Text

Official Exhibit - ENT000318-00-BD01 - 2009 Annual Radioactive Effluent Release Report
	ML12338A695
Person / Time
Site:	Indian Point
Issue date:	04/29/2010
From:	Robert Walpole; Entergy Nuclear Operations
To:	; Atomic Safety and Licensing Board Panel, Document Control Desk
	SECY RAS
References
	RAS 22136, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, NL-10-04S
	Download: ML12338A695 (296)
	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)

ENT000318

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ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Submitted: March 29, 2012

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0 Exhibit #: ENT000318-00-BD01 Identified: 10/15/2012

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Admitted: 10/15/2012 Withdrawn:

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0- Rejected:

Other:

Stricken:

Indian Point Energy Center 450 Broadway, GSB

<<tEntergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Licensing Manager NL-10-04S April 29, 2010 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

2009 Annual Radioactive Effluent Release Report Docket No. SO-03, SO-247, SO-286 License Nos. DPR-S, DPR-26, DPR-64

Dear Sir or Madam:

Enclosure 1 to this letter provides Entergy Nuclear Operations, Inc.'s (ENO's) Annual Effluent and Waste Disposal Report for 2009. This report is submitted in accordance with Technical Specification S.6.3 and Regulatory Guide 1.21.

There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact myoffice at (914) 734-6710.

Sincerely, RW/dmt

Enclosures:

1. 2009 Annual Radioactive Effluent Release Report

2. 2009 Offsite Dose Calculation Manual Changes and Justification Package .

NL-10-045 Page 2 of 2 cc: Mr. John P. Boska, NRC NRR Senior Project Manager Mr. Samuel J. Collins, Regional Administrator, NRC Region I IPEC NRC Senior Resident Inspectors Office Mr. Ted Smith, NRC Unit 1 Project Manager Mr. Francis J. Murray, President and CEO, NYSERDA (w/o attachment)

Mr. Paul Eddy, New York State Dept. of Public Service (w/o attachment)

Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Mgmt, NYSDEC Mr. Robert Snyder, NYS Department of Health Mr. Chuck Nieder, NYS Department of Environmental Conservation Mr. Robert Oliveira, American Nuclear Insurers Chief, Compliance Section, New York State DEC, Division of Water Regional Water Engineer, New York State DEC

ENCLOSURE 1 TO NL-10-045 2009 Annual Radioactive Effluent Release Report ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 1, 2, AND 3 DOCKET NOS. 50-03, 50-247, AND 50-286 LICENSE NO. DPR-5, DPR-26, AND DPR-64

Docket No. 50-3, 50-247, & 50-286 Page 1 of 49 Radioactive Effluent Release Report: 2009 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 5E-5 uCi/ml (without gas or tritium) for routine effluents, and procedural guidance for optimizing decay and treatment of liquid waste.

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

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 EIl = 3.05E-01 Mev/dis Ey= 6.28E-01 Mev/dis 2nd Quarter EIl = 3.20E-01 Mev/dis Ey= 7.25E-01 Mev/dis 3rd Quarter EIl = 1.74E-01 Mev/dis Ey= 1.34E-01 Mev/dis 4th Quarter EIl = 1.50E-01 Mev/dis Ey= 9.71E-02 Mev/dis Unit 3:

1st Quarter EIl = 2.04E-01 Mev/dis Ey= 1.43E-01 Mev/dis 2nd Quarter EIl = 3.33E-01 Mev/dis Ey= 7.34E-01 Mev/dis 3rd Quarter EIl = 4.36E-01 Mev/dis Ey= 1.18E+00 Mev/dis 4th Quarter EIl = 4.38E-01 Mev/dis Ey= 1.19E+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, which 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 of49 b/c) lodines and Particulates lodine-131 and particulate releases are quantified by collecting a continuous sample of ventilation air on a Triethylenediamine (TEDA) impregnated, activated charcoal cartridge and a glass-fiber filter paper. These samples are changed weekly as required in the RECS. The concentration of isotopes found by analysis of these samples is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged.

If no 1-131 is identified in weekly vent samples, "_" is entered in Table 1A. A typical Minimum Detectable Activity (MDA) for weekly 1-131 analyses is 1.0E-13 uCi/cc, which is 100 times lower than ODCM requirements.

