E-01 2.82E-01 2.82E-Ol 2.82E-Ol 2.82E-01 BE-7 3.29E-01 7.45E-01 3.69E-Ol O.OOE+OO 7.83E-01 O.OOE+OO 1.28E+02 NA-24 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 P-32 4.96E+07 3.08E+06 1.92E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.57E+06 CR-51 O.OOE+OO O.OOE+OO 4.31E+00 2.58E+00 9.50E-Ol 5.72E+00 1. 08E+03 MN-54 O.OOE+OO 5.43E+03 1. 04E+03 O.OOE+OO 1.61E+03 O.OOE+OO 1.66E+04 MN-56 O.OOE+OO 1.37E+02 2.42E+Ol O.OOE+OO 1.73£+02 O.OOE+OO 4.36E+03 FE-55 3.21E+04 2.21E+04 5.16E+03 O.OOE+OO O.OOE+OO 1.24E+04' 1.27E+04 FE-59 5.06E+04 1.19E+05 4.56E+04 O.OOE+OO O.OOE+OO 3.32E+04 3.96E+05 CO-58 O.OOE+OO 5.15E+02 1.15E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+04 CO-60 O.OOE+OO 1.48E+03 3.26E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.78E+04 NI-63 4.97E+04 3. 45E+03 . 1.67E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.19E+02 NI-65 2.02E+02 2.62E+01 1.20E+01 O.OOE+OO O.OOE+OO O.OOE+OO 6.65E+02 CU-64 O.OOE+OO 9.08E+01 4.26E+01 O.OOE+OO 2.29E+02 O.OOE+OO 7.74E+03 ZN-65 1. 61E+05 5.13E+05 2.32E+05 O.OOE+OO 3.43E+05 O.OOE+OO 3.23E+05 ZN-69 3.43E+02 6.57E+02 4.57E+01 O.OOE+OO 4.27E+02 O.OOE+OO 9.87E+01 8R-83 O.OOE+OO O.OOE+OO 4.05E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.84E+01 BR-84 O.OOE+OO O.OOE+OO 5.25E+01 O.OOE+OO O.OOE+OO O.OOE+OO 4.13E-04 BR-85 O.OOE+OO O.OOE+OO 2.16E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.01E+05 4.72E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.00E+04 RB-88 O.OOE+OO 2.91E+02 1. 54E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-09 RB-89 O.OOE+OO 1.93E+02 1.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1. 12E-11 SR-89 2.57E+04 O.OOE+OO 7.37E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.12E+03 SR-90 6.32E+05 O.OOE+OO 1.55E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.82E+04 SR-91 4.72E+02 O.OOE+OO 1.91E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.25E+03 SR-92 1.79E+02 O.OOE+OO 7.75E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 Y-90 6.07E+00 O.OOE+OO 1.63E-01 O.OOE+OO O.OOE+OO O.OOE+OO 6.43E+04 Y-91M 5.73E-02 O.OOE+OO 2.22E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.68E-01 Y-91 8.89E+01 O.OOE+OO 2.38E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.89E+04 Y-92 5.33E-Ol O.OOE+OO 1. 56E-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.33E+03 Y-93 1.69E+00 O.OOE+OO 4.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.36E+04 ZR-95 1.63E+00 5.22E-01 3.54E-01 O.OOE+OO 8.20E-01 O.OOE+OO 1.66E+03 ZR-97 9.00E-02 1.82E-02 8.30E-03 O.OOE+OO 2.74E-02 O.OOE+OO 5.63E+03 NB-95 4.83E+00 2.69E+00 1.44E+00 O.OOE+OO 2.65E+00 O.OOE+OO 1.63E+04 MO-99 O.OOE+OO 1.28E+02 2.43E+01 O.OOE+OO 2.90E+02 O.OOE+OO 2.97E+02 TC-99M 1.59E-02 4.50E-02 5.73E-01 O.OOE+OO 6.84E-01 2.21E-02 2.66E+01 TC-101 1.64E-02 2.36E-02 2.32E-01 O.OOE+OO 4.25E-01 1.21E-02 7.09E-14 RU-I03 1.10E+02 O.OOE+OO 4.74E+01 O.OOE+OO 4.20E+02 O.OOE+OO 1.28E+04 RU-105 9.16E+00 O.OOE+OO 3.62E+00 O.OOE+OO 1.18E+02 O.OOE+OO 5.60E+03 RU-106 1. 64E+03 O.OOE+OO 2.07E+02 O.OOE+OO 3.16E+03 O.OOE+OO 1.06E+05 AG-llOM 4.58E+02 4.23E+02 2.51E+02 O.OOE+OO 8.32E+02 O.OOE+OO 1. 73E+05 58-122 3.47E+01 7.99£-01 1.20E+01 5.38£-01 O.OOE+OO 2.08E+01 1.32E+04 SB-124 4.86E+02 9.20E+00 1.91E+02 1.18E+00 O.OOE+OO 3.79E+02 1.38E+04 5B-125 3.11E+02 3.47E+00 7.40E+01 3.l6E-01 O.OOE+OO 2.40E+02 3.42E+03 Indian Point 3 aDCM Page 2-15 Revision 18

Indian Point 3 aDeM Page 2-16 Revision 18 aDCM Part 1\ - Calculational Methodologies Table 2 - 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 BE-7 3.58E-01 8.02E-01 4.01E-01 O.OOE+OO 8.50E-01 O.OOE+OO 9.76E+01 NA-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 P-32 5.40E+07 3.35E+06 2.09E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.54E+06 CR-51 O.OOE+OO O.OOE+OO 4.44E+00 2.47E+00 9.73E-01 6.34E+00 7.46E+02 MN-54 O.OOE+OO 5.33E+03 1.06E+03 O.OOE+OO 1.59E+03 O.OOE+OO 1. 09E+04 MN-56 O.OOE+OO 1.43E+02 2.54E+01 O.OOE+OO 1.81E+02 O.OOE+OO 9.40E+03 FE-55 3.35E+04 2.37E+04 5.54E+03 O.OOE+OO O.OOE+OO 1. 51E+04 1.03E+04 FE-59 5.20E+04 1. 21E+05 4.69E+04 O.OOE+OO O.OOE+OO 3.83E+04 2.87E+05 CO-58 O.OOE+OO 5.10E+02 1.18E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.04E+03 CO-60 O.OOE+OO 1. 48E+03 3.32E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E+04 NI-63 5.15E+04 3.64E+03 1. 75E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E+02 NI-65 2.18E+02 2.79E+01 1. 27E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+03 CU-64 O.OOE+OO 9.53E+01 4.48E+01 O.OOE+OO 2.41E+02 O.OOE+OO 7.39E+03 ZN-65 1.46E+05 5.07E+05 2.36E+05 O.OOE+OO 3.24£+05 O.OOE+OO 2.15E+05 ZN-69 3.73E+02 7.10E+02 4.97E+01 O.OOE+OO 4.64E+02 O.OOE+OO 1.31E+03 r:' BR-83 O.OOE+OO O.OOE+OO 4.41E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I"~ BR-84 O.OOE+OO O.OOE+OO 5.55E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 2.34£+00 0.00£+00 0.00£+00 O.OOE+OO 0.00£+00 RB-86 O.OOE+OO 1.09E+05 5.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 RB-88 O.OOE+OO 3.12E+02 1. 66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-05 RB-89 O.OOE+OO 2.01E+02 1.42£+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-07 SR-89 2.79E+04 O.OOE+OO 8.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.33£+03 SR-90 5.27E+05 O.OOE+OO 1.30E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E+04 SR-91 5.12E+02 O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.32£+03 SR-92 1.94E+02 O.OOE+OO 8.25E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.93E+03 Y-90 6.57E+00 O.OOE+OO 1. 77E-01 O.OOE+OO 0.00£+00 O.OOE+OO 5.42E+04 Y-91M 6.18E-02 O.OOE+OO 2.36E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+00 Y-91 9.64E+01 O.OOE+OO 2.58E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.95E+04 Y-92 5.80E-01 O.OOE+OO 1.68E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+04 Y-93 1.84E+00 O.OOE+OO 5.03E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.61E+04 ZR-95 1.68E+00 5.29£-01 3.64£-01 O.OOE+OO 7.78E-01 O.OOE+OO 1. 22E+03 ZR-97 9.65E-02 1.91E-02 8.80E-03 O.OOE+OO 2.90E-02 O.OOE+OO 5.17E+03 NB-95 4.86E+00 2.70E+00 1.48E+00 O.OOE+OO 2.61E+00 O.OOE+OO 1. 15E+04 MO-99 O.OOE+OO 1.36E+02 2.60E+01 O.OOE+OO 3.12E+02 O.OOE+OO 2.44E+02 TC-99M 1.63E-02 4.55E-02 5.89E-01 O.OOE+OO 6.77E-01 2.52E-02 2.98E+01 TC-101 1.77E-02 2.51E-02 2.47E-01 O.OOE+OO 4.55E-01 1.53E-02 4.30E-09 RU-103 1.15E+02 O.OOE+OO 4.93E+01 O.OOE+OO 4.06E+02 O.OOE+OO 9.63E+03 RU-105 9.85E+00 O.OOE+OO 3.82E+00 O.OOE+OO 1.24E+02 O.OOE+OO 7.96E+03 RU-106 1.77E+03 O.OOE+OO 2.23E+02 O.OOE+OO 3.42E+03 O.OOE+OO 8.50E+04 AG-llOM 4.45E+02 4.22E+02 2.56E+02 O.OOE+OO 8.04E+02 O.OOE+OO 1.18E+05 SB-122 4.35E+01 8.47E-01 1.27E+01 5.53E-01 O.OOE+OO 2.72E+01 9.13E+03 SB-124 5.09E+02 9.40E+00 1.99E+02 1. 16E+00 O.OOE+OO 4.45E+02 1.03E+04 S8-125 3.27E+02 3.58E+00 7.64E+01 3.11E-01 O.OOE+OO 2.85E+02 2.53E+03 Indian Point 3 aDCM Page 2-17 Revision 18

aDCM Part II - Calculational Methodologies

/'

,I..*. :

Table 2 - 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCilm1 ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.96E+03 1. 07E+03 3.96E+02 8.28E+02 O.OOE+OO O.OOE+OO 8.75E+03 TE-127M 7.48E+03 2.65E+03 8.90E+02 1.78E+03 3.03E+04 O.OOE+OO 1.87E+04 TE-127 1.22E+02 4.33E+01 2.63E+01 8.44E+01 4.95E+02 O.OOE+OO 9.44E+03 TE-129M 1.26E+04 4.68E+03 2.00E+03 4.07E+03 5.28E+04 O.OOE+OO 4.74E+04 TE-129 3.47E+01 1.29E+01 8.44E+00 2.48E+01 1.46E+02 O.OOE+OO 1.90E+02 TE-131M 1.89E+03 9.06E+02 7.55E+02 1.36E+03 9.44E+03 O.OOE+OO 7.27E+04 TE-131 2.16E+01 8.90E+00 6.75E+00 1.66E+01 9.44E+01 O.OOE+OO 1.77E+00 TE-132 2.70E+03 1.71E+03 1. 61E+03 1. 80E+03 1.64E+04 O.OOE+OO 5.42E+04 1-130 5.06E+01 1.46E+02 5.84E+01 1.19E+04 2.25E+02 O.OOE+OO 1.12E+02 1-131 2.87E+02 4.02E+02 2.16E+02 1.17E+05 6.92E+02 O.OOE+OO 7.95E+01 I-132 1.37E+Ol 3.58E+01 1.29E+01 1.21E+03 5.64E+01 O.OOE+OO 1.56E+01 I-133 9.87E+01 1.67E+02 5.11E+01 2.34E+04 2.94E+02 O.OOE+OO 1.27E+02 1-134 7.17E+00 1.90E+01 6.82E+00 3.17E+02 2.99E+01 O.OOE+OO 2.50E-01 I-135 2.99E+01 7.71E+01 2.86E+01 4.96E+03 1.22E+02 O;OOE+OO 8.54E+01 CS-134 4.24E+04 9.97E+04 4.63E+04 O.OOE+OO 3.17E+04 1.21E+04 1.24E+03 CS-136 4.35E+03 1. 71E+04 1.15E+04 O.OOE+OO 9.32E+03 1. 47E+03 1.38E+03

... CS-137 5.67E+04 7.54E+04 2.63E+04 O.OOE+OO 2.57E+04 9.97E+03 1.07E+03

( C8-138 3.93E+01 7.54E+Ol 3.77E+01 O.OOE+OO 5.57E+Ol 6.48E+00 3.42E-02

\ ...........

BA-139 7.05E+00 4.96E-03 2.05E-01 O.OOE+OO 4.67E-03 3.42E-03 6.28E+01 BA-140 1.44E+03 1.76E+00 9.28E+01 O.OOE+OO 5.98E-01 1.19E+00 2.22E+03 BA-141 3.40E+00 2.54E-03 1.14E-01 O.OOE+OO 2.36E-03 1.74E-03 7.25E-06 BA-l42 1.52E+00 1.52E-03 9.33E-02 O.OOE+OO 1.28E-03 1.01E-03 4.65E-12 LA-14 0 1. 67E+00 8.20E-01 2.18E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+04 LA-l42 8.58E-02 3.81E-02 9.49E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+03 CE-141 3.49E+00 2.33E:l-00 2.67E-01 O.OOE+OO 1.10E+00 O.OOE+OO 6.66E+03 CE-143 6.16E-01 4.48E+02 5.01E-02 O.OOE+OO 2.01E-01 O.OOE+OO 1.35E+04 CE-144 1.82E+02 7.55E+Ol 9.80E+00 O.OOE+OO 4.51E+01 O.OOE+OO 4.59E+04 PR-143 6.28E+00 2.51E+00 3.13E-01 O.OOE+OO 1.46E+00 O.OOE+OO 2.07E+04 PR-144 2.06E-02 8.44E-03 1. 05E-03 O.OOE+OO 4.84E-03 O.OOE+OO 2.27E-05 NO-l47 4.50E+00 4.89E+00 2.93E-01 O.OOE+OO 2.87E+00 O.OOE+OO 1.76E+04 W-187 3.22E+02 2.62E+02 9.19E+01 O.OOE+OO O.OOE+OO O.OOE+OO 7.10E+04 NP-239 3.98E-02 3.75E-03 2.08E-03 O.OOE+OO 1.18E-02 O.OOE+OO 6.03E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1. 25E+02 2.10E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+03 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 4.36E-02 1.08E-02 3.95E-03 O.OOE+OO 1.27E-02 O.OOE+OO 2.58E+02 CO-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SN-1l3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 3.46E+01 2.22E+01 2.32E+01 2.84E+01 2.12E+02 O.OOE+OO 1. 28E+00 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 2-18 Revision 18

aDCM Part II - Calculational Methodologies Table 2 - 3 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.81E-01 1. 81E-01 1. 81E-Ol 1. 81E-01 1.81E-01 1. 81E-01 BE-7 4.77E-01 8.08E-01 5.33E-01 O.OOE+OO 7.96E-01 O.OOE+OO 4.52E+01 NA-24 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 P-32 6.98E+07 3.27E+06 2.69E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1. 93E+06 CR-51 O.OOE+OO O.OOE+OO 4.86E+00 2.70E+00 7.37E-01 4.92E+00 2.58E+02 MN-54 O.OOE+OO 4.20E+03 1.12E+03 O.OOE+OO 1.18E+03 O.OOE+OO 3.53E+03 MN-56 O.OOE+OO 1.31E+02 2.96E+01 O.OOE+OO 1.59E+02 O.OOE+OO 1.90E+04 FE-55 4.55E+04 2.42E+04 7.48E+03 O.OOE+OO O.OOE+OO 1.37E+04 4.47E+03 FE-59 6.53E+04 1.06E+05 5.27E+04 O.OOE+OO (').OOE+OO 3.07E+04 1.10E+05 CO-58 O.OOE+OO 4.20E+02 1.29E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+03 CO-60 O.OOE+OO 1.23E+03 3.64E+03 O.OOE+OO O.OOE+OO O.OOE+OO 6.84E+03 NI-63 6.85E+04 3.67E+03 2.33E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.47E+02 NI-65 2.83E+02 2.66E+01 1.55E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.26E+03 CU-64 O.OOE+OO 9.05E+01 5.47E+01 O.OOE+OO 2.19E+02 O.OOE+OO 4.25E+03 ZN-65 1.55E+05 4.12E+05 2.56E+05 O.OOE+OO 2.59E+05 O.OOE+OO 7.23£+04 ZN-69 4.94E+02 7.14E+02 6.60E+01 O.OOE+OO 4.33E+02 O.OOE+OO 4.50E+04 BR-83 O.OOE+OO O.OOE+OO 5.67E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

( BR-84 O.OOE+OO O.OOE+OO

\ 6.56E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 3.02E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.06E+05 6.50E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.80E+03 RB-88 O.OOE+OO 3.00E+02 2.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1. 47E+01 RB-89 O.OOE+OO 1.85E+02 1.64E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+00 SR-89 3.63E+04 O.OOE+OO '1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1. 41E+03 8R-90 4.68E+05 O.OOE+OO 1.19E+05 O.OOE+OO O.OOE+OO O.OOE+OO 6.30E+03 SR-91 6.60E+02 O.OOE+OO 2.49E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E+03 SR-92 2.48E+02 O.OOE+OO 9.96E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+03 Y-90 8.79E+00 O.OOE+OO 2.35E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+04 Y-91M 8.17E-02 O.OOE+OO 2.97E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+02 Y-91 1.29E+02 O.OOE+OO 3.44E+00 O.OOE+OO O.OOE+OO O.OOE+OO 1. 71E+04 Y-92 7.70E-01 O.OOE+OO 2.20E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+04 Y-93 2.44E+00 O.OOE+OO 6.69E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+04 ZR-95 2.10E+00 4.62E-01 4.11E-01 O.OOE+OO 6.62E-01 O.OOE+OO 4.82E+02 ZR-97 1.27E-01 1.83E-02 1. 08E-Q2 O.OOE+OO 2.63E-02 O.OOE+OO 2.77E+03 NB-95 5.75E+00 2.24E+00 1.60E+00 O.OOE+OO 2.10E+00 O.OOE+OO 4.14E+03 MO-99 O.OOE+OO 1.31E+02 3.23E+01 O.OOE+OO 2.79E+02 O.OOE+OO 1.08E+02 TC-99M 1.99E-02 3.89E-02 6.46E-01 O.OOE+OO 5.66E-01 1.98E-02 2.22E+01 TC-101 2.30E-02 2.41E-02 3.06E-Ol O.OOE+OO 4.11E-01 1.27E-02 7.66E-02 RU-103 1.48E+02 O.OOE+OO 5.67E+01 O.OOE+OO 3.72E+02 O.OOE+OO 3.82E+03 RU-105 1.30E+01 O.OOE+OO 4.73E+00 O.OOE+OO 1.15E+02 O.OOE+OO 8.50E+03 RU-106 2.36E+03 O.OOE+OO 2.95E+02 O.OOE+OO 3.19E+03 O.OOE+OO 3.68E+04 AG-ll0M 5.24E+02 3.54E+02 2.83E+02 O.OOE+OO 6.59E+02 O.OOE+OO 4.21E+04 8B-122 5.80E+01 8.56E-01 1. 70E+01 7.43E-01 O.OOE+OO 2.36E+01 4.46E+03 SB-124 6.55E+02 8.50E+00 2.29E+02 1.44E+00 O.OOE+OO 3.63E+02 4.09E+03 8B-125 4.22E+02 3.25E+00 8.85E+01 3.91E-01 O.OOE+OO 2.35E+02 1. 01E+03 Indian Point 3 aDCM Page 2-19 Revision 18

ODeM Part II - Calculational Methodologies Table 2 - 3 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 3.81E+03 1.03E+03 5.08E+02 1.07E+03 O.OOE+OO O.OOE+OO 3.68E+03 TE-127M 9'. 67E+03 2.60E+03 1.15E+03 2.31E+03 2.76E+04 O.OOE+OO 7.83E+03 TE-127 1.58E+02 4.25E+01 3.38E+01 1.09E+02 4.48E+02 O.OOE+OO 6.15E+03 TE-129M 1.63E+04 4.55E+03 2.53E+03 5.25E+03 4.78E+04 O.OOE+OO 1.99E+04 TE-129 4.48E+01 1.25E+01 1. 06E+01 3.20E+01 1. 31E+02 O.OOE+OO 2.79E+03 TE-131M 2.41E+03 8.33E+02 8.86E+02 1.71E+03 8.06E+03 O.OOE+OO 3.38E+04 TE-131 2.78E+01 8.46E+00 8.26E+00 2.12E+01 8.40E+01 O.OOE+OO 1.46E+02 TE-132 3.38E+03 1. 50E+03 1.81E+03 2.18E+03 1. 39E+04 O.OOE+OO 1.51E+04 1-130 6.28E+01 1. 27E+02 6.54E+01 1.40E+04 1. 90E+02 O.OOE+OO 5.94E+01 1-131 3.70E+02 3.72E+02 2.12E+02 1.23E+05 6. 11E+02 O.OOE+OO 3.31E+01 1-132 1. 72E+01 3.16E+01 1.45E+01 1. 47E+03 4.84E+01 O.OOE+OO 3.72E+01 1-133 1. 27E+02 1.58E+02 5.96E+01 2.93E+04 2.63E+02 O.OOE+OO 6.35E+01 1-134 9.02E+00 1.67E+01 7.70E+00 3.85E+02 2.56E+01 O.OOE+OO 1.11E+01 1-135 3.77E+01 6.78E+01 3.21E+01 6.00E+03 1. 04E+02 O.OOE+OO 5.16E+01 CS-134 5.15E+04 8.44E+04 1.78E+04 O.OOE+OO 2.62E+04 9.39E+03 4.55E+02 CS-136 5.17E+03 1.42E+04 9.19E+03 O.OOE+OO 7.56E+03 1.13E+03 4.99E+02 CS-137 7.19E+04 6.88E+04 1.02E+04 O.OOE+OO 2.24E+04 8.07E+03 4.31E+02 CS-138 5.01E+01 6.97E+01 4.42E+01 O.OOE+OO 4.90E+01 5.28E+00 3.21E+01 BA-139 9.34E+00 4.99E-03 2.71E-01 O.OOE+OO 4.35E-03 2.93E-03 5.39E+02 BA-140 1.87E+03 1.64E+00 1.09E+02 O.OOE+OO 5.35E-01 I

9.79E-01 9.50E+02 BA-l41 4.51E+00 2.53E-03 1. 47E-01 O.OOE+OO 2.19E-03 1.48E-02 2.57E+00 BA-l42 1.97E+00 1.42E-03 1.10E-0,1 O.OOE+OO 1.15E-03 8.35E-04 2.57E-02 LA-14 0 2.16E+00 7.55E-01 2.54E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+04 LA-142 1.12E-01 3.57E-02 1.12E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+03 CE-141 4.65E+00 2.32E+00 3.45E-01 O.OOE+OO 1.02E+00 O.OOE+OO 2.90E+03 CE-143 8.19E-01 4.44E+02 6.44E-02 O.OOE+OO 1. 86E-01 O.OOE+OO 6.51E+03 CE-144 2.44E+02 7.64E+01 1. 30E+01 O.OOE+OO 4.23E+01 O.OOE+OO 1.99E+04 PR-143 8.40E+00 2.52E+00 4.17E-01 O.OOE+OO 1.37E+00 O.OOE+OO 9.06E+03 PR-144 2.76E-02 8.53E-03 1. 39E-03 O.OOE+OO 4.51E-03 O.OOE+OO 1.84E+Ol ND-147 5.96E+00 4.83E+00 3.74E-01 O.OOE+OO 2.65E+00 O.OOE+OO 7.65E+03 W-187 4.08E+02 2.42E+02 1.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.40E+04 NP-239 5.15E-02 3.70E-03 2.60E-03 O.OOE+OO 1.07E-02 O.OOE+OO 2.74E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.15E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.43E+02 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 5.55E-02 1.00E-02 4.68E-03 O.OOE+OO 1.11E-02 O.OOE+OO 3.09E+03 CD-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 0.00£+00 SN-1l3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

\ BA-133 O.OOE+OO O.OOE+OO O.OOE,..OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 4.31E+01 1.94E+01 2.59E+01 3.41E+01 1.80E+02 O.OOE+OO 1.97E+02 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO, HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 ODCM Page 2-20 Revision 18

ODCM Part \I - Calculational Methodologies Table 2-4 Bio-Accumulation Factors for Liquid Effluent Isotopes (pCi/kg per pCi/liter)

Freshwater Saltwater Freshwater Saltwater ISOTOPE Fish Invertebrates 1 ISOTOPE Fish Invertebrates BFi BIi 1 BFi BIi

1------------------------------------

H-3 9.000E-01 9.300E-01 TE-125M 4.000E+02 1.000E+02 BE-7 2.000E+00 2.000E+02 TE-127M 4.000E+02 1.000E+02 NA-24 1.000E+02 1.900E-01 TE-127 4.000E+02 1.000E+02 P-32 1.000E+05 3.000E+04 .TE-129M 4.000E+02 1.000E+02 CR-51 2.000E+02 2.000E+03 TE-129 4.000E+02 1.000E+02 MN-54 4.000E+02 4.000E+02 TE-131M 4.000E+02 1.000E+02 MN-56 4.000E+02 4.000E+02 TE-l31 4.000E+02 1.000E+02 FE-55 1.000E+02 2.000E+04 TE-132 4.000E+02 1.000E+02 FE-59 1.000E+02 2.000E+04 I-l30 1.500E+01 5.000E+01 CO-58 5.000E+01 1.000E+03 I-l31 1.500E+01 5.000E+01 CO-60 5.000E+01 1.000E+03 1-132 1.500E+01 5.000E+01 NI-63 1.000E+02 2.500E+02 1-133 1.500E+01 5.000E+01 NI-65 1.000E+02 2.500E+02 1-134 1.500E+01 5.000E+01 CU-64 5.000E+01 1.700E+03 1-135 1.500E+01 5.000E+01 ZN-65 2.000E+03 5.000E+04 CS-134 2.240E+02 2.240E+02 ZN-69 2.000E+03 5.000E+04 CS-l36 2.240E+02 2.240E+02 BR-83 4.200E+02 3.100E+00 CS-137 2.240E+02 2.240E+02 BR-84 4.200E+02 3.100E+00 CS-l38 2.240E+02 2.240E+02 BR-85 4.200E+02 3.100E+00 BA-139 4.000E+00 1.000E+02 RB-86 2.000E+03 1.700E+Ol BA-140 4.000E+00 1.000E+02 RB-88 2.000E+03 1. 700E+01 BA-141 4.000E+00 1.000E+02 RB-89 2.000E+03 1.700E+01 BA-142 4.000E+00 1.000E+02 SR-89 3.000E+01 2.000E+01 LA-140 2.500E+01 1.000E+03 SR-90 3.000E+01 2.000E+01 LA-142 2.500E+01 1.000E+03 3R-91 3.000E+01 2.000E+01 CE-141 1.000E+00 6.000E+02 SR-92 3.000E+01 2.000E+01 CE-l43 1.000E+00 6.000E+02 Y-90 2.500E+01 1.000E+03 CE-144 1.000E+00 6.000E+02 Y-91M 2.500E+01 1.000E+03 PR-143 2.500E+01 1.000E+03 Y-91 2.500E+01 1.000E+03 PR-144 2.500E+01 1.000E+03 Y-92 2.500E+01 1. 000E+03 ND-14 7 2.500E+01 1.000E+03 Y-93 2.500E+01 1.000E+03 W-187 1.200E+03 3.000E+01 ZR-95 3.300E+00 8.000E+01 NP-239 1.000E+01 1.000E+01 ZR-97 3.300E+00 8.000E+01 K-40 O.OOOE+OO O.OOOE+OO NB-95 3.000E+02 1.000E+02 CO-57 5.000E+01 1.000E+03 MO-99 1.000E+01 1.000E+01 SR-85 O.OOOE+OO O.OOOE+OO TC-99M 1.500E+01 5.000E+01 Y-88 O.OOOE+OO O.OOOE+OO TC-101 1.500E+01 5.000E+01 NB-94 3.000E+02 1.000E+02 RU-103 1.000E+01 1.000E+03 NB-97 3.000E+02 1.000E+02 RU-105 1.000E+Ol 1.000E+03 CD-I09 O.OOOE+OO O.OOOE+OO RU-106 1.000E+01 1.000E+03 SN-113 O.OOOE+OO O.OOOE+OO AG-llON 2.300E+00 5.000E+03 BA-133 O.OOOE+OO O.OOOE+OO SB-122 1.000E+00 3.000E+02 TE-134 4.000E+02 1. 000E+02 3B-124 1.000E+00 3.000E+02 CE-139 O.OOOE+OO O.OOOE+OO 3B-125 1.000E+00 3.000E+02 HG-203 O.OOOE+OO O.OOOE+OO Bio-Accumulation Factors and DFi's for Noble Gases 0 t

Indian Point 3 ODCM Page 2-21 Revision 18

aDCM Part II - Calculational Methodologies Figure 2-1 Radioactive liquid Waste Effluent System Flow Diagram Flash Tank Vent see Fiqure 3-1 IP #1 Waste Processing S/G D Steam SID I Generator I----'--------r----'------~ Flash Tank S Slowdown (4) C H

A R

Condenser }-----'

- ['" '"\]

Polisher G

E Turbine Hall Drains

_______ ~Monitor Tank Vent Waste I See Figure 3-1 .

Holdup Waste Tanks Processing Monitor Tanks C Fan Cooler A Unit N

.....- - - -... Service A Water L

FCU Motor R R Coolers Component Cooling Water Component Cooling Heat Exchanger Servic Waterl------------.-------.t r Component Cooling Heat Exchanger 1------'

u

~~

Service I L_ Component o Water . Cooling 0 0 0 ---------. '/01 Water Ground and Storm Water

-----. Hudson River Indian Point 3 aDCM Page 2-22 Revision 18

ODCM Part II - Calculational Methodologies 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Releases - General Information 3.1.1 The surveillance and lower limit of detection requirements for gaseous radioactive effluents are contained in the RECS. Lower limits of detection calculations are addressed in ODCM Part If, Appendix B.

3.1.2 A completed and properly authorized Airborne Radioactive Waste Release Permit shall be issued prior to the release of airborne activity from the waste gas holding system and containment purge. If a containment purge exceeds 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months in duration then the purge will be considered a continuous, long term release for reporting purposes (See Section 3.1.16).

3.1.3 Since Indian Point is a two unit site, the derived instantaneous J.lCi/sec limits delineated in Section 3.2.1 are apportioned to each site. The time-average limits in 3.2.2, 3.2.3, and 3.2.4 are "per reactor" limits and the full dose limits are applicable to IP3.

3.1.4 During Modes 5 and 6, there is no flowpath for a release from the Condenser Air Ejector, and the monthly grab sample described in Radiological Effluent Controls Table 3.4.1-1 is not required. During normal plant operation without a primary to secondary leak, almost all gaseous releases are through the main '.

Plant Vent. A negligible amount may be identified in the Administration Building and Radioactive Machine Shop vents. In the event of extended operation with a primary to secondary leak, low level releases are expected from both the blowdown flash tank vent and condenser air ejector. However, the limits on steam generator leakage are much more restrictive than those for effluent releases. Allocation of portions of the allowable release rate to these various release points is not warranted. If the instantaneous release rate is used (taking advantage of the one hour averaging allowed by 3.3.1 or 3.4.1), then all release points will be considered when establishing the Plant Vent alarm setpoint per ODCM Part II, Section 1.

3.1.5 For releases that are expected to continue for periods over two days, a new release permit will normally be issued each day. Containment purge release permits may be closed, with the release reclassified as continuous building ventilation when activity in containment is sufficiently reduced, at the discretion of the Chemistry Superintendent. However, when plant conditions change that will cause the activity in containment or any other permitted release of extended duration to significar:ltly change, a new permit shall be issued.

3.1,6 Assurance that the combined gaseous releases from Units 2 and 3 do not exceed Section 3.2.1 limits for the site is provided by administrative controls for both units. These controls include apportionment of the 10CFR20 limitations and back-calculating radiation monitor setpoints accordingly. these calculations are discussed in Appendix A.

Indian Point 3 ODCM Page 3-1 Revision 18

ODCM Part II - Calculational Methodologies 3.1.7 By mutual agreement with units 2 and 3 Shift Supervisors, one unit can reduce or eliminate discharges for a period of time to allow the other unit to use the full site permissible discharge rate, or a specific portion thereof, for discharge when necessary.

3.1.8 Conservative release rate limitations have been established to aid in controlling time average dose limits. The annual average limit shall normally be used for calculating limitations on discharge. If this limitation unduly restricts an individual release, the quarterly average release rate limit (/lCi/sec) may be used for the release provided the quarterly time average dose limit will not be exceeded and the Site Operations Manager or his assistant is in agreement.

The instantaneous limit may be used if the General Manager, Plant Operations or his designee is in agreement. If determined to be required, Chemistry may provide a true instantaneous limit based on the actual or suspected mixture.

Along with the permissions above, the Chemistry Superintendent or his designee should review the calculations for application of this true (ODCM) instantaneous limit. An hour is generally used as the default interval in which to determine the proximity to this limit in uCi/sec or mrem/yr.

3.1.9 Containment Pressure Reliefs Containment pressure reliefs occur frequently enough to be considered continuous releases. Grab samples of containment atmosphere are obtained periodically to ensure the use of accurate mixtures in effluent calculations. To ensure that the release rate will not be exceeded, the containment noble gas monitor (R-12) and the expected flowrate are used to calculate release rates from containment and at the stack effluent The effluent noble gas monitor in the plant vent is used to verify these calculations.

3.1.10 Composite Particulate Samples One of the following methods will be used to obtain a composite sample:

Samples will be taken weekly and integrated monthly; or

Samples will be taken weekly and counted together once per month.

3.1.11 Gas Storage Tank Activity Limit The quantity of radioactivity in each gas storage tank is limited to 50,000 Ci of noble gas, per RECS 2.11. This limit was calculated using the equations from Section 5.6.1 of NUREG 0133 and the following parameters:

Ki = 294 mrem-m 3//lCi-yr, Xe-133 equivalent Table B-1 (RG 1.109)

X/O =1.03 x 10-3 sec/m 3, Indian Point 3 FSAR Oit must be calculated so that the dose is less than 500 mrem in a year:

. (500mrem)* 3.15£+7 seelyr Olt= =52,011 Ci; 50,000 Ci (1E6/lCi! Ci)(294mrem - m 3 / /lCi - yr)(l ,03£ - 3 sec! m 3 )

Indian Point 3 ODCM Page 3-2 Revision 18

ODCM Part II - Calculational Methodologies This limit assumes 100% Xe-133 as per NUREG 0133. Utilizing the Ki from an expected mixture during RCS degasification 3

Ki = 787mrem-m flCi - yr '

the gas tank conservative administrative limit should be 19,400 curies.

The basis for assuring that accidental gas releases from liquid holdup tanks do not exceed Section 3.2.1 limits, is Technical Specifications 3.4.16 ( ~ 1 J.tCi/cc Dose Equivalent lodine-131 in Reactor Coolant). Using the assumptions discussed in FSAR section 14.2.3, the potential total curies in the liquid holdup tanks is limited to less than the conservative limit for the Gas Storage Tanks (19,400 curies). .

3.1.12 Gas Storaqe Tank Surveillance Requirements There are two methods available to ensure that the activity in the gas storage tank is within the conservative administrative limit (19400 Ci).

1.94E+4*lE6jiCiICi

=.117E + 2jiC'/

I CC

psia

2.83E4cc/ ft3 525ft3 (164.7 14.7 psia J

1. The total gaseous activity will normally be limited to less than 117 J.tCi/cc.

If this concentration limit is exceeded, then the contents of the tank will be monitored and actions taken to ensure the 19,400 curie per tank limit is not exceeded.

2. The waste gas line monitor (R-20) reads in J.tCi/cc. It allows for control of waste gas tank curie content by limiting the input concentration to 117 J.tCilcc, thereby limiting the curies to 19,400.

Large gas decay tanks on fill and CVCS tanks (which are indicative of the gas mixture in or from the reuse system) are continuously monitored for H2 and O2 through in-line instrumentation. With either in-line instrument out of service, a grab sample of the tank on receipt shall be taken daily, unless in degassing operation, when the periodicity is every four hours.

Other primary system tank cover gases can be manually directed through these instruments for individual samples.