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

A compositing method of analyzing for gross alpha is used per the station ODCMs. An absence of any positive Gross Alpha value for the quarter is identified on Table 1A as "_". A typical MDA for gross alpha is 8.0E-14 uCi/cc, which is over 100 times lower than ODCM requirements.

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

A compositing method of analyzing for gross alpha is used per the station ODCM. When there has been no positive Gross Alpha identified in a quarter,

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

Liquid Effluent volumes of waste released on Table 2A are differentiated between processed fluids (routine liquid waste and Unit 1's North Curtain Drain), and water discharged through monitored pathways identified in the ODCM, but NOT processed (SG Slowdown and Unit 1's Sphere Foundation Drain Sump).

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

However, to prevent confusion with regard to measures. undertaken to convert liquid to solid waste (resin cleanup), the volumes of processed and unprocessed waste are reported separately on Table 2A.

Docket No. 50-3, 50-247, & 50-286 Page 4 of 49

5. Batch Releases Airborne:

Unit 1 and 2 Airborne Releases Qtr::1;~<, I:;: Qtr 2 .~ .Qtr3 '.' Qtr 4':' 2009* .

Number of Batch Releases 43 49 62 64 218 Total Time Period (min 3280 3470 4340 4750 15800 Maximum Time Period min 125 236 173 175 236 Average Time Period min 76.3 70.9 70.0 74.2 72.7 Minimum Time Period min 4.00 27.0 10.0 2.00 . 2.00 Unit 3 Airborne Releases Otr*1***~ Qtr 2. Qtr 3.* 1<' 0tr 4 ", ' '2009 Number of Batch Releases 21 35 35 40 131 Total Time Period min 2520 3450 5100 6120 17200 Maximum Time Period min 419 174 233 216 419 Average Time Period min 120 98.5 146 153 131 Minimum Time Period min 3.00 4.00 9.00 4.00 3.00 Liquid:

Unit 1 and 2 Liquid Releases ' Qtr1 Qtr 2. . Qtr3. ,~ Qtr. 4G:.' : .':2009.::

Number of Batch Releases 5 4 11 11 31 Total Time Period min 535 408 1120 1090 3160 Maximum Time Period min 133 107 114 106 133 Average Time Period min 107 102 102 99.2 102 Minimum Time Period min 87.0 95.0 92.0 93.0 87.0 Unit 3 Liquid Releases *;*Qfr 1 Otr 2 Qtr 3 Qtr4/ 2009 Number of Batch Releases 38 33 23 *7 101 Total Time Period min 4780 3900 2500 782 12000 Maximum Time Period min 256 272 118 117 272

. Average Time Period min 126 118 109 112 118 Minimum Time Period min 106 77.0 92.0 103 77.0 Average Stream Flow:

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

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

Year Quarter Flow lets) 2007 Fourth. 53,970 2008 First 135,500 2008 Second 74,600 2008 Third 33,110

Docket No. 50-3, 50-247, & 50-286 Page 5 of 49

6. Abnormal Releases a) Liquid General Groundwater IPEC's groundwater monitoring program and the process (model) for quantification of effluent remained unchanged in 2009, from that of 2008. The resulting offsite dose as a result of the station's continuing natural attenuation was very small, similar to 2008's totals. Groundwater doses are included in the total dose table of Section E, the Dose-To-Man section of this report. Details of the IPEC Radiological Groundwater Monitoring Program are provided in Section H of* this report, and include the following: .

1) an update on the current condition of IPEC's GW natural attenuation,

2) a discussion of the removal of fuel (source term) from Unit 1, and

3) per the aDCM and NEI 07-07, a summary table of all groundwater radio-analyses results in 2009.

Unit 1 Foundation Drain (80-10)

A new 80-10 release path was added to the IPEC sampling regime in 2008, and continued through 2009. Contributors to this drain line are primarily roof and footing drains near Unit 1, but since it showed occasional trace levels of Cs-137, a project was initiated to determine the source and minimize flow. The trace contaminants were determined to originate in the South Curtain Drain around Unit 1, seeping into footing drains, and into this pathway (rather than diverting to the North Curtain Drain).

Activities underway (through the corrective action program) include efforts to minimize inputs to the line, and improve flow rate determination methods. During dry periods, the line has been evaluated to transport less than 2 gpm to the canal. An inspection cover has been installed in an area to observe flow, and efforts continue with regard to flow measurement methodologies in various atmospheric conditions.

Currently, only trace Cs-137 and H-3 have been identified in the system. Although this activity is included in monthly and annual effluent quantification, the integrated totals remain well below 80-10 or effluent threshold limits. .

Storm Drain Contamination Event. March 2009 A small increase in routine levels of tritium was discovered in a storm drain well upstream of the Unit 3 effluent point, in March 2009. Investigation led to the most likely source being an episodic local spill of a small amount of primary water directly into the drain. An in-depth investigation and conclusions were captured in the corrective action program, including comparison and interface with the NEI 07-07 groundwater protection program. No contamination was observed downstream of the effected drain, with no measurable effluent impact. Nonetheless, the calculated micro-curies and offsite dose due to this tritium potentially being released to the canal were included in the monthly effluent report. The totals remain mathematically insignificant with regard to site totals, and less than one ten-millionth of effluent limits.

b) Gaseous None.

Docket No. 50-3, 50-247, & 50-286 Page 6 of 49

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.

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

-Effected Details

.Interval '..'

09-18-09 Instrument failed regularly scheduled test. Parts were 15:51 determined necessary. After arrival on site, it was determined Unit 2 liquid that these parts were not precisely "like and kind". After to investigation and procurement of correct parts, the instrument waste effluent flow rate meter, was successfully tested and placed back in service.

12-16-09 CT-971 09:45 During this interval, flow rate measurement was estimated per aDCM and lower tier requirements using level instruments.

(88.7 days)

Instrument failed its routine calibration. Further testing was performed to compare this aDCM-required instrument with a redundant instrument that appeared to be working.

Investigation ensued as to why the values were outside desirable tolerances with each other.

10-08-09 16:30 Parts for the aDCM instrument were deemed necessary and ordered from vendor. Parts were not readily available. After Unit 2 Plant Vent to parts arrived, re-calibration was scheduled but re-prioritized to flow rate meter, approximately April, 2010.

SV2-DPT 01-01-10 00:00 Compensatory measurements were made per the ODCM and lower tier procedures (and the redundant, non-ODCM (84.3 days in 2009) instrument remains in service).

Additionally, a manual measurement of vent flow rate was performed to increase confidence. The manually* determined flow rate compared favorably with the corrected values from the non-ODCM instrument.

12-19-09 The level instrument failed due to a problem with freeze 21:53 protection caused by a failure of an associated strip heater. The heater strip was replaced, but the level instrument failed its to calibration retest. A new instrument was pursued but eventually U3 Primary Water determined not to be feasible. Instead, parts were procured, Storage Tank 01-01-10 installed, and the instrument was successfully calibrated and level instrument, 00:00 returned to service on Jan 21, 2010 at .12:41.

LT-1131 (12.1 days in While out of service, compensatory measures (level estimates) 2009, but 32.6 were performed per the aDCM and lower tier procedures days total) whenever water was moved into or out of the tank.

Docket No. 50-3, 50-247, & 50-286 Page 7 of 49

7. ODCM Reporting Requirements (continued)

Other Reporting Criteria:

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

ODCM and PCP changes:

There was no change to the Process Control Program for IPEC.

The IPEC ODCM was updated to Revision 2, in July 2009, to include:

a Monitoring Well at the Lafarge location, and to simultaneously reclassify two wells onsite as part of the Radiological Groundwater Monitoring Program (RGWMP) instead of the REMP.

Some improvements in definition, controls, and details of the RGWMP in RECS Section 5.6 and Appendix J.

Updates to the ODCM release point sketches (Appendices B & C), showing the effluent interface with programs like IE Bulletin 80-10, environmental, and groundwater.

See Section G of this report, and the Addendum covering the ODCM updates.

Lost ODCM airborne filter sample at vendor lab:

In August, 2009, a vendor lab accidently lost sample media from Unit 3's Plant Vent millifilter prior to testing for gross alpha and strontium. IPEC requests Gross Alpha and strontium activities from the vendor on a monthly basis, although, strontium is only required quarterly. The loss of sample was due to broken glassware at the vendor lab.

The filters are tested for gamma several times before they are shipped to the vendor, and no gamma contamination was identified. No alpha or strontium has been identified on these filters in several decades of testing.