3.1.13 The normal flow rate measurement for the Radioactive Machine Shop (RAMS) and the Plant Vent (PV) is obtained from the installed process monitor. When the instrument is out of service, the estimated flow from the RAMS is obtained by summing each operable exhaust fan's design flow rate. Estimated flow from the PV is obtained similarly, or from an alternate flow instrument (still considered an estimate). The design system flow rate of 12500 CFM is used for Administration Building ventilation. The process flow rate monitor surveillance requirements specified in RECS Table 3.2-1 are not applicable for the Administration Building, nor are they applicable when the RAMS or PV installed instruments are out of service and rated fan flow is used.

Indian Point 3 ODCM Page 3-3 Revision 18

ODCM Part II - Calculational Methodologies 3.1.14 The activity released via the blowdown flash tank vent is determined by obtaining the steam generator blowdown Tritium, Noble Gas, and Iodine activity, partitioned per Regulatory Guide 1.42 "Interim Licensing Policy On As Low As Practicable for Gaseous Radioiodine Releases from Light Water Cooled Nuclear Power Reactors" (from NUREG 0472, Rev3, DRAFT 6, TABLE 3.3-13), or Reference 4, "An Evaluation to Demonstrate the Compliance of the Indian Point Reactors with the Design Objectives of 10CFR50, Appendix I".

3.1.15 Carbon 14 is released at a rate of 9.6 curies per GW(e)/yr based upon studies performed by the New York State Department of Health at Indian Point 3. This is released in a gaseous form, the primary dose from which is in the CO2 form.

Therefore, these are exempt from the dose limits specified in Sections 2.4.1, 2.4.3 and 2.4.4 of the RECS. The Carbon 14 doses resulting from these releases are calculated in accordance with the methodology in Reg. Guide 1.109 and listed in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. This calculation is performed using the fraction of carbon 14 released in the CO2 form (26%).

3.1.16 Evaluations of previous gas decay tank and containment purge releases have been performed. These evaluations indicate that these "Short Term Releases" (less than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year and less than 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months per quarter) are sufficiently random to utilize the long term meteorological dispersion factor (NUREG 0133, Section 3.3, Page 8). The short-term correction factor, will only be used when non-random releases are to be made an a routine basis.

3.1.17 The liquid waste Monitor Tanks have an airborne release pathway. The original plant design limited the gases through this pathway by reducing the entrained gases to less than 2E-3 J.lCi/ml. The removal of the CVCS gas stripper under modification 86-3-122 CVCS requires the quantification of these gases when the entrained gaseous activity in the Monitor Tank inlet exceeds 2E-3 J.lCilml.

No action is required if the inlet noble gas concentration is less than 2E-3 J.lCi/ml. This gas release will be quantified by calculating the difference (in

/lCi's) between the gaseous activity added to the tank and the gaseous activity present in the effluent release sample. This difference will be quantified as an airborne ground level batch release, using a specifically determined ground level dispersion constant (Section 3.5.3).

A separ.ate release permit evaluating this release is not required prior to release. Calculation of this rate of release is not required, however the time average dose contribution shall be calculated and controlled per Sections 3.3 and 3.4 of the ODCM. Section 3.6 provides additional detail relative to the finite cloud correction assumptions for this pathway.

3.1.18 Airborne releases from the Steam Generator Safety or Atmospheric Dump Valves can occur during a Primary to Secondary leak. Tritium, Noble Gas, and Iodine effluent doses are determined using a source term activity (Main Steam or Steam Generator Blowdown), an Iodine partition factor (per Section 3.1.14),

and a release rate, determined from Engineering Design Calculation 187 (Steam Generator Atmospherics), or deSign flowrate (from Steam Generator Safeties) at specific pressures in the Steam Generator.

Indian Point 3 ODCM Page 3-4 Revision 18

ODCM Part II - Calculational Methodologies 3.1.19 Other release pathways resulting from Primary to Secondary leakage include the steam driven auxiliary feed pump vent, the gland seal exhaust vent, the air ejector vent, and the Feed Water heater flash tank vent. Offsite doses from these or other abnormal airborne release pOints are calculated by obtaining the release rate (from system descriptions and/or steam tables corrected for system pressure, as applicable) and source term activity (eg. Main Steam, Reactor Coolant, or best estimate) for Tritium, Noble Gas, and Iodine, partitioned as per Section 3.1.14.

3.1.20 The Monitor Tank vent, the Condenser Air Ejector, and the Gland Seal Exhaust points are ground level releases. Unless otherwise designated, other release points are considered mixed mode, per Section 3.6.

3.2 Gaseous Effluent Dose Calculation Requirements 3.2.1 Section 2.4.1 of the RECS requires that the dose rate due to radioactive materials released in gaseous effluents from the site at or beyond the site boundary shall be limited to:

a) For noble gases: Less than or equal to 500 mrem/yrto the total body and less than or equal to 3000 mrem/yr to the skin; and b) For Iodine 131, Tritium, and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or' equal to 1500 mrem/yr to any organ.

The methodologies for performing these calculations are discussed in Sections 3.3.1 and 3.3.2, respectively.

3.2.2 Section 2.4.2 of the RECS requires that the air dose due to noble gases released in gaseous effluents from each reactor unit at or beyond the site boundary shall be limited to:

a) During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.

b) During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

The methodology for calculating these doses is discussed in Section 3.3.3.

NOTE: If either of the above limits is exceeded by a factor of two or more, then cumUlative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per Section 2.6. of the RECS.

Indian Point 3 ODCM Page 3-5 Revision 18

ODCM Part II - Calculational Methodologies 3.2.3 Section 2.4.3 of the RECS requires that the dose to a member of the general public from Iodine 131, Tritium, and radionuclides in particulate form (half-lives

> 8 days) in gaseous effluents released from each reactor unit shall be limited to:

a) Less than or equal to 7.5 mrem to any organ during a calendar quarter b) Less than or equal to 15 mrem to any organ during a calendar year.

Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined at least once every 31 days. The methodology for calculating these doses is discussed in Section 3.3.4.

NOTE: If either of the previous limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per Section 2.6 of the RECS.

3.2.4 Section 2.4.4 of the RECS requires that for each reactor unit, the appropriate portions of the gaseous radwaste treatment system shall be used to reduce radioactive effluents in gaseous waste prior to their discharge when projected gaseous effluent air dose at the site boundary when averaged over 31 days, would exceed 0.2 mrad for gamma radiation\or 0.4 mrad for beta radiation.

These doses are projected based on the dose methodology discussed in Section 3.3.3 (noble gas) and 3.3.4 (iodine). The average of previous months' doses is used to project future dose as follows:

Dose 1 ==

Current Month Dose + Previous months' Dose

+/-

major I

p anne d 1

[ Projection number of months used [

evolutions The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

The appropriate portions of the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous releases when the projected doses averaged over 31 days, would exceed 0.3 mrem to any organ (at nearest residence). Dose due to gaseous releases from the site shall be calculated at least once every 31 days.

3.3 Dose Methodology (Computer Calculation) 3.3.1 Instantaneous Dose Rates - Noble Gas Releases When the instantaneous limit applies, the process radiation monitor response or release rate can be averaged over a one-hour time interval.

3.3.1.1 The equations developed in this section are used to meet the calculational requirements of paragraph 3.2.1. The magnitude of this pathway is the same for all age groups so there is no critical group. .

Indian Point 30DCM Page 3-6 Revision 18

aDCM Part II - Calculational Methodologies Based on an agreement with Unit 2, Indian Point Unit 3 utilizes 50% of the site release limit as measured in Ci/sec which translates to 55.4% of the applicable dose rate limit for noble gas releases.

Each unit has different dispersion factors due to their relative positions to the critical sector of the unrestricted area boundary. The conversion from dose rate to Ci/sec was determined with the use of a model which incorporates a finite cloud exposure correction. The methodology is discussed in Section 3.6.

A calculation showing the relationship between Ci/sec and dose rates from Units 2 and 3 is shown in Appendix A. The equations for calculating the dose rate limitations are obtained from NUREG 0133 (Ref. 1, Section 5.2.1).

Utilizing the above assumptions, these equations reduce to the following which are to be summed for each nuclide, i. (Note Section 3.1.6 allows use of higher release rates up to the maximum of the allowable maximum permissible discharge rate.)

~ [(Li':' 1. IMi) * ( %)*(Qi)] ~ 1,766 mrem/yr to the skin; Where:

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per JlCifm 3 (finite cloud correction included, per Table 3-4).

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per JlCi/m 3 , per Table 3-5.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per JlCi/m 3 (finite cloud correction included, per Table 3-6).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per JlCi/m 3 , per Table 3-7.

Qi-The release rate of radionuclides, i, in gaseous effluent for all release points in JlCifsec; (X/Q) =. For all vent releases, the highest calculated annual averaged relative concentration at the critical receptor (SWat 350 meters),

4.47E-6 sec/m 3 , as shown on Page 1 of Appendix A.

The Ki, Li, Mi, and Ni factors were obtained from Table B-1 of Regulatory Guide 1.109 and are included in this document as Tables 3-4, 3-5, 3-6,

, and 3-7 respectively. The Ki and Mi factors have a finite cloud correction

, factor included.

Indian Point 3 aDCM Page 3-7 Revision 18

aDCM Part II - Calculational Methodologies

/ ../.0,

,r

-.'." . 3.3.1.2 These equations can also be expressed in the following manner:

(K) <Qt) (X I Q) = mrem/yr dose to whole body (i + 1. 1M) (X I Q) (Qt) =mrem/yr dose to skin Where:

Qt = The release rate of all noble gases summed together in

)..lCi/sec, i.e., the sum of all Q i.

n K = (l/Qt) L

=1 cQi) (Ki)

- n L = (lIQt) Li~1 Qi) (Li) n M = (1/Q1) L ;=1 Qi) (Mi) n N = (1/ Qt) L (Q i) Ni)

=1 The values of K, L, M , and N are listed in Table 3-8 for the unrestricted area boundary.

3.3.2 Instantaneous Dose Rates 131, Part w/>8 day tYz . and H-3 ,

The equation developed in this section is used to meet the calculational requirements of RECS 2.4.1. The critical organ is considered to be the child thyroid as stated in Section 4.0 of the RECS. Based on different dispersion to the critical sector of the unrestricted area boundary for units 2 and 3, 50% of the site release limit (in Ci/sec) translates to 67.2% of the applicable dose rate limit for unit 3 (see Appendix A). The equation for calculating the dose rate limitation is abbreviated from that shown in NUREG 0133 (Ref. 1, Section 5.2.1, Pg. 25) in that ground plane and milk pathways are not considered due to inSignificant contribution compared to the inhalation pathway. Utilizing the above assumptions, this equation reduces to the following:

L (Pi * (XlQ)

Qi) must be less than 1008 mrem/yr Where:

Pi = The dose parameter for radionuclides other than noble gases for the inhalation pathway in mrem/yr per f!Ci/m 3 . These parameters (calculated in Section 3.3.2.1) are calculated separately for each isotope, age group, and organ.

Indian Point 3 aDCM Page 3-8 Revision 18

aDCM Part /I - Calculational Methodologies Qi = The release rate of radionuclide 131 and particulates, i, in gaseous effluents for all release points in !lCi/sec.

XJQ =4.47E-6 sec/m 3

The annual average dispersion parameter for the inhalation pathway at the controlling location (350 meters SW) due to all vent releases (see Page 1 of Appendix A and Section 3.5).

3.3.2.1 Calculation of Pilin): Inhalation Dose Factor Pi (inhalation) =K' (BR) DFAi (mrem/yr per !lCi/m3 )

Where:

K' = A constant of conversion, 106 pCi/!lCi BR = The breathing rate of each age group as per 3.3.4.5.a (Table E-5 of Reg. Guide 1.109).

DFAi = The inhalation dose factor for each age group, organ, and nuclide, in mrem/pCi. These values are taken from Reg Guide 1.109, Table E-7 through E-9 and are reproduced in Tables 3-1a through 3-1d.

3.3.3 Time Average Dose - Noble Gas Release 3.3.3.1 The equations in this section are used to meet the calculational requirements of Paragraphs 3.2.2 and 3.2.4. All releases at IP3NPP are assumed to be mixed mode unless indicated otherwise. The magnitude for this pathway is the same for all age groups so there is no critical group. Dispersion parameters are discussed in Section 3.5.

3.3.3.2 The equation for calculating the dose limitations are obtained from NUREG 0133 (Ref. 1, Section 5.3). The doses are evaluated at the unrestricted area boundary in the worst meteorological section (SSW sector at 380 meters). These equations reduce to the following:

gamma air mrad =3.17 E -8* LMi [(XJQ)(Qi) + (xJq)(qi) + (x/qm,)(qi mt )]

i beta air mrad = 3.17 E - 8* L Ni [(XJQ)(Qi) + (xJq)(qi) + (xJqmt)(qi mt )]

Where:

Air dose *Iimits are as fOllows:

Any Calendar Quarter Any Calendar Year Gamma Air Smrad 10 mrad Beta Air 10 mrad 20 mrad Indian Point 3 aDCM Page 3-9 Revision 18

ODCM Part II - Calculational Methodologies

/ (X/Q) =The highest calculated annual average relative

(

'. concentration for the unrestricted area boundary in the SW sector at 350 meters for long term releases (greater than 500 hrs/yr or 150 hrs/qtr or as noted in 3.1.16), 4.47E-6 sec/m3 .

(x/q) = The relative concentration for the unrestricted area boundary for short term releases (equal to or less than 500 hrs/yr or 150 hrs/qtr and not random as defined in NUREG 0133, Section 3.3). This value is calculated as per Section 3.5.

(x/qmt)=The relative concentration for the unrestricted area boundary for ground level releases from the monitor tank vents in the SW sector at 350 meters, per Section 3.5.3, in sec/m 3 .

Mi = The air dose factor due to gamma emission for each identified noble gas radionuclide in mrad/yr per f.l.Ci/m 3 .

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per f.l.Ci/m 3 .

qi ml = The total releases of noble gas radionuclides in monitor tank vents in f.l.Ci. Releases shall be cumulative over the calendar quarter or years as appropriate.

qi = The total release of noble gas radionuclides in gaseous effluents, i, for short term releases (equal to or less than 500 hrs/yr or 150 hrs/qtr and not random as defined in NUREG 0133, Section 3.3) from all vents, in f.l.Ci. Releases shall be cumulative over the calendar quarter or year as appropriate.

Qi = The total release of noble gas radionuclides in gaseous effluents, i, for long term releases (greater than 500 hrs/yr or 150 hrs/qtr or as noted in 3.1.16) from all vents in f.l.Ci. Releases shall be cumulative over the calendar quarter or year as appropriate.

3.17 E-8 = The inverse of the number of seconds in a year.

The air dose factors Mi and Ni were obtained from Table B-1 of Regulatory Guide 1.109 and are listed in Table 3-6 and 3-7 respectively. The M air dose factors are finite cloud corrected.

Indian Point 3 ODCM Page 3-10 Revision 18

ODeM Part \I - Calculational Methodologies 3.3.4 Time Averaged Dose - Radioiodine 131. Part w/t1h. >8 days. and Tritium 3.3.4.1 The equations in this section are used to meet the calculational requirements of Paragraphs 3.2.3 and 3.2.4.,

3.3.4.2 The pathways considered in this analysis are inhalation, ground plane, and vegetable ingestion at the nearest resident. The meat and milk ingestion pathways are not considered because of the lack of milk-producing cows within ten miles of the plant, and because of the high degree of commercial, industrial, and residential land usage in the area, as defined by the land use census. Doses are calculated at the nearest resident using meteorological data from the worst sector (SSW sector at 1525 meters) for conservativism.

3.3.4.3 The equations for calculating the dose limitations are obtained from NUREG 0133 (Ref. 1, Section 5.3). These equations reduce to the following:

During any calendar quarter:

(3.17E-08)*I (Ri(WQi + wqi) must be less than 7.5 mrem During any calendar year:

(3.17E-08)*I (Ri(WQi + wqi) must be less than 15 mrem Where:

Qi = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for long term releases as defined in Section 3.1.16, in IlCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

qi = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for short term releases as defined in Section 3.1.16, in IlCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

W = The dispersion or deposition parameter (based on meteorological data defined in Section 3.5) for estimating the dose to an individual at the nearest resident for long term releases as defined in Section 3.1.16.

Indian Point 3 aDCM Page 3-11 Revision 18

aDCM Part II - Calculational Methodologies w = The vent dispersion or deposition parameter for estimating the dose to an individual at the nearest resident for short term releases (as defined in Section 3.1.16) and calculated as in Section 3.5.

3.17 E-08 = The inverse number of seconds in a year.

Ri = The dose factor for each identified pathway, organ, and radionuclide, i, in m2 "mrem/yr per ~Ci/sec or mrem/yr per

~Ci/m3. These dose factors are determined as described in Sections 3.3.4.5a-d.

3.3.4.4 Utilizing the assumptions contained in Section 3.3.4.3, these equations for the nearest resident reduce to the following:

DN== (3.17E-8) ~)Ri(I)*[Wn(in)Qi + wn(in)qi] + (Ri(G)+ Ri(V>>*[Wn(dep)Qi + wn(dep)qi))

Where:

DN = total dose at the nearest residence, and must be less than or equal to 7.5 mrem per quarter, and less than or equal to 15 mrem Annually.

Wn(in} = The highest calculated annual average dispersion ,

parameter for the inhalation pathway for the nearest residence in the unrestricted area located in the SSW sector at 1574 meters, 1.02E-6 sec/m 3*

wn(in) = The dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area located in the SSW sector at 1574 meters, 1.02E-6 sec/m 3 ,

corrected for short term releases.

Wn(dep)= The highest calculated annual average deposition parameter for the nearest residence in the unrestrict~d area located in the South sector at 1133 meters, 7.45E-9 m- 2 for all isotopes except Tritium, which uses the X/Q value instead (1.02E-6 sec/m 3 ).

wn( dep)= The deposition parameter for the nearest residence in the unrestricted area located in the South sector at 1133 meters, 7.45E-9 m-2 for all isotopes except Tritium, which uses the X/Q value instead (1.02E-6 sec/m 3 ), corrected for short term releases.

(

\....

Indian Point 3 aDCM Page 3-12 Revision 18

aDCM Part II - Calculational Methodologies Qi = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for long term releases as defined earlier, (uCi).

(ji = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for short term releases as defined earlier (uCi).

Ri (I): Inhalation pathway factor for each radionuclide, i.

Ri (G): Ground plane pathway factor for each radionuclide, i.

Ri (V): Vegetation pathway factor for each radionuclide, i.

3.3.4.S Calculation of Dose Factors 3.3.4.S.a Calculation of Ri (I) lX/Q) Inhalation Pathway Factor Ri (I) (X/Q) =K'[(BR) a] [(OFAi) a](mrem/yr per JlCi/m 3 )

Where:

K' = Constant of unit conversion, 106 pCi/uCi (BR) a = Breathing rate of the receptor of age group (a) in m3/yr.

(from Regulatory Guide 1.109, Table E-S)

Infant = 1400 (m 3/yr)

Child = 3700 (m 3/yr)

AdultlTeen = 8000 (m 3/yr)

(DFAi) a = The maximum organ inhalation dose factor for the receptor of age group (a) for the ith radionuclide in mrem/pCi. The total body is considered as an organ in the selection of (DFAi)a.

Indian Point 3 aDCM Page 3-13 Revision 18

aDCM Part II - Calculational Methodologies Child and infant inhalation dose factors are generally more restrictive, however, doses from each age group are calculated separately. The (DFAi)a values are listed in Tables 3-1a through 3-1d. The Ri values for the inhalation pathway are listed in Table 3-10a through 3-10d.

3.3.4.5.b Calculation of Ri(G)(D/Q) Ground Plane Pathway Factor

. K'K"(SF)(DFGi)(1- e(-kil) m 2 *mrem/ yr RZ(G)(DIQ) = Ki uCi/sec Where:

K' = A constant of conversion, 106 pCi/JlCi.

K" = A constant of conversion, 8760 hr/yr.

ki = Decay constant for the ith radionuclide sec* 1

t = The exposure time, 4.73 x 108 sec (15 years).

DFGi = The ground plane dose conversion factor for ith radionuclide (mrem/hr per pCi/m 2 ).

SF =Shielding factor (dimensionless) =0.7 (from Table E-15 of Regulatory Guide 1.109).

The values of DFGi were obtained from Table E-6 of Regulatory Guide 1.109 and are listed in Table 3-2. These values were used to calculate Ri(G), which is the same for all age groups\and organs and is listed in Table 3-12.

Indian Point 3 aDCM Page 3-14 Revision 18

ODCM Part II - Calculational Methodologies 3.3.4.5.c Calculation of Ri(V)(D/Q) - Vegetation Pathway Factor Where:

K' = Constant of conversion, 106 pCi/flCi r = Dimensionless correction factor for Iodine and Particulate from Table E-15 of Reg Guide 1.109, as follows:

0.2 for particulates 1.0 for radioiodine DFLia = Reg Guide 1.109 dose factor for each nuclide, in mrem/pCi, for each age group.

Ual = Consumption rate of fresh leafy vegetation by the receptor in age group (a) in kg/yr.

ki = Decay constant for the radionuclide, in sec -1 UaS = Consumption rate of non-leafy vegetables by the receptor in age group (a) in kg/yr.

fL = The fraction of the annual intake of leafy vegetation grown locally.

fg = The fraction of the annual intake of non-leafy vegetation grown locally.

kw = Decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec -1 (corresponding to a 14 day half-life).

tL = The average time between harvest of leafy vegetation and its consumption in seconds.

th = The average time between harvest of stored vegetation and its consumption in seconds.

Yv = The vegetation area density in kg/m 2

Indian Point 3 ODCM Page 3-15 Revision 18

aDCM Part II - Calculational Methodologies The concentration of Tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri(V) is based on X/Q:

(RiV) (XJQ) = K'K"[(UaL)fL +(UaS)fg](DFLi)a (0.75)(0.5/H) (mrem/yr per /-tCi/m 3 )

Where:

K" = A constant of unit conversion, 1000 gm/kg H = Absolute humidity of the atmosphere in gm/m 3 . This value may

/ " be considered as 8 gm/m 3 (NUREG 0133, pg 27) in lieu of site specific information.

0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the, feed grass water to the atmospheric water DFLia for each age group is given in Tables 3-~a through 3-3d.

Ri(V) values are listed in Table 3-11a through 3-11c.

Indian Point 3 aDCM Page 3-16 Revision 18

aDCM Part II - Calculational Methodologies Ri(V) Parameters Are From The Following Sources:

PARAMETER VALUE Reg Guide 1.109 Table r (dimensionless) 1.0 for radioiodines E-15 0.2 for particulates (DFLi) a (mrem/pCi)

Each radionuclide E-11 to E-14 UaL (kg/yr) - infant 0 E-5

- child 26 E-5

- teen 42 E-5

- adult 64 E-5 UaS (kg/yr) - infant 0 E-5

- child 520 E-5

- teen 630 E-5

- adult 520 E-5 fL (dimensionless) 1.0 E-15 fg (d imensionless) 0.76 E-15 tL (seconds) 8.6E4(1 day) E-15 th (seconds) 5.18E6 (60 days) E-15 Yv (kg/m 2 ) 2.0 E-15

/

\ ...... "

Indian Point 3 aDCM Page 3-17 Revision 18

ODCM Part \I - Calculational Methodologies 3.4 Backup Simplified Dose Methodology The dose calculation procedures described in this section are provided for use as a backup whenever the primary computer methodology cannot be followed.

3.4.1 Instantaneous Dose Rates - Noble Gas Releases Note: When the instantaneous limit applies, the process radiation monitor response or release rate can be averaged over a one-hour time interval.

3.4.1.1 This section describes the alternative calculational methods to meet the requirements of Paragraph 3.2.1. These methods provide calculational results as per section 3.3.1.

3.4.1.2 To determine an acceptable noble gas instantaneous release rate in

/lei/sec, a standard isotopiC mixture of noble gases may be assumed.

This isotopiC mixture was measured for a mixture of isotopes typical of reactor coolant with exposed fuel. This requirement is evaluated at the worst sector of the unrestricted area boundary. Based on this isotopic mixture, standard Ks, Ls, Ms, and Ns (lower case s denotes a weighted sum, see Table 3-8) can be determined using the technique presented in paragraph 3.3.1.2 and Ki, Li, Mi, and Ni values from Tables 3.4-7. The data and results of this calculation are shown in Table 3-8.

3.4.1.3 The isotopic mixture chosen was obtained from a reactor coolant sample during an operating period with exposed fuel. Table 3-8 contains the mixture data and the fractional relative abundance of each isotope. These standard factors can be used with the equations and limits presented in Section 3.3.1.

3.4.1.4 Utilizing the equations from Paragraph 3.3.1.2 and the values from Table 3-8, conservative unit 3 maximum release limits for all noble gases in

/lei/sec are calculated in Appendix A and summarized below:

Maximum instantaneous release rates:

. 266 266 JiG ( )

Qt~

Ks(X I Q)

~ ( X 8.49E + 2 4.47 E - 6

) ~ 7.00E + 4 - WholeBody sec Qt~ 1806 < 1806 ~1.75E+5JiCi(Skin)

(Ls + 1.1Ms)(X / Q) (2306)(4.47 E - 6) sec Indian Point 3 ODeM Page 3-18 Revision 18

aDCM Part \I - Calculational Methodologies 3.4.1.5 For individual release rate determinations, alternate computer codes and/or a Hand Calculation Template serve as back up methodologies should the primary computer method be inoperable. These methods comply with calculations in Section 3.3.1.

3.4.2 Instantaneous Dose Rates-I-131. Particulates w/tYz >8 days. & H-3 3.4.2.1 This section describes the alternative calculational method to meet the requirements of Paragraph 3.2.1. The purposes of this method is to provide backup calculational techniques, both computer aided and hand calculated, which approximate section 3.3.2.

3.4.2.2 To determine an acceptable iodine and particulate release rate, it is assumed that the limit on these releases shall be met if the total noble gas concentration in the VC is at least a factor of 20,000 more than the concentration of radioiodine and long lived particulates or VC iodines and long lived particulates are less than 1E-7 /lCi/cc. This has historically been the case and this assures that the noble gas activity will be limiting.

3.4.2.3 Backup instantaneous dose rate calculations can be performed with an alternate computer code or by formatted hand calculations. These methods are identical to section 3.3.2.

3.4.3 Time Averaged Dose - Noble Gas Releases 3.4.3.1 This section describes alternative methods of meeting the requirements of Paragraphs 3.2.2 and 3.2.4, and the alternative methods of implementing the calculation techniques presented in Section 3.3.3.

3.4.3.2 The values of Ki, li, Mi , and Ni for the Plant Vent (PV) mixed mode releases and the Monitor Tank (MT) ground plane releases are determined for each release using the dispersion parameter for the site boundary in the worst sector. The calculations are as follows:

PV Ki = (Ki) * (X I Q)PV and MTKi = (Ki)*(XIQ)MT PV li = (Li) * (X I Q)PV and MTLi = (li)*(XIQ)MT PV Mi = (Mi) * (X I Q)PV and MTMi =(Mi) * (X I Q)MT PVNi = (Ni) * (XIQ)MT and MTNi = (Ni)*(XIQ)MT Where:

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per

/lCi/m 3 (finite cloud correction used).

Indian Point 3 aDCM Page 3-19 Revision 18

aDCM Part II - Calculational Methodologies Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide in mrem/yr per IlCi/m3.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per IlCi/m3 (finite cloud correction used).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per IlCi/m3.

(X/Q)PV = The highest calculated annual average dispersion parameter for the noble gas pathway at the unrestricted area boundary, 4.47E-6 sec/m 3 and applicable to plant vent mixed mode releases.

(X/Q)MT = The highest calculated annual average X/Q for ground level monitor tank noble gas release pathway, S.OOE-S sec/m 3

3.4.3.3 Determine weighted average dose factors as follows:

All values of Ki, Li, Mi, and Ni are shown in Table 3-4 through 3-7 for the unrestricted area boundary.

Each of the following expressions is summed over all the nuclides:

{ PVKt = ~)Ki * (Cil Ct)]

PV Lt = L [Li * (Ci / Ct)]

PVMt = L[Mi*(Ci / Ct)]

PVNt = L[Ni*(CiICt)]

For the monitor tank pathway, MTKt, MTLt, MTMt, and MTNt are calculated in the same way as for plant vent (PV) releases above, except that Ci and Ct apply to gaseous activity for the monitor tank vent pathway.

Where:

Ci = Concentration of isotope i (IlCi/cc) in analysis, t (for either PVor MT pathway)

Ct = Concentration of all noble gas isotopes (IlCi/cc) for a specific analysis, t, (for either the PV or MT pathway)

These calculations can be performed by hand (via formatted procedure) or by using alternate computer codes to compute all or part of the dose calculation.

Indian Point 3 aDCM Page 3-20 Revision 18

aDCM Part \I - Calculational Methodologies 3.4.3.4 Calculate resultant doses and compare with limits as per 3.3.3. The sum of all releases in a calendar quarter or calendar year should be compared to the limits of Section 3.2.2 and 3.2.4 as appropriate for gamma air dose and beta air dose.

3.4.4 'Time Averaged Dose-Iodine 131 and Particulates w/t"h days& H-3 3.4.4.1 This section describes the alternate methods of meeting the requirements of Paragraphs 3.2.3 and 3.2.4 and of implementing the calculational techniques presented in Section 3.3.4.

3.4.4.2 If the primary computer method is inoperable, dose calculations can be performed by:

a) an alternate computer code which complies with Section 3.3.4, using all identified Iodine and Particulate isotopes; or -

b) hand calculations (via a formalized departmental procedure) which comply with Section 3.3.4.

3.4.4.3 Sum the Iodine, Particulate, and Tritium dose contributions and compare quarterly and annual totals to the limits described in Section 3.2.3.

3.5 Calculation of Meteorological Dispersion Factors 3.5.1 For the purpose of these calculations, the site boundary was taken to be the unrestricted area boundary. The distances to the site boundary and nearest residents are shown in Table 3-9 for each of the 16 major compass sectors.

Site boundary distances at IPEC are measured from the applicable unit's Plant Vent, while distances to the nearest resident in each of these sectors is measured from a common point, the unit 1 superheater stack.

In the sectors where the Hudson River forms the site or exclusion area boundary, the near shore is assumed as the boundary of the "unrestricted area", because, in general, IPEC does not attempt to control population on the river. Potential confusion regarding the near or far shore for this application is effectively removed per the definition of "unrestricted area" in NUREG 0133 (Ref. 1, Section 2.2. Page 6). This section states that these criteria do "not include areas over water bodies" and the river is therefore not applicable for evaluating the maximum unrestricted area boundary concentrations.

Indian Point 3 aDCM Page 3-21 Revision 18

ODCM Part 11- Calculational Methodologies 3.5.2 The atmospheric transport and diffusion model used in the evaluation of dispersion and deposition factors is the sector-average straight-line model in Regulatory Guide 1.111 (Ref. 15) for mixed-mode releases with plume-rise effects, downwash, and building-wake correction.

The analyses were carried out using the AEOLUS-3 computer code (Ref. 16) and are documented in detail in Ref. 17. Hourly meteorological data was collected from 1981 through 1990, and updated with data from 1992 to 2002, in accordance with the accuracy requirements of Regulatory Guide 1.23 (Ref.

18). The data recovery index for these periods was in excess of 99%.

Comparison of the new meteorological data with previous data continues to show little difference in the overall dispersion conditions at the site. In the analyses, wind-speed coefficients in Regulatory Guide 1.111 were used to extrapolate the measured wind speeds to the height of the main vent (on top of the primary containment). Also, the regulatory plume entrainment model was used to determine plume partitioning between ground-level and elevated releases, and no credit was taken for decay and depletion in transit.

Recirculation effects were accounted for by confining in-valley flows within the valley out to a distance of 10 miles (up or down the valley) and allowing a portion of them to return to the site without additional dilution.

3.5.3 To meet the calculational requirements of Paragraphs 3.2.1, 3.2.2, and 3.2.4 the annual average dispersion factors are calculated approximately once every ten years, for each compass sector at the site unrestricted area boundary. The most restrictive meteorological dispersion and deposition factors determined from this accumulation of data is currently presented in Attachment A.

The distances to the site boundary and nearest resident in each sector were determined from the land use census and global positioning technology, and are listed in Table 3-9.

For the monitor tank release pathway, ground level dispersion values (X/Q) were assessed using the methodology discussed in Section 3.5.2. The most restrictive X/Q was determined to be in the SW sector at 350m with a value of 3

5.00E-5 sec/m (concentration X/Q per Ref. 21). This value is specific only to the Monitor Tank pathway for noble gas dose at the site boundary.

3.5.4 To meet the calculational requirements of Paragraph 3.2.3 (Iodines and Particulates), the annual average deposition and dispersion parameters were calculated for the nearest residents in each of the compass sectors.

Because no real dairy exists within 5 miles of the power plant, the grass-cow-milk pathway and its dispersion factor are not included.

Indian Point 3 ODeM Page 3-22 Revision 18

ODCM Part II - Calculational Methodologies Dispersion and deposition parameters for the nearest resident were calculated using the models and data described in Sec. 3.5.2 above and are as follows:

Wn(in) = The highest calculated annual average dispersion parameters for the inhalation pathway for the nearest residence in the unrestricted area, per Attachment A.

Wn( dep)= The highest calculated annual average deposition parameters for the ground plane and vegetation pathways for the nearest residence in the unrestricted area, per Attachment A.

For Tritium in the vegetation pathway, Wn(in) is used.

NOTE: For the monitor tank pathway, iodines and particulates are effectively removed by demineralization, therefore dispersion parameters are not needed for this pathway.

3.5.5 To meet the calculational requirements of Paragraphs 3.2.2, 3.2.3 and 3.2.4 and the calculation methodologies described in Sections 3.3..4 and 3.3.3, short term release dispersion and deposition factors may need to be calculated.

For this document, short term release dispersion and deposition factors are determined from the long term annual average parameters and a method presented by Sagendorf in NUREG 0324 (Ref. 5) as recommended by NUREG 0133 (Ref. 1, Section 3.3, Page 8). This method makes use of a factor (F),

developed for a particular compass sector and distance, which is simply multiplied by the annual average dispersion or deposition parameter for the same sector and distance to develop the corresponding short-term parameter.

This factor is defined as:

F = [NTOTAU8760]m Where:

F = The non-dimensional correction factor used to convert annual average dispersion or deposition factors to short term dispersion or deposition factors.

Indian Point 3 ODeM Page 3-23 Revision 18

/

aDCM Part II - Calculational Methodologies NTaTAL = The total duration of a short-term release (or releases) in hours, during a chosen reporting period.

10g(ANMX I F15MX) m = log(8760) 8760 = The total number of hours in a year.

ANMX = The calculated historical average dispersion (sec/m 3 ) or deposition (m-2) factor for the compass sector and distance of interest.

F15MX = The short term dispersion (sec/m 3 ) or deposition (m-2) factor for the compass sector and distance of interest.

This is the 15th percentile value such that worse weather conditions can only exist 15% of the time and better weather conditions 85% of the time.

The atmospheric transport and diffusion model used in the evaluation of short-term dispersion and deposition parameters (F15MX) is the Gaussian plume-centerline model in Regulatory Guide 1.145 (Ref. 19),

adapted for mixed-mode releases with plume-rise effects, downwash, building-wake correction and plume meander considerations.

As was the case with the annual average parameters, the analyses were carried out using the AEOLUS-3 computer code (Ref. 16) and the most recent 10-year hourly meteorological data. They are documented in detail in Reference 17.

Note that, in line with the guidance in NUREG-0133 (Ref. 1, Sec. 5.3.1, page 29), short-term releases (equal to or less than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year) are considered to be cumulative over the calendar quarter or year, as appropriate. However, from Sec. 3.1.16 of the aDeM Part II, and in line with Sec. 3.3, page 8 of NUREG-0133, gas-decay tank releases and containment purges have been determined to be sufficiently random so as to permit use of the long-term dispersion and deposition parameters for assessment of their radiological impact.

Indian Point 3 aDCM Page 3-24 Revision 18

ODCM Part II - Calculational Methodologies 3.5.6 The short term 15th percentile dispersion or deposition factor for use in the equation of the preceding paragraphs and the simplified F factor equation for mixed-mode releases to critical locations of each IPEC unit are as follows:

a) Site Boundary Noble Gas:

Unit 2 Unit 3 F15MX = 7.724E-5 sec/m3 1.590E-4 sec/m 3 ANMX = 2.219E-6 sec/m 3 4.470E-6 sec/m 3 m = 10g(AN.MX / F15.MX) = _ 0.391 -0.393 10g(8760) 391 393 F= [NTOTAU8760rO. [NTOTAU8760rO.

b) Nearest Residence Inhalation:

Unit 2 Unit 3 F15MX = 4.992E-5 sec/m 3 4.888E-5 sec/m 3 ANMX = 1.030E-6 sec/m 3 1.016E-6 sec/m3 m = 10g(AN.MX / F15.MX) = _ 0.428 - 0.427 log(8760)

F= [NTOTAU8760r°.428 [NTOTAU8760r°.427 c) Nearest Residence Deposition:

Unit 2 Unit 3 2

F15MX = 3.995E-7 m- 4.019E-7 m-2 ANMX = 7.517E-9 m-2 7.451E-9 m-2 m = 10g(AN.MX / F15MX) = _ 0.438 - 0.439 log(8760)

F= [NTOTAU8760r°.438 [NTOTAU8760r°.439 d} The slopes ("mil) for ground level short term correction factors are calculated in a similar fashion, from ground level data found in Reference 17:

Unit 2 Site Boundary Noble Gas: -0.390 -0.397 Nearest Resident Inhalation: -0.427 -0.427 Nearest Resident Deposition: -0.455 -0.455 Indian Point 3 ODCM Page 3-25 Revision 18

ODCM Part II - Calculational Methodologies 3.6 Justification for and Use of Finite Cloud Assumption for Assessing Site Boundarv Dose Two models are available for the computation of doses from external gamma radiation:

a) The semi-infinite cloud model, which is conservatively applicable only for ground-level releases assumes ground level airborne concentrations are the same throughout a cloud that is large in extent relative to the photon path lengths in air.

b) The finite-cloud model, which takes into consideration the actual plume dimensions and the elevation above the receptor.

The semi-infinite cloud model (which is normally used in a variety of applications because of its simplicity) has two drawbacks:

1. It could be overly conservative for receptors close to the release point (particularly for ground,"level releases under stable conditions with limited plume dispersion) due to the basis that the high concentration at the receptor is assumed to exist everywhere, and;

2. It is not suitable for elevated releases since gamma radiation emanating from the radioactive cloud could still reach a receptor on the ground even though the plume is still aloft (the concentration at ground level is equal to zero).

For practical applications, it is possible to define isotope-dependent finite-cloud correction factors to express the difference in external radiation exposures between a finite cloud (which may be either at ground level or elevated) and a semi-finite cloud.

Physically, when such a correction factor is applied to the calculated ground-level concentration resulting from a given plume, it will define the equivalent concentration in a semi-infinite cloud which would yield the same external exposure as the finite cloud.

Such a correction factor is a function of both the airborne radionuclide energy and of plume dispersion under the prevailing conditions. At distant receptors, where the plume dimensions reach limiting conditions, such correction factors reduce to unity.

The AEOlUS-3 code (which was used for the determination of the annual average dispersion and deposition parameters listed in Section 3.5), also has the capability of providing a basis for computation of isotope-specific finite-cloud correction factors based on the models in "Meteorology and Atomic Energy" (Ref. 20, Sec. 7.5.2). The code was used (along with the mixed-mode release option and the 10-year hourly meteorological data base) for the determination of the correction factors as would be applicable at the IPEC site boundary. Note that the correction factors can be viewed as adjustment factors to the dose conversion factors in Regulatory Guide 1.109 (Ref. 3) for immersion in semi-infinite clouds. The nuclide specific correction factors and adjusted dose factors are presented in Tables 3-4 and 3-6 for the IP3 site boundary.

For the monitor tank pathway (ground release concentration )(fQ), use of the finite cloud corrected data presented in tables 3-4 and 3-6 will provide a conservative result. The conservativism is due to the indicated correction factors for the mixed mode case yielding larger correction factors per nuclide. However, in the event that a ground level specific finite cloud correction factor is desired (which will yield lower calculated doses) the Xe-133 gamma )(fQ value may be used as described in Reference 21.

Indian Point 3 ODCM Page 3-26 Revision 18

ODCM Part 11- Calculational Methodologies 3.7 Direct Radiation Measurements and Total Dose Calculations (40CFR190)

Per RECS 3.6, the direct radiation component for potential offsite dose is determined by Radiological Engineering (using References 26 through 29) as follows:

Direct Radiation Dose =VC + IRWSF + SGM + RMHA + etc where; VC = The Vapor Containment structure IRWSF = The Interim Radioactive Waste Storage Facility SGM = The Steam Generator Mausoleum RMHA = A Radioactive Material Handling Area, as posted

= The ith RMHA Other structures or tanks are included as determined by Radiological Engineering.

The calculations in References 26 through 29 were performed in order to meet the requirements of NRC Generic Letter 81-38, 11/10/1981, Storage of Low-Level Radioactive Wastes at Power Reactor Sites.

"Offsite doses from onsite storage must be sufficiently low to account for other uranium fuel cycle sources (e.g., an additional dose of <1 mrem/year is not likely to cause the limits of 40 CFR 190 to be exceeded). On site dose limits will be controlled per 10 CFR 20 ... "

(

\ The IRWSF, SGM, and RMHAs fence line dose rates are limited by department procedures to keep dose rates at the SITE BOUNDARY fence < 1 mrem/yr based on calculations performed in References 26 through 29. These calculations contain realistic occupancy factors for the SITE BOUNDARY fence and the nearest neighbor.

3.8 Gaseous Effluent Dose to MEMBERS OF THE PUBLIC Visiting the Site Per RECS Section 4 (bases) and the discussion regarding gaseous effluent dose rate, visiting MEMBERS OF THE PUBLIC will receive negligible dose, as calculated per ODCM Part II, Sections 3.3.3 and 3.3.4, due the application of multiplicative occupancy factors. These factors are determined by comparing the expected hours on site to 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months (the number of hours in a year, which is used in the calculations demonstrated in Sections 3.3.3 and 3.3.4). Examples of these calculations are as follows:

example 1: Several students visit the site for an 8-hour guided tour.

Their occupancy factor is: 8 1 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 1 8760 = 3.8E-6 These factors, when multiplied by doses calculated per Sections 3.3.3 and 3.3.4, demonstrate that dose to these MEMBERS OF THE PUBLIC is negligible, despite any potential reduction in the atmospheric dispersion. '

Indian Point 3 ODCM Page 3-27 Revision 18

ODCM Part II - Calculational Methodologies

/'

( ","

Table 3-la ADULT INHALATION DOSE FACTORS (mrern per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 O.OOE+OO O.OOE+OO O.OOE+OP 1. 08E-05 Cr-51 O.OOE+OO O.OOE+OO 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 O.OOE+OO 4.95E-06 7.87E-07 O.OOE+OO 1.23E-06 1. 75E-04 9.67E-06 Mn-56 O.OOE+OO 1. 55E-I0 2.29E-11 O.OOE+OO 1.63E-I0 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 O.OOE+OO O.OOE+OO 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 O.OOE+OO O.OOE+OO 1. 27E-04 2.35E-05 Co-58 O.OOE+OO 1. 98E-07 2.59E-07 O.OOE+OO O.OOE+OO 1.16E-04 1.33E-05 Co-60 O.OOE+OO 1.44E-06 1.85E-06 O.OOE+OO O.OOE+OO 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 O.OOE+OO O.OOE+OO 2.23E-05 1.67E-06 Ni-65 1.92E-I0 2.62E-11 1.l4E-11 O.OOE+OO O.OOE+OO 7.00E-07 I.S4E-06 Cu-64 O.OOE+OO 1. 83E-I0 7.69E-11 O.OOE+OO 5.78E-I0 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-OS 5.82E-06 O.OOE+OO 8.62E-06 1. 08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-l3 O.OOE+OO 5.27E-12 1. 15E-07 2.04E-09 Br-83 O.OOE+OO O.OOE+OO 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.90E-08 Br-84 O.OOE+OO O.OOE+OO 3.91E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.05E-13 Br-85 O.OOE+OO O.OOE+OO 1.60E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.69E-05 7.37E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.08E-06 Rb-88 O.OOE+OO 4.84E-08 2.41E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.18E-19 Rb-89 O.OOE+OO 3.20E-08 2.12E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.l6E-2l Sr-89 3.80E-05 O.OOE+OO 1.09E-06 O.OOE+OO O.OOE+OO 1.75E-04 4.37E-05 Sr-90 1.24E-02 O.OOE+OO 7.62E-04 O.OOE+OO O.OOE+OO 1.20E-03 9.02E-OS Sr-91 7.74E-09 O.OOE+OO 3.l3E-10 O.OOE+OO O.OOE+OO 4.56E-06 2.39E-05 Sr-92 8.43E-I0 O.OOE+OO 3.64E-11 O.OOE+OO O.OOE+OO 2.06E-06 5.38E-06 Y-90 2.61E-07 O.OOE+OO 7.01E-09 O.OOE+OO O.OOE+OO 2.12E-05 6.32E-05 Y-91rn 3.26E-11 O.OOE+OO 1.27E-12 O.OOE+OO O.OOE+OO 2.40E-07 1. 66E-I0 Y-91 5.78E-05 O.OOE+OO 1.55E-06 O.OOE+OO O.OOE+OO 2.13E-04 4.81E-OS Y-92 1.29E-09 O.OOE+OO 3.77E-11 O.OOE+OO O.OOE+OO 1.96E-06 9.19E-06 Y-93 1.18E-08 O.OOE+OO 3.26E-10 O.OOE+OO O.OOE+OO 6.06E-06 5.27E-05 Zr-95 1. 34E-05 4.30E-06 2.91E-06 O.OOE+OO 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 O.OOE+OO 3.71E-09 9.84E-06 6.54E-05 Nb-95 1. 76E-06 9.77E-07 5.26E-07 O.OOE+OO 9.67E-07 6.31E-05 1.30E-05 Mo-99 O.OOE+OO 1.51E-08 2.87E-09 O.OOE+OO 3.64E-08 1. l4E-05 3.10E-05 Tc-99rn 1.29E-13 3.64E-l3 4.63E-12 O.OOE+OO 5.52E-12 9.55E~08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 O.OOE+OO 1.35E-13 4.99E-08 1.36E-21 Ru-l03 1.91E-07 O.OOE+OO 8.23E-08 O.OOE+OO 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 O.OOE+OO 3.89E-11 O.OOE+OO 1.27E-I0 1.37E-06 6.02E-06 Ru-l06 8.64E-06 O.OOE+OO 1.09E-06 O.OOE+OO 1.67E-05 1.17E-03 1.14E-04 Ag-110rn 1.35E-06 1.25E-06 7.43E-07 O.OOE+OO 2.46E-06 5.79E-04 3.78E-05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 O.OOE+OO 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 O.OOE+OO 2.18E-04 1. 26E-05 Indian Point 3 ODCM Page 3-28 Revision 18

ODCM Part /I - Calculational Methodologies Table 3-1a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.27E-07 1.98E-07 5.84E-08 1. 31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1. 58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1. 20E-04 1. 87E-05 Te-127 1. 75E-IO 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1. 45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1. 55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1. 82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1. 74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 O.OOE+OO 9.61E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 O.OOE+OO 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 O.OOE+OO 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 O.OOE+OO 1. 11E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 O.OOE+OO 1. 26E-10 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 O.OOE+OO 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 O.OOE+OO 3.59E-05 1. 22E-05 1. 30E-06 Cs-136 4.88E-06 1.83E-05 1. 38E-05 O.OOE+OO 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 O.OOE+OO 2.78E-05 9.40E-06 1. 05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 O.OOE+OO 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+OO 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 O.OOE+OO 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+OO 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 O.OOE+OO 2.86E-15 1.49E-07 1. 96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 O.OOE+OO O.OOE+OO 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 O.OOE+OO O.OOE+OO 7.91E-07 2.64E-07 Ce-l41 2.49E-06 1. 69E-06 1.91E-07 O.OOE+OO 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1. 72E-08 1.91E-09 O.OOE+OO 7.60E-09 9.97E-06 2.83E-05 Ce.-144 4.29E-04 1. 79E-04 2.30E-05 O.OOE+OO 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 O.OOE+OO 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1. 56E-12 1.91E-13 O.OOE+OO 8.8lE-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 O.OOE+OO 4.45E-07 2.76E-05 2.16E-05 W-187 1. 06E-09 8.85E-10 3.10E-10 O.OOE+OO O.OOE+OO 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 O.OOE+OO 8.75E-09 4.70E-06 1.49E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 8.65E-08 8.39E-08 O.OOE+OO O.OOE+OO 4.62E-05 3.93E-06 S:r:-85 4.00E-06 O.OOE+OO 9.70E-05 O.OOE+OO O.OOE+OO 6.00E-05 7.60E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.78E-11 7.03E-12 2.56E-12 O.OOE+OO 8.18E-12 3.00E-07 3.02E-08 Cd-109 O.OOE+OO 4.90E-05 1.60E-06 O.OOE+OO 4.70E-05 9.10E-05 8.20E-06 3n-113 8.20E-06 2.70E-07 5.60E-07 1.70E-07 O.OOE+OO 1.20E-04 1.50E-06 Ba-133 9.50E-06 4.20E-07 2.50E-06 O.OOE+OO 2.10E-09 1.90E-04 1.00E-05 Te-134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.34E-07 2.97E-11 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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Indian Point 3 ODCM Page 3-29 Revision 18

aDCM Part II - Calculational Methodologies

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Table 3-lb TEEN INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.59E-07 1. 59E-07 1. 59E-07 1.59E-07 1.59E-07 1.59E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.72E-06 1. 72E-06 1.72E-06 1. 72E-06 1. 72E-06 1. 72E-06 1. 72E-06 P-32 2.36E-04 1. 37E.-05 8.95E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-05 Cr-51 O.OOE+OO O.OOE+OO 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 O.OOE+OO 6.39E-06 1.05E-06 O.OOE+OO 1.59E-06 2.48E-04 8.35E-06 Mn-56 O.OOE+OO 2.12E-10 3.15E-11 O.OOE+OO 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 O.OOE+OO O.OOE+OO 1.55E-05 7.99E-07 Fe-59 1.99E-06 .4.62E-06 1.79E-06 O.OOE+OO O.OOE+OO 1. 91E-04 2.23E-05 Co-58 O.OOE+OO 2.59E-07 3.47E-07 O.OOE+OO O.OOE+OO 1.68E-04 1.19E-05 Co-60 O.OOE+OO 1.89E-06 2.48E-06 O.OOE+OO O.OOE+OO 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 O.OOE+OO O.OOE+OO 3.84E-05 1. 77E-06 Ni-65 2.73E-10 3.66E-11 1. 59E-11 O.OOE+OO O.OOE+OO 1.17E-06 4.59E-06 Cu-64 O.OOE+OO 2.54E-10 1.06E-I0 O.OOE+OO 8.01E-10 1. 39E-06 7.68E-06 Zn-65 4.82E-06 1. 67E-05 7.80E-06 O.OOE+OO 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1. 15E-11 8.07E-13 O.OOE+OO 7.53E-12 1.98E-07 3.56E-08 Br-83 O.OOE+OO O.OOE+OO 4.30E-OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.41E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.29E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.38E-05 1. 05E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.21E-06 Rb:"88 O.OOE+OO 6.82E-08 3.40E-08 O.OOE+OO O.OOE+OO O.OOE+OO 3.65E-15 Rb-89 O.OOE+OO 4.40E-08 2.91E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.22E-17 Sr-89 5.43E-05 O.OOE+OO 1.56E-06 O.OOE+OO. O.OOE+OO 3.02E-04 4.64E-05 Sr-90 1.35E-02 O.OOE+OO 8.35E-04 O.OOE+OO O.OOE+OO 2.06E-03 9.56E-05 Sr-91 1.10E-08 O.OOE+OO 4.39E-10 O.OOE+OO O.OOE+OO 7.59E-06 3.24E-05 Sr-92 1.19E-09 O.OOE+OO 5.08E-11 O.OOE+OO O.OOE+OO 3.43E-06 1.49E-05 Y-90 3.73E-07 O.OOE+OO 1. 00E-08 O.OOE+OO O.OOE+OO 3.66E-05 6.99E-05 Y-91m 4.63E-11 O.OOE+OO 1.77E-12 O.OOE+OO O.OOE+OO 4.00E-07 3.77E-09 Y-91 8.26E-05 O.OOE+OO 2.21E-06 O.OOE+OO O.OOE+OO 3.67E-04 5.11E-05 Y-92 1. 84E-09 O.OOE+OO 5.36E-11 O.OOE+OO O.OOE+OO 3.35E-06 2.06E-05 Y-93 1.69E-OS O.OOE+OO 4.65E-I0 O.OOE+OO O.OOE+OO 1. 04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 O.OOE+OO S.42E-06 3.36E-04 1. 86E-05 Zr-97 1.72E-OS 3.40E-09 1.57E-09 O.OOE+OO 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 O.OOE+OO 1. 25E-06 9.39E-05 1.21E-05 Mo-99 O.OOE+OO 2.11E-08 4.03E-09 O.OOE+OO 5.14E-OS 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 O.OOE+OO 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 O.OOE+OO 1.90E-13 8.34E-08 1. 09E-16 Ru-l03 2.63E-07 O.OOE+OO 1.12E-07 O.OOE+OO 9.29E-07 9.79E-05 1. 36E-05 Ru-l05 1.40E-I0 O.OOE+OO 5.42E-11 o.ooboo 1.76E-10 2.27E-06 1. 13E-05 Ru-l06 1.23E-05 O.OOE+OO 1. 55E-06 O.OOE+OO 2.38E-05 2.01E-03 1. 20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 O.OOE+OO 3.13E-06 8.44E-04 3.41E-05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 O.OOE+OO 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 O.OOE+OO 3.42E-04 1. 24E-05 Indian Point 3 aDCM Page 3-30 Revision 18

aDCM Part II - Calculational Methodologies Table 3-1b TEEN INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 O.OOE+OO 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1. 99E-05 Te-127 2.51E-I0 1. 14E-I0 5.52E-11 1. 77E-I0 9.10E-I0 1. 40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72£-07 6.49£-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20£-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03£-09 9.06E-09 5.49E-08 2.97£-05 7.76E-05 Te-131 1.97E-12 1. 04£-12 6.30£-13 1. 55E-12 7.72E-12 2.92£-07 1. 89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 O.OOE+OO 1.14E-06 1-131 4.43£-06 6.14E-06 3.30£-06 1. 83£-03 1.05E-05 O.OOE+OO 8.11E-07 1-132 1. 99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 O.OOE+OO 1. 59E-07 1-133 1. 52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 O.OOE+OO 1.29E-06 1-134 1. 11E-07 2.90E-07 1. 05E-07 4.94E-06 4.58E-,07 O.OOE+OO 2.55E-09 1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1. 86E-06 O.OOE+OO 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 O.OOE+OO 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 O.OOE+OO 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 O.OOE+OO 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00£+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1. 18E-13 4.87£-12 O.OOE+OO 1. 11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 O.OOE+OO 2.85E-09 2.54E-04 2.86E-05 Ba-141 1. 78E-11 1.32E-14 5.93E-13 O.OOE+OO 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 O.OOE+OO 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 O.OOE+OO O.OOE+OO 2.6SE-05 6.09E-05 La-142 1. 20E-10 5.31E-11 1. 32E-11 O.OOE+OO O.OOE+OO 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+OO 1.11E-06 7.67E-05 1.5SE-05 Ce-143 3.32E-OS 2.42E-08 2.70E-09 O.OOE+OO 1.08E-OS 1.63E-05 3.l9E-05 Ce-144 6.11E-04 2.53E-0.4 3.28E-05 O.OOE+OO 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 S.2SE-OS O.OOE+OO 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 O.OOE+OO 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 O.OOE+OO 6.28E-07 4.65E-05 2.2SE-05 W-187 1.50E-09 1.22E-09 4.29E-10 O.OOE+OO O.OOE+OO 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 O.OOE+OO 1. 25E-OS 8.11E-06 1.65E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.18E-07 1.15E-07 O.OOE+OO O.OOE+OO 7.33E-05 3.93E-06 Sr-:S5 5.00E-06 O.OOE+OO 1.30E-06 O.OOE+OO O.OOE+OO 8.80E-05 6.90E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO- O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.93E-11 9.72E-12 3.55E-12 O.OOE+OO 1. 14E-11 4.91E-07 2.71E-07 Cd-109 O.OOE+OO 1.00E-04 3.40E-06 O.OOE+OO 6.7'OE-05 1.60E-04 S.60E-06 Sn-113 1.50E-05 4.70E-07 9.70E-07 2.90E-07 O.OOE+OO 2.00E-04 1.50E-06 Ba-133 4.70E-05 S.00E-07 3.30E-06 O.OOE+OO 2.80E-09 2.90E-04 9.70E-06 Te-134 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2. 91E-11 6.75E-07 1.37E-09 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-31 Revision 18

aDCM Part II - Calculational Methodologies Table 3-1c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-05 Cr-51 O.OOE+OO O.OOE+OO 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 O.OOE+OO 1. 16E-05 2.57E-06 O.OOE+OO 2.71E-06 4.26E-04 6.19E-06 Mn-56 O.OOE+OO 4.48E-10 8.43E-11 O.OOE+OO 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 O.OOE+OO O.OOE+OO 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 O.OOE+OO O.OOE+OO 3.43E-04 1.91E-05 Co-58 O.OOE+OO 4.79E-07 8.55E-07 O.OOE+OO O.OOE+OO 2.99E-04 9.29E-06 Co-60 O.OOE+OO 3.55E-06 6.12E-06 O.OOE+OO O.OOE+OO 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 O.OOE+OO O.OOE+OO 7.43E-05 1. 71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 O.OOE+OO O.OOE+OO 2.21E-06 2.27E-05 Cu-64 O.OOE+OO 5.39E-10 2.90E-I0 O.OOE+OO 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 O.OOE+OO 1.93E-05 2.69E-04 4.41E-06 Zn-69 1. 81E-11 2.61E-11 2.41E-12 O.OOE+OO 1.58E-11 3.84E-07 2.75E-06 Br-83 O.OOE+OO O.OOE+OO 1.28E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.48E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 6.84E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.36E-05 3.09E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.16E-06 Rb-88 O.OOE+OO 1.52E-07 9.90E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.66E-09 Rb-89 O.OOE+OO 9.33E-08 7.83E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E-I0 Sr-89 1.62E-04 O.OOE+OO 4.66E-06 O.OOE+OO O.OOE+OO 5.83E-04 4.52E-05 Sr-90 2.73E-02 O.OOE+OO 1. 74E-03 O.OOE+OO O.OOE+OO 3.99E-03 9.28E-05 Sr-91 3.28E-08 O.OOE+OO 1.24E-09 O.OOE+OO O.OOE+OO 1.44E-05 4.70E-05 Sr-92 3.54E-09 O.OOE+OO 1.42E-I0 O.OOE+OO O.OOE+OO 6.49E-06 6.55E-05 Y-90 1. 11E-06 O.OOE+OO 2.99E-08 O.OOE+.OO O.OOE+OO 7.07E-05 7.24E-05 Y-91m 1.37E-10 O.OOE+OO 4.98E-12 O.OOE+OO O.OOE+OO 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+OO 6.59E-06 O.OOE+OO O.OOE+OO 7.10E-04 4.97E-05 Y-92 5.50E-09 O.OOE+OO 1. 57E-I0 O.OOE+OO O.OOE+OO 6.46E-06 6.46E-05 Y-93 5.04E-08 O.OOE+OO 1.38E-09 O.OOE+OO O.OOE+OO 2.01E-05 1. 05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 O.OOE+OO 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 O.OOE+OO 1.0SE-08 3.06E-OS 9.49E-OS Nb-95 6.35E-06 2.48E-06 1.77E-06 O.OOE+OO 2.33E-06 1.66E-04 1. 00E-05 Mo-99 O.OOE+OO 4.66E-08 1.15E-08 O.OOE+OO 1.06E-07 3.66E-05 3.42E-OS Tc-99m 4.81E-13 9. 41E-13 1. S6E-11 O.OOE+OO 1.37E-11 2.S7E-07 1.30E-06 Tc-l01 2.19E-14 2.30E-14 2.91E-13 O.OOE+OO 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 O.OOE+OO 2.90E-07 O.OOE+OO 1.90E-06 1. 79E-04 1.21E-05 Ru-10S 4.13E-10 O.OOE+OO 1.50E-10 O.OOE+OO 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 O.OOE+OO 4.57E-06 O.OOE+OO 4.97E-05 3.87E-03 1.16E-04 Ag-11 Om 4.56E-06 3.08E-06 2.47E-06 O.OOE+OO 5.74E-06 1.48E-03 2.71E-05 Sb~122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 1.55E-OS 2.00E-07 5.41E-06 3.41E-08 O.OOE+OO 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 O.OOE+OO 6.27E-04 1.09E-05 Indian Point 3 aDCM Page 3-32 Revision 18

aDCM Part II - Calculational Methodologies

,r*****.

f Table 3-1c CHILD INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-i25m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 O.OOE+OO 1. 29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1. 72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1. 91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1. 93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1. 37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1. 78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.S8E-08 4.79E-07 1.02E-04 3.72E-OS I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 O.OOE+OO 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.OOE+OO 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1. 69E-06 O.OOE+OO 8.65E-07 I-133 4.48E-06 S.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+OO 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 O.OOE+OO 2.58E-07 I-135 1.33E-06 2.36E-06 1. 12E-06 2.14E-04 3.62E-06 O.OOE+OO 1.20E-06 Cs-134 1. 76E-04 2.74E-04 6.07E-05 O.OOE+OO 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.l4E-05 O.OOE+OO 2 .. 58E-05 3.93E-06 1. 13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 O.OOE+OO 7.63E-05 2.81E-05 9.78E-07 Cs-138 1. 71E-07 2.27E-07 1.50E-07 O.OOE+OO 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-I0 2.66E-13 1. 45E-11 O.OOE+OO 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 O.OOE+OO 5.71E-09 4.71E-04 2.75E-05 Ba-141 S.29E-11 2.9S£-14 1. 72£-12 O.OOE+OO 2.S6E-14 7.89£-07 7.44E-08 Ba-142 1. 35E-11 9.73E-15 7.S4E-13 O.OOE+OO 7.87E-15 4.44E-07 7.41E-10 La-l40 1.74E-07 6.08E-08 2.04E-08 O.OOE+OO O.OOE+OO 4.94E-OS 6.10E-05 La-l42 3.50E-10 1. 11E-10 3.49E-11 O.OOE+OO O.OOE+OO 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 O.OOE+OO 2.31E-06 1. 47E-04 1.S3E-OS Ce-143 9.89E-08 S.37E-08 7.77E-09 O.OOE+OO 2.26E-08 3.12E-OS 3.44E'=OS Ce-144 1.83E-03 S.72E-04 9.77E-05 O.OOE+OO 3.17E-04 3.23E-03 1. OSE-04 Pr-l43 4.99E-06 1. 50E-06 2.47E-07 O.OOE+OO 8.11E-07 1.17E-04 2.63E-OS Pr-144 1.61E-11 4.99E-12 8.10E-13 O.OOE+OO 2.64E-12 4.23E-07 S.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 O.OOE+OO 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 O.OOE+OO O.OOE+OO 1. lIE-OS 2.46E-OS Np-239 1.26E-07 9.04E-09 6.35E-09 O.OOE+OO 2.63E-08 1.S7E-05 1.73E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 2.44E-07 2.88E-07 O.OOE+OO O.OOE+OO 1.37E-04 3.S8E-06 Sr-8S 1. 20E-05 O.OOE+OO 3.20E-06 O.OOE+OO O.OOE+OO 1.S0E-04 5.S0E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO o.,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 1.16E-10 2.08E-11 9.73E-12 O.OOE+OO 2.31E-11 9.24E-07 7.S1E-06 Cd-109 O.OOE+OO 1.90E-04 8.00E-06 O.OOE+OO 1.70E-04 3.00E-04 8.10E-06 Sn-113 3.80E-OS 8.90E-07 2.30E-06 7.10E-07 O.OOE+OO 3.60E-04 1.30E-06 Ba-133 1.10E-04 1.10E-06 1. 00E-05 O.OOE+OO 5.40E-09 5.20E-04 8.30E-06 Te-134 1.53E-11 8.81E-12 9.40E-12 1.24E-11 5.71E-11 1.23E-06 4.87E-07 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-33 Revision 18

ODCM Part" - Calculational Methodologies Table 3-1d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1. 45E-03 8.03E-05 5.53E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E-05 Cr-51 O.OOE+OO O.OOE+OO 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 O.OOE+OO 1.81E-05 3.56E-06 O.OOE+OO 3.56E-06 7.14E-04 5.04E-06 Mn-56 O.OOE+OO 1.10E-09 1.58E-I0 O.OOE+OO 7.86E-10 8.95E-06 5.12E-05 Fe-55 1. 4lE-05 8.39E-06 2.38E-06 O.OOE+OO O.OOE+OO 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 O.OOE+OO O.OOE+OO 7.25E-04 1.77E-05 Co-58 O.OOE+OO 8.71E-07 1.30E-06 O.OOE+OO O.OOE+OO 5.55E-04 7.95E-06 Co-60 O.OOE+OO 5.73E-06 8.4lE-06 O.OOE+OO O.OOE+OO 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 O.OOE+OO O.OOE+OO 1. 49E-04 1.73E-06 Ni-65 1. 71E-09 2.03E-10 8.79E-ll O.OOE+OO O.OOE+OO 5.80E-06 3.58E-05 Cu-64 O.OOE+OO 1.34E-09 5.53E-10 O.OOE+OO 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 O.OOE+OO 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6. 91E-11 5.13E-12 O.OOE+OO 2.87E-11 1.05E-06 9.44E-06 Br-83 O.OOE+OO O.OOE+OO 2.72E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.86E-07 O.OOE+OO 0.00E+00 O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.46E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.36E-04 6.30E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-06 Rb-88 O.OOE+OO 3.98E-07 2.05E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-07 Rb-89 O.OOE+OO 2.29E-07 1.47E-07 O.OOB+OO O.OOE+OO O.OOE+OO 4.87E-08 Sr-89 2.84E-04 O.OOE+OO 8.15E-06 O.OOE+OO O.OOE+OO 1.45E-03 4.57E-05 Sr-90 2.92E-02 O.OOE+OO 1. 85E-03 O.OOE+OO O.OOE+OO 8.03E-03 9.36E-05 Sr-91 6.83E-08 O.OOE+OO 2.47£-09 0.00£+00 0.00£+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 O.OOE+OO 2.79E-I0 O.OOE+OO O.OOE+OO 1.70£-05 1.00E-04 Y-90 2.35E-06 O.OOE+OO 6.30E-08 O.OOE+OO O.OOE+OO 1.92E-04 7.43E-05 Y-91m 2.91E-10 O.OOE+OO 9.90E-12 O.OOE+OO O.OOE+OO 1.99E-06 1.68E-06 Y-91 4.20E-04 O.OOE+OO 1.12E-05 O.OOE+OO O.OOE+OO 1.75E-03 5.02E-05 Y-92 1.17E-08 O.OOE+OO 3.29E-10 O.OOE+OO O.OOE+OO 1.75E-05 9.04E-05 Y-93 1. 07E-07 O.OOE+OO 2.91E-09 O.OOE+OO O.OOE+OO 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99£-05 1.45E-05 O.OOE+OO 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 O.OOE+OO 1.85E-08 7.88E-05 1. 00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 O.OOE+OO 3.37E-06 3.42E-04 9.05E-06 Mo-99 O.OOE+OO 1.18E-07 2.31E-08 O.OOE+OO 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.0(:iE-12 2.66E-11 O.OOE+OO 2.22E-11 5.79E-07 1. 45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 O.OOE+OO 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 O.OOE+OO 4.85E-07 O.OOE+OO 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 O.OOE+OO 2.93E-10 O.OOE+OO 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 O.OOE+OO 7.77E-06 O.OOE+OO 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 O.OOE+OO 7.80E-06 2.62E-03 2.36E-05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 O.OOE+OO 1. 89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 O.OOE+OO 1.17E-03 1.05E-05 Indian Point 3 aDCM Page 3-34 Revision 18

aDeM Part 1\ - Calculational Methodologies Table 3-1d INFANT INHALATION DOSE FACTORS (mrern per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 O.OOE+OO 3.19E-04 9.22E-06 Te-l27rn 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1. 59E-05 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1. 74E-05 Te-129rn 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1. 20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131rn 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1. 13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1. 69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+OO 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1. 06E-02 3.70E-05 O.OOE+OO 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 O.OOE+OO 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 O.OOE+OO 1. 54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 O.OOE+OO 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 O.OOE+OO 1. 31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 O.OOE+OO 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 O.OOE+OO 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 O.OOE+OO 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 O.OOE+OO 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 O.OOE+OO 4.23E-13 4.25E-06 3.64E-05 Ba-l40 4.00E-05 4.00E-08 2.07E-06 O.OOE+OO 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 O.OOE+OO 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 O.OOE+OO 1.36E-14 1. 11E-06 4.95E-07 La-l40 3.61E-07 1.43E-07 3.68E-08 O.OOE+OO O.OOE+OO 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 O.OOE+OO O.OOE+OO 5.87E~06 4.25E-05 Ce-141 1. 98E-05 1. 19E-05 1.42E-06 O.OOE+OO 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1. 38E-07 1.58E-08 O.OOE+OO 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 O.OOE+OO 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 O.OOE+OO 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1. 72E-12 O.OOE+OO 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 O.OOE+OO 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 O.OOE+OO O.OOE+OO 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 O.OOE+OO 4.73E-08 4.25E-05 1. 78E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 4.65E-07 4.58E-07 O.OOE+OO O.OOE+OO 2.71E-04 3.47E-06 Sr-85 2.70E-05 O.OOE+OO 5.40E-06 O.OOE+OO O.OOE+OO 3.00E-04 4.80E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.44E-10 5. 21E-11 1. 88E-11 O.OOE+OO 4.07E-11 2.37E-06 1.92E-05 Cd-109 O.OOE+OO 2.60E-04 1.00E-05 O.OOE+OO 2:00E-04 6.20E-04 8.00E-06 Sn-1l3 6.00E-05 1.60E-06 3.60E-06 1.30E-06 O.OOE+OO 7.80E-04 1.20E-06 Ba-l33 1.90E-04 1. 70E-06 1.30E-05 O.OOE+OO 8.90E-09 9.10E-04 7.70E-06 Te-l34 3.18E-11 2.04E-11 1. 68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDeM Page 3-35 Revision 18

aDCM Part II - Calculational Methodologies Table 3-2 2

Total Body & Skin Ground Plane Dose Factors (mrem/hr per pCi/m )

with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody(DFg} Skin(DFs)

H-3 12.350 Y 1. 00E-02 O.OOE+OO O.OOE+OO Be-7 53.300 0 1.00E-04 O.OOE+OO O.OOE+OO Na-24 15.000 H 4.00E-02 2.50E-08 2.90E-08 P-32 14.290 D 2.50E-02 O.OOE+OO O.OOE+OO Cr-51 27.704 D 2.20E-03 2.20E-10 2.60E-10 Mn-54 312.500 0 2.50E-04 5.80E-09 6.80E-09 Mn-56 2.578 H 2.50E-04 1.10E-08 1.30E-08 Fe-55 2.700 Y 1. 20E-03 O.OOE+OO O.OOE+OO Fe-59 44.529 0 1.20E-03 8.00E-09 9.40£-09 Co-58 70.800 0 1.00E-03 7.00E-09 8.20£-09 Co-60 5.271 Y 1.00E-03 1.70E-08 2.00£-08 Ni-63 96.000 Y 6.70E-03 O.OOE+OO O.OOE+OO Ni-65 2.520 H 6.70E-03 3.70E-09 4.30E-09 Cu-64 12.701 H 1.40E-02 1. 50E-09 1.70£-09 Zn-65 243.900 D 3.90E-02 4.00E-09 4.60E-09 Zn-69 0.950 H 3.90E-02 O.OOE+OO O.OOE+OO Br-83 2.390 H 5.00E-02 6.40E-11 9.30E-11 Br-84 0.530 H 5.00E-02 1. 20E-08 1.40E-08 Br-85 0.050 H 5.00E-02 O.OOE+OO O.OOE+OO Rb-86 18.660 D 3.00E-02 6.30E-10 7.20E-I0 Rb-88 0.297 H 3.00E-02 3.50E-09 4.00E-09 Rb-89 0.253 H 3.00E-02 1.50E-08 1.80E-08 Sr-89 . 50.500 0 8.00E-04 5.60E-13 6.50E-13 Sr-90 29.120 Y 8.00E-04 O.OOE+OO O.OOE+OO Sr-91 9.500 H 8.00E-04 7.10E-09 8.30£-09 Sr-92 2.710 H 8.00£-04 9.00E-09 1.00£-08 Y-90 2.667 0 1.00E-05 2.20E-12 2.60£-12 Y-91m 0.829 H 1. 00E-05 3.80E-09 4.40£-09 Y-91 58.510 0 1.00E-05 2.40E-11 2.70E-11 Y-92 3.540 H 1.00E-05 1.60E-09 1.90£-09 Y-93 10.100 H 1.00E-05 5.70E-10 7.80E-10 Zr-95 63.980 0 5.00E-06 5.00E-09 5.80E-09 Zr-97 16.900 H 5.00E-06 5.50E-09 6.40E-09 Nb-95 35.150 0 2.50E-03 5.10E-09 6.00E-09 Mo-99 2.750 0 7.50E-03 1.90E-09 2.20E-09 Tc-99m 6.020 H 2.50E-02 9.60£-10 1. 10E-09 Tc-l01 0.237 H 2.50E-02 2.70£-09 3.00E-09 Ru-103 39.280 D 1.00E-06 3.60£-09 4.20E-09 Ru-105 4.440 H 1.00E-06 4.50£-09 5.10E-09 Ru-106 368.200 D 1.00E-06 1.50£-09 1.80E-09 Ag-llOm 249.900 0 5.00E-02 1.80E-08 2.10E-08 Sb-122 2.700 0 1.50E-03 O.OOE+OO O.OOE+OO Sb-124 60.200 D 1.50E-03 1. 30£-08 1.50£-08 Sb-125 2.770 Y 1.50E-03 3.10£-09 3.50E-09 Indian Point 3 aDCM Page 3-36 Revision 18

aDCM Part II - Calculational Methodologies Table 3-2 2

Total Body & Skin Ground Plane Dose Factors (mrem/hr per pCi/m )

with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody(DFg) Skin (DFs)