Upon discovery of the breakage, an evaluation was performed at IPEC regarding any special operational or maintenance activities at Unit 3 (during the specified interval), to determine whether or not a potential, rare activity could have contributed to a positive gross alpha or strontium on these filters.

No unique activities were performed during this interval at Unit 3.

Therefore, "less than" values from the months before and after August 2009 were applied to the effluent report.

The vendor is NUPIC approved, with a good history of acceptable cross-checks and inter-comparisons. Because the lab quickly identified the error and does not have a history of these kinds of rare occurrences, no further action was initiated. However, this issue was captured in IPEC's corrective action program for tracking I trending.

Docket No. 50-3, 50-247, & 50-286 Page 8 of 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2009

Docket No. 50-3, 50-247, & 50-286 Page 90f49 TABLE lA INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

GASEOUS E.FFLUENTS - SUMMATION OF ALL RELEASES Year Est. Tolal A Rssioo &Adivation Gases Units Qtr1 Qtr2 Qtr3 Qr4 2000 % Error

1. Tolal Relea:;e O* 1.S0E-01 S.14E-a2 9.1SE-01 7.2SE-01 1.B4E-+OO ~25

2. Averag:l relea:;e rate LCi/soc 1.93E-a2 6. 54E-OO *1.15E-01 9.13E-a2 5.B4E-02 B. Icx:lines

1. Tdallcx:line-131 0 - - - - O.OOE-+OO ~25

2. Averag:l relea:;e rate LCi/soc - - - - O.OOE-+OO

c. Partirulates

1. Tdal Release, IMth 0 9.32E-OO - - - 9. 32E-06 ~25 half-life> 8 davs

2. Averag:l relea:;e rate LCi/soc 120E-OO - - - 2. 95E-07

3. GrcSs Alpha 0 - - - - - ~25 D. Triti l.IT1

1. Tdal relea:;e 0 215E+Q0 3.42E+00 3.69800 282E+00 1.21 E-+01 . ~25

2. Averag:l relea:;e rate LCi/soc 2.76E-01 4.3SE-01 4.64E-01 3.5SE-01 3.83E-01

- Irdicates < fvDA

Docket No. 50-3, 50-247, & 50-286 Page 10 of 49 TABLE lC INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr2 Qtr 3 Qtr4 2009 I

2) lodines 1-131 Ci O.OOE+OO 1-133 Ci O.OOE+OO 1-135 Ci O.OOE+OO I Total~fpiP~uocll:,':J:*i~*. 9j.' O.Q.QE+OO.i . O.OOE+OO O.OOE+OO O:OOE+OOO.OOE+OO

3) Particu lates ICs-137 Ci 9.32E-06 9.32E-06

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 11 of49 TABLE lC INDIAN POINT 1 and 2 - BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 2009 Ar-41 Ci 6.38E-02 2.79E-02 3.94E-02 2.94E-02 1.60E-01 Kr-85 Ci O.OOE-+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m Ci 9.04E-04 4.02E-05 3.59E-03 4.48E-05 4.58E-03 Kr-87 Ci 8.50E-04 O.OOE+OO 1.20E-03 2.79E-06 2.05E-03 Kr-88 Ci 1.77E-03 2.11E-05 4.31E-03 4.12E-05 6.14E-03 Xe-131m Ci 4.88E-04 2.50E-04 4.12E-03 6.46E-03 1.13E-02 Xe-133 Ci 6.30E-02 2.13E-02 7.42E-01 6.80E-01 1.51E+OO Xe-133m Ci 8.98E-04 3.02E-04 1.19E-02 5.70E-03 1.88E-02 Xe-135 Ci 1.60E-02 1.53E-03 1.05E-01 3.88E-03 1.27E-01 Xe-135m Ci 2.27E-03 O.OOE+OO 2.34E-03 7.11 E-06 4.63E-03 Xe-138 Ci 4.99E-04 O.OOE+OO 6.06E-04 1.57E-06 1.11E-03

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 49 TABLE lA INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES YfS Est. Tota A Rssim & Adivation GaSES Lhits Qr1 Qlr2 Qr3 Qr4 2009 % Error