Te-125m 58.000 o 1. 00E-03 3.50E-11 4.80E-11 Te-127m 109.000 D 1. 00E-03 1.10E-12 1.30E-12 Te-l27 9.350 H 1. 00E-03 1.00E-11 1.10E-11 Te-129m 33.600 D 1.00E-03 7.70E-10 9.00E-I0 Te-129 1.160 H 1. 00E-03 7.10E-10 8.40E-10 Te-131m 30.000 H 1.00E-03 8.40E-09 9.90E-09 Te-131 0.417 H 1. 00E-03 2.20E-09 2.60E-06 Te-132 3.258 D 1. 00E-03 1.70E-09 2.00E-09 1-130 12.360 H 6.00E-03 1.40E-08 1.70E-08 1-131 8.040 D 6.00E-03 2.80E-09 3.40E-09 1-132 2.300 H 6.00E-03 1. 70E-08 2.00E-08 1-133 20.800 H 6.00E-03 3.70E-09 4.50E-09 1-134 0.877 H 6.00E-03 1.60E-08 1.90E-08 1-135 6.610 H 6.00E-03 1.20E-08 1.40E-08 Cs-134 2.062 Y 1.20E-02 1.20E-08 1. 40E-08 Cs-136 13.100 D 1.20E-02 1.50E-08 1.70E-08 Cs-137 30.000 y 1. 20E-02 4.20E-09 4.90E-09 Cs-138 0.537 H 1. 20E-02 2.10E-08 2.40E-08 Ba-139 1. 378 H 4.00E-04 2.40E-09 2.70E-09 Ba-140 12.740 0 4.00E-04 2.10E-09 2.40E-09 Ba-Hl 0.304 H 4.00E-04 4.30E-09 4.90E-09 Ba-142 0.177 H 4.00E-04 7.90E-09 9.00E-09 La-140 1.678 D 5.00E-06 1.50E-08 1.70E-08 La-142 1.542 H 5.00E-06 1. 50E-08 1.80E-08 Ce-141 32.501 D 1.00E-04 5.50E-10 6.20E-10 Ce-143 33.000 H 1.00E-04 2.20E-09 2.50E-09 Ce-144 284.300 D 1. 00E-04 3.20E-10 3.70E-10 Pr-143 13.560 D 5.00E-06 O.OOE+OO O.OOE+OO Pr-144 0.288 H 5.00E-06 2.00E-I0 2.30E-10 Nd-147 10.980 D 5.00E-06 1. 00E-09 1. 20E-09 W-187 23.900 H 5.00E-04 3.10E-09 3.60E-09 Np-239 2.360 D 5.00E-06 9.50E-10 1.10E-09 K-40 1.28E+09 Y 1. 00E-02 O.OOE+OO O.OOE+OO Co-57 270.900 D 1.00E-03 9.10E-10 1. 00E-09 Sr-85 64.840 D 8.00E-04 O.OOE+OO O.OOE+OO Y-88 106.640 D 1.00E-05 O.OOE+OO O.OOE+OO Nb-94 2.03E+04 Y 2.50E-03 O.OOE+OO O.OOE+OO Nb-97 1. 202 H 2.50E-03 4.60E-09 5.40E-09 Cd-109 1.271 Y 1.20E-04 O.OOE+OO O.OOE+OO Sn-1l3 115.100 D 2.50E-03 O.OOE+OO O.OOE+OO Ba-133 10.740 Y 4.00E-04 O.OOE+OO O.OOE+OO Te-134 0.697 H 1.00E-03 1.00E-09 1.20£-09 Ce-139 137.660 D 1.00E-04 O.OOE+OO O.OOE+OO Hg-203 46.600 D 3.80E-02 O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-37 Revision 18

aDCM Part I( - Calculational Methodologies Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 Be-7 2.77E-09 6.26E-09 3.10E-09 O.OOE+OO 6.58E-09 O.OOE+OO 1.08E-06 Na-24 1. 70E-06 1.70E-06 1. 70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-05 Cr-51 O.OOE+OO O.OOE+OO 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 O.OOE+OO 4.57E-06 8.72E-07 O.OOE+OO 1.36E-06 O.OOE+OO 1.40E-05 Mn-56 O.OOE+OO 1. 15E-07 2.04E-08 O.OOE+OO 1. 46E-07 O.OOE+OO 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 O.OOE+OO O.OOE+OO 1.06E-06 1.09E-06 Fe-59 4.34E-06 1. 02E-05 3.91E-06 O.OOE+OO O.OOE+OO 2.85E-06 3.40E-05 Co-58 O.OOE+OO 7.45E-07 1.67E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E-05 Co-60 O.OOE+OO 2.14E-06 4.72E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1. 74E-06 Cu-64 O.OOE+OO 8.33E-08 3.91E-08 O.OOE+OO 2.10E-07 O.OOE+OO 7.10E-06 Zn-65 4.84E-06 1.54E-05 6. 96E-06 O.OOE+OO 1.03E-05 O.OOE+OO 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 O.OOE+OO 1.28E-08 O.OOE+OO 2.96E-09 Br-83 O.OOE+OO O.OOE+OO 4.02E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E-08 Br-84 O.OOE+OO O.OOE+OO 5.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.09E-13 Br-85 O.OOE+OO O.OOE+OO 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.11E-05 9.83E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.16E-06 Rb-88 O.OOE+OO 6.05E-08 3.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.36E-19 Rb-89 O.OOE+OO 4.01E-08 2.82E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-21 Sr-89 3.08E-04 O.OOE+OO 8.84E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.94E-05

. Sr-90 7.58E-03 O.OOE+OO 1. 86E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.19E-04 Sr-91 5.67E-06 O.OOE+OO 2.29E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-05 Sr-92 2.15E-06 O.OOE+OO 9.30E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.26E-05 Y-90 9.62E-09 O.OOE+OO 2.58E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-04 Y-91m 9.09E-11 O.OOE+OO 3.52E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-10 Y-91 1.41E-07 O.OOE+OO 3.77E-09 O.OOE+OO O.OOE+OO O.OOE+OO 7.76E-05 Y-92 8.45E-10 O.OOE+OO 2.47E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-05 Y-93 2.68E-09 O.OOE+OO 7.40E-11 O.OOE+OO O.OOE+OO O.OOE+OO 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 O.OOE+OO 1.53E-08 O.OOE+OO 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+OO 5.12E-I0 O.OOE+OO 1. 05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 O.OOE+OO 3.42E-09 O.OOE+OO 2.10E-05 Mo-99 O.OOE+OO 4.31E-06 8.20E-07 O.OOE+OO 9.76E-06 O.OOE+OO 9.99E-06 Tc-99m 2.47E-I0 6.98E-I0 8.89E-09 O.OOE+OO 1.06E-08 3.42E-I0 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 O.OOE+OO 6.59E-09 1. 87E-10 1.10E-21 Ru-l03 1.85E-07 O.OOE+OO 7.97E-08 O.OOE+OO 7.06E-07 O.OOE+OO 2.16E-05 Ru-l05 1. 54E-08 O.OOE+OO 6.08E-09 O.OOE+OO 1.99E-07 O.OOE+OO 9.42E-06 Ru-l06 2.75E-06 O.OOE+OO 3.48E-07 O.OOE+OO 5.31E-06 O.OOE+OO 1. 78£-04 Ag-llOm 1.60E-07 1.48£-07 8.79E-08 O.OOE+OO 2.91£-07 0.00£+00 6.04E-05 Sb-122 2.00E-07 4.60E-09 6.90E-08 3.10E-09 O.OOE+OO 1.20E-07 7.60E-05 Sb-124 2.80E-06 5.30E-08 1.10E-06 6.80E-09 O.OOE+OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 O.OOE+OO 1.38£-06 1.97E-05 Indian Point 3 aDCM Page 3-38 Revision 18

aDCM Part 1\ - Calculational Methodologies Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILL!

Te-125m 2.68E-o.6 9.71E-o.7 3.59E-o.7 8.o.6E-o.7 1.09E-o.S o..o.OE+Oo. 1.07E-o.S Te-127m 6.77E-o.6 2.42E-06 8.25E-07 1. 73E-06 2.75E-o.5 O.o.o.E+o.o. 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 O.OOE+OO 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-OS O.OOE+OO 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 O.OOE+OO 2.37E-08 Te-131m 1. 73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+OO 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+o.O 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+OO 7.71E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 O.OOE+OO 1.92E-06 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 O.OOE+OO 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+OO 1.02E-07 1-133 1.42E-06 2.47E-06 7.S3E-07 3.63E-04 4.31E-o.6 O.OOE+Oo. 2.22E-o.6 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+OO 2.51E-I0 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+OO 1. 31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 O.OOE+OO 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-OS O.OOE+OO 1.43E-05 1. 96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-OS O.OOE+OO 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1. 09E-07 5.40E-08 O.OOE+OO 8.01E-08 7.91E-09 4.6SE-13 Ba-139 9.70E-o.8 6.91E-11 2.84E-09 o..OOE+OO 6.46E-:11 3.92E-11 1. 72E-07 Ba-140 2.03E-o.5 2.55E-o.8 1.33E-o.6 o..o.OE+OO 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 O.Oo.E+o.O 3.31E-11 2.o.2E-11 2.22E-17 Ba-142 2.13E-o.8 2. 19E-11 1.34E-o.9 o..o.o.E+Oo. 1.85E-11 1. 24E-11 3.o.o.E-26 La-140 2.5o.E-09 1.26E-o.9 3.33E-1o. O.OOE+o.o. o..OOE+OO o..OOE+Oo. 9.25E-05 La-142 1. 28E-I0 5.82E-11 1. 45E-11 o..Oo.E+OO O.OOE+OO O.o.OE+o.O 4.25E-07 Ce-141 9.36E-09 6.33E-o.9 7.18E-1o. o..OOE+OO 2.94E-09 O.OOE+OO 2.42E-05 Ce-143 1. 65E-09 1.22E-06 1.35E-I0 o..OOE+Oo. 5.37E-Io. O.OOE+OO 4.56E-05 Ce-144 4.88E-07 2.04E-o.7 2.62E-o.8 o..OOE+Oo. 1.21E-07 o..o.OE+o.o. 1.65E-o.4 Pr-143 9.20E-09 3.69E-09 4.56E-Io. O.o.OE+OO 2.13E-09 O.OOE+OO 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 O.OOE+OO 7.05E-12 O.OOE+OO 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-I0 o..o.o.E+OO 4.2SE-09 O.o.o.E+o.O 3.49E-OS W-187 l.o.3E-o.7 8.61E-08 3.01E-o.8 O.Oo.E+OO o..OOE+OO O.OOE+OO 2.82E-o.5 Np-239 1.19E-09 1.17E-10 6.45E-11 O.Oo.E+o.o. 3.65E-1o. o..o.OE+O'O 2.4o.E-05 K-4o. o..o.o.E+o.O o..o.o.E+o.o. o..o.OE+o.o. o..o.o.E+Oo. o..o.o.E+o.o. o..OOE+Oo. o..Oo.E+o.O Co-S7 O.o.o.E+o.o. 1. 7 SE-o.7 2.91E-07 o..o.o.E+o.o. o..o.o.E+o.O o..o.OE+Oo. 4.44E-o.6 Sr-85 o..Oo.E+Oo. o..o.OE+Oo. o..o.OE+Oo. O.OOE+o.O o..o.o.E+o.o. o..o.o.E+o.o. o..OOE+o.o.

Y-88 O.o.o.E+o.o. o..o.o.E+o.o. o..o.o.E+o.O o..o.o.E+o.o. o..o.o.E+o.o. o..o.OE+o.o. o..o.o.E+o.O Nb-94 O.Oo.E+Oo. O.OOE+Oo. o..OOE+Oo. O.OOE+o.O O.o.o.E+o.O o..Oo.E+o.o. O.o.OE+o.o.

Nb-97 S.22E-11 1.32E-11 4.82E-12 o..o.o.E+o.O 1. 54E-11 O.o.o.E+Oo. 4.87E-o.8 Cd-109 O.OOE+o.O O.Oo.E+o.O O.Oo.E+o.O O.Oo.E+OO O.OOE+o.o. O.OOE+OO o..OOE+OO Sn-1l3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O:OOE+OO O.o.OE+OO o..OOE+OO Ba-133 O.OOE+OO O.OOE+o.O O.Oo.E+OO o..OOE+OO O.OOE+OO O.OOE+OO o..OOE+OO Te-134 3.24E-08 2.12E-o.8 1. 30E-08 2.83E-08 2.05E-o.7 O.o.o.E+OO 3. S9E-11 Ce-139 O.OOE+OO O.o.o.E+OO O.OOE+Oo. O.OOE+OO O.OOE+OO o..OOE+OO o..OOE+OO Hg-203 O'OOE+Oo. O.OOE+OO O.OOE+o.O O.OOE+OO o..OOE+OO O.OOE+OO o..Oo.E+OO Indian Point 3 ODCM Page 3-39 Revision 18

aDCM Part II - Calculational Methodologies Table 3-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1. 06E-07 1. 06E-07 1.06E-07 1.06E-07 1.06E-07 1. 06E-07 Be-7 3.96E-09 8.87E-09 4.43E-09 O.OOE+OO 9.40E-09 O.OOE+OO 1.08E-06 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-05 Cr-51 O.OOE+OO O.OOE+OO 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 O.OOE+OO 5.90E-06 1.17E-06 O.OOE+OO 1.76E-06 O.OOE+OO 1.21E-05 Mn-56 O.OOE+OO 1.58E-07 2.81E-08 O.OOE+OO 2.00E-07 O.OOE+OO 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+OO O.OOE+OO 1. 70E-06 1. 16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 O.OOE+OO O.OOE+OO 4.32E-06 3.24E-05 Co-58 O.OOE+OO 9.72E-07 2.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-05 Co-60 O.OOE+OO 2.81E-06 6.33E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.19E-06 Cu-64 O.OOE+OO 1.15E-07 5.41E-08 O.OOE+OO 2.91E-07 O.OOE+OO 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 O.OOE+OO 1. 28E-05 O.OOE+OO 8.47E-06 Zn-69 1.47E-08 2.80E-08 1. 96E-09 O.OOE+OO 1.83E-08 O.OOE+OO 5.16E-08 Br-83 O.OOE+OO O.OOE+OO 5.74E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 7.22E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

(

Br-85 O.OOE+OO O.OOE+OO 3.05E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I, Rb-86 O.OOE+OO 2.98E-05 1. 40E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.41E-06

'. Rb-88 O.OOE+OO 8.52E-08 4.54E-08 O.OOE+OO O.OOE+OO O.OOE+OO 7.30E-15 Rb-89 O.OOE+OO 5.50E-08 3.89E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.43E-17 Sr-89 4.40E-04 O.OOE+OO 1.26E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.24E-05 Sr-90 8.30E-03 O.OOE+OO 2.05E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-04 Sr-91 8.07E-06 O.OOE+OO 3.21E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-05 Sr-92 3.05E-06 O.OOE+OO 1.30E-07 O.OOE+OO O.OOE+OO O.OOE+OO 7.77E-05 Y-90 1.37E-08 O.OOE+OO 3.69E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E-04 Y-91m 1.29E-10 O.OOE+OO 4.93E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.09E-09 Y-91 2.01E-07 O.OOE+OO 5.39E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.24E-05 Y-92 1.21E-09 O.OOE+OO 3.50E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.32E-05 Y-93 3.83E-09 O.OOE+OO 1.05E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 O.OOE+OO 1.91E-08 O.OOE+OO 3.00E-05 Zr-97 2.37E-09 4.69E-I0 2.16E-I0 O.OOE+OO 7.11E-I0 O.OOE+OO 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 O.OOE+OO 4.42E-09 O.OOE+OO 1.95E-05 Mo-99 O.OOE+OO 6.03E-06 1.15E-06 O.OOE+OO 1.38E-05 O.OOE+OO 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 O.OOE+OO 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 O.OOE+OO 9.26E-09 3.12E-10 8.75E-l7 Ru-l03 2.55E-07 O.OOE+OO 1. 09E-07 O.OOE+OO 8.99E-07 O.OOE+OO 2.13E-05 Ru-105 2.18E-08 O.OOE+OO 8.46E-09 O.OOE+OO 2.75E-07 O.OOE+OO 1.76E-05 Ru-l06 3.92E-06 O.OOE+OO 4.94E-07 O.OOE+OO 7.56E-06 O.OOE+OO 1. 88E-04 Ag-11 Om 2.05£-07 1.94E-07 1.18E-07 O.OOE+OO 3.70E-07 0.00£+00 5.45E-05 Sb-122 3.30£-07 6.42E-09 9.64E-08 4.19E-09 O.OOE+OO 2.06E-07 6.92E-05 Sb-124 3.86E-06 7.12E-08 1. 51E-06 8.79E-09 O.OOE+OO 3.37E-06 7.81E-05 Sb-125 2.48E-06 2.71E-08 5.79E-07 2.36E-09 O.OOE+OO 2.16E-06 1.92E-05 Indian Point 3 aDCM Page 3-40 Revision 18

aDCM Part \I - Calculational Methodologies Table 3-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-12Sm 3.83E-06 1.38E-06 S.12E-07 1.07E-06 O.OOE+OO O.OOE+OO 1. 13E-OS Te-127m 9.67E-06 3.43E-06 1. 15E-06 2.30E-06 3.92E-05 O.OOE+OO 2.4lE-05 Te-127 1. 58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 O.OOE+OO 1. 22E-05 Te-129m 1.63E-05 6.05E-06 2.S8E-06 S.26E-06 6.82E-OS O.OOE+OO 6.12E-OS Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 O.OOE+OO 2.4SE-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-OS O.OOE+OO 9.39E-OS Te-131 2.79E-08 1.15E-08 8.72E-09 2.1SE-08 1. 22E-07 O.OOE+OO 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 O.OOE+OO. 7.00E-OS 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+OO 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1. 41E-05 O.OOE+OO 1. 62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1. 15E-06 O.OOE+OO 3.18E-07 1-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+OO 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+OO 5.10E-09 1-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 O.OOE+OO 1. 74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 O.OOE+OO 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+OO 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1. 49E-04 5.19E-05 O.OOE+OO 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49£:.. 07 7.45E-08 O.OOE+OO 1.10E-07 1.28E-08 6.76E-11 Ba-139 1. 39E~07 9.78E-11 4.05E-09 O.OOE+OO 9.22E-11 6.74E-11 1. 24E-06 Ba-140 2.84E-05 3.48E-08 1. 83E-06 O.OOE+OO 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.7lE-08 5.01E-11 2.24E-09 O.OOE+OO 4.65E-11 3.43E-11 1. 43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 O.OOE+OO 2.53E-11 1. 99E-11 9.18E-20 La-l40 3.48E-09 1. 7lE-09 4.55E-10 O.OOE+OO O.OOE+OO O.OOE+OO 9.82E-05 La-l42 1.79E-10 7. 95E-11 1. 98E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 O.OOE+OO 4.18E-09 O.OOE+OO 2.54E-05 Ce-143 2.35E-09 1. 7lE-06 1. 91E-10 O.OOE+OO 7.67E-10 O.OOE+OO 5.14E-05 Ce-l44 6. 96E-07 2.88E-07 3.74E-08 O.OOE+OO 1.72E-07 O.OOE+OO 1.75E-04 Pr-143 1. 31E-08 5.23E-09 6.52E-10 O.OOE+OO 3.04E-09 O.OOE+OO 4.31E-05 Pr-144 4.30E-11 1. 76E-11 2.18E-12 O.OOE+OO 1. 01E-11 O.OOE+OO 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 O.OOE+OO 5.99E-09 O.OOE+OO 3.68E-05 W-187 1. 46E-07 1.l9E-07 4.17E:-08 O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-05 Np-239 1. 76E-09 1. 66E-10 9.22E-11 O.OOE+OO 5.21E-10 O.OOE+OO 2.67E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 2.38E-07 3.99E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 7.37E-11 1. 83E-11 6.68E-12 O.OOE+OO 2. 14E-11 O.OOE+OO 4.37E-07 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-llJ O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 O.OOE+OO 1. 66E-09 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3.. 41 Revision 18

ODCM Part II - Calculational Methodologies Table 3-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 Be-7 1.18E-08 2.00E-08 1.32E-08 O.OOE+OO 1.97E-08 O.OOE+OO 1.12E-06 Na-24 5.80E-06 5.80E-06 5*.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E-05 Cr-51 O.OOE+OO O.OOE+OO 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 O.OOE+OO 1.07E-05 2.85E-06 O.OOE+OO 3.00E-06 O.OOE+OO 8.98E-06 Mn-56 O.OOE+OO 3.34E-07 7.54E-08 O.OOE+OO 4.04E-07 O.OOE+OO 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 O.OOE+OO O.OOE+OO 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-OS 1.33E-OS O.OOE+OO O.OOE+OO 7.74E-06 2.78E-OS Co-58 O.OOE+OO 1.80E-06 5.51E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE-05 Co-60 O.OOE+OO S.29E-06 1.56E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.93E-05 Ni-63 S.38E-04 2.88E-OS 1. 83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-06 Ni-6S 2.22E-06 2.09E-07 1.22E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.S6E-OS Cu-64 O.OOE+OO 2.45E-07 1.48E-07 O.OOE+OO S.92E-07 O.OOE+OO 1.15E-05 Zn-6S 1.37E-05 3.6SE-OS 2.27E-05 O.OOE+OO 2.30E-OS O.OOE+OO 6.41E-06 Zn-69 4.38E-08 6.33E-08 S.8SE-09 O.OOE+OO 3.84E-08 O.OOE+OO 3.99E-06 Br-83 O.OOE+OO O.OOE+OO 1. 71E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S O.OOE+OO O.OOE+OO 9.12E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 6.70E-05 4.12E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.31E-06 Rb-88 O.OOE+OO 1.90E-07 1.32E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.32E-09 Rb-89 O.OOE+OO 1. 17E-07 1.04E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-09 Sr-89 1.32E-03 O.OOE+OO 3.77E-05 O.OOE+OO O.OOE+OO O.OOE+OO S.l1E-OS Sr-90 1. 70E-02 O.OOE+OO 4.31E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-04 Sr-91 2.40E-OS O.OOE+OO 9.06E-07 O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-05 Sr-92 9.03E-06 O.OOE+OO 3.62E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1. 71E-04 Y-90 4.11E-08 O.OOE+OO 1.10E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 Y-91m 3.82E-10 O.OOE+OO 1.39E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.48E-07 Y-91 6.02E-07 O.OOE+OO 1.61E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.02E-05 Y-92 3.60E-09 O.OOE+OO 1.03E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-04 Y-93 1.14E-08 O.OOE+OO 3.13E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1. 70E-04 Zr-95 1. 16E-07 2.55E-08 2.27E-08 O.OOE+OO 3.65£-08 O.OOE+OO 2.66£-OS Zr-97 6.99E-09 1. 01E-09 5.96E-10 O.OOE+OO 1.4S£-09 O.OOE+OO 1.53E-04 Nb-95 2.2SE-08 8.76E-09 6.26E-09 0.00£+00 8.23£-09 O.OOE+OO 1.62E-05 Mo-99 O.OOE+OO 1.33E-OS 3.29E-06 O.OOE+OO 2.84£-OS O.OOE+OO 1.10E-05 Tc-99m 9.23E-10 1. 81E-09 3.00E-08 O.OOE+OO 2.63E-08 9.19E-10 1. 03E-06 Tc-l01 1.07E-09 1.12E-09 1. 42E-08 O.OOE+OO 1. 91E-08 5.92E-10 3.S6E-09 Ru-103 7.31E-07 O.OOE+OO 2.81£-07 O.OOE+OO 1.84E-06 O.OOE+OO 1.89E-OS Ru-10S 6.4SE-08 O.OOE+OO 2.34E-08 O.OOE+OO 5.67E-07 O.OOE+OO 4.21E-05 Ru-l06 1.17E-05 O.OOE+OO 1. 46E-06 O.OOE+OO 1.58E-OS O.OOE+OO 1.82E-04 Ag-llOm 5.39E-07 3.64E-07 2.91E-07 O.OOE+OO 6.78E-07 O.OOE+OO 4.33E-05 Sb-122 9.83E-07 1.45£-08 2.88E-07 1.26E-08 O.OOE+OO 4.00E-07 7.56E-05 Sb-124 1. 11E-05 1.44E-07 3.88E-06 2.44E-08 O.OOE+OO 6.15E-06 6.93E-OS Sb-12S 7.15E-06 S.SlE-08 1.50E-06 6.63E-09 0.00£+00 3.98£-06 1. HE-OS Indian Point 3 ODCM Page 3-42 Revision 18

aDCM Part II - Calculational Methodologies

/".

{' .

Table 3-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 O.OOE+OO O.OOE+OO 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 O.OOE+OO 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 O.OOE+OO 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+OO 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+OO 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.4lE-05 O.OOE+OO 1. 01E-04 T8-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 O.OOE+OO 4.36E-07 Te-132 1. 01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+OO 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 O.OOE+OO 2.76E-06 1-131 1. 72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+OO 1.54E-06 1-132 8.00E-07 1. 47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+OO 1. 73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+OO 2.95E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1. 79E-05 1. 19E-06 O.OOE+OO 5.16E-07 1-135 1.75E-06 3.15E-06 1. 49E-06 2.79E-04 4.83E-06 O.OOE+OO 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 O.OOE+OO 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+OO 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+OO 1.02E-04 3.67E-05 1. 96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 O.OOE+OO 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1. 20E-08 O.OOE+OO 1.93E-I0 1.30E-I0 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 O.OOE+OO 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1. 12E-10 6.51E-09 O.OOE+OO 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 O.OOE+OO 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 O.OOE+OO 8.68E-09 O.OOE+OO 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+OO 1.59E-09 O.OOE+OO 5.55E-05 Ce-144 2.08E-06 6.52E-07 1. 11E-07 O.OOE+OO 3.61E-07 O.OOE+OO 1. 70E-04 Pr-143 3.93E-08 1. 18E-08 1.95E-09 O.OOE+OO 6.39E-09 O.OOE+OO 4.24E-05 Pr-144 1. 29E-10 3.99E-11 6.49E-12 O.OOE+OO 2. 11E-11 O.OOE+OO 8.59E-08 Nd-147 2.79E-08 2.26E-08 1. 75E-09 O.OOE+OO 1.24E-08 O.OOE+OO 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+OO 1.09E-09 O.OOE+OO 2.79E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 4.93E-07 9.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.04E-06 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.17E-10 3. 92E-11 1. 83E-11 O.OOE+OO 4.35E-11 O.OOE+OO 1.21E-05 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 O.OOE+OO 5.89E-07 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-43 Revision 18

aDCM Part II - Calculational Methodologies Table 3-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 Be-7 2.26E-08 4.72E-08 2.51E-08 O.OOE+OO 3.34E-08 O.OOE+OO 1.11E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1. 70E-03 1.00E-04 6.59E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E-05 Cr-51 O.OOE+OO O.OOE+OO 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 O.OOE+OO 1.99E-05 4.51E-06 O.OOE+OO 4.41E-06 O.OOE+OO 7.31E-06 Mn-56 O.OOE+OO 8.18E-07 1.41E-07 O.OOE+OO 7.03E-07 O.OOE+OO 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 O.OOE+OO O.OOE+OO 4.39E-06 1. 14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 O.OOE+OO O.OOE+OO 1. 59E-05 2.57E-05 Co-58 O.OOE+OO 3.60E-06 8.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 8.97E-06 Co-60 O.OOE+OO 1.08E-05 2.55E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.05E-05 Cu-64 O.OOE+OO 6.09E-07 2.82E-07 O.OOE+OO 1. 03E-06 O.OOE+OO 1. 25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 O.OOE+OO 3.06E-05 O.OOE+OO 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 O.OOE+OO 6.98E-08 O.OOE+OO 1. 37E-05 Br-83 O.OOE+OO O.OOE+OO 3.63E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.82E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.94E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.70E-04 8.40E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E-06 Rb-88 O.OOE+OO 4.98E-07 2.73E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.85E-07 Rb-89 O.OOE+OO 2.86E-07 1. 97E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.74E-08 Sr-89 2.51E-03 O.OOE+OO 7.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.16E-05 Sr-90 1.85E-02 O.OOE+OO 4.71E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-04 Sr-91 5.00E-05 O.OOE+OO 1.81E-06 O.OOE+OO O.OOE+OO O.OOE+OO 5.92E-05 Sr-92 1.92E-05 O.OOE+OO 7.13E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E-04 Y-90 8.69E-08 O.OOE+OO 2.33E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 Y-91m 8.10E-10 O.OOE+OO 2.76E-ll O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-06 Y-91 1. 13E-06 O.OOE+OO 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.10E-05 Y-92 7.65E-09 O.OOE+OO 2.15E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E-04 Y-93 2.43E-08 O.OOE+OO 6.62E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 O.OOE+OO 5.41E-08 O.OOE+OO 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 O.OOE+OO 2.56E-09 O.OOE+OO 1.62£-04 Nb-95 4.20E-08 1. 73E-08 1. 00E-08 O.OOE+OO 1. 24E-08 O.OOE+OO 1.46E-05 Mo-99 O.OOE+OO 3.40E-05 6.63E-06 O.OOE+OO 5.08E-05 O.OOE+OO 1.12E-05 Tc-99m 1. 92E-09 3.96E-09 5.10E-08 O.OOE+OO 4.26E-08 2.07E-09 1. 15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 O.OOE+OO 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 O.OOE+OO 4.95E-07 O.OOE+OO 3.08E-06 O.OOE+OO 1.80E-05 Ru-105 1.36E-07 O.OOE+OO 4.58E-08 O.OOE+OO 1.00E-06 O.OOE+OO 5.41E-05 Ru-106 2. HE-OS O.OOE+OO 3.01E-06 O.OOE+OO 2.85E-05 O.OOE+OO 1.83E-04 Ag-llOm 9.96E-07 7.27E-07 4.81E-07 O.OOE+OO 1.04E-06 O.OOE+OO 3.77E-05 Sb-122 2.10E-06 3.85E-08 6.13E-07 3.14E-08 O.OOE+OO 1.09E-06 7.65E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 O.OOE+OO 1. 34E-05 6.60E-.05 Sb-125 1. 23E-05 1.19E-07 2.53E-06 1.54E-08 O.OOE+OO 7.72E-06 1.64E-05 Indian Point 3 aDCM Page 3-44 Revision 18

aDCM Part II - Calculational Methodologies Table 3-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00£+00 O.OOE+OO 1.11E-05 Te-127m 5.85£-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+O.O 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+OO 2.10E-05 Te-129m 1.00E-04 3.43E-05 1. 54E-05 3.84E-05 2.50£-04 O.OOE+OO 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O.OOE+OO 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+OO 1.03E-04 Te-131 1. 76E-07 6.50E-08 4.94E-08 1. 57E-07 4.50E-07 O.OOE+O.o 7.11E-06 Te-132 2.08E-05 1. 03£-05 9.61E-06 1. 52E-05 6.44E-05 O.OOE+OO 3.81E-05 I-130 6.00E-06 1. 32E-05 5.30E-06 1.48E-03 1.45£-05 O.OOE+OO 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1. 39E-02 4.94£-05 O.OOE+OO 1.51E-06 I-132 1. 66E-06 3.37E-06 1.20E-06 1.58E-04 3.76£-06 O.OOE+OO 2.73E-06 I-133 1. 25E-05 1. 82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+OO 3.08E-06 I-134 8.69E-07 1. 78E-06 6.33E-07 4.15E-05 1. 99E-06 O.OOE+OO 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+OO 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+OO 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+OO 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 O.OOE+OO 1.64E-04 6.64E-05 1. 91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 O.OOE+OO 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 O.OOE+OO 3.51E-10 3.54E-10 5.58E-05

/' .... Ba-140 1. 71E-04 1. 71E-07 8.81E-06 O.OOE+OO 4.06E-08 1.05E-07 4.20E-05 i

\

Ba-141 4.25E-07 2.91E-10 1. 34E-08 O.OOE+OO 1.75E-10 1. 77E-10 5.19E-06 Ba-l42 1.84E-07 1.53E-10 9.06E-09 O.OOE+OO 8.81E-11 9.26E-11 7.59E-07 La-l40 2.11E-08 8.32E-09 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.77E-05 La-142 1.10E-09 4.04E-10 9. 67E-11 O.OOE+OO O.OOE+OO O.OOE+OO 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 O.OOE+OO 1.48E-08 O.OOE+OO 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 O.OOE+OO 2.86E-09 O.OOE+OO 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+OO 4.93E-07 O.OOE+OO 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+OO 1. 13E-08 O.OOE+OO 4.29E-05 Pr-144 2.74E-10 1.06E-10 1. 38E-11 O.OOE+OO 3.84E-11 O.OOE+OO 4.93E-06 Nd-l47 5.53E-08 5.68E-08 3.48E-09 O.OOE+OO 2.19E-08 O.OOE+OO 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 O.OOE+OO 1.98E-09 O.OOE+OO 2.87E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.15E-06 1.87E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.92E-06 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+.OO Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-45 Revision 18

aDeM Part II - Calculational Methodologies

.(~/., ......

f", Table 3 - 4 TOTAL BODY DOSE FACTORS Ki FROM NOBLE GASES (GAMMA)

FINITE CLOUD **

CORRECTION NUCLIDE Gamma TB* X (pCi/uCi) X FACTOR Ki***

Kr-83rn 7.56E-08 1.00E+6 5.78E-Ol 4.37E-02 Kr-85m 1.17E-03 1. 00E+6 4.46E-01 5.22E+02 Kr-85 1. 61E-05 1.00E+6 3.85E-01 6.19E+00 Kr-87 5.92E-03 1.00E+6 3.09E-01 1.83E+03 Kr-88 1.47E-02 1.00E+6 2.88E-Ol 4.23E+03 Kr-89 1.66E-02 1. 00E+6 3.03E-Ol 5.03E+03 Kr-90 1.56E-02 1.00E+6 3.29E)"01 5.13E+03 C""

'" Xe-131m 9.15E-05 1.00E+6 5.62E-01 5.14E+01 Xe-133m 2.51E-04 1.00E+6 5.12E-Ol 1.29E+02 Xe-133 2.94E-04 1. 00E+6 5.78E-Ol 1.70E+02 Xe-135m 3.12E-03 1. 00E+6 3.87E-Ol . 1.21E+03 Xe-135 1. 81E-03 1. 00E+6 4.55E-01 8.24E+02 Xe-137 1. 42E-03 1. 00E+6 3.65E-01 5.18E+02 Xe-138 8.83E-03 1.00E+6 3.14E-01 2.77E+03 Ar-41 8.84E-03 1.00E+6 3.21E-01 2.84E+03

From Regulatory Guide 1.109, Table 8-1 (mrern/yr per pCi/cu mtr)

- The finite cloud correction factor is described in Section 3.6.

- - Ki (mrem/yr per uCi/cu mtr)

Indian Point 3 aDCM Page 3-46 Revision 18

aDCM Part II - Calculational Methodologies

/ ..............

f Table 3 - 5 SKIN DOSE FACTORS Li FROM NOBLE GASES (BETA)

NUCLIDE Beta Skin* x (pCi/uCi) Li**

Kr-83m O.OOE+OO 1. OOE+6 O.OOE+OO Kr-85m 1.4 fiE-03 1.00E+6 1.46E+03 Kr-85 1.34E-03 1.00E+6 1. 34E+03 Kr-87 9.73E-03 1.00E+6 9.73E+03 Kr-88 2.37E-03 1. OOE+6 2.37E+03 Kr-89 1.01E-02 1.00E+6 1.01E+04 Kr-90 7.29E-03 1.00E+6 7.29E+03 Xe-131m 4.76E-04 1. OOE+6 4.76E+02 Xe-133m 9.94E-04 1.00E+6 9.94E+02 Xe-133 3.06E-04 1.00E+6 3.06E+02 Xe-135m 7.llE-04 1. OOE+6 7.11E+02 Xe-135 1.86E-03 1. OOE+6 1. 86E+03 Xe-137 1.22E-02 1.00E+6 1. 22E+04 Xe-138 4.13E-03 1.00E+6 4.13E+03 Ar-41 2.69E-03 1.00E+6 2.69E+03

From Regulatory Guide 1.109, Table 8-1 (mrem/yr per pCi/eu mtr)

- Li (mrem!yr per uCi/eu mtr)

Indian Point 3 aDCM Page 3-47 Revision 18

ODCM Part II - Calculational Methodologies Table 3 - 6 AIR DOSE FACTORS Mi FROM NOBLE GASES (GAMMA)

FINITE CLOUD **

CORRECTION NUCLIDE Garruna* x (pCi/uCi) X FACTOR Mi***

Kr-83m 1. 93E-05 1. 00E+6 5.78E-01 1. 12E+Ol Kr-85m 1. 23E-03 1. 00E+6 4.46E-01 5.49E+02 Kr-85 1.72E-05 1. 00E+6 3.85E-01 6.62E+00 Kr-87 6.17E-03 1. 00E+6 3.09E-01 1.91E+03 Kr-88 1.52E-02 1.00E+6 2.88E-01 4.37E+03 Kr-89 1.73E-02 1.00E+6 3.03E-01 5.24E+03 Kr-90 1.63E-02 1.00E+6 3.29E-01 5.36E+03 Xe-131m 1.56E-04 1.00E+6 5.62E-01 8.77E+01 Xe-133m 3.27E-04 1.00E+6 5.12E-01 1. 68E+02 Xe-133 3.53E-04 1. 00E+6 5.78E-01 2.04E+02 Xe-135m 3.36E-03 1.00E+6 3.87E-01 1.30E+03 Xe-135 1. 92E-03 1. 00E+6 4.55E-01 8.74£+02 Xe-137 1. 51E-03 1. 00E+6 3.65E-01 5.51E+02 Xe-138 9.21E-03 1.00E+6 3.14E-01 2.89E+03 Ar-41 9.30E-03 1.00E+6 3.21E-01 2.99E+03

From Regulatory Guide 1. 109, Table B-1 (mrad/yr per pCi/cu mtr)

- The finite cloud correction factor is described in Section 3.6.

- - Mi (mrad/yr per uCi/cu mtr)

Indian Point 3 ODCM Page 3-48 Revision 18

ODCM Part II - Calculational Methodologies Table 3 - 7 AIR DOSE FACTORS Ni FROM NOBLE GASES (BETA)

NUCLIDE Beta* x (pCi/uCi) Ni**

Kr-83m 2.88E-04 I.OOE+6 2.88E+02 Kr-85m 1. 97E-03 1.00E+6 1. 97E+03 Kr-85 1.95E-03 1. 00E+6 1.9SE+03 Kr-87 1.03E-02 I.OOE+6 1. 03E-t04 Kr-88 2.93E-03 1. OOE+6 2.93E+03 Kr-89 1.06E-02 I.OOE+6 1. 06E+04 Kr-90 7. 83E...,03 1.OOE+6 7.83E+03 Xe-131m 1.l1E-03 I.OOE+6 1.l1E+03 Xe-133m 1.48E-03 1. OOE+6 1.48E+03 Xe-133 1.OSE-03 1. OOE+6 1.0SE+03 Xe-135m 7.39E-04 1. OOE+6 7.39E+02 Xe-13S 2.46E-03 1. OOE+6 2.46E+03 Xe-137 1. 27E-02 1.00E+6 1.27E+04 Xe-138 4.7SE-03 1.00E+6 4.7SE+03 Ar-4l 3.28E-03 1.00E+6 3.28E+03

From Regulatory Guide 1.109, Table B-1 (mrad/yr per pCi/eu mtr)

- Ni (mrad/yr per uCi/eu mtr)

Indian Point 3 ODCM Page 3-49 Revision 18

ODCM Part II - Calculational Methodologies TABLE3-8 NOBLE GAS DOSE FACTORS For Instantaneous and Time Average Mixtures at the Site Boundary Radionuclide Instantaneous Time Average Mix (%) MixjD/ol Kr-85m 3.09 Kr-85 0 18.98 Kr-87 2.80 Kr-88 5.22 Xe-131m 0 0.162 Xe-133m 1.39 0.485 Xe-133 56.8 78.1 Xe-13Sm 1.34 Xe-135 19.2 2.21 Xe-138 2.81 Ar-41 7.43 Total 100 100

( Unit 2 effective Unit 3 effective Unit 2 effective Unit 3 effective instantaneous instantaneous average average dose factors dose factors dose factors dose factors units K = 1507 K = 849 mremJyr per uCilm J K "" 237 K = 153

-L = 1310 L = 1310 mremJyr per uCilmJ L =540 L = 540

-M = 1601 M = 905 mrad/yr per uCi/m3 M = 281 M = 181 N = 1977 N = 1977 mrad/yr per uCilm3 N = 1254 N = 1254 Instantaneous Mixture Basis:

This mix defines the shared-site noble gas limits between the two units, and is used for administrative guidelines for instantaneous releases based on an RCS noble gas mix at 1.6 yrs into a 24-month cycle, with two failed fuel rods, per Reference 30. These mixtures provide conservative application for calculating setpoints per 10CFR20, in terms of uCi/sec before an actual sample of the release is available, per Appendix A.

Time Averaged Release Mixture Basis:

This mix defines the routine (time-averaged) releases from either unit. It was derived from average noble-gas releases from year 2000-2003 at IPEC units 2 and 3 per Reference 30. They are used in conjunction with calculations to determine representative quarterly and annual time averaged release rates in curies per second for administrative purposes only, per Appendix A Indian Point 3 ODCM Page 3-50 Revision 18

ODCM Part II - Calculational Methodologies TABLE 3-9 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCE Sept9 r i Distance Distance Distance to Site ,'.to Site". ' ' to, nearest Boundary Boundary residence.

by I Jrorn Uni~2' " from:Unlt3 " , from Unit 1 ":"":','

c;()mpass Plant Vent, , PlanfVent, superheab:~t,* .'.

,R?im '," in meters ihmeters" I, ,inmeters .' .'

,: :, "\":"',

N RIVER RIVER 1788.1 NNE RIVER RIVER 3111.3 NE 550 744 1907.3 ENE 600 775 1478.2 E 662 785 1370.9 ESE 569 622 715.2 SE 553 564 1168.2 SSE 569 551 1239.7 S 700 566 1132.5 SSW 755 480 1573.5 SW 544 350 3015.9 WSW RIVER RIVER 2169.6 W RIVER RIVER 1918.7 WNW RIVER RIVER 1752.4 NW RIVER RIVER 1692.7 NNW RIVER RIVER 1609.3 Distances to the Site Boundary are unit-specific and measured from the applicable unit's Plant Vent release point. Distances to the Nearest Residence are measured from the Unit 1 Superheater Stack for both Units 2 and 3, per Reference 31.

Indian Point 3 ODCM Page 3-51 Revision 18

aDCM Part II - Calculational Methodologies Table 3-10a 3

ADOLT INHALATION Ri (I) (mrem/yr per uCi 1m )

. Isotope BONE LIVER TOT BODY THYROID KIDNEY LONG GILLI H-3 O.OOE+OO 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1. 26E+03 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1. 02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 P-32 1. 32E+06 7.71E+04 5.01E+04 O.OOE+OO O.OOE+OO O.OOE+OO 8.64E+04 Cr-51 O.OOE+OO O.OOE+OO 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 Mn-56 O.OOE+OO 1.24E+00 1.83E-01 O.OOE+OO 1. 30E+00 9.44E+03 2.02E+04 fe-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 fe-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+05 Co-58 O.OOE+OO 1. 58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 1. 06E+05 Co-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 Ni-65 1. 54E+00 2.10E-01 9.12E-02 O.OOE+OO O.OOE+OO 5.60E+03 1.23E+04 Cu-64 O.OOE+OO 1. 46E+00 6.15E-01 O.OOE+OO 4.62E+00 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51E-02 4.52E-03 O.OOE+OO 4.22E-02 9.20E+02 1.63E+01 Br-83 O.OOE+OO O.OOE+OO 2.41E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 Br-84 O.OOE+OO O.OOE+OO 3.13E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 Br-85 O.OOE+OO O.OOE+OO 1.28E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 Rb-88 O.OOE+OO 3.87E+02 1.93E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 Rb-89 O.OOE+OO 2.56E+02 1.70E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 Sr-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1.40E+06 3.50E+05 Sr-90 9.92E+07 O.OOE+OO 6.10E+06 O.OOE+OO O.OOE+OO 9.60E+06 7.22E+05 Sr-91 6.19E+01 O.OOE+OO 2.50E+00 O.OOE+OO O.OOE+OO 3.65E+04 1.91E+05 Sr-92 6.74E+00 O.OOE+OO 2.91E-01 O.OOE+OO O.OOE+OO 1.65E+04 4.30E+04 Y-90 2.09E+03 O.OOE+OO 5.61E+01 O.OOE+OO O.OOE+OO 1.70E+05 5.06E+05 Y-91m 2.61E-01 O.OOE+OO 1.02E-02 O.OOE+OO O.OOE+OO 1.92E+03 1.33E+00 Y-91 4.62£+05 O.OOE+OO 1.24E+04 O.OOE+OO O.OOE+OO 1.70E+06 3.85E+05 Y-92 1. 03E+01 O.OOE+OO 3.02E-01 O.OOE+OO O.OOE+OO 1.57E+04 7.35E+04 Y-93 9.44E+01 0.00£+00 2.61E+00 O.OOE+OO O.OOE+OO 4.85E+04 4.22E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+OO 5.42E+04 1.77E+06 1.50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+00 O.OOE+OO 2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 O.OOE+OO 7.74E+03 5.05E+05 1.04E+05 Mo-99 O.OOE+OO 1. 21E+02 2.30£+01 O.OOE+OO 2.91£+02 9.12E+04 2.48E+05 Tc-99m 1.03E-03 2.91E-03 3.70E-02 O.OOE+OO 4.42E-02 7.64E+02 4.16E+03 Tc-101 4.18E-05 6.02E-05 5.90E-04 O.OOE+OO 1.08E-03 3.99E+02 1.09E-ll Ru-103 1.53£+03 O.OOE+OO 6.58E+02 O.OOE+OO 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 O.OOE+OO 3.11E-01 O.OOE+OO 1.02E+00 1.10E+04 4.82E+04 Ru-106 6.91E+04 O.OOE+OO 8.72E+03 O.OOE+OO 1.34E+05 9.36E+06 9.12E+05 Ag-llOm 1. 08E+04 1.00E+04 5.94E+03 O.OOE+OO 1. 97E+04 4.63E+06 3.02E+05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 O.OOE+OO 2.48E+06 4.06E+05 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 O.OOE+OO 1. 74E+06 1.01E+05 Indian Point 3 aDCM Page 3-52 Revision 18

ODCM Part II - Calculational Methodologies Table 3-l0a 3

ADULT INHALATION Ri (I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127m 1.26E+04 5.77E+03 1. 57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1. 40E+00 6.42E-01 3.10E-01 1.06E+00 5.10E+00 6.51E+03 5.74E+04 Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 Te-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-Ol 1.94E+03 1. 57E+02 Te-131m 6.99E+01 4.36E+01 2.90E+Ol 5.50E+01 3.09E+02 1.46E+05 5.56E+05 Te-131 1. 11E-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1. 39E+03 1.84E+Ol Te-l32 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 I-l30 4.58E+03 1.34E+04 5.28E+03 1. 14E+06 2.09E+04 O.OOE+OO 7.69E+03 I-l31 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.l3E+04 O.OOE+OO 6.28E+03 I-l32 1. 16E+03 3.26E+03 1.16E+03 1. 14E+05 5.18E+03 O.OOE+OO 4.06E+02 I-l33 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 I-l34 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO 1. 01E+00 I-l35 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.11E+04 O.OOE+OO 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1. 46E+05 1.10E+05 O.OOE+OO 8.56E+04 1.20E+04 1.17E+04 Cs-l37 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 7.52E+04 8.40E+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 O.OOE+OO 4.80E+02 4.86E+Ol 1.86E-03 Ba-139 9.36E-01 6.66E-04 2.74E-02 O.OOE+OO 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27E+06 2.18E+05 Ba-141 1. 00E-01 7.53E-05 3.36E-03 O.OOE+OO 7.00E-05 1.94E+03 1.16E-07

.... Ba-142 2.63E-02 2.70E-05 1.66E-03 O.OOE+OO 2.29E-05 1.19E+03 1.57E-16

( La-140 3.44E+02 1.74E+02 4.58E+01 O.OOE+OO O.OOE+OO 1.36E+05 4.58E+05 La-142 6.83E-Ol 3.10E-Ol 7.72E-02 O.OOE+OO O.OOE+OO 6.33E+03 2.11E+03 Ce-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+OO 6.26E+03 3.62E+05 1.20E+05 Ce-143 1.86E+02 1. 38E+02 1.53E+01 O.OOE+OO 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43E+06 1. 43E+06 1. 84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 Pr-144 3.01E-02 1.25E-02 1.53E-03 O.OOE+OO 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.10E+03 3.65E+02 O.OOE+OO 3.56E+03 2.21E+05 1. 73E+05 W-187 8.48E+00 7.08E+00 2.48E+00 O.OOE+OO O.OOE+OO 2.90E+04 1.55E+05 Np-239 2.30E+02 2.26E+01 1.24E+01 O.OOE+OO 7.00E+Ol 3.76E+04 1.19E+05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 6.92E+02 6.71E+02 O.OOE+OO O.OOE+OO 3.70E+05 3.14E+04 Sr-85 3.20E+04 O.OOE+OO 7.76E+05 O.OOE+OO O.OOE+OO 4.80E+05 6.08E+04 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.22E-Ol 5.62E-02 2.05E-02 O.OOE+OO 6.54E-02 2.40E+03 2.42E+02 Cd-109 O.OOE+OO 3.92E+05 1.28E+04 O.OOE+OO 3.76E+05 7.28E+05 6.56E+04 Sn-113 6.56E+04 2.16E+03 4.48E+03 1.36E+03 O.OOE+OO 9.60E+05 1.20E+04 Ba-133 7.60E+04 3.36E+03 2.00E+04 O.OOE+OO 1.68E+01 1.52E+06 8.00E+04 Te-l34 3.07E-02 2.58E-02 1.26E-02 2.75E-02 1. 74E-01 3.47E+03 2.38E-01 Ce-l39 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 ODCM Page 3-53 Revision 18

aDCM Part II - Calculational Methodologies Table 3-10b 3

TEEN INHALATION Ri (I) (mrem/yr per uCi/m )

Isotope BONE LIVEF, TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.27E+03 1. 27E+03 1.27E+03 1. 27E+03 1. 27E+03 1.27E+03 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1. 38E+04 P-32 1. 89E+06 1.10E+05 7.16E+04 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E+04 Cr-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 Mn-54 O.OOE+OO 5.11E+04 8.40E+03 O.OOE+OO 1. 27E+04 1.98E+06 6.68E+04 Mn-56 O.OOE+OO 1.70E+00 2.52E-01 O.OOE+OO 1. 79E+00 1. 52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+OO O.OOE+OO 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+OO O.OOE+OO 1.53E+06 1. 78E+05 Co-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO 1.34E+06 9.52E+04 Co-60 O.OOE+OO 1. 51E+04 1. 98E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.07E+05 1. 42E+04 Ni-65 2.18E+00 2.93E-01 1.27E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+00 8.48E-01 O.OOE+OO 6.41E+00 1.11E+04 6.14E+04 Zn-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 1.24E+06 4.66E+04 Zn-69 4.83E-02 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1.58E+03 2.85E+02 Br-83 O.OOE+OO O.OOE+OO 3.44E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.83E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+04 Rb-88 O.OOE+OO 5.46E+02 2.72E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E-05 Rb-89 O.OOE+OO 3.52E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.38E-07 Sr-89 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71E+05 Sr-90 1.08E+08 O.OOE+OO 6.68E+06 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Sr-91 8.80E+01 O.OOE+OO 3.51E+00 O.OOE+OO O.OOE+OO 6.07E+04 2.59E+05 Sr-92 9.52E+00 O.OOE+OO 4.06E-01 O.OOE+OO O.OOE+OO 2.74£+04 1. 19E+05 Y-90 2.98E+03 O.OOE+OO 8.00E+01 O.OOE+OO O.OOE+OO 2.93E+05 5.59E+05 Y-91m 3.70E-01 O.OOE+OO 1.42E-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 Y-91 6.61E+05 O.OOE+OO 1.77E+04 0.00£+00 O.OOE+OO 2.94£+06 4.09E+05 Y-92 1.47E+01 O.OOE+OO 4.29E-01 O.OOE+OO O.OOE+OO 2.68E+04 1.65E+05 Y-93 1.35E+02 O.OOE+OO 3.72E+00 O.OOE+OO O.OOE+OO 8.32E+04 5.79E+05 Zr-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 O.OOE+OO 4.12E+01 1.30E+05 6.30E+05 Nb-95 1. 86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 Mo-99 O.OOE+OO 1.69E+02 3.22E+01 O.OOE+OO 4.11E+02 1.54E+05 2.69E+05 Tc-99m 1.38E-03 3.86E-03 4.99E-02 O.OOE+OO 5.76E-02 1.15E+03 6.13E+03 Tc-101 5.92E-05 8.40E-05 8.24E-04 O.OOE+OO 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+00 O.OOE+OO 4.34E-01 O.OOE+OO 1.41E+00 1.82E+04 9.04E+04 Ru-106 9.84E+04 O.OOE+OO 1. 24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 Ag-llOm 1.38E+04 1.31E+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 ' 4.30E+04 7.94E+02 1.68E+04 9.76E+01 O.OOE+OO 3.85E+06 3.98E+05 Sb-125 7.38E+04 8.08E+02 1. 72£+04 7.04E+01 O.OOE+OO 2.74E+06 9.92E+04 Indian Point 3 aDCM Page 3-54 Revision 18

aDCM Part" - Calculational Methodologies 1'...... 17',.".

~

Table 3-l0b 3

TEEN INHALATION Ri(I) (rnrern/yr per uCi/rn )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LONG GILLI Te-125rn 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 5.36E+05 7.50E+04 Te-127rn 1. 80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1. 59E+05 Te-127 2.01E+00 9.12E-01 4.42E-01 1. 42E+00 7.28E+00 1.12E+04 8.08E+04 Te-129m 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131rn 9.84E+01 6.01E+01 4.02E+01 7.25E+Ol 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1. 24E-02 6.18E-02 2.34E+03 1. 51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 1-130 6.24E+03 1. 79E+04 7.17E+03 1.49E+06 2.75E+04 O.OOE+OO 9.12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 O.OOE+OO 1. 27E+03 1-133 1. 22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1.03E+04 1-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+OO 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 6.95E+03 Cs-134 5.02E+05 1. 13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.10E+05 1.78E+04 1.09E+04 C5-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 O.OOE+OO 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+00 9.44E-04 3.90E-02 O.OOE+OO 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+Ol 3.52E+03 O.OOE+OO 2.28E+01 2.03E+06 2.29E+05 Ba-141 1. 42E-01 1.06E-04 4.74E-03 O.OOE+OO 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 O.OOE+OO 3.14E-05 1.91E+03 4.79E-I0 La-140 4.79E+02 2.36E+02 6.26E+Ol O.OOE+OO O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-Ol 1.06E-01 O.OOE+OO O.OOE+OO 1.02E+04 1. 20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1. 94E+02 2.16E+Ol O.OOE+OO 8.64E+Ol 1. 30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21E+06 1.34E+07 8.64E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 O.OOE+OO 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1. 82E+05 W-187 1. 20E+01 9.76E+00 3.43E+00 O.OOE+OO O.OOE+OO 4.74E+04 1.77E+05 Np-239 3.38E+02 3.19E+01 1.77E+01 O.OOE+OO 1.00E+02 6.49£.+04 1.32E+05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 9.44E+02 9.20E+02 O.OOE+OO O.OOE+OO 5.86E+05 3.14E+04 Sr-85 4.00E+04 O.OOE+OO 1.04E+04 O.OOE+OO O.OOE+OO 7.04E+05 5.52E+04 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.14E-Ol 7.78E-02 2.84E-02 O.OOE+OO 9.12E-02 3.93E+03 2.17E+03 Cd-109 O.OOE+OO 8.00E+05 2.72E+04 O.OOE+OO 5.36E+05 1.28E+06 6.88E+04 Sn-1l3 1.20E+05 3.76E+03 7.76E+03 2.32E+03 O.OOE+OO 1.60E+06 1. 20E+04 Ba-133 3.76E+05 6.40E+03 2.64E+04 O.OOE+OO 2.24E+01 2.32E+06 7.76E+04 Te-134 4.25E-02 3.48E-02 2.91E-02 3.57E-02 2.33E-01 5.40E+03 1.10E+Ol Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

(

\

Indian Point 3 aDCM Page 3-55 Revision 18

aDCM Part II - Calculational Methodologies Table 3-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 P-32 2.60E+06 1.14E+05 9.88E+04 O.OOE+OO O.OOE+OO O.OOE+OO 4.22E+04 Cr-51 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+Ol 2.43E+Ol 1.70E+04 1. 08E+03 Mn-54 O.OOE+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1.58E+06 2.29E+04 Mn-56 O.OOE+OO 1.66E+00 3.12E-Ol O.OOE+OO 1.67E+00 1.31E+04 1.23E+OS Fe-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1. 67E+04 O.OOE+OO O.OOE+OO 1. 27E+06 7.07E+04 Co-58 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 Co-60 O.OOE+OO 1.31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+OS 6.33E+03 Ni-6S 2.99E+00 2.96E-01 1.64E-01 O.OOE+OO O.OOE+OO 8.18E+03 8.40E+04 Cu-64 O.OOE+OO 1.99E+00 1. 07E+00 O.OOE+OO 6.03E+00 9.S8E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 Zn-69 6.70E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 1.42E+03 1.02E+04 Br-83 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO S.48E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S O.OOE+OO O.OOE+OO 2.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.98E+OS 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO S.62E+02 3.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E+01 Rb-89 O.OOE+OO 3.45E+02 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.89E+00 Sr-89 5.99E+05 O.OOE+OO 1. 72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+OS Sr-90 1.01E+08 O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Sr-91 1.21E+02 O.OOE+OO 4.59E+00 O.OOE+OO O.OOE+OO 5.33E+04 1.74E+OS Sr-92 1. 31E+01 O.OOE+OO 5.25E-01 O.OOE+OO O.OOE+OO 2.40E+04 2.42E+05 Y-90 4.11E+03 O.OOE+OO 1. 11E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 Y-91m 5.07E-01 O.OOE+OO 1. 84E-02 O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 Y-91 9.14E+OS O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1. 84E+OS Y-92 2.04E+01 O.OOE+OO 5.81E-01 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+OS Y-93 1.86E+02 O.OOE+OO S . 11E+OO O.OOE+OO O.OOE+OO 7.44E+04 3.89E+OS Zr-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 O.OOE+OO 3.88E+01 1.13E+OS 3.S1E+OS Nb-95 2.35E+04 9.18E+03 6.S5E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 Mo-99 O.OOE+OO 1.72E+02 4.2SE+01 O.OOE+OO 3.92E+02 1.3SE+OS 1.27E+05 Tc-99m 1.78E-03 3.48E-03 S.77E-02 O.OOE+OO 5.07E-02 9.S1E+02 4.81E+03 Tc-101 8.10E-OS 8.S1E-OS 1.08E-03 O.OOE+OO 1.4SE-03 S.8SE+02 1.63E+01 Ru-103 2.79E+03 O.OOE+OO 1. 07E+03 O.OOE+OO 7.03E+03 6.62E+OS 4.48E+04 Ru-10S 1.53E+00 O.OOE+OO 5.55E-01 O.OOE+OO 1. 34E+00 1.S9E+04 9.9SE+04 Ru-106 1.36E+OS O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+OS 1.43E+07 4.29E+05 Ag-llOm 1.69E+04 1. 14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.00E+05 Sb-l22 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 O.OOE+OO 2.32E+06 4.03E+04 Indian Point 3 aDCM Page 3-56 Revision 18

aDcM Part II - Calculational Methodologies

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f Table 3-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 4.77E+05 3.38E+04 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.361::+04 1.48E+06 7.14E+04 Te-127 2. 77E+OO* 9.51E-Ol 6.10E-Ol 1.96E+00 7.07E+00 1.00E+04 5.62E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1. 76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38£-02 7.14E-02 2.57E-Ol 2.93E+03 2.55E+04 Te-131m 1.34E+02 5.92E+Ol 5.07E+Ol 9.77E+Ol 4.00E+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77£+03 3.77E+05 1.38£+05 I-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.OOE+OO 5. 11E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 I-132 2.12E+03 4.07E+03 1. 88E+03 1.94E+05 6.25E+03 0.00£+00 3.20E+03 I-133 1. 66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 I-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1. 34E+04 O.OOE+OO 4.44E+03 Cs-134 6.51E+05 1.01E+06 2.25E+05 O.OOE+OO 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 O.OOE+OO 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.OOE+OO 6.22E+02 6.81E+01 2.70E+02 Ba-139 1.84E+00 9.84E-04 5.36E-02 O.OOE+OO 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11E+Ol 1.74E+06 1.02E+05 Ba-141 1. 96E-01 1.09E-04 6.36E-03 O.OOE+OO 9.47E-05 2.92E+03 2.75E+02 Ba-142 4.99E-02 3.60E-05 2.79E-03 O.OOE+OO 2.91E-05 1.64E+03 2.74E+00 La-l40 6.44E+02 2.25E+02 7.55E+01 O.OOE+OO O.OOE+OO 1.83E+05 2.26E+05 La-l42 1.29E+00 4.11E-Ol 1.29E-01 O.OOE+OO O.OOE+OO 8.70E+03 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90E+03 O.OOE+OO 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+01 O.OOE+OO 8.36E+01 1.15E+05 1.27E+05 Ce.:..144 6.77E+06 2.12E+06 3.61E+05 O.OOE+OO 1.17E+06 1.20E+07 3.89E+05 Pr-143 1. 85E+04 5.55E+03 9.l4E+02 O.OOE+OO 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.00E-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 .J Nd-147 1. 08E+04 8.73E+03 6.81E+02 O.OOE+OO 4.81E+03 3.28E+05 8.21E+04 W-187 1.63E+Ol 9.66E+00 4.33E+00 O.OOE+OO O.OOE+OO 4.11E+04 9.10E+04 Np-239 4.66E+02 3.34E+01 2.35E+01 O.OOE+OO 9.73E+01 5.81E+04 6.40E+04 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 9.03E+02 1.07E+03 O.OOE+OO O.OOE+OO 5.07E+05 1.32E+04 Sr-85 4.44E+04 O.OOE+OO 1. 18E+04 O.OOE+OO O.OOE+OO 5.55E+05 2.04E+04 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 4.29E-01 7.70E-02 3.60E-02 O.OOE+OO 8.55E-02 3.42E+03 2.78E+04 Cd-109 O.OOE+OO 7.03E+05 2.96E+04 O.OOE+OO 6.29E+05 1. 11E+06 3.00E+04 Sn-113 1. 41E+05 3.29E+03 8.51E+03 2.63E+03 O.OOE+OO 1.33E+06 4.81E+03 Ba-133 4.07E+05 4.07E+03 3.70E+04 O.OOE+OO 2.00E+Ol 1.92E+06 3.07E+04 Te-134 5.66E-02 3.26E-02 3.48E-02 4.59E-02 2.11E-01 4.55E+03 1.80E+03 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-57 Revision 18

aDCM Part II - Calculational Methodologies

/ .....

~.

Table 3-10d 3

INFANT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 6.47E+02 6.47E+02 6.47E+02 6.*47E+02 6.47E+02 6.47E+02 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.06E+04 1.06E+04 1.06E+04 1. 06E+04 1.06E+04 1.06E+04 1.06E+04 P-32 2.03E+06 1.12E+05 7.74E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 Cr-51 O.OOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 Mn-56 O.OOE+OO 1.54E+00 2.21E-01 O.OOE+OO 1.10E+00 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 Fe-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04 Co-58 O.OOE+OO 1. 22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1. 11E+04 Co-60 O.OOE+OO 8.02E+03 1. 18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 Ni-65 2.39E+00 2.84E-01 1.23E-01 O.OOE+OO O.OOE+OO 8.12E+03 5.01E+04 Cu-64 O.OOE+OO 1. 88E+00 7.74E-Ol O.OOE+OO 3.98E+00 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 O.OOE+OO 4.02E-02 1.47E+03 1.32E+04 Br-83 O.OOE+OO O.OOE+OO 3.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Rb-88 O.OOE+OO 5.57E+02 2.87E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E+02 Rb-89 O.OOE+OO 3.2lE+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+01

/'"

'.'.... Sr-89 3.98E+05 O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 Sr-90 4.09E+07 O.OOE+OO 2.59E+06 O.OOE+OO O.OOE+OO 1.12E+07 1.31E+05 Sr-91 9.56E+01 O.OOE+OO 3.46E+00 O.OOE+OO O.OOE+OO 5.26E+04 7.34E+04 Sr-92 1.05E+01 O.OOE+OO 3.91E-01 O.OOE+OO O.OOE+OO 2.38E+04 1.40E+05 Y-90 3.29E+03 O.OOE+OO 8.82E+01 O.OOE+OO O.OOE+OO 2.69E+05 1.04E+05 Y-91m 4.07E-01 O.OOE+OO 1.39E-02 O.OOE+OO O.OOE+OO 2.79E+03 2.35E+03 Y-91 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 7.03E+04 Y-92 1.64E+Ol O.OOE+OO 4.61E-01 O.OOE+OO O.OOE+OO 2.45E+04 1.27E+05 Y-93 ],.50E+02 O.OOE+OO 4.07E+00 O.OOE+OO O.OOE+OO 7.64E+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11E+04 1. 75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+01 1.17E+01 O.OOE+OO 2.59E+01 1.10E+05 1.40E+05 Nb-95 1. 57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 1. 27E+04 Mo-99 O.OOE+OO 1. 65E+02 3.23E+01 O.OOE+OO 2.65E+02 1. 35E+05 4.87E+04 Tc-99m 1.40E-03 2.88E-03 3.72E-02 O.OOE+OO 3.11E-02 8.11E+02 2.03E+03 Tc-101 6.51E-05 8.23E-05 8.12E-04 O.OOE+OO 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.02E+03 O.OOE+OO 6.79E+02 O.OOE+OO 4.24E+03 5.52E+05 1.61E+04 Ru-105 1.22E+00 O.OOE+OO 4.10E-01 O.OOE+OO 8.99E-01 1.57E+04 4.84E+04 Ru-l06 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 1.64E+05 Ag-110m 9.98E+03 7.22E+03 5.00E+03 O.OOE+OO 1.09E+04 3.67E+06 3.30E+04 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 3.79E+04 5.56E+02 1.20E+04 1.01E+02 O.OOE+OO 2.65E+06 5.91E+04 Sb-125 5.17E+04 4.77E+02 1.09E+04 6.23E+Ol O.OOE+OO 1.64E+06 1.47E+04

/'

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Indian Point 3 aDCM Page 3-58 Revision 18

aDCM Part" - Calculational Methodologies Table 3-l0d 3

INfANT INHALATION Ri(I} (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.76E+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+OO 4.47E+05 1. 29E+04 Te-127m 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+04 9.53E-Ol 4.89E-Ol 1.85E+00 4.86E+00 1. 03E+04 2.44E+04 Te-129m 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-Ol 3.00E+03 2.63E+04 Te-131m 1.07E+02 5.50E+Ol 3.63E+Ol 8.93E+Ol 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1. 76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 I-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 O.OOE+OO 1.99E+03 I-l31 3.79E+04 4.44E+04 1. 96E+04 1.48E+07 5.18E+04 O.OOE+OO 1.06E+03 I-l32 1. 69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 O.OOE+OO 1.90E+03 I-133 1. 32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 I-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+OO 1.29E+03 I-US 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 O.OOE+OO 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 O.OOE+OO 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04 1.35E+05 5.29E+04 O.OOE+OO 5.64E+04 1.18E+04 1. 43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 O.OOE+OO 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+00 9.84E-04 4.30E-02 O.OOE+OO 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+Ol 2.90E+03 O.OOE+OO 1. 34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-Ol 1.08E-04 4.97E-03 O.OOE+OO 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 O.OOE+OO 1. 90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.00E+02 5.15E+Ol O.OOE+OO O.OOE+OO 1.68E+05 8.48E+04 La-142 1.03E+00 3.77E-Ol 9.04E-02 O.OOE+OO O.OOE+OO 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.67E+04 1. 99E+03 O.OOE+OO 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E+02 1.93E+02 2:21E+Ol O.OOE+OO 5.64E+Ol 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1. 76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 O.OOE+OO 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.00E+02 O.OOE+OO 3.15E+03 3.22E+05 3.12E+04 W-187 1.30E+Ol 9.02E+00 3.12E+00 O.OOE+OO O.OOE+OO 3.96E+04 3.56E+04 Np-239 3.71E+02 3.32E+Ol 1.88E+Ol O.OOE+OO 6.62E+Ol 5.95E+04 2.49E+04 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 6.51E+02 6.41E+02 O.OOE+OO O.OOE+OO 3.79E+05 4.86E+03 Sr-85 3.78E+04 O.OOE+OO 7.56E+03 O.OOE+OO O.OOE+OO 4.20E+05 6.72E+03 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.42E-01 7.29E-02 2.63E-02 O.OOE+OO 5.70E-02 3.32E+03 2.69E+04 Cd-109 O.OOE+OO 3.64E+05 1.40E+04 O.OOE+OO 2.80E+05 8.68E+05 1.12E+04 Sn-113 8.40E+04 2.24E+03 5.04E+03 1.82E+03 O.OOE+OO 1.09E+06 1.68E+03 Ba-133 2.66E+05 2.38E+03 1.82E+04 O.OOE+OO 1.25E+01 1.27E+06 1.08E+04 Te-134 4.45E-02 2.86E-02 2.35E-02 4.07E-02 1. 34E-01 4.10E+03 3.54E+03 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-59 Revision 18

aDCM Part II - Calculational Methodologies Table 3-11a ADULT INGESTION (Leafy Vegetable) Ri(V) 2 3 m

mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 Be-7 9.36E+04 2.11E+05 1.05E+05 O.OOE+OO 2.22E+05 O.OOE+OO 3.65E+07 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 P-32 1.40E+09 8.73E+'07 5.43E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+08 Cr-51 O.OOE+OO O.OOE+OO 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 Mn-54 O.OOE+OO 3.13E+08 5.97E+07 O.OOE+OO 9.31E+07 O.OOE+OO 9.58E+08 Mn-56 O.OOE+OO 1.59E+01 2.82E+00 O.OOE+OO 2.02E+Ol O.OOE+OO 5.07E+02 Fe-55 2.10E+08 1.45E+08 3.38E+07 O.OOE+OO O.OOE+OO 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.13E+08 O.OOE+OO O.OOE+OO 8.27E+07 9.86E+08 Co-58 O.OOE+OO 3.07E+07 6.89E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+08 Co-60 O.OOE+OO 1.67E+08 3.69E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+09 Ni-63 1.04E+10 7.21E+08 3.49E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+08 Ni-65 6.15E+01 7.99E+00 3.64E+00 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E+02 Cu-64 O.OOE+OO 9.20E+03 4.32E+03 O.OOE+OO 2.32E+04 O.OOE+OO 7.84E+05 Zn-65 3.17E+08 1. 01E+09 4.56E+08 O.OOE+OO 6.75E+08 O.OOE+OO 6.36E+08 Zn-69 8.73E-06 1. 67E-05 1. 16E-06 O.OOE+OO 1. 09E-05 O.OOE+OO 2.51E-06 Br-83 O.OOE+OO O.OOE+OO 3.11E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.47E+00