1. Tolal Relea;;e a 528E-01 6.30E-a2 3.:BE-02 5.09E-a2 6.76E-01 :!:25

2. Averag3 relec:se rate t.CiI~ 6.79E-a2 a01E-CG 4.27E-03 6.40E-CG 2.14E-a2 B la::Iines

1. Tdal la::Iin& 131 a - - - - O.O<E+OO :!:25

2. Averag3 relec:se rate t.CiI~ - - - - 0.0(£+00 C PartiOJlates

1. Tdal Relec:se, wth half-life> 8 daIS a - - - - 0.0(£+00 +25

2. Averag3 relea;;e rate t.CiI~ - - - - 0.0(£+00

3. Qa;s .Alpha a - - - - 0.0(£+00 :!:25 D. Tritiun

1. Tdal relec:se a 3.5ff:+OO 6.57E+OO 4.96800 4. 1!E+OO 1.9:£+01 +25

2. Averag3 relec:se rate t.CiI~ 4.61E-01 a35E-01 6.24E-01 5.22E-01 6.11E-01

- Indicates < M:)6.

Docket No. 50-3, 50-247, & 50-286 Page 13 of 49 TABLE lC INDIAN POINT 3 - CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 2009 Ar-41 Ci O.OOE+OO 2.33E-02 O.OOE+OO O.OOE+OO 2.33E-02 Xe-133 Ci 2.98E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.98E-01 Xe-135 Ci 1.76E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.76E-01

2) lodines 1-131 Ci O.OOE+OO 1-133 Ci O.OOE+OO 1-135 Ci O.OOE+OO

3) Particu lates I" Tomitar PerioH/i:i::::.>

", \""'q' .... . ;*. <<)::i*:i,~ '*~*Ii('........* ;*.*.C

- - :'::'} . '.>

, .*.'.'..... ,.*".*i,1..:. *.,.,\,..*':,....

.'. .'.* t. \i<, .I':

- indicates < M DA

Docket No. 50-3, 50-247, & 50-286 Page 14 of 49 TABLE lC INDIAN POINT 3 BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

Nuclides Released Year

1) Fission Gases Units Qtr1 Qtr 2 Qtr 3 Qtr4 2009 Ar-41 Ci 1.28E-02 1.16E-02 3.11E-02 4.69E-02 1.02E-01 Kr-85 Ci 2.24E-03 S.82E-03 8.0SE-03 Kr-85m Ci 7.94E-06 7.94E-06 Kr-87 Ci O.OOE+OO Kr-88 Ci O.OOE+OO Xe-131 m Ci 3.13E-05 3.13E-05 Xe-133 Ci 3.90E-02 2.01 E-02 2.86E-03 3.96E-03 6.60E-02 Xe-133m Ci 5.79E-05 3.62E-04 420E-04 Xe-135 Ci 7.84E-04 1.70E-03 2.54E-05 2.50E-03 Xe-135m Ci O.OOE+OO If: *.~q~Ef9r;*e~f:i9B.

' .':~/;;:~<.*;~.:::x;, -,"

1

~*~9~~%

Ci ;;. 3.96E-02 3.40E-'02 5.09E1.62 1!r:79E~01;

(,b:;>:;;,i--:-:";

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 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT C. LIQUID EFFLUENTS 2009

Docket No. 50-3, 50-247, & 50-286 Page 16 of 49 TABLE 2A INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Tctal A. Rssion & Pctivation Products %Erra Units Qtr 1 Qtr2 Qtrl Qtr4 2000

1. Total Release (rot irdLd ing Tritium, Gr Alpha, & Gases) a 3.10E-03 1.17E-02 1.54E-02 7.11 E-03 3.73E-02 .:!:25 2 Average Di luted Crnc uCilml 6.ffiE-12 1.72E-11 1.79E-11 9.68E-12 1.36E-11 B. Tritium

1. Tolal Release Ci 1.14E+02 1.07E+02 2. 77E+02 3.87E+02 8. 86E+02 .:!:25 2 Average Di luted Crnc uCi/ml 2.42E-07 1.57E-07 3. 23E-07 5.28E-07 3.22E-07 C. Dissdved & Entrained Gases

1. Tolal Release Ci O.OOE+OO 0.0(£+00 3. 34E-05 1.59E-04 1.92E-04 .:!:25 2 AverageDiluted Cone uCilml O.OOE+OO 0.0(£+00 3:89E-14 2.16E-13 6.99E-14 D. Gross Alp,a