. Br-84 O.OOE+OO O.OOE+OO 2.48E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1. 94E-16 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

., .... Rb-86 O.OOE+OO 2.19E+08 1.02E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.33E+07

{

Rb-88 O.OOE+OO 3.43E-22 1.82E-22 O.OOE+OO O.OOE+OO O.OOE+OO 4.74E-33

\, ....... Rb-89 O.OOE+OO 1.39E-26 9.74E-27 O.OOE+OO O.OOE+OO O.OOE+OO 8.05E-40 Sr-89 9.96E+09 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+09 Sr-90 6.05E+11 O.OOE+OO 1.48E+11 O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+10 Sr-91 3.05E+05 O.OOE+OO 1.23E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1. 45E+06 Sr-92 4.27E+02 O.OOE+OO 1. 85E+01 O.OOE+OO O.OOE+OO O.OOE+OO 8.45E+03 Y-90 1. 33E+04 O.OOE+OO 3.56E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+08 Y-91m 5.22E-09 O:OOE+OO 2.02E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E-08 Y-91 5. 11E+06 O.OOE+OO 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.81E+09 Y-92 9.15E-01 O.OOE+OO 2.68E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+04 Y-93 1. 70E+02 O.OOE+OO 4.68E+00 O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+06 Zr-95 1.17E+06 3.77E+05 2.55E+05 O.OOE+OO 5.91E+05 O.OOE+OO 1.19E+09 Zr-97 3.37E+02 6.81E+01 3.11E+01 O.OOE+OO 1.03E+02 O.OOE+OO 2.11E+07 Nb-95 1. 43E+05 7.94E+04 4.27E+04 O.OOE+OO 7.85E+04 O.OOE+OO 4.82E+08 Mo-99 O.OOE+OO 6.15E+06 1.17E+06 O.OOE+OO 1.39E+07 O.OOE+OO 1.43E+07 Tc-99m 3.10E+00 8.77E+00 1.12E+02 O.OOE+OO 1.33E+02 4.30E+00 5.19E+03 Tc-101 8.22E-31 1.18E-30 1.16E-29 O.OOE+OO 2.13E-29 6.05E-31 3.56E-42 Ru-103 4.76E+06 O.OOE+OO 2.05E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.56E+08 Ru-105 5.39E+01 0.00E+00 2.13E+01 O.OOE+OO 6.96E+02 O.OOE+OO 3.29E+04 Ru-106 1.93E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1. 25E+10 Ag-llOm 1.05E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+07 O.OOE+OO 3.98E+09 Sb-122 2.80E+05 6.43E+03 9.65E+04 4.34E+03 O.OOE+OO 1.68E+05 1.06E+08 Sb-124 1.04E+08 1.96E+06 4.07£+07 2.52E+05 O.OOE+OO 8.07E+07 2.94E+09 Sb-125 1.37E+08 1. 53E+06 3.25E+07 1.39E+05 O.OOE+OO 1. 05E+08 1.50E+09 Indian Point 3 aDCM Page 3-60 Revision 18

ODCM Part II - Calculational Methodologies Table 3-11a ADULT INGESTION (Leafy Vegetable) Ri (V) 2 3 m

mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 O.OOE+OO 3.86E+08 Te-127m 3.49E+08 1. 25E+08 4.26E+07 8.92E+07 1.42E+09 O.OOE+OO 1.17E+09 Te-l27 5.66E+03 2.03E+03 1. 22E+03 4.19E+03 2.31E+04 O.OOE+OO 4.47E+05 Te-129m 2.-51E+08 9.38E+07 3.98E+07 8.63E+07 1. 05£+09 O.OOE+OO 1. 27E+09 Te-129 7.62E-04 2.87E-04 1.86E-04 5.85E-04 3.20E-03 O.OOE+OO 5.75E-04 Te-l31m 9.12E+05 4.46E+05 3.72E+05 7.06E+05 4.52E+06 O.OOE+OO 4.43E+07 Te-l31 1. 50E-15 6.27E-16 4.74E-16 1.23E-15 6.57E-15 O.OOE+OO 2.l3E-16 Te':'l32 4.30E+06 2.78E+06 2.61E+06 3.07E+06 2.68E+07 O.OOE+OO 1.32E+08 I-l30 3.92E+05 1.16E+06 4.57E+05 9.81E+07 1.81E+06 O.OOE+OO 9.96E+05 1-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 O.OOE+OO 3.05E+07 I-l32 5.76E+01 1. 54E+02 5.39E+Ol 5.39E+03 2.45E+02 O.OOE+OO 2.89E+01 I-l33 2.09E+06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 O.OOE+OO 3.26E+06 I-l34 9.65E-05 2.62E-04 9.38E-05 4.54E-03 4.17E-04 O.OOE+OO 2.29E-07 I-l35 3.90E+04 1.02E+05 3.77E+04 6.73E+06 1.64E+05 O.OOE+OO 1.15E+05 Cs-l34 4.67E+09 1.11E+I0 9.08E+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.24E+07 1.68E+08 1.21E+08 O.OOE+OO 9.32E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.81E+08 1.68E+08 Cs-138 3. 91E-11 7.73E-11 3.83E-11 O.OOE+OO 5.68E-11 5.61E-12 3.30E-16 Ba-139 2.68E-02 1.91E-05 7.86E-04 O.OOE+OO 1.79E-05 1.08E-05 4.76E-02 Ba-140 1.28E+08 1.61E+05 8.38E+06 O.OOE+OO 5.46E+04 9.20E+04 2.63E+08 Ba-l41 1.15E-21 8.70E-25 3.89E-23 O.OOE+OO 8.09E-25 4.94E-25 5.43E-31 Ba-142 2.46E-39 2.53E-42 1.55E-40 O.OOE+OO 2.14E-42 1.43E-42 O.OOE+OO La-140 1.98E+03 9.98E+02 2.64E+02 O.OOE+OO O.OOE+OO O.OOE+OO. 7.33E+07 La-l42 1.41E-04 6.43E-05 1.60E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.69E-01 Ce-141 1.97E+05 1. 33E+05 1.51E+04 O.OOE+OO 6.19E+04 O.OOE+OO 5.10E+08 Ce-143 9.98E+02 7.38E+05 8.16E+Ol O.OOE+OO 3.25E+02 O.OOE+OO 2.76E+07 Ce-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+OO 8.16E+06 O.OOE+OO 1. 11E+10 Pr-143 6.26E+04 2.51E+04 3.10E+03 O.OOE+OO 1.45E+04 O.OOE+OO 2.74E+08 Pr-144 3.09E-26 1.28E-26 1.57E-27 O.OOE+OO 7.23E-27 O.OOE+OO 4.44E-33 Nd-147 3.33E+04 3.85E+04 2.31E+03 O.OOE+OO 2.25E+04 O.OOE+OO 1.85E+08 1'1-187 3.82E+04 3.19E+04 1. 12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.05E+07 Np-239 1.43E+03 1. 41E+02 7.76E+01 O.OOE+OO 4.39E+02 O.OOE+OO 2.89E+07 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.17E+07 1.95E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.97E+08 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.15E-06 5.45E-07 1. 99E-07 O.OOE+OO 6.35E-07 O.OOE+OO 2.01E-03 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Ba-l33 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 3.56E-08 2.33E-08 1.43E-08 3.11E-08 2.25E-07 *0. OOE+OO 3.95E-11 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 ODCM Page 3-61 Revision 18

r.

aDCM Part II - Calculational Methodologies

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Table 3-11b TEEN INGESTION (Leafy Vegetable) Ri(V) 2 3 m

mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 Be-7 1.43E+05 3.20E+05 1.60E+05 O.OOE+OO 3.39E+05 O.OOE+OO 3.90E+07 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 P-32 1.61E+09 9.97E+07 6.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+0,8 Cr-51 O.OOE+OO O.OOE+OO 6.17E+04 3.43E+04 1.35E+04 8.81E+04 1.04E+07 Mn-54 O.OOE+OO 4.54E+08 9.01E+07 O.OOE+OO 1.36E+08 O.OOE+OO 9.32E+08 Mn-56 O.OOE+OO 1.43E+01 2.55E+00 O.OOE+OO 1. 81E+01 O.OOE+OO 9.44E+02 Fe-55 3.26E+08 2.31E+08 5.39E+07 O.OOE+OO O.OOE+OO 1. 47E+08 1.00E+08 Fe-59 1.79E+08 4.18E+08 1.61E+08 O.OOE+OO O.OOE+OO 1.32E+08 9.88E+08 Co-58 O.OOE+OO 4.36E+07 1.00E+08 O.OOE+OO O:OOE+OO O.OOE+OO 6.01E+08 Co-60 O.OOE+OO 2.49E+08 5.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 Ni-63 1.61E+10 1. 13E+09 5.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+08 Ni-65 5.72E+01 7.31E+00 3.33E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.97E+02 Cu-64 O.OOE+OO 8.34E+03 3.92E+03 O.OOE+OO 2.11E+04 O.OOE+OO 6.47E+05 Zn-65 4.24E+08 1. 47E+09 6.86E+08 O.OOE+OO 9.42E+08 O.OOE+OO 6.23E+08 Zn-69 8.18E-06 1.56E-05 1.09E-06 O.OOE+OO 1.02E-05 O.OOE+OO 2.87E-05 Br-83 O.OOE+OO O.OOE+OO 2.91E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.25E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.74E+08 1. 29E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.05E+07 Rb-88 O.OOE+OO 3.17E-22 1. 69E-22 O.OOE+OO O.OOE+OO O.OOE+OO 2.71E-29 Rb-89 O.OOE+OO 1. 25E-26 8.82E-27 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E-35 Sr-89 1.51E+10 O.OOE+OO 4.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+09 Sr-90 7.51E+11 O.OOE+OO 1.85E+11 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+10 Sr-91 2.85E+05 O.OOE+OO 1. 13E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1. 29E+06 Sr-92 3.97E+02 O.OOE+OO 1.69E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.01E+04 Y-90 1.24E+04 O.OOE+OO 3.34E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Y-9lm 4.86E-09 O.OOE+OO 1.86E-10 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-07 Y-91 7.84E+06 O.OOE+OO 2.10E+05 0.00£+00 O.OOE+OO O.OOE+OO 3.21E+09 Y-92 8.60E-01 O.OOE+OO 2.49E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.36E+04 Y-93 1.59E+02 O.OOE+OO 4.36E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.86E+06 Zr-95 1. 72E+06 5.43E+05 3.73E+05 O.OOE+OO 7.98E+05 O.OOE+OO 1.25E+09 Zr-97 3.12E+02 6.18E+01 2.85E+01 O.OOE+OO 9.37E+01 O.OOE+OO 1.67E+07 Nb-95 1.93E+05 1.07E+05 5.89E+04 O.OOE+OO 1.04E+05 O.OOE+OO 4.57E+08 Mo-99 O.OOE+OO 5.65E+06 1.08E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.01E+07 Tc-99m 2.74E+00 7.63E+00 9.89E+01 O.OOE+OO 1.14E+02 4.24E+00 5.01E+03 Tc-101 7.64E-31 1. 09E-30 1.07E-29 O.OOE+OO 1.97£-29 6.62E-31 1.86E-37 Ru-103 6.81E+06 O.OOE+OO 2.91E+06 O.OOE+OO 2.40E+07 O.OOE+OO 5.69E+08 Ru-105 5.00E+01 O.OOE+OO 1.94E+01 O.OOE+OO 6.31E+02 O.OOE+OO 4.04E+04 Ru-106 3.10E+08 O.OOE+OO 3.90E+07 O.OOE+OO 5.97E+08 O.OOE+OO 1.48E+10 Ag-11 Om 1.52E+07 1.43E+07 8.72£+06 O.OOE+OO 2.74E+07 O.OOE+OO 4.03E+09 Sb-122 3.03E+05 5.89£+03 8.85£+04 3.85E+03 O.OOE+OO 1.89E+05 6.35E+07 Sb-124 1.54E+08 2.84E+06 6.02£+07 3.50E+05 O.OOE+OO 1. 34E+08 3.11E+09 Sb-125 2.14E+08 2.34£+06 5.00E+07 2.04E+05 0.00£+00 1.86E+08 1. 66E+09

( ..

Indian Point 3 aDCM Page 3-62 Revision 18

aDCM Part II - Calculational Methodologies

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r, -

Table 3-11b TEEN INGESTION (Leafy Vegetable) Ri(V) 2 3 m

mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILL I Te-125m 1. 48E+08 5.34E+07 1.98E+07 4.14E+07 O.OOE+OO O.OOE+OO 4.37E+08 Te-127m 5.51E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 O.OOE+OO 1.37E+09 Te-127 5.34E+03 1.89E+03 1.15E+03 3.68E+03 2.16E+04 O.OOE+OO 4.12£+05 Te-129m 3.62E+08 1. 34E+08 5.73E+07 1.17E+08 1. 51E+09 O.OOE+OO 1.36E+09 Te-129 7.14E-04 2.66E-04 1. 74E-04 5.10E-04 3.00E-03 O.OOE+OO 3.90E-03 Te-131m 8.44E+05 4.05E+05 3.38E+05 6.09E+05 4.22E+06 O.OOE+OO 3.25E+07 Te-131 1. 39E-15 5.75E-16 4.36E-16 1.07E-15 6.10E-15 O.OOE+OO 1.14£-16 Te-132 3.91E+06 2.47E+06 2.33E+06 2.61E+06 2.37E+07 O.OOE+OO 7.84E+07 1-130 3.51E+05 1.01E+06 4.05E+05 8.28E+07 1. 56E+06 O.OOE+OO 7.80£+05 1-131 7.69E+07 l~. 08E+08 5.78E+07 3.14E+10 1. 85E+08 O.OOE+OO 2.13E+07 1-132 5.19E+01 1. 36E+02 4.88E+01 4.58E+03 2.14E+02 O.OOE+OO 5.92E+01 1-133 1.94E+06 3.29E+06 l.00E+06 4.59E+08 5.76E+06 O.OOE+OO 2.49E+06 1-134 8.73E-05 2.31E-04 8.31E-05 3.85E-03 3.65E-04 O.OOE+OO 3.05E-06 1-135 3.-52E+04 9.07E+04 3.36E+04 5.83E+06 l.43E+05 O.OOE+OO 1.00E+05 Cs-134 7.10E+09 1. 67E+I0 7.75E+09 O.OOE+OO 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.34E+07 1. 71E+08 1.15E+08 O.OOE+OO 9.30E+07 l.47E+07 1.37E+07 Cs-137 1.01E+I0 1. 35E+10 4.69E+09 O.OOE+OO 4.59E+09 1.78E+09 1.92E+08 Cs-138 3.61E-11 6.93E-11 3.47E-11 O.OOE+OO 5.12E-11 5.96E-12 3.15E-14 Ba-139 2.52E-02 1.78E-05 7.35E-04 O.OOE+OO 1.67E-05 l. 22E-05 2.25E-Ol Ba-140 1.37E+08 1.68E+05 8.85E+06 O.OOE+OO 5.70E+04 1. 13E+05 2.12E+08 Ba-141 1. 08E-21 8.04E-25 3.59E-23 O.OOE+OO 7.46E-25 5.50E-25 2.29E-27

( Ba-142 2.27E-39 2.27E-42 1. 40E-40 O.OOE+OO 1. 92E-42 1.51E-42 O.OOE+OO

\

La-140 1. 81E+03 8.89E+02 2.37E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E+07 La-142 1.30E-04 5.76E-05 1.43E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+00 Ce-141 2.83E+05 1.89E+05 2.17E+04 O.OOE+OO 8.89E+04 O.OOE+OO 5.40E+08 Ce-143 9.33E+02 6.79E+05 7.58E+01 O.OOE+OO 3.04E+02 O.OOE+OO 2.04E+07 Ce-144 5.27E+07 2.18E+07 2.83E+06 O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 Pr-143 7.00E+04 2.80E+04 3.49E+03 O.OOE+OO 1.63E+04 O.OOE+OO 2.30E+08 Pr-144 2.89E-26 1.18E-26 1. 47E-27 O.OOE+OO 6.80E-27 O.OOE+OO 3.19E-29 Nd-147 3.62E+04 3.94E+04 2.36E+03 O.OOE+OO 2.31E+04 O.OOE+OO 1. 42E+08 W-187 3.55E+04 2.90E+04 1.02E+04 O.OOE+OO O.OOE+OO O.OOE+OO 7. 84E+06 (

Np-239 1.39E+03 1.31E+02 7.28E+Ol O.OOE+OO 4.11E+02 O.OOE+OO 2.11E+07 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.79E+07 3.00E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.33E+08 Sr-85 O.OOE+OO 0.00£+00 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.00E-06 4.95E-07 1.81E-07 O.OOE+OO 5.79E-07 O.OOE+OO 1.18E-02 Cd-l09 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO Te-134 3.23E-08 2.07£-08 2.17E-08 2.65E-08 1.98E-07 O.OOE+OO l.20E-09 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDeM Page 3-63 Revision 18

ODCM Part II - Calculational Methodologies t""':""'"

\

Table 3-11c CHILD INGESTION (Leafy Vegetable) Ri(V) 2 3 m

mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 Be-7 3.37E+05 5.72E+05 3.77E+05 O.OOE+OO 5.63E+05 O.OOE+OO 3.20£+07 Na-24 3.73E+05 3.73£+05 3.73£+05 3.73E+05 3.73E+05 3.73E+05 3.73£+05 P-32 3.37E+09 1.58E+08 1.30E+08 O.OOE+OO O.OOE+OO 0.00£+00 9.31E+07 Cr-51 O.OOE+OO O.OOE+OO 1.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06 Mn-54 O.OOE+OO 6.65E+08 1.77E+08 0.00£+00 1. 86E+08 O.OOE+OO 5.58E+08 Mn-56 O.OOE+OO 1. 88E+01 4.24E+00 O.OOE+OO 2.27E+01 O.OOE+OO 2.72E+03 Fe-55 8.01£+08 4.25E+08 1.32E+08 0.00£+00 O.OOE+OO 2.40£+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 O.OOE+OO O.OOE+OO 1.86E+08 6.68E+08 Co-58 0.00£+00 6.44E+07 1. 97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+08 Co-60 O.OOE+OO 3.78E+08 1. 12E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+09 Ni-63 3.95E+10 2.11E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+08 Ni-65 1.05E+02 9.89E+00 5.77E+00 O.OOE+OO O.OOE+OO O.OOE+OO 1. 21E+03 Cu-64 O.OOE+OO 1.10E+04 6.64E+03 O.OOE+OO 2.66E+04 O.OOE+OO 5.16E+05 Zn-65 8.12E+08 2.16E+09 1. 35E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 Zn-69 1.51E-05 2.18E-05 2.02E-06 O.OOE+OO 1.32E-05 O.OOE+OO 1.37E-03 Br-83 O.OOE+OO O.OOE+OO 5.37E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.82E-11 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 0.00£+00 4.52E+08 2.78E+08 O.OOE+OO 0.00£+00 0.00£+00 2.91E+07 Rb-88 0.00£+00 4.37E-22 3.04E-22 O.OOE+OO O.OOE+OO O.OOE+OO 2.15E-23 Rb-89 0.00£+00 1. 64E-26 1. 46E-26 O.OOE+OO O.OOE+OO O.OOE+OO 1. 43E-28 Sr-89 3.59E+I0 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.39£+09 Sr-90 1.24E+12 O.OOE+OO 3. 15E+11 O.OOE+OO O.OOE+OO O.OOE+OO 1. 67E+10 Sr-91 5.24£+05 O.OOE+OO 1.98E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+06 Sr-92 7.28E+02 O.OOE+OO 2.92E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.38E+04 Y-90 2.30E+04 O.OOE+OO 6.17E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.56E+07 Y-91m 8.91E-09 0.00£+00 3.24E-10 O.OOE+OO O.OOE+OO 0.00£+00 1.74E-05 Y-91 1.86E+07 O.OOE+OO 4.99E+05 0.00£+00 O.OOE+OO 0.00£+00 2.48E+09 Y-92 1.58E+00 O.OOE+OO 4.53E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.58E+04 Y-93 2.93E+02 O.OOE+OO 8.04E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.37E+06 Zr-95 3.86E+06 8.48E+05 7.55E+05 O.OOE+OO 1.21E+06 O.OOE+OO 8.84E+08 Zr-97 5.70E+02 8.24E+01 4.86E+Ol O.OOE+OO 1.18E+02 O.OOE+OO 1.25E+07 Nb-95 4.12E+05 1.60E+05 1.15E+05 O.OOE+OO 1.51E+05 O.OOE+OO 2.97E+08 Mo-99 O.OOE+OO 7.71E+06 1. 91E+06 O.OOE+OO 1.65E+07 O.OOE+OO 6.38E+06 Tc-99m 4.71E+00 9.24E+00 1.53E+02 O.OOE+OO 1.34E+02 4.69E+00 5.26E+03 Tc-101 1.4lE-30 1.47E-30 1.87E-29 O.OOE+OO 2.51E-29 7.78E-31 4.68E-30 Ru-103 1.53E+07 O.OOE+OO 5.88E+06 O.OOE+OO 3.85E+07 O.OOE+OO 3.96E+08 Ru-105 9.16E+01 O.OOE+OO 3.32E+01 O.OOE+OO 8.05E+02 O.OOE+OO 5.98E+04 Ru-106 7.45E+08 O.OOE+OO 9.30E+07 O.OOE+OO 1.01E+09 O.OOE+OO 1.16E+10 Ag-110m 3.21E+07 2.17E+07 1.73E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.58E+09 Sb-122 5.58E+05 8.24E+03 1.64E+05 7.16E+03 O.OOE+OO 2.27E+05 4.30E+07 Sb-124 3.52E+08 4.56E+06 1.23E+08 7.73E+05 O.OOE+OO 1.95E+08 2.20E+09 Sb-125 4.99E+08 3.84E+06 1. 05E+08 4.63E+05 O.OOE+OO 2.78E+08 1.19E+09 Indian Point 3 ODCM Page 3-64 Revision 18

aDCM Part II - Calculational Methodologies

(

Table 3-11c CHILD INGESTION (Leafy Vegetable) Ri(V) 2 3 m

mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.51E+08 9.50E+07 4.67E+07 9.84E+07 O.OOE+OO O.OOE+OO 3.38E+08 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 O.OOE+OO 1.07E+09 Te-127 9.85E+03 2.65E+03 2.11E+03 6.81E+03 2.80E+04 O.OOE+OO 3.85E+05 Te-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 O.OOE+OO 1.03E+09 Te-129 1.32E-:-03 3.69E-04 3.14E-04 9.43E-04 3.87E-03 O.OOE+OO 8.23E-02 Te-131m 1.54E+06 5.33E+05 5.68E+05 1.10E+06 5.16E+06 O.OOE+OO 2.16E+07 Te-131 2.57E-15 7.83E-16 7.64E-16 1. 97E-15 7.77E-15 O.OOE+OO 1.35E-14 Te-132 7.00E+06 3.10E+06 3.74E+06 4.51E+06 2.88E+07 O.OOE+OO 3.12E+07 1-130 6.16E+05 1. 24E+06 6.41E+05 1. 37E+08 1.86E+06 O.OOE+OO 5.82E+05 1-131 1. 43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 O.OOE+OO 1.28E+07 1-132 9.22E+Ol 1.69E+02 7.79E+01 7.86E+03 2.59E+02 O.OOE+OO 1.99E+02 1-133 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.28E+06 O.OOE+OO 1. 76E+06 1-134 1.55E-04 2.88E-04 1.32E-04 6.62E-03 4.40E-04 O.OOE+OO 1.91E-04 1-135 6.26E+04 1.13E+05 5.33E+04 9.97E+06 1.73E+05 O.OOE+OO 8.58E+04 Cs-134 1.60E+I0 2.63E+10 5.55E+09 O.OOE+OO 8.15E+09 2.93E+09 1.42E+08 Cs-136 8.17E+07 2.25E+08 1. 45E+08 O.OOE+OO 1.20E+08 1.78E+07 7.90E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 1.43E+08 Cs-138 6.57E-11 9. 13E-11 5. 79E-11 O.OOE+OO 6.43E-11 6.91E-12 4.21E-11 Ba-139 4.65E-02 2.48E-05 1. 35E-03 O.OOE+OO 2.17E-05 1.46E-05 2.69E+00 Ba-140 2.75E+08 2.41E+05 1.60E+07 O.OOE+OO 7.84E+04 1.44E+05 1.39E+08 Ba-141 1. 99E-21 1.11E-24 6.47E-23 O.OOE+OO 9.62E-25 6.53E-24 1. 13E-21 Ba-l42 4.11E-39 2.96E-42 2.29E-40 O.OOE+OO 2.39E-42 1. 74E-42 5.36E-41 La-l40 3.25E+03 1.14E+03 3.83E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.17E+07 La-l42 2.35E-04 7.49E-05 2.35E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E+01 Ce-141 6.56E+05 3.27E+05 4.86E+04 O.OOE+OO 1.43E+05 O.OOE+OO 4.08E+08 Ce-143 1.72E+03 9.31E+05 1.35E+02 O.OOE+OO 3.91E+02 O.OOE+OO 1.36E+07 Ce-144 1.27E+08 3.98E+07 6.78E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1. 04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 O.OOE+OO 2.37E+04 O.OOE+OO 1.57E+08 Pr-l44' 5.37E-26 1. 66E-26 2.70E-27 O.OOE+OO 8.79E-27 O.OOE+OO 3.58E-23 Nd-147 7.15E+04 5.79E+04 4.48E+03 O.OOE+OO 3.18E+04 O.OOE+OO 9.17E+07 W-187 6.47E+04 3.83E+04 1. 72E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+06 Np-239 2.57E+03 1.84E+02 1.29E+02 O.OOE+OO 5.33E+02 O.OOE+OO 1.36E+07 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 2.99E+07 6.04E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+08 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.64E-06 6.57E-07 3.07E-07 O.OOE+OO 7.29E-07 O.OOE+OO 2.03E-01 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 5.76E-08 2.59E-08 3.46E-08 4.56E-08 2.40E-07 O.OOE+OO 2.63E-07 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 3 aDCM Page 3-65 Revision 18

ODCM Part II - Calculational Methodologies Table 3-12 Total Body & Skin Ground Plane Dose Factors Ri (G) and Ri(S) 2 (m

mrem/yr per uCi/sec)

-1 Isotope Decay Constant (sec) Ri(G) Ri(S)

H-3 1.780E-09 O.OOE+OO O.OOE+OO Be-7 1. 505E-07 O.OOE+OO O.OOE+OO Na-24 1.284E-05 1.19E+07 1.39E+07 P-32 5.614E-07 O.OOE+OO O.OOE+OO Cr-51 2.896E-07 4.66E+06 5.51E+06 Mn-54 2.567E-08 1. 39E+09 1.62E+09 Mn-56 7.467E-05 9.03E+05 1.07E+06 Fe-55 8.141E-09 O.OOE+OO O.OOE+OO Fe-59 1.802£-07 2.72E+08 3.20E+08 Co-58 1. 133E-07 3.79E+08 4.44E+08 Co-60 4.170E-09 2.15E+10 2.53E+10 Ni-63 2.290E-10 O.OOE+OO O.OOE+OO Ni-65 7.641E-05 2.97E+05 3.45E+05 Cu-64 1.516E-05 6.07E+05 6.88E+05 Zn-65 3.289E-08 7.46E+08 8.58E+08 Zn-69 2.027E-04 O.OOE+OO O.OOE+OO Br-83 8.056E-05 4.87E+03 7.08E+03 Br-84 3.633E-04 2.03E+05 2.36E+05 Br-85 3.851E-03 O.OOE+OO O.OOE+OO Rb-86 4.299E-07 8.99E+06 1.03E+07 Rb-88 6.490E-04 3.31E+04 3.78£+04 Rb-89 7.600E-04 1.21E+05 1.45E+05 Sr-89 1. 589E-07 2.16E+04 2.51E+04 Sr-90 7.548E-10 O.OOE+OO O.OOE+OO Sr-91 2 '. 027E-05 2.15E+06 2.51E+06 Sr-92 7.105E-05 7.77E+05 8.63E+05 Y-90 3.008E-06 4.48E+03 5.30E+03 Y-91m 2.324£-04 1.00E+05 1.16£+05 Y-91 1.371£-07 1.07E+06 1. 21£+06 Y-92 5.439E-05 1.80E+05 2.14E+05 Y-93 1.906E-05 1.83E+05 2.51£+05 Zr-95 1. 254E-07 2.45E+08 2.84E+08 Zr-97 1. 139E-05 2.96E+06 3.44E+06 Nb-95 2.282E-07 1. 37E+08 1.61E+08 Mo-99 2.917E-06 3.99E+06 4.62E+06 Tc-99m 3.198E-05 1. 84E+05 2.11E+05 Tc-101 8.136E-04 2.04E+04 2.26E+04 Ru-103 2.042E-07 1.08E+08 1.26E+08 Ru-105 4.337E-05 6.36E+05 7.21E+05 Ru-106 2.l79E-08 4.22E+08 5.07E+08 Ag-llOm 3.210E-08 3.44E+09 4.01E+09 Sb-122 2.971E-06 O.OOE+OO O.OOE+OO Sb-124 1.333E-07 5.98E+08 6.90E+08 Sb-125 7.935£-09 2.34E+09 2.64E+09 Indian Point 30DCM Page 3-66 Revision 18

aDCM Part II - Calculational Methodologies

/'~"-""'"

\., Table 3-12 Total Body & Skin Ground Plane Dose Factors Ri{G) and Ri{S) 2 (m

mrem/yr per uCi/sec)

-1 Isotope Decay Constant (sec) Ri(G) Ri(S)

Te-125m 1. 383E-07 1. 55E+06 2.13E+06 Te-127m 7.360E-08 9.16E+04 1.08E+05 Te-127 2.059E-05 2.98E+03 3.28E+03 Te-129m 2.388E-07 1. 98E+07 2.31E+07 Te-129 1.660E-04 2.62E+04 3.10E+04 Te-131m 6.418E-06 8.03E+06 9.46E+06 Te-131 4.621E-04 2.92E+04 3.45E+07 Te-132 2.462E-06 4.23E+06 4.98E+06 1-130 1. 558E-05 5.51E+06 6.69E+06 1-131 9.978E-07 1.72E+07 2.09E+07 1-132 8.371E-05 1. 25E+06 1.46E+06 1-133 9.257E-06 2.45E+06 2.98E+06 1-134 2.196E-04 4.47£+05 5.30E+05 1-135 2.913E-05 2.53E+06 2.95E+06 Cs-l34 1.066E-08 6.86E+09 8.00E+09 Cs-136 6.124E-07 1.50£+08 1.70E+08

{' Cs-137 7.327E-I0 1.03E+10 1.20E+10

" .. Cs-138 3.588E-04 3.59£+05 4.10E+05 Ba-139 1.397E-04 1. 05E+05 1.19E+05 Ba-140 6.297E-07 2.04E+07 2.34E+07 Ba-141 6.323E-04 4.17E+04 4.75E+04 Ba-142 1. 090E-03 4.44E+04 5.06E+04 La-140 4.781E-06 1.92E+07 2.18E+07 La-l42 1. 24 9E-04 7.36E+05 8.84E+05 Ce-141 2.468E-07 1. 37E+07 1.54E+07 Ce-l43 5.835E-06 2.31E+06 2.63E+06 Ce-144 2.822E-08 6.95E+07 8.04E+07 Pr-143 5.916E-07 O.OOE+OO O.OOE+OO Pr-144 6.685E-04 1. 83E+03 2.11E+03 Nd-147 7.306E-07 8.39E+06 1.01E+07 W-187 8.056E-06 2.36E+06 2.74E+06 Np-239 3.399E-06 1.71E+06 1.98E+06 K-40 1. 717E-17 O.OOE+OO O.OOE+OO Co-57 2.961E-08 1.88E+08 2.07E+08 Sr-85 1.237E-07 O.OOE+OO O.OOE+OO Y-88 7.523E-08 O.OOE+OO O.OOE+OO Nb-94 1.083E-12 O.OOE+OO O.OOE+OO Nb-97 1.602E-04 1.76E+05 2.07E+05 Cd-109 1.729E-08 O.OOE+OO O.OOE+OO Sn-1l3 6.970E-08 O.OOE+OO O.OOE+OO Sa-l33 2.047E-09 O.OOE+OO O.OOE+OO Te-134 2.764E-04 2.22E+04 2.66E+04 Ce-139 5.828E-08 O.OOE+OO O.OOE+OO

/., Hg-203 1.722E-07 O.OOE+OO O.OOE+OO r

\""

Indian Point 3 aDCM Page 3-67 Revision 18

aDCM Part II - Calculational Methodologies APPENDIX A Page 1 af6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Primary Assumptions:

1. Units 2 and 3 effective dose factors (KLMN) are equivalent, except for site-specific finite cloud correction, as required.

2. Each unit shares 50% of the total allowable release rate, Q, in Cifsec.

Therefore, Q3 = Q2 for instantaneous releases.

Given the following long-term meteorological data:

Unit 1/2:

Concentration Finite-Cloud Deposition Unit 1 or 2 Receptor XlQ GammaXlQ D/Q Release Points (seclm 3) l(sec/m3) - Xe133 (11m2) 2.219E-06 1.974E-06 1.407E-OB Site Boundary ISSW, 755 m] [SSW, 755 m] [SSW, 755 m]

Primary Vent 1.030E-06 9.714E-07 7.517E*09 Nearest Residence Releases [SSW, 1574 mJ [SSW, 1574 mJ [S, 1133 mJ 2.B73E-05 1.215E-05 B.759E*OB .

Site Boundary Ground Level [SSW, 440 m] [SSW, 440 mJ [SSW, 440 mJ Releases 5.15BE-06 3.06BE-06 1.B7BE*OB Nearest Residence

[SSW, 1374 mJ [SSW, 1374 m] [S, 933 m]

Unit 3:

Concentration Finite*Cloud Deposition Unit 3 Receptor XlQ GammaXlQ D/Q Release Point fsec/m3) [seclm3) - Xe133 (11m2) 4.473E-06 3.171E-06 2.599E-OB

. Site Boundary

[SW, 350 m] [SSW, 4BO ml [SSW, 4BO m]

Primary Vent 1.016E-06 9.606E-07 7.451E-09 Nearest Residence Releases [SSW, 1574 m] [SSW, 1574 m] [S, 1133 m]

6.9BOE-05 2.350E-05 2.012E-07 Site Boundary Ground Level [SSW, 250 m] [SSW, 250 m] [SSW, 250 m]

Releases 5.15BE-06 3.06BE-06 1.B7BE-OB Nearest Residence

[SSW, 1374 m] [SSW, 1374 m] [S, 933 m]

(.......

Indian Point 3 aDCM Page 3-68 Revision 18

aDCM Part II - Calculational Methodologies APPENDIX A Page 2 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Instantaneous Release Rates vs Dose Rates Indian Point units 2 and 3 share a common site boundary limit of 500 mrem/yr. This 500 mrem/yr limit was divided between the units based upon a 50-50 split of the release rate in /-lCi/sec.

Because each unit has its own XJQ and K-bar, equal /-lCi/sec discharges from each plant will result in different dose rates for each plant at the most restrictive site boundary location. In order to define the split of the 500 mrem/yr limit, IPEC units i and 3 must base the dose split on the mixture presented in Table 3-8.

Dose Split Between IP2 and IP3 A. Instantaneous Dose Rates and Calculation of Allowable Release Rate in uCi/sec:

i. Whole Body Dose Rate Calculations:

Given:

a) site limit is 500 mrem/yr b} IP3 worst sector XJQ = 4.47E-6 sec/m 3 mremem 3 c) IP3 K-bar for instantaneous mixture = 849 - - - -

j.JCi e yr d) IP2 worst sector XJQ = 2.22E-6 sec/m3 3

mremem e) IP2 K-bar for instantaneous mixture =1507 - ---

j.JCi e yr f) Q = /-lCi/sec Solve for Q:

Q [(XJQ 3 ) (K bar3) + (XJQ 2 ) (K bar2)] = 500 mrem/yr Q [(4.47E-6) (849) + (2.22E-6) (1507)] = 500 mrem/yr Solving for Q' a default back-calculated instantaneous release rate for either unit:

Q = 7.00E+4/-lCi/sec In other words, if both units were releasing at this rate, with the default instantaneous mixture identified in Table 3-8, IPEC would be releasing at 500 mrem/yr (the RECS and 10CFR20 release rate limit).

Since this value assumes ALL releases are included (per unit), a partitioning factor should be applied for each applicable release point when this limit is used. Should it become necessary to "borrow" from the other unit, isotopic mixtures from specific sample results should replace the dose factors used in this default calculation. Without specific sample data, the default SITE release rate limit is then: 1.40E5 uCi/sec.

Indian Point 3 aDCM Page 3-69 Revision 18

aDCM Part II - Calculational Methodologies

'APPENDIX A Page 3 of 6

(' CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3

\ ..;,.,.

ii. Skin Dose Rate Calculations:

Given:

a) site limit is 3,000 mrem/yr b) IP3 worst sector XJO = 4.47E-6 sec/m 3 3

c) IP3 (Li + 1.1 Mi) = 2306 mren:. m j.iCz

yr d) IP2 XJO for SSW sector = 2.22E-6 sec/m 3 mrem.m 3 e) IP2 (Li + 1.1 Mi) = 3071 j.iCi. yr f) Q = uCi/sec Solve for Q:

Q [(XJOh (Li + 1.1 Mih + (XJOh (Li + 1.1 Mih] = 3,000 mrem/yr Q [(4.47E-6) (2306) + (2.22E-6) (3071)] = 3,000mrem/yr Q = 1. 75E+5 J!Ci/sec (less restrictive than Whole Body) iii. Solve for WB dose rate commitments per site (with Q =7.00E+4 uCi/sec)

Indian Point 2:

. 3 mrem.m 3 (7.00E+4 J!Cl/sec) (2.22E-6 sec/m ) (1507 ) =234 mrem/yr jlCi. yr Indian Point 3:

. mrem.m 3 (7.00E+4 J!Ci/sec) (4.47E-6 sec/m 3) (849 ) =266 mrem/yr j.iCi. yr The less restrictive skin dose rate limit for each unit (information only):

mrem .m 3 Unit 2: (1.75E+5 uCi/sec) (2.22E-6 sec/m 3) (3071 ) =1194 mrem/yr jlCi. yr mrem.m 3 Unit 3: (1.75E+5 uCi/sec) (4.47E-6 sec/m 3 ) (2306 ) =1806 mrem/yr j.iCi. yr .

Indian Point 3 aDCM Page 3-70 Revision 18

ODCM Part 1/ - Calculational Methodologies APPENDIX A Page 4 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 RELEASE RATE LIMITS FOR QUARTERLY AND ANNUAL AVERAGE NOBLE GAS RELEASES For a Calendar Quarter For a Calendar Year Gamma air dose 5 mrad limit 10 mrad limit Beta air dose 10 mrad limit 20 mrad limit I. Assumptions: 1. Doses are delivered to the air at the site boundary.

2. Finite cloud geometry is assumed for noble gas releases at site boundary.

3. XJQ for Unit 2 2.22E-6 sec/m 3 , (Q release rate uCi/sec)

4. XJQ for Unit 3 =4.47E-6 sec/m3 , (Q =release rate uCi/sec)

5. Gamma and Beta air dose factors (M and N), Corrected for finite cloud geometry (as described on Table 3-8) are as follows:

Unit 2 effective Unit 3 effective Units average dose factors average dose factors M = 281 M = 181 mrad/yr per uCi/m J N = 1254 N = 1254 mrad/yr I:>er uCi/m 3 II. Calculation of Quarterly Release Rates:

a) for gamma dose: (Q )*[(M)(XJQ)] less than or equal to 5 mrad/qtr b) for beta dose: (Q )*[(N)(XJQ)] less than or equal to 10 mrad/qtr unit 2 unit 3 5mrad I qtr gamma dose rate Q = = 3.21 E+4 /-LCi/sec 2.47E+4/-LCi/sec (1I4yr)(M)(X IQ) lOmrad I qtr beta dose rate Q = = 1.44E+4 IlCi/sec 7.14E+3 /-LCi/sec (1I4yr)(N)(X / Q)

Based on the above analysis, the beta dose is limiting for time average doses. Therefore, the allowable quarterly average release rates are 1.44E+4 /-LCi/sec for unit 2 and 7.14E+3

/-LCi/sec for unit 3.

III. Calculation of Calendar Year Release Rate Annual limits are one half of quarterly limits. Therefore, using Beta air dose as most limiting, the maximum annual average release rates are 7.20E+3 /-LCi/sec for unit 2 and 3.57E+3

(

/-LCi/sec for unit 3.

Indian Point 3 ODCM Page 3-71 Revision 18

ODCM Part II - Calculational Methodologies APPENDIX A Page 5 of 6

('.... CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE INSTANTANEOUS RELEASE RATE for 1-131 & Particulates wi TY2 > 8 DAYS)

Given: Wv(in): X/Q at the Site Boundary for IP3 =4.47E-6 sec/m3 Wv(in): X/Q at the Site Boundary for IP2 =2.22E-6 sec/m3 PI(c) =1.62 E7 mreml yr pCiI m 3 Assumed Pathway: Child Inhalation at Unrestricted Area Boundary

)

Solve the following equation for Q:

[( Q)PI(c)(Wv(in>> Unit 3] + [( Q)PI(c)(Wv(in>> Unit 2] = 1500 mrem/yr

. . mrem / yr IP3: (Q )PI(c)(Wv(in>>3 = Q

1.62E7 3 4.47E-6 s/m 3 = Q.

72.4 -mrem

/ yr j.lCi / m j.lCi / sec

(

< .~ .. - IP2: (Q)PI(c)(Wv(in>>2 =Q.

1.62E7 mrem/yr 3 2.22E-6 s/m 3

.. mrem/yr

= Q

36.0 ----=--

j.lCi / m j.lCi I sec The sum equals: (108) ( Q) mrem/yr per uCi/sec Limit is 1500 mrem/yr per site:

Therefore: 108

Q mrem / yr = 1500 mrem/yr j.lCi I sec Q = 1.38E+1 fJ.Ci/sec (for each unit) 3 IP3 Dose Contribution: 1.38E+1 pCi

1.62E7 mrem m

4.47 E _ 6 sec = 1003 mrem/yr sec yr j.lCi m3 3

IP2 Dose Contribution: 1.38E+1 pCi

1.62E7 mrem m

2.22£ _ 6 sec = 497 mrem/yr sec yr j.lCi m3

-=-1500 Sum mrem/yr Approximately a 67 133 % dose split for IP3 and IP2 respectively .

Indian Point 3 ODCM Page 3-72 Revision 18

ODCM Part II - Calculational Methodologies APPENDIX A Page 6 of 6

( CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE RELEASE RATES FOR IODINE I PARTICULATE TIME AVERAGE QUARTERLY AND ANNUAL DOSE LIMITS AT THE NEAREST RESIDENT Dose factors for the child, thyroid (for Iodine 131) are used for this category as a conservative assumption since this nuclide has the highest thyroid dose factor of all iodines and particulates, and its most significant effect in on the child age group. The H-3 dose factor is about 4 orders of magnitude less significant and its contribution to the total dose is considered negligible. The back-calculated release rate for Iodine and Particulate is as follows:

Given: Unit 2 Unit 3 XJQ (in sec/m 3 at the nearest resident) 1.03E-6 1.02E-6 D/Q (in m*2 at the nearest resident) 7.52E-9 7.45E-9 RI(c) = 1.62E+7 mreml ~r, child thyroid inhalation dose factor for 1-131 (for both units) j.JCil m 2 mreml yr RG = 1. 72E+ 7 m , ground plane dose factor for 1-131 (for both units) j.JCi I sec RV(c) = 4.75E+10 m2 mreml yr, child thyroid vegetation dose factor for 1-131 (for both units) j.JCilsec

(

Calculating the allowable time average release rate by solving the following equation for Q:

Q [(Rlc)(XJQ) + (RG)(D/Q) + (RVc)(D/O)] = limit in mrem/yr Unit 2 Unit 3 Q (Rlc)(XJO) in mrem/yr per uCi/sec = 16.7

Q 16.5

Q Q (RG) (D/O) in mrem/yr per uCi/sec = 0.129

Q 0.128*Q Q (RVc)(D/Q) in mrem/yr per uCi/sec = 357 *Q 354* Q The sum for each unit ( X

Q ) in mrem/yr per uCi/sec. 374

Q 371

Q Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr). Solving for. Q yields:

. mreml yr .

(IP2) Q

374 . = 30 mrem/yr Q =8.02E-2 J.l.Ci/sec (Quarterly Limit) j.JCz Isec Annual limit is Y:! quarterly limit, or 15 mrem to any organ/yr = 4.01 E-2 /lCi/sec (Annual Limit)

. mremlyr .

(IP3) Q

371 . = 30 mrem/yr Q = 8.1 OE-2 /lCi/sec (Quarterly Limit) j.JCzlsec

(. Annual limit is Y:! quarterly limit, or 15 mrem to any organ/yr = 4.05E-2/lCi/sec (Annual Limit)

Indian Point 3 ODCM Page 3-73 Revision 18

aDCM Part II - Calculational Methodologies Figure 3-1 Gaseous Radioactive Waste Effluent System Flow Diagram Batch Vents Cant.

Release Point Monitor Tanks liquid Waste Cant.

Release Point Recifc See

.............,.........,.........,..........--'--.River Figure 2-1 i--

I I PV

,________________________________ _ __ IL __

I I

I Primary Auxiliary I

Building Fill RCV-014 Waste Gas Cant.

Tanks Rele.ase Point Cant.

Release Radioactive Point Machine Shop Cont.

II.dministratlon Release Building Points

32 AUx Feed Pump Excess Steam Vent Main Steam I\tmospherics and Safeties SIG BID Flash Tank STEAM Vent

32Aux GEN Generator Feed Pump Blow-down FlashTank to to BDR River Indian Point 3 aDCM Page 3-74 Revision 18

ODCM Part II - Calculational Methodologies 4.0 SAMPLE LOCATIONS Figure 4-1 is a map which shows the location of environmental sampling points within 2 miles of the Indian Point Plant. Figure 4-2 is a map providing the same information for pOints at greater distances from the plant. Figure 4-3 shows additional environmental sample points within a ten I \{ 07 mile radius of the plant.

Table 4-1 provides a description of all environmental sample locations and the sample types collected at each of these locations. The air sample locations were chosen considering the highest average annual D/Q sectors and the practicality of locating continuous air samplers.

All distances on these tables are measured from the unit 1 stack. I '/01 The Ground Water Monitoring Program interfaces with the REMP at selected boundary locations where Monitoring Wells have been established to assist in early warning of potential effluent or 1/07 REMP concerns. Boundary interface locations are included in the REMP (Table 4-1 page 4).

J All other ground water sampling locations are defined in the Ground Water Monitoring Program and station procedures.

Indian Point 3 ODCM Page 4-1 Revision 18

ODCM Part II - Calculational Methodologies FIGURE 4-1 ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS I '( 01 Within Two Miles of Indian Point N

~

.~ lona Peekskill Island Westchester County Rockland County @ Indian pOint~A:

Ib1 [I] (i) 1 mile 131121 Hudson River Ict I 2 c 9

@11J Buchanan I

Key: 6. - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# Ib1 - Fish and Invertebrates o -Air Particulate & Radioiodine A# (where available downstream)

<> - HR Shoreline Sediment wc#

Indian Point 3 ODCM Page 4-2 Revision 18

ODCM Part II - Calculational Methodologies FIGURE 4-2 ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS I '/01 Within Ten Miles of Indian Point N

~ Roseton (20.7 mi. N): 0 @ le3 Upstream: Ib2 Orange County Putnam County Bear Mountain Bridge Smiles Rockland County Westchester County Key: 0 - Direct Radiation Sample Location DR# Ic3 - Broadleaf Vegetation o - Air Particulate & Radioiodine A# Ib2 - Fish and Invertebrates

<> - HR Shoreline Sediment Wc# (where available o -Waterborne: Drinking Wb# upstream)

Indian Point 3 ODCM Page 4-3 Revision 18

ODCM Part II - Calculational Methodologies FIGURE 4-3

(.

ENVIRONMENTAL SAMPLING POINTS I 'ID1 ADDITIONAL SAMPLING LOCATIONS Roseton (20.7 mi. N): 23 : p .

Orange County Putnam County Cold Spring (10.88 mi. N) : 84 :.

Bear Mountain: Bridge 10: . .

17: 'Y

<>r-----t-...

.. 22: . - -...... 104l105:gw 29:

_ _ _....

Rockland County Westchester County Hudson

8:dw RiVer 5 miles Key: - - Air Particulate & Radioiodine <>- HR Shoreline Sediment

- Aquatic Vegetation .-Soil

. . - HR Bottom Sediment gw - Ground Water Boundary Monitoring p - Precipitation (see detailed site map) dw - Drinking Water Indian Point 3 ODCM Page 4-4 Revision 18

ODCM Part II - Calculational Methodologies TABLE 4-1 (Page 1 of 4)

(...... ,

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATIONI I Y07 STATION LOCATION DISTANCE DR1/57 Roa Hook 2.0 mi- N DR2/59 Old Pemart Avenue 1.8 mi - NNE DR3/90 Charles Point 0.88 mi-NE DR4/28 Lents Cove 0.45 mi - ENE DR5/35 Broadway and Bleakley Avenue 0.37 mi - E DR6/88 .. Reuter-Stokes Pole #6 0.32mi- ESE DR7/14 Water Meter House 0.3 mi-SE DR8/03 Service Center Building 0.35 mi - SSE DR9/34 South East Corner of Site 0.52 mi - S DR10/05 NYU Tower 0.88mi-SSW DR11/53 White Beach 0.92mi-SW DR12/74 West Shore Drive - South 1.59mi-WSW DR13/76 West Shore Drive - North 1.21 mi-W DR14/78 Rt. 9W, across from RlS #14 1.2mi-WNW DR15/80 Rt. 9W - South of Ayers Road 1.02 mi - NW DR16/82 Ayers Road 1.01 mi -NNW DR17/58 Rt. 90 - Garrison 5.41 mi-N DR18/60 Gallows Hill Road and Sprout Brook Road 5.02 mi - NNE DR19/62 West Brook Drive (near the Community Center) 5.03 mi-NE DR20/64 Lincoln Road - Cortlandt (School Parking Lot) 4.6 mi - ENE DR21/66 Croton Ave. - Cortlandt 4.87 mi- E DR22/67 Colabaugh Pond Rd. - Cortlandt 4.5 mi- ESE DR23/69 Mt. Airy & Windsor Road 4.97 mi-SE DR24/92 Warren Rd. - Cortlandt 3.84 mi -SSE DR25/71 Warren Ave. - Haverstraw 4.83 mi - S DR26/72 Railroad Ave. & 9W Haverstraw 4.53 mi-SSW DR27/73 Willow Grove Rd. & Captain Faldermeyer Drive 4.97mi-SW DR28/81 Palisades Parkway, Lake Welch Exit 4.96mi-WSW DR29/77 Palisades Parkway 4.15 mi-W DR30/79 Anthony Wayne Park 4.57 mi-WNW DR31/75 Palisades Parkway 4.65mi-NW DR32/83 Rt. 9W Fort Montgomery 4.82mi-NNW DR33/33 Hamilton Street (Substation) 2.88 mi- NE DR34/38 Furnace Dock (Substation) 3.43 mi - SE DR35/89 Highland Ave. & Sprout Brook Rd. (near Rock Cut) 2.89 mi- NNE DR36/61 Lower South Street and Franklin Street 1.3 mi - NE DR37/56 Verplanck - Broadway & 6 th St. 1.25 mi -SSW DR38/20 Cortlandt Yacht Club (aka Montrose Marina) 1.5 mi - S DR39/29 Grassy Point 3.37 mi -SSW DR40/23 Roseton (control station) 20.7 mi - N I ~I 07 DR41/27 Croton Point 6.36 mi-SSE

(

\

Indian Point 3 ODeM Page 4-5 Revision 18

aDCM Part II - Calculational Methodologies TABLE 4-1 (Page 2 of 4)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATIONI STATION LOCATION DISTANCE Airborne A1/4 Algonquin Gas Line 0.28 mi-SW A2/94 IPEG Training Center 0.39 mi-S A3/95 Meteorological Tower 0.46 mi-SSW A4/5 NYU Tower 0.88 mi -SSW A5/23 *Roseton 20.7mi-N Waterborne - Surface (Hudson River Water)

Wa1/9 *Plant Inlet (Hudson River Intake) 0.16 mi - W Wa2/10 Discharge Canal (Mixing Zone) 0.3 mi - WSW Waterborne - Drinking Wb1/7 Camp Field Reservoir 3.4 mi - NE Soil From Shoreline Wc1/53 White Beach 0.92mi-SW Wc2/50 *Manitou Inlet 4.48 mi-NNW Exposure PathwavlSample: Milk There are no milch animals whose milk is used for human consumption within 8 km distance of Indian Point; therefore, no milk samples are taken.

Exposure Pathway/Sample: Ingestion-Fish and Invertebrates The RECS designate two required sample locations labeled Ib1/25 and Ib2/23. The downstream Ib1 location and samples will be chosen where it is likely to be affected by plant discharge. Ib2 will be a location upstream that is not likely to be affected by plant discharge. The following species along with other commercially/recreationally important species are considered acceptable:

Striped Bass Pumpkin Seed American Eel Bluegill Sunfish White Catfish Crabs White Perch Blueback Herring Exposure Pathway/Sample: Ingestion-Food Products (Broad Leaf Vegetation)

Ic1/95 Meteorological Tower 0.46 mi - SSW Ic2/94 IPEC Training Center 0.39 mi - S Ic3/23 *Roseton 20.7 mi - N

Control Station Indian Point 3 ODCM Page 4-6 Revision 18

ODCM Part II .;.. Calculational Methodologies

( TABLf; 4-1

~

(Page 3 of 4)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATIONI SAMPLE I 101 STATION LOCATION DISTANCE TYPES DR8/3 Service Center Building 0.35 mi - SSE 3 A1/4 Algonquin Gas line 0.28 mi-SW 1,2 A4,DR10/5 NYU Tower 0.88 mi-SSW 1,2,3 Wb1/7 Camp Field Reservoir 3.4 mi - NE 6

- /8 Croton Reservoir 6.3 mi - SE 6 YD7 Wa1/9 *Plant Inlet (Hudson River Intake) 0.16 mi-W 7 Wa2l1 0 Discharge Canal (Mixing Zone) 0.3mi-WSW 7,8 DR7/14 Water Meter House 0.3 mi -SE 3

- /17 Off Verplanck 1.5mi-SSW 8,9,10 YO?

DR38/20 Cortlandt Yacht Club (AKA 1.5 mi-S 3 Montrose Marina)

- /22 Lovett Power Plant 1.6 mi -WSW 1,2 I VOl Ib2,A5,DR40,lc3/23 *Roseton 20.7 mi-N 1,2,3,4,5,11,12 Ib1/25 where available, downstream N/A 12 DR41/27 Croton Point 6.36mi -SSE 1,2,3 DR4/28 Lents Cove 0.45 mi - ENE 3,8,9,10

("

\ ';..*. , .. DR39/29 Grassy Point 3.37 mi-SSW 1,2,3 DR33/33 Hamilton Street (Substation) 2.88 mi - NE 3 DR9/34 South East Corner of Site 0.52 mi-S 3 DR5/35 Broadway & Bleakley Avenue 0.37 mi- E 3 DR34/38 Furnace Dock (Substation) 3.43 mi -SE 3

- /44 Wc2/50 Peekskill Gas Holder Building

Manitou Inlet 1.84 mi - NE 4.48 mi-NNW 1,2,11 10 I Y07 Wc1,DR11/53 White Beach 0.92mi-SW 3,10 DR37/56 Verplanck - Broadway & 6th Street 1.25 mi - SSW 3 DR1/57 Roa Hook 2.0 mi-N 3 DR17/58 Rt. 90 Garrison 5.41 mi-N 3 DR2/59 Old Pemart Ave. 1.8 mi - NNE 3 DR18/60 Gallows Hill Road and Sprout Brook 5.02 mi-NNE 3 Road DR36/61 Lower South Street and Franklin 1.3 mi - NE 3 Street DR19/62 West Brook Drive (near the 5.03 r

mi - NE 3 Community Center)

DR20/64 lincoln Road - Cortlandt (School 4.6 mi -ENE 3 Parking Lot)

DR21/66 Croton Ave. - Cortlandt 4.87 mi - E 3 DR22/67 Colabaugh Pond Rd. - Cortlandt 4.5 mi- ESE 3 DR23/69 Mt. Airy & Windsor Road 4.97 mi - SE 3

/

Control Station ** Items are in excess of RECS requirements I 107 Indian Point 3 ODCM Page 4-7 Revision 18

ODCM Part II - Calculational Methodologies

( TABLE 4*1 (Page 4 of 4)

ENVIRONMENTAL SAMPLING POINTS SAMPLE 1107 DESIGNATIONI SAMPLE STATION LOCATION DISTANCE TYPES DR25/71 Warren Avenue - Haverstraw 4.83 mi - S 3 DR26/72 Railroad Ave. & 9W - Haverstraw 4.53mi-SSW 3 DR27173 Willow Grove Rd. & Captain Faldermeyer Dr 4.97 mi -SW 3 DR12/74 West Shore Drive - South 1.59 mi-WSW 3 DR31/75 Palisades Parkway 4.65mi-NW 3 DR13/76 West Shore Drive - North 1.21 mi-W 3 DR29/77 Palisades Parkway 4.15mi-W 3 DR14/78 Rte. 9W, across from RlS #14 1.2 mi -WNW 3 DR30/79 Anthony Wayne Park 4.57mi-WNW 3 DR15/80 Rte. 9W - South of Ayers Road 1.02 mi- NW 3 DR28/81 Palisades Parkway, Lake Welch Exit 4.96mi-WSW 3 DR16/82 Ayers Road 1.01 mi - NNW 3 DR32/S3 Rte. 9W - Fort Montgomery 4.82mi-NNW 3

- /84

- /85 Cold Spring Quality Control 10.88 mi - N 8,9,10 6

1'/07 DR6/8S Reuter-Stokes Pole #6 0.32 mi - ESE 3

( DR35/S9 Highland Ave. & Sprout Brook Rd (rock cut) 2.89 mi - NNE 3 DR3/90 Charles Point 0.S8 mi- NE 3 DR24/92 Warren Rd. - Cortlandt 3.84 mi -SSE 3 A2,Ic2/94 IPEC Training Center 0.39mi -S 1,2,4,5 A3, Ic1/95 Meteorological Tower 0.46 mi - SSW 1,2,4,5 MW-40/104 Boundary Well #40 0.21 mi - SW 13 Y07 MW-51/105 Boundary Well #51 0.18 mi - SSW 13

- Items are in excess of RECS requirements Sample types are:

1. Air particulates S. H.R. bottom sediment-silt

2. Radioiodine 9. H.R. aquatic vegetation

3. Direct gamma 10. H.R. shoreline soil

4. Broadleaf vegetation 11. Fallout

5. Soil 12. Fish and invertebrates

6. Drinking water 13. Ground water boundary monitoring

7. Hudson River (H.R.) water (see ODCM Part II, Figure 1-1) I '101 t

Indian Point 3 ODCM Page 4-S Revision 18

ODCM Part II - Calculational Methodologies APPENDIX B DETECTION CAPABILITIES The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

2.71 + 3.29 Sb

J1 +(Tb)

LLD= Ts Ts E

V

k

Y

e-.<J where:

LLD= The lower limit of detection as defined above (as picocurie per unit mass or volume)

The sample counting time in minutes The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

The background count time in minutes E= The counting efficiency (as counts per transformation) v= The sample size (in units of mass or volume) k= A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per IlCi)

Y= The fractional radiochemical yield (when applicable)

A= The radioactive decay constant for the particular radionuclide t = The elapsed time between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times.

The IP3 Radiological Environmental Monitoring Program, REMP, uses an LLD formula that assumes equal background and sample count times, in accordance with the RECS. When the above LLD formula is more appropriate for the effluents program, it may be used.

1 Indian Point 3 ODCM Page 4-9 Revision 18

ODeM Part /I - Calculational Methodologies The constants 2.71 and 3.29 and the general LLD equation were derived from the following two sources:

1) Currie, L.A. "Limits for Qualitative Detection of Quantitative Determination". (Anal. Chem.

40:586-593, 1968); and,

2) Mayer, Dauer "Application of Systematic Error Bounds to Detection Limits for Practical Counting". (HP Journal 65(1): 89-91, 1993)

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within! one FWHM (Full-Width-at-Half-Maximum) eriergy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement process and not as an a posteriori (after the fact) limit for a particular measurement.

To handle the a posteriori problem, a decision level must be defined. The remainder of Appendix B discusses the use of the Critical Level concept. Following an experimental observation, one must

{ decide whether or nota real Signal was, in fact, detected. This type of binary qualitative decision is subject to two kinds of error: deciding that the radioactive material is present when it is not (a: Type I error), and the converse, failing to decide that it is present when it is (b: Type /I error). The maximum acceptable Type I error (a), together with the standard deviation, Snet, of the net signal when the net signal equals zero, establish the Critical Level, Lc, upon which decisions may be based.

Operationally, an observed signal, S, must exceed Lc to yield the decision, detected.

Lc = kas b( 1+T Jfs)O.5 where:

ka is related to the standardized normal distribution and corresponds to a probability level of 1-a.

For instance, selection of a = 0.01 corresponds to a 99% confidence level that activity is present.

When determining the Lc for different measurement processes, it is allowable to set a at less than or equal to 0.05 as long as the following condition is met:

To set ~ for Lc determination at less than 0.05, the equation for the LLD (which places ~ less than or equal to 0.05) should be employed to verify that the calculated LLD is less than or equal to the LLDs specified in the IP-3 RECS. This calculation, if necessary, will be performed on a case by case basis.

(.

Indian Point 3 ODCM Page 4-10 Revision 18

Unit 2 aDeM Revision 10 Justification Package Prepared by: Steven Sandike Brief Summary of Changes January, 2007 aDCM Part I Added definition of Pri to Sec Leak in 01.1 (from U3 ODCM).

2 Added Service Water and Turbine Hall Drains to Table 03.1.1-1 and clarified differentiation between sampling and analysis.

3 Added notes (i) and (j) to the Notes following Table 03.1.1-1 for FeedwaterfTH Drains, and need for beta analyses.

4 Listed effective tanks in DLCO 3. 1.4.

5 Reworded DSR 3. 1.4. 1 to identify that the determination is performed in accordance with the ODCM.

6 Clarified VCPR sample requirements in Table 3.2.1-1, footnote (i) for periods when both VC Rad Mons (R-41 & 42) are OOS.

7 Clarified Table 3.3.1-1, (2a), adding footnote (g), specifying which SW monitors are required when systems are in service.

8 Clarified Condition "G" in DLCO 3.3.2 to stipulate this condition refers to gas decay tanks.

9 Added Sr-90 requirements to the REMP in Table 0 3.5.1-1, Sections 3c (sediment) and 4b (Fish / Invertebrates).

10 Added Site Boundary Monitoring Well sample requirements to Table 0 3.5. 1-1 as Section 3d per the GWMP.

11 Added Sr-90 to Tables 0 3.5.1-2 and 0 3.5.1-3 with note identifying the GWMP interface with the REMP.

12 Added clarification for the meaning of LLD in Table 0 3.5.1-3, note c, from U3 ODCM.

13 Expanded the explanation of the UNRESTRICTED AREA maps in section 0 4.1, and added specific map for release points.

14 Add additional verbiage to Section D 5.1 to include all of U3 ODCM information for the joint annual REMP report.

15 Added Section 5.6 to identify the Ground Water Monitoring Program and its key components.

aDeM Part II 16 Added a discussion of IE Bulletin 80-to program (from U3 ODCM) to Section 1.1.

17 Added a section describing concentration limits on tanks to comply with the 10 curie limit (from U3 ODCM) to Section 1. 1.

18 Added a paragraph to Section 1. 1 to identify potentially necessary additional release quantification from the GWMP.

19 Added References 24 and 25 regarding the GWMP.

20 Added ground and storm water representation to Appendix B.

21 Modified Appendix G, pages 5-7 to show "additional" sample points, rather than "RECS or non-RECS".

22 Denoted samples that are NOT required by RECS in Appendix G (pages 3 and 4).

23 Added Boundary Wells (MW-40 and MW-51) to Appendix G, page 4, and explained note 13. as supporting GWMP.

Each change is discussed in detail on the following pages. This information is to be included in the OSRC presentation, the 50.59 package, and the next Annual Effluent Release Report sent to the Commission per Reg Guide 1.21

Unit 2 aDeM Revision 10 Justification Package item # 1 of 23 Jan, 2007 OBJECTIVE:

Add definition of Pri to Sec Leak in 01.1 (from U3 ODCM).

DESCRIPTION OF CHANGES:

Added the definition of Pri to Sec Leak from Unit 3 ODCM into the definition section of U2 ODCM.

IMPACT:

None.

JUSTIFICATION:

This definition includes detailed criteria from plant parameters to differentiate diffusion of H-3 through the SG U-tubes, from an actual Primary to Secondary Leak. It has been in station procedures and the unit 3 ODCM for several years and was added to the U2 ODCM for completeness and to better prepare for the upcoming merge of ODCMs into one document.

Unit 2 aDeM Revision 10 Justification Package item # 2 of 23 Jan, 2007 OBJECTIVE:

Add Service Water and Turbine Hall Drains to Table 03.1.1-1 and clarify differentiation between sampling and analysis.

DESCRIPTION OF CHANGES:

Added Service Water and Turbine Hall Drains to this table; in addition to the earlier entry, which had been simply entitled "Continuous Releases". Clarified the differences between Sample and analysis frequency where composites were involved.

IMPACT:

None.

JUSTIFICATION:

This section of the RECS, following NUREG 1301, simply splits batch and continuous liquid effluent sampling requirements into two general categories. However, as not all continuous releases have the same requirements. These two types of continuous releases were added as separate lines. These criteria have not changed, but were copied into the Unit 2 aDCM from the Unit 3 aDCM and station procedures in preparation of merging the ODCMs, and for completeness and accuracy with regard to these special continuous releases.

Unit 2 ODeM Revision 10 Justification Package item # 3 of 23 Jan,2007 OBJECTIVE:

Add notes (i) and (j) to the Notes following Table D3.1.1-1 for FeedwaterfTH Drains. Identify beta analyses required when gamma activity is detected for these pathways.

DESCRIPTION OF CHANGES:

Added notes (i) and U) to the Notes following Table D3.1.1-1 for FeedwaterfTH Drains. Add the Beta analyses requirement when gamma activity is detected for these pathways.

IMPACT:

None.

JUSTIFICATION:

These two new types of continuous releases were added to the aDCM on separate lines to ensure completeness and assist in merging the document with Unit 3's aDCM. The requirement for Beta analyses only applies if gamma isotopes are present for these streams, as they are not normally monitored for Beta emitters. Beta activity in these systems would be identified either from known SG Tube leaks (already monitored via SG blowdown) or documented Service Water leaks. These criteria have not changed, but were copied into the Unit 2 aDCM from the Unit 3 aDCM and station procedures in preparation of merging the ODCMs, and for completeness and accuracy with regard to these special continuous releases.

IUnit 2 aDeM Revision 10 Justification Package item # 4 of 23 Jan, 2007 OBJECTIVE:

List effective tanks in DLCO 3.1.4.

DESCRIPTION OF CHANGES:

Listed the effected tanks within the DLCO, rather than just the bases.

IMPACT:

None.

JUSTIFICATION:

This clarification enhancement was performed to provide the brief list of effected tanks directly within the LCO, rather than leave this information to only the BASES. The CONDITION statement refers to

" ... limits in any listed tanJ('. It was not clear (without actually listing the tanks below this phrase), exactly WHICH tanks were effected by this LCO. While it may be an expectation to refer to the BASES section for this kind of information, there are only two permanent tanks involved in this LCO, and it was much more clear to simply list them within the LCO. Additionally, this improvement helps to consolidate methodologies between ODCMs, as unit 3 ODCM lists the tanks effected in unit 3.

Unit 2 aDeM Revision 10 Justification Package item # 5 of 23 Jan,2007 OBJECTIVE:

Reword DSR 3.1.4.1 to identify that the determination is performed in accordance with the' ODCM.

DESCRIPTION OF CHANGES:

Reworded DSR 3.1.4.1 to identify that a DETERMINATION is to be performed in accordance with the ODCM .

.IMPACT:

None.

JUSTIFICATION:

Adding this explanation ensures that a grab sample of an idle tank is not automatically required to demonstrate compliance with this surveillance. While isolating, recirculating, and sampling are always an option, "determining" that the curie level of an outdoor tank can also be accomplished by tracking the curie contents from inlet concentrations and volume added, which in many case, is zero.

Station procedures, as well as this section of the ODeM, limit the concentration in these tanks such that ten curies cannot be approached at any time. This improvement will ensure there is a means of determining the curie content, while precluding mandated significant resource expenditure for idle tanks which can otherwise be proven well below the ten curie limit.

Unit 2 aDeM Revision 10 Justification Package item # 6 of 23 Jan,2007 OBJECTIVE:

Clarify VCPR sample requirements when both R-41 and R-42 are OOS (no VC rad monitor available).

DESCRIPTION OF CHANGES:

Clarify Table D 3.2.1-1, Note (i) to provide VCPR sample requirements when both R-41 and R-42 are OOS (no VC rad monitor available). While this note had previously identified the requirement for a VC noble gas grab sample when R-42 was ODS, the additional requirement of two independent samples was added if the particulate monitor is also ODS.

IMPACT:

None. Plant lower tier procedures already had incorporated this clarification.

JUSTIFICATION:

These criteria were added to the ODCM for clarity and completeness as a result of the generally incomplete guidance for VCPR applications in the NUREG 1301. Lower tier procedures include this guidance at both operating units, when both VC rad monitors are DOS. While a noble gas grab sample would suffice when the gas monitor was DOS, the lack of the particulate monitor as well indicates no automatic isolation at the source. Therefore, additional assurance of absence of risk appears warranted.

Unit 2 aDeM Revision 10 Justification Package item # 7 of 23 Jan,2007 OBJECTIVE:

Clarify Table 3.3.1-1, (2a) and add footnote (g) to specify which SW monitors are required when systems are in service.

DESCRIPTION OF CHANGES:

Identified in four distinct lines, the Service Water monitor requirements, to clarify the redundancy of R-46/53 (FCUs), but still identify the need for individual channels (one per instrument) for the other Service Water effluent lines. Added Note (g) to ensure requirements were clearly specified.

IMPACT:

None. Plant lower tier procedures already had incorporated this clarification.

JUSTIFICATION:

These criteria were added to the ODCM for clarity and completeness as a result of less specific guidance in earlier revisions. While either R-46 or R-53 satisfies the requirement for FCU SW effluent, the other SW lines listed require the applicable monitor to be in service while there is a Service Water effluent.

This improvement from the simplistic listing in NUREG 0472 is consistent with the FSAR description, NUREG 1301, system descriptions, and industry benchmarking.

Unit 2 aDeM Revision 10 Justification Package item # 8 of 23 Jan,2007 OBJECTIVE:

Clarify Condition "Gil in OLCO 3.3.2 to stipulate this condition refers to gas decay tanks.

DESCRIPTION OF CHANGES:

Clarify OLCO 3.3.2, Condition "Gil, that this stipulation*applies to gas decay tanks. (Inserted "gas decay tank" prior to "release" in the completion time block). .

IMPACT:

None.

JUSTIFICATION:

This clarification was necessary as a result of inadvertent omission of the gas decay tank reference when this LCO was converted into NUREG 1431 format for ITS. As a result, it had occasionally been inappropriately applied to Plant Vent applications. NUREG 1301 clearly stipulates this control with regard to gas decay tank releases with an inoperable radiation monitor. .

Unit 2 aDeM Revision 10 Justification Package item # 9 of 23 Jan,2007 OBJECTIVE:

Add Sr-90 requirements to the REMP in Table D 3.5.1-1, Sec 3c (sediment) and 4b (Fish/lnv).

DESCRIPTION~OF CHANGES:

Added a requirement for analysis of Sr-90 in Shoreline Sediment, Ground Water, and Fish/Invertebrates in Table 2.7-1. Clarified that for the ingestion pathway, this analysis involves edible portions of fish and invertebrates, in 2 nd column (Section 4b)

IMPACT:

Fish, Ground Water, and Shoreline Sediment samples for the REMP will now require Sr-90 analyses.

JUSTIFICATION:

Sr-90 was added to these tables as a commitment from the Ground Water investigation. While the old values of ETSR in 1977 were evaluated for application, a new dose basis for the values selected was performed per IPEC-CHM-06-026. This memo establishes LLDs and Reporting Levels by comparisons to ratios of other isotopes and EPA drinking water standards, as well as a determination of ensuring the LLD represents 10% or less of the annual critical organ dose contribution for Sr-90 in both water and fish.

The resulting LLD~ dropped Slightly from those in practice when Sr-90 was last required in the REMP.

Reporting levels were then extrapolated from comparisons to other nuclides and to the drinking water guidelines.

The memo also made clear the distinction between these values (applying solely to the REMP) and values determined for use in the Ground Water Monitoring Program (GWMP), which may involve other criteria. Reporting levels and LLDs for ground water are included in the GWMP and station procedures.

Unit 2 aDeM Revision 10 Justification Package item # 10 of 23 Jan, 2007 OBJECTIVE:

Add Site Boundary Monitoring Well sample requirements to Table 0 3.5.1-1 as Section 3d per the GWMP. .

DESCRIPTION OF CHANGES:

Added Site Boundary Monitoring Well sample requirements to Table 0 3.5.1-1 in Section 3d.

Identified 2 wells, sampled quarterly for gamma spec, H-3, and Sr-90.

IMPACT:

Increased annual operating cost and new procedural requirements for the REMP.

JUSTIFICATION:

Analyzing for these isotopes on the way to the site boundary will help define the extent of any potential plume. It will give an early warning of possible movement toward the actual site boundary in these directions. This effort is required by the NEI initiative and a commitment to the NRC and local stakeholders (NL-06-033, #2 and #3).

Unit 2 aDeM Revision 10 Justification Package item # 11 of 23 Jan, 2007 OBJECTIVE:.

Add Sr-90 to Tables D3.5.1-2 and D3.5.1-3 with note identifying the GWMP interface with the REMP.

DESCRIPTION OF CHANGES:

Reporting Levels and LLDs for Sr-90 were reinstated into these tables, as a result of adding the requirement to analyze for this isotope. Added a note to ensure there is a clear understanding of the interface between the GWMP and the REMP (such that LLDs and Reporting Levels are understood to be potentially different between the two).

IMPACT:

None. Vendor labs have verified ability to meet LLDs.

JUSTIFICATION:

Sr-90 was added to these tables as a commitment from the Ground Water investigation. While the old values of ETSR in 1977 were evaluated for application, a new dose basis for the values selected was performed per IPEC-CHM-06-026. This memo establishes LLDs and Reporting Levels by comparisons to ratios of other isotopes and EPA drinking water standards, as well as a determination of ensuring the LLD represents 10% or less of the annual critical organ dose contribution for Sr-90 in both water and fish.

The resulting LLDs dropped slightly from those in practice when Sr-90 was last required in the REMP.

Reporting levels were then extrapolated from comparisons to other nuclides and to the drinking water guidelines.

The memo also made clear the distinction between these values (applying solely to the REMP) and values determined for use in the Ground Water Monitoring Program (GWMP), which may involve other criteria. Reporting levels and LLDs for ground water are included in the GWMP and station procedures.

Unit 2 aDeM Revision 10 Justification Package item # 12 of 23 Jan, 2007 OBJECTIVE:

Add clarification for the meaning of LLD in Table D 3.5.1-3, note c, from U3 ODCM.

DESCRIPTION OF CHANGES:

The definition of LLD in note (c) at the end of this table was expanded to include the differentiation between a priori and a posteriori measurements.

IMPACT:

None.

JUSTIFICATION:

The added definition from U3 aDCM was added here to U2 aDCM to ensure complete understanding of the application and purpose of the REMP LLDs, as well as to continue the effort to merge the station's ODCMs into one document. This enhancement to the definition is in addition to NUREG 1301 requirements, but consistent with industry standard understanding of the term "LLD".

Unit 2 aDeM Revision 10 Justification Package item # 13 of 23 Jan,2007 OBJECTIVE:

Expand the explanation of the UNRESTRICTED AREA maps in section D 4.1, and add a specific map for release points.

DESCRIPTION OF CHANGES:

Indicated the GWMP Boundary Wells (MW-40 and MW-51) on the site boundary map, and removed the confusing complexity of identifying release points on this map. Included a second, more detailed map of the power block area, specifically for identifying release points. Section D 4.1.1 was also updated to include a description of the maps included in the ODCM for this purpose.

IMPACT:

None.

JUSTIFICATION:

A map showing the unrestricted area and effluent release points is required by NUREG 1301.

Using 2 maps more clearly complies with these requirements. The maps include all the desired functionality, and allow for the addition of locating the GWMP boundary wells.

The location of these new Monitoring Wells ("boundary wells" per the NEI initiative) cannot be shown on other REMP maps, due to the fact that the REMP maps indicate sample locations OFFSITE. Since boundary wells are WITHIN the site boundary, a map associated with the UNRESTRICTED AREA serves as an ideal location for this additional purpose.

Unit 2 aDeM Revision 10 Justification Package item # 14 of 23 Jan,2007 OBJECTIVE:

Add additional verbiage to Section D 5.1 to include all of U3 aDCM information for the joint annual REMP report.

DESCRIPTION OF CHANGES:

Add the due date for the report, and all the additional information from the U3 aDCM to this section describing the requirements of the annual radiological environmental operating report.

IMPACT:

None. The REMP continues to be a site-wide enterprise and one set of regulations apply.

JUSTIFICATION:

The items listed under Section D 5.1 were taken directly from NUREG 1301. More detail had been included in Unit 3's equivalent section. This added detail included a due date for the report and a reference to the Radiological Assessment Branch Technical Position, Rev 1, November 1979. Unit 2 had not been required to list or comply with this assessment in earlier versions of the ODCM. These criteria have applied, however, to the site's unified REMP even before consolidation, per NUREG 0133 and 1301, which identifies the potential for combining REMP-related efforts and reports for multiple units on one site. Therefore, for completeness and to facilitate the pending effort to merge the ODCMs into one, these criteria are now specified directly in both ODCMs.

Unit 2 aDeM Revision 10 Justification Package item # 15 of 23 Jan, 2007 OBJECTIVE:

Add Section 5.6 to identify the Ground Water Monitoring Program and its key components.

DESCRIPTION OF CHANGES:

Add a section to the Admin portion of the REGS to ensure licensing basis inclusion of the GWMP and comply with commitments NL-06-033, #4 and #5.

IMPACT:

Lower tier procedures as well as an SMM are drafted for implementing the GWMP.

JUSTIFICATION:

This new section is added to the REGS Admin Requirements to ensure the GWMP maintains a tie to the licensing basis requirements and NRG commitments, as well as the NEI initiative. Placing the overview and general requirements of the program (defined in the SMM for GWMP) here in the REGS ensures continued connection with the licensing basis, in a similar fashion as the effluents and environmental monitoring programs.

Unit 2 aDeM Revision 10 Justification Package item # 16 of 23 Jan, 2007 OBJECTIVE:

Add a discussion of IE Bulletin 80-10 program (from U3 ODCM) to Section 1.1.

DESCRIPTION OF CHANGES:

Included a paragraph of the interface between the ODCM and the 80-10 program in Section 1.1, as already identified in the Unit 3 ODCM.

IMPACT:

None.

JUSTIFICATION:

This section is added for clarity and completeness, to facilitate eventual merging of the site's ODCMs, and to ensure the current Unit- 2 aDCM includes specific examples of how the ODCM and 80-10 programs interact. These include storm drains and the Spent Fuel Pool aux cooling systems.

Unit 2 aDeM Revision 10 Justification Package item # 17 of 23 Jan, 2007 OBJECTIVE:

Add a paragraph to Section 1.1, describing concentration limits on tanks to comply with the 10 curie limit.

DESCRIPTION OF CHANGES:

Add the equivalent U3 aDCM paragraph describing how outdoor liquid tan~ curie levels are controlled by limiting the concentration of the tanks. Included are specific calculations showing the volume and back-calculated concentration in the tank corresponding to 10 curies. Additionally, a phrase is added to identify the option of determining the curie content from volumes and inlet concentrations.

IMPACT:

None. Station lower tier procedures (IP-SMM-CY-001, Radioactive Effluents Control Program, and others) already include these tank concentration limits.

JUSTIFICATION:

Adding these criteria to the ODCM maintains the licensing basis methodology already employed to ensure the tanks remain less than 10 curies. The verbiage and equations were copied from the U3 aDeM (and made applicable to the Unit 2 tanks) to facilitate the pending merge of these documents into a site aDCM.

Unit 2 aDeM Revision 10 Justification Package item # 18 of 23 Jan,2007 OBJECTIVE:

Add a paragraph to Section 1.1 to identify potentially necessary additional release quantification from the GWMP.

DESCRIPTION OF CHANGES:

Summarize the inputs to the process of quantifying groundwater's contribution to offsite dose, in a similar fashion to the discussion of inputs to other quantification methodologies, per NL-06-033, #1. These inputs include source term, release rate, and the dilution factor.

IMPACT:

None.

JUSTIFICATION:

Quantification methodologies for all effluent calculations are discussed in this section of the aDCM

(

(Calculational Methodologies). Hence, an overview of the Ground Water calculational inputs is added to this section of the ODCM. Once these inputs are gathered, this step refers to Reg Guide 1.109 processes like other liquid effluent, for determining the offsite dose. Beyond the basic tenants of quantifying ground water effluent, the details of this quantification process, like other liquid and airborne pathways, are provided in station procedures.

Unit 2 aDeM Revision 10 Justification Package item # 19 of 23 Jan, 2007 OBJECTIVE:

Add References 24 and 25 regarding the GWMP.

DESCRIPTION OF CHANGES:

The bases for GWMP release rates and dilution factors are added as References 32 and 33.

IMPACT:

None.

JUSTIFICATION:

Release rate and dilution flow quantification bases are provided in these references. They involve approved methodologies for determining these inputs and are included as references for completeness.

Unit 2 aDeM Revision 10 Justification Package item # 20 of 23 Jan, 2007 OBJECTIVE:

Add ground and storm water representation to Appendix B.

DESCRIPTION OF CHANGES:

Added representation of these pathways to the flow diagram.

IMPACT:

None.

JUSTIFICATION:

This effort results in a more complete representation of all liquid effluent.

Unit 2 aDeM Revision 10 Justification Package item # 21 of 23 Jan,2007 OBJECTIVE:

Modify Appendix G, pages 5-7 to show "additional" sample points, rather than "REGS or non-REGS".

DESCRIPTION OF CHANGES:

Discontinue the differentiation of REGS and NON-REGS atop the pages of sample locations.* Instead, samples that are in excess of REGS requirements are denoted in the list of locations.

IMPACT:

None.

JUSTIFICATION:

Data from extra sample locations will continue to be collected for historical purposes. The attempt to differentiate REGS and NON-REGS locations generated confusion with regard to the fact that all locations listed in the ODGM are required by the "ODGM", if not the "REGS". This effort was a hold-over from pre-ITS implementation and has no purpose in our more modern ODGMs, all of which is governed by the 50.59 process.

Simplifying, all samples listed are required due to their presence in the ODGM, and those in excess of the RECS are so designated.

Unit 2 ODeM Revision 10 Justification Package item # 22 of 23 Jan, 2007 OBJECTIVE:

Denote samples that are NOT required by REGS in Appendix G (pages 3 and 4).

DESCRIPTION OF CHANGES:

In place of identifying sample locations as REGS or NON-REGS, this verbiage was replaced by a notation for each effected sample location as being in excess of REGS requirements.

IMPACT:

None JUSTIFICATION:

This improvement clarifies that although all samples are required by the ODGM, some are in excess of REGS requirements. Samples listed are continued for historical purposes. This update reduces confusion with regard to RECS and NON-REGS sampling by eliminating those terms in favor of notation identifying effected sample location as being "in excess of REGS requirements".

Unit 2 aDeM Revision 10 Justification Package' item # 23 of 23 Jan, 2007 OBJECTIVE:

Add Boundary Wells (MW-40 and MW-51) to Appendix G, page 4, and explain note 13 as supporting GWMP.

DESCRIPTION OF CHANGES:

Added boundary well sample requirements to the REMP per NL-06-033, #2, and #3.

IMPACT:

Increased annual operating cost and new procedural requirements for the REMP.

NEM procedures are updated for this inclusion.

References of this interface are drafted in the GWMP implementing procedures.

JUSTIFICATION:

The commitment to add these boundary wells to the REMP was driven from the NEI ground water initiative. The interface between the REMP and the GWMP is identified as these boundary wells in the REMP, and are added to the aDeM in excess of the requirements of NUREG 1301.

Entergy Nuclear Northeast Indian Point Units 1, 2 TITLE: OFFSITE DOSE CALCULATION MANUAL (ODeM)

Rev. 10 WRITIENBY:

date REVIEWED BY: II"~

date J JIC/D+

OSRC REVIEW: m+-(o,- OO}

date APPROVED BY: ~\ lj\ 67 date <<t EFFECTIVE DATE:

1-'/~-1 date

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL PAGE 03.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Monitoring Program D 3.5.1-1 D 3.5.2 Land Use Census D 3.5.2-1 D 3.5.3 Interlaboratory Comparison Program D 3.5.3-1 03.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System D3.6.1-1 04.0 DESIGN FEATURES D 4.1 UNRESTRICTED AREA D 4.1-1 05.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report D 5.1-1 D 5.2 Radioactive Effluent Release Report D 5.2-1 D 5.3 Special Reports D 5.3-1 D5.4 Major Changes to Radwaste Treatment Systems D 5.4-1 D 5.5 Process Control Program D 5.5-1 Indian Point 2 ii Revision 10

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL BASES PAGE B D3.0 APPLICABILITY B D 3.0 ODCM Limiting Condition for Operation (DLCO) B D 3.0-1 B D 3.0 ODCM Surveillance Requirement (DSR) B D 3.0-1 B D 3.1 RADIOACTIVE LIQUID EFFLUENTS B D 3.1.1 Liquid Effluents Concentration B D 3.1.1-1 B D 3.1.2 Liquid Effluents Dose B D 3.1.2-1 B D 3.1.3 Liquid Radwaste Treatment System B D 3.1.3-1 B D 3.1.4 Liquid Holdup Tanks B D 3.1.4-1 B D3.2 RADIOACTIVE GASEOUS EFFLUENTS B D 3.2.1 Gaseous Effluents Dose Rate B D 3.2.1-1 B D 3.2.2 Gaseous Effluents Dose - Noble Gas B D 3.2.2-1 B D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate B D 3.2.3-1 B D 3.2.4 Gaseous Radwaste Treatment System B D 3.2.4-1 B D 3.2.5 Ventilation Exhaust Treatment System B D 3.2.5-1 B D 3.2.6 Gas Storage Tanks B D 3.2.6-1 B D3.3 INSTRUMENTATION B D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation B D 3.3.1-1 B D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation B D 3.3.2-1 B D3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE B D 3.4.1 Radioactive Effluents Total Dose B D 3.4.1-1 B D3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B D 3.5.1 Radiological Environmental Monitoring Program BD3.5.1-1 B D 3.5.2 Land Use Census B D 3.5.2-1 B D 3.5.3 Interlaboratory Comparison Program B D 3.5.3-1 B D3.6 SOLID RADIOACTIVE WASTE B D 3.6.1 Solid Radwaste Treatment System BD3.6.1-1 Indian Point 2 111 Revision 10

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL PART II CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENT METHODOLOGY 1.1 Liquid Effluent Model Assumptions and Information 1 1.2 Determination of Setpoints for Liquid Effluent Monitors 2 1.3 Determining the Dose for Radioactive Liquid Effluents 2 1.4 Dose Calculations 3 2.0 GASEOUS EFFLUENT METHODOLOGIES 2.1 Gaseous Effluent Model Assumptions and Information 13 2.2 Determination of Releases from Indirectly Monitored Sources 15 2.3 Noble Gas Releases Dose Rates for Total Body and Skin 15 2.4 Determining the Radioiodines, 8-day Particulate and Tritium Instantaneous Doses from Gaseous Releases 17 2.5 Gamma Air Dose for Noble Gas Releases 18 2.6 Beta Air Dose for Noble Gas Releases 20 2.7 Determining the Radioiodines, 8-day Particulate and Tritium Cumulative Doses from Gaseous Releases 20 2.8 Gas Storage Tank Activity Limit 25 3.0 TOTAL DOSE DETERMINATIONS 3.1 10CFR190 Dose Evaluation 68 3.2 Doses from Liquid Releases 68 3.3 Doses from Atmospheric Releases 68 4.0 SETPOINT CALCULATIONS 4.1 Liquid Monitor Setpoints 69 4.2 Gaseous Monitor Setpoints 70 5.0 LOWER LIMIT OF DETECTION 72 REFERENCES 74 APPENDICES Appendix A: Dispersion and Deposition Factors 75 Appendix B: Liquid Effluent Simplified Flow Diagram 76 Appendix C: Gaseous Effluent Simplified Flow Diagram 77 Appendix 0: Steam Partition Factor Calculation (f ) 78 Indian Point 2 iv Revision 10

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL APPENDICES (Continued)

Appendix E: Allowed Diluted Concentration (ADC) 79 Appendix F: Conversion Factors for Liquid Effluent Monitors 80 Appendix G: Environmental Sampling Points 81 Appendix H: Interlaboratory Comparison Program 88 Appendix I: Calculation of Allowable Release Rates for Indian Point Units 2 and 3 89 Indian Point 2 v Revision 10

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES PART I - RADIOLOGICAL EFFLUENT CONTROLS D 3.1.1-1 Radioactive Liquid Waste Sampling and Analysis D 3.1.1-2 D 3.2.1-1 Radioactive Gaseous Waste Sampling and Analysis D 3.2.1-2 D 3.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1-6 D 3.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2-5 D 3.5.1-1 Radiological Environmental Monitoring Program D 3.5.1-6 D 3.5.1-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples D 3.5.1-9 D 3.5.1-3 Detection Capabilities for Environmental Sample Analysis D3.5.1-10 Indian Point 2 VI Revision 10

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION* MANUAL LIST OF TABLES PART II CALCULATIONAL METHODOLOGIES 1-1 Summary of Liquid RECS 5 1-2 Site Related Adult Ingestion Dose Commitment Factors 6 1-3 Site Related Teen Ingestion Dose Commitment Factors 8 1-4 Site Related Child Ingestion Dose Commitment Factors 10 1-5 Bio-Accumulation Factors for Liquid Effluent Isotopes . 12 2-1 Summary of Gaseous RECS 27 2-2a Adult Inhalation Dose Factors 28 2-2b Teen Inhalation Dose Factors 30 2-2c Child Inhalation Dose Factors 32 2-2d Infant Inhalation Dose Factors 34 2-2e Total Body and Skin Ground Plane Dose Factors, with Isotope Half Life

" and Stable Element Transfer Data 36 2-3a Adult Ingestion Dose Factors 38 2-3b Teen Ingestion Dose Factors 40 2-3c Child Ingestion Dose Factors 42 2-3d Infant Ingestion Dose Factors 44 2-4 Total Body Dose Factors, Ki, from Noble Gas (Gamma) 46 2-5 Skin Dose Factors, Li, from Noble.Gas (Beta) 47 2-6 Air Dose Factors, Mi, from Noble Gas (Gamma) 48 2-7 Air Dose Factors, Ni, from Noble Gas (Beta) 49 2-8 Noble Gas Dose Factors for Instantaneous and Time Average Mixtures at the Site Boundary 50 2-9 Locations of Site Boundary and Nearest Residence 51 2-10a Adult Inhalation Ri(l) 52 2-10b Teen Inhalation Ri(l) 54 2-10c Child Inhalation Ri(l) 56 2-10d Infant Inhalation Ri(l) 58 2-11a Adult Ingestion (Leafy Vegetable) Ri(V) 60 2-11 b Teen Ingestion (Leafy Vegetable) Ri(V) 62 2-11c Child Ingestion (Leafy Vegetable) Ri(V) 64 2-12 Total Body and Skin Ground Plane Dose Factors Ri(G) and Ri(S) 66 Indian Point 2 Vll Revision 10

TABLE OF CONTENTS - OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES PART I - RADIOLOGICAL EFFLUENT CONTROLS 4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE D 4.1-2 GASEOUS AND LIQUID EFFLUENTS Indian Point 2 viii Revision 10

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts:

Radiological Effluent Controls, Part I, and Calculational Methodologies, Part II.

Part I, Radiological Effluent Controls, includes: (1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3 respectively.

Part II, Calculational Methodologies: provides the methodology to manually calculate radiation dose rates and doses to individual persons in UNRESTRICTED AREAS in the vicinity of Indian Point due to the routine release of gaseous and liquid effluents. Long term cumulative effects are usually calculated through computer programs employing approved methodology, often using real-time meteorology in the case of gaseous effluents. Other computer programs are utilized to routinely estimate the doses due to radioactivity in liquid effluents. Manual dose calculations are performed when computerized calculations are not available. The ODCM also provides setpoint methodology that is applied to effluent monitors and optionally to other process monitors. Reference numbers are bracketed [ ] to assist users.

The ODCM implements the Units 1 and 2 Radiological Effluent Control Specifications with respect to 10CFR20 Appendix B (pre-1994) permissible concentration criteria and also the design objectives of 10CFR50 Appendix I. The ODCM implements the methodology of Reg.

'Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I" and NUREG-0133 "Guidance Manual for Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." Other references may be cited to permit reasonable handling of a situation not covered by either of the two cited references. Simplifying assumptions have been made and justified to permit formulation of more workable methodologies for implementing RECS dose calculation requirements.

Indian Point 2 ix Revision 10

Definitions D 1.1 D 1.0 USE AND APPLICATION D 1.1 Definitions

NOTE------------------------------------------------

Terms defined in Technical Specifications and the following additional defined terms appear in capitalized type and are applicable throughout these specifications and bases.

Term Definition GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM is any system RADWASTE designed and installed to reduce radioactive gaseous effluents by TREATMENT collecting primary coolant system offgases from the primary system and SYSTEM providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF MEMBER(S) OF THE PUBLIC includes a/l persons who are not THE PUBLIC occupationally associated with the site. This category does not include employees of the utility, their contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

MAXIMUM MPCW is that concentration of a radionuclide equal to the most PERMISSIBLE conservative of the soluble or insoluble liquid concentration limits CON CENTRATION specified in (pre-1984) 10CFR20, Appendix B, Table II, Column 2.

WATER (MPCW)

OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL shall contain the CALCULATION current methodology and parameters used in the calculation of offsite MANUAL doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program.

PRIMARY TO A PRIMARY TO SECONDARY LEAK is defined by a quantifiable leak SECONDARY rate equal to or greater than 0.5 gpd, AND LEAK a} The presence of fission or activation products in the secondary fluid, verified as Steam Generator U-tube leaks (and not from other known contamination, such as IVSWS leaks), OR 101 b) Tritium activity in the secondary fluid indicating an increase above historical baseline (normal diffusion) of 5.00E-6 uCi/ml or greater.

PROCESS The PROCESS CONTROL PROGRAM is a manual containing and/or CONTROL referencing selected operational information concerning the PROGRAM solidification of radioactive wastes from liquid systems.

(

Indian Point 2 D1.1-1 Revision 10

Definitions 01.1 o 1.1 Definitions PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

SITE BOUNDARY The SITE BOUNDARY is that line beyond which the land is neither owned, leased, nor otherwise controlled by either Entergy Nuclear Indian Point 2 (ENIP2), Entergy Nuclear Operations, Inc. (ENO), or other site licensee.

SOLIDIFICATION SOLIDIFICATION is the conversion of wet wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased.

radioactivity.

UNRESTRICTED An UNRESTRICTED AREA is any area at or beyond the SITE AREA BOUNDARY, access to which is not controlled by either ENIP2, ENO, or other site licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. (See Figure 0 4.1-1)

VENTILATION A VENTILATION EXHAUST TREATMENT SYSTEM is any system EXHAUST designed and installed to reduce gaseous radioiodine or radioactive TREATMENT material in particulate form in effluents by passing ventilation or vent SYSTEM exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required.

Indian Point 2 . 01.1-2 Revision 10

Logical Connectors D 1.2

(" 1.0 USE AND APPLICATION

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1.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and are applicable throughout the Offsite Dose Calculation Manual and Bases.

1.3 Completion Times Completion Times are discussed in Section 1.3 of the Technical SpeCifications and are applicable throughout the Offsite Dose Calculation Manual and Bases.

1.4 Frequency Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the Offsite Dose Calculation Manual and Bases Indian Point 2 D 1.2-1 Revision 10

Indian Point 2 Offsite Dose Calculation Manual PART I - RADIOACTIVE EFFLUENT CONTROLS

APPLICABILITY 03.0 c 03.0 OOCM Limiting Condition for Operation (OLCO) Applicability OLCO 3.0.1 OLCOs shall be met during the MODES or other specified condition in the Applicability, except as provided in OLCO 3.0.2.

OLCO 3.0.2 Upon discovery of a failure to meet a OLCO, the Required Actions of the associated Conditions shall be met, except as provided in OLCO 3.0.5.

If the OLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

OLCO 3.0.3 When a OLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to:

a. Restore compliance with the OLCO or associated ACTIONS, and

b. Enter the circumstances into the Corrective Action Program.

NOTE--------------------------

OLCO 3.0.3.b shall be completed if OLCO 3.0.3 is entered.

Exceptions to this Specification are stated in the individual Specifications.

OLCO 3.0.4 Not Applicable to ODCM Specifications.

OLCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TRO 3.0.B for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

Indian Point 2 03.0-1 Revision 10

APPLICABILITY D 3.0 D 3.0 ODCM Surveillance Requirement (DSR) Applicability DSR 3.0.1 DSRs shall be met during the MODES or other specified conditions in the Applicability for individual DLCOs, unless otherwise stated in the DSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the DLGO. Failure to perform a Surveillance within the speCified Frequency shall be failure to meet the DLCO except as provided in DSR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specifi,ed limits.

DSR 3.0.2 The specified Frequency for each DSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this SpeCification are stated in the individual Specifications.

DSR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the DLGO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the DLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the DLGO must immediately be declared not met, and the applicable Condition(s) must be entered.

Indian Point 2 D 3.0-2 Revision 10

Liquid Effluents Concentration D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluents Concentration DLCO 3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure D 4.1-1) shall be limited to:

a. The MPCW concentrations as defined in D1.1 for radionuclides other than dissolved or entrained noble gases; and

b. 2 x 10-4 IJCi/ml total activity concentration for dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of. A.1 Initiate action to restore Immediately radioactive material concentration to within limits.

released in liquid effluents to UNRESTRICTED AREAS exceeds limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.1.1 Perform radioactive liquid waste sampling and activity In accordance with analysis. Table D 3.1.1-1 DSR 3.1.1.2 Verify the results of the DSR 3.1.1.1 analyses to In accordance with assure that the concentrations at the point of release Table D 3.1.1-1 are maintained within the limits of DLCO 3.1.1.

Indian Point 2 Page 3.1.1 - 1 Revision 10

Liquid Effluents Concentration 03.1.1 Table 03.1.1-1 (Page 1 of2)

Radioactive Liquid Waste Sampling and Analysis lOWER LIMIT LIQUID MINIMUM OF DETECTION RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS (lLD) in uCi/ml, TYPE TYPE FREQUENCY FREQUENCY (a),{g),(c)

1. Batch Waste Principal Release Tanks Gamma Emitters 5E-7 (b) Grab Sample Each Batch (h) Each Batch (h)

Mo-99, Ce-144 5E-6 eg, Waste Tanks, 1-131 1E-6 SG Dissolved and One batch per Draindowns, Grab Sample 31 days {h} 31 days Entrained Gases 1E-5 etc (gamma emitters)

H-3 1E-5 Composite (d) Each batch (h) 31 days Gross Alpha 1E-7 Sr-89, Sr-90 5E-8 Composite (d) Each batch (h) 92 days Fe-55 1E-6

2. Continuous Releases (e)

Composite (d) Composite Principal Gamma eg, SG 7 days Emitters (c) 5E-7 Blowdown, NCO, Mo-99, Ce-144 5E-6 SFDS, 1-131 1E-6 etc Dissolved and Grab Sample 31 days 31 days Entrained Gases 1E-5 (gamma emitters)

H-3 1E-5 31 days Gross Alpha 1E-7 Composite (d) Composite Sr-ag, Sr-90 5E-8 92 days Fe-55 1E-6

3. Service Water Grab Sample 31 days Gamma and Beta Per liquid batch 31 days (in Radiologically emitters (j) releases, above.

Controlled Areas)

4. Turbine Hall Drains, SG Composite Gamma and Beta Per liquid batch Composite Cd} 7 days Feedwater (i) emitters (j) releases, above.

Indian Point 2 Page 3.1.1 - 2 Revision 10

Liquid Effluents Concentration 03.1.1 Table D 3.1.1-1 (Page 2 of2)

Radioactive Liquid Waste Sampling and Analysis (a) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD shall be determined in accordance wit~

the methodology and parameters in the ODCM. It should be recognized that the LLD is defined as an a priori (before-the-fact) limit representing the capability of a measurement system and not as an a posterior (after-the-fact) limit for a particular measurement.

(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by the method described in Part II, Section 1.4 to assure representative sampling.

(c) The principal gamma emitters for which the LLD applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5 x 10-6!lCi/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identified, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to SpeCification D 5.2.

(d) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(e) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(f) When operational or other limitations preclude specific gamma radionuclide analysiS in batch releases, the proviSions of Regulatory Guide 1.21 (Revision 1), Appendix A Section C.4 and Appendix A, Section B shall be followed.

(g) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentration near the LLD. Under these c~cumstances, the LLD may be increased in inverse proportion to the magnitude of the gamma yield (Le., 5 x 10' /I where I is the photon abundance expressed as a decimal fraction).

(h) Complete prior to each release.

(i) Steam Generator Feedwater and Turbine Hall Drains are adequately monitored from Steam Generator Blowdown Composites. Increased monitoring need only be performed when a Primary to Secondary leak exists, as defined in REGS Section D.1.1.

(j) Beta emitters need only be analyzed if gamma emitters have been positively identified.

Indian Point 2 Page 3.1.1 - 3 Revision 10

Liquid Effluents Dose 03.1.2 o 3.1 RADIOACTIVE LIQUID EFFLUENTS o 3.1.2 Liquid Effluents Dose DLCO 3.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials released in liquid effluents from each unit to UNRESTRICTED AREAS (Figure 04.1-1) shall be limited to:

a. ~ 1.5 mrem to the whole body and ~ 5 mrem to any organ during any calendar quarter; and

b. ~ 3 mrem to the whole body and ~ 10 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose to a A. 1 Prepare and submit to the 30 days MEMBER OF THE NRC, pursuant to 0 5.3, a PUBLIC from the release Special Report that of radioactive materials in (1) Identifies the cause(s) liquid effluents to for exceeding the limit(s)

UNRESTRICTED AREAS and exceeds limits. (2) Defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.1.2.

Indian Point 2 03.1.2 - 1 Revision 10

Liquid Effluents Dose

.03.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units times the limits. (including outside storage tanks, etc.).

AND Immediately B.2 Verify that the limits of DLCO 3.4 have not been exceeded.

C. Required Action B.2 and C.1 Prepare and submit to the 30 days Associated Completion NRC, pursuant to D 5.3, a time not met. Special Report, as defined in 10 CFR 20.2203 (a)(4), of Required Action A.1 shall also include the following:

(1 ) The corrective action( s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources,

. including all effluent pathways and direct radiation, for the calendar year that includes the release(s),

and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

Indian Point 2 03.1.2 - 2 Revision 10

Liquid Effluents Dose D 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.2.1 Determine cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year .

Indian Point 2 . D 3.1.2 - 3 Revision 10

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS

( .....

D 3.1.3 Liquid Radwaste Treatment System DLCO 3.1.3 The Liquid Radwaste Treatment System shall be in operation when projected liquid effluent doses, from each unit, to UNRESTRICTED AREAS (Figure D 4.1-1) would be:

a. > 0.06 mrem to the total body in a 31 day period; or

b. >0.2 mrem to any organ in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION CO.MPLETION TIME A. Radioactive liquid waste A.1 Prepare and submit to the 30 days being discharged without NRC, pursuant to D 5.3, a treatment. Special Report that includes:

(1) An explanation of why liquid radwaste was being discharged without Projected doses due to the treatment, identification liquid effluent, from the of any inoperable unit, to UNRESTRICTED equipment or AREAS would exceed subsystems, and the limits. reason for the inoperabifity, (2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action( s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.3.1 Project the doses due to liquid effluents from each unit 31 days to UNRESTRICTED AREAS.

Indian Point 2 D 3.1.3 - 1 Revision 10

Liquid Holdup Tanks 03.1.4 o 3.1 LIQUID EFFLUENTS o 3.1.4 Liquid Holdup Tanks DLCO 3.1.4 Radioactive liquid contained in unprotected outdoor liquid storage tanks shall be limited to $; 10 Curies, excluding tritium and dissolved or entrained gases.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.

listed tank:

PWST A.2 Initiate measures to reduce 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months RWST content to within the limits.

Waste Distillate Storage Tanks

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Outdoor Temporary Tanks A.3 Describe the events leading to Prior to submittal of the condition in the next Radioactive Radioactive Effluent Release Effluent Release Report. Report SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.4.1 Determine that the quantity of radioactivity in 31 days, during periods outdoor liquid unprotected tanks (listed above) does not exceed the limit.

where radioactive liquid is being added to the

'/01 tanks. in accordance with the methodology and parameters of the ODeM Indian Point 2 03.1.4 - 1 Revision 10

Gaseous Effluents Dose Rate D 3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate DLCO 3.2.1 The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (Figure D 4.1-1) shall be limited to: .

a. For noble gases, s 500 mrem/yr to the whole body and s 3000 mrem/yr to the skin and

b. For 1-131, tritium (H-3) and all radionuclides in particulate form with half-lives> 8 days, s 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The dose rate( s) at or A.1 Restore the release rate to Immediately beyond the SITE within the limit.

BOUNDARY due to radioactive gaseous effluents exceeds limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.1.1 The dose rate from noble gases in gaseous In accordance with effluents shall be determined to be within the limits Table D 3.2.1-1 of DLCO 3.2. 1.a.

DSR 3.2.1.2 The dose rate from 1-131, H-3 and all In accordance with Table D 3.2.1-1 radionuclides in particulate form with half-lives

> 8 days in gaseous effluents shall be determined to be within the limits of DLCO 3.2.1.b.

Indian Point 2 03.2.1 -1 Revision 10

Gaseous Effluents Dose Rate D 3.2.1 r"" . Table D 3.2.1-1 (Page 1 of 2)

I

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Radioactive Gaseous Waste Sampling and Analysis SAMPLE LOWER GASEOUS SAMPLE SAMPLE ANALYSIS SAMPLE LIMIT OF RELEASE FREQUENCY TYPE FREQUENCY ANALYSIS DETECTION TYPE (LLD) Ca)

Principal Noble

1. Waste Gas Grab 1E-4 Each Tank (h) Each Tank (h) Gas (NG)

Storage Tank Sample f,!Ci/cc Gamma Emitters (b)

Principal NG Grab Purge Each Purge (h) Each Purge (h) Gamma 1E-4 Sample

2. Emitters (b) f,!Ci/cc Vapor Containment Principal NG Press Grab 1E-4 31 days (i) 31 days (i) Gamma Relief Sample Il Ci/ cc Emitters (b)

Principal NG 1E-4

3. Condenser Air Grab 31 days 31 days Gamma Ejector Sample ) IlCi/cc Emitters (b)

Principal NG Grab 1E-4

4. Continuous 31 days (c) 31 days (c) Gamma Sample Il CilcC Ventilation: \ Em itters (b)

H-3 1E-6

a. Main Plant Continuous 31 days (e) H-3 Specific IlCi/ cc Vent (unit 2)

b. Stack Vent Charcoal 1E-12 Continuous (f) 7 days (c), (g) 1-131 (unit 1) Sample f,!Ci/cc Principal Particulate Gamma 1 E-11 Continuous (f) 7 days (c), (g) Emitters (b)

Sample f..l Ci/ cc (1-131, Others)

Composite 1E-11 Particulate Continuous (f) 31 days Gross Alpha Sample f,!Ci/cc Composite Particulate 1E-11 Continuous (f) 92 days Sr-89/ Sr-90 Sample f,!Ci/cc Noble Gases Noble Gas 1E-6 Continuous (f) Continuous (f) Gross Beta Monitor f..lCi/cc(d) or Gamma Indian Point 2 D 3.2.1 - 2 Revision 10

NL-08-068, Official Exhibit - ENT00316A-00-BD01 - 2007 Annual Radioactive Effluent Release Report. Part 1 of 3

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NL-08-068, Official Exhibit - ENT00316A-00-BD01 - 2007 Annual Radioactive Effluent Release Report. Part 1 of 3

Text

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Dear Sir:

Enclosure:

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