11. Tolal Release Ci +25 E. Vd ume of Waste Released

1. A"ocessoo Waste (LW &NCO) liters 1.05E+06 1. 83E+06 2. 19E+06 2.40E+06 7.46E+06 +10 2 Urprocessed (SGBD, SFOS, U1 FO) liters 4.49E+07 5. 13E+07 4.49E+07 4.31E+07 1. 84E+08 +10 F. Vdume of Dilution Water

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 17 of 49 TABLE 28 INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

CONTINUOUS RADIOACTIVE EFFLUENT Year Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr4 2009 Cs-137 Ci 1.02E-03 8.00E-03 4.58E-03 1.50E-03 1.51E-02 Ni-63 Ci O.OOE+OO Sr-89 Ci O.OOE+OO Sr-90 Ci 3.98E-04 5.23E-04 3.42E-04 3.02E-04 1.57E-03

- Indicates < MDA

Docket No. SO-3, SO-247, & SO-286 Page 18 of 49 TABLE 2B INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

BATCH RADIOACTIVE EFFLUENT Year Nuclides Released Units Qtr 1 Qtr 2 Qtr l Qtr 4 2009 Ag-110m Ci O.OOE+OO Co-S8 Ci 4.21 E-OS 1.23E-05 1.18E-OS 6.62E-OS Co-60 Ci 6.S3E-OS 3.80E-05 1.40E-04 6.83E-06 2.S0E-04 Cr-S1 Ci O.OOE+OO Cs-134 Ci 1.10E-OS 4.S2E-05 3.13E-04 l.69E-04 Cs-137 Ci 2.18E-04 4.70E-04 3.17E-03 4.94E-04 4.lSE-Ol Mn-S4 Ci O.OOE+OO Ni-63 Ci 2.69E-04 2.10E-03 S.SOE-03 1.S1 E-03 9.l7E-Ol Sb-124 Ci O.OOE+OO Sb-12S Ci 1.08E-03 S.14E-04 1.32E-03 3.30E-03 6.21E-03 Sr-90 Ci O.OOE+OO Te-123m Ci O.OOE+OO Te-12Sm Ci O.OOE+OO Dissolved & Entrained Gas Kr-8S Ci O.OOE+OO Xe-133 Ci 3.34E-OS 1.S9E-04 1.92E-04 I, ,.T::o""'t'a"'I'* f.o/'r}Pe'n':~,J;j(::::' ,. i:. ',;j:"

"-,-~'----,-.-,--- - ---~_~-/;,. ;~;:i{~: '>/,,:';

- Indicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 19 of 49 TABLE 2A INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Year Est. Total A. Fission & .Activation Products 2009 % Error Units Qtr 1 Qtr2 Qtr3 Qtr4

1. Total Release (rot inellKling Ci 3.87E-03 1.86E-02 2. 35E-03 5. 15E-04 2.53E-02 :!:25 Tritium, Gr Alpha, & Gases)

2. Average Diluted Cone uCi/ml 8.19E-12 2.73E-11 2.74E-12 7.01E-13 922E-12

8. Tritium

1. Tolal Release Ci 720E+02 1.08E+02 1.33E+02 125E+01 9. 73E+02 :!:25

2. Average Diluted Cone uCi/ml 1.52E-06 1.5SE-07 1.55E-07 1.71 E-OS 3.54E-07 C. Dissaved & Entrained Gases

1. Tolal Release Ci 7.43E-03 6.35E-04 4.62E-04 4.50E-06 S.53E-03 :!:25

2. AverageDilutoo Cone uCilml 1.57E-11 9.32E-13 5.37E-13 6.13E-15 3.10E-12 D. Gross Alpha

1. Tolal Release Ci I O.OOE+OO I + 25 E. Volume of Waste Releasoo

1. A-ocessed Fluids (fvbn Talks) liters 1.39E+06 S.48E+05 6.00E+05 1.S0E+05 3.02E+06 :!:10

2. Unprocessed Fluids (sGs) liters 1.77E+06 1.35E+07 2.77E+OO 1.64E+06 1.97E+07 +10 F. Vaume of Dilution Water

'- irdicates < MDA

Docket No. 50-3, 50-247, & 50-286 Page 20 of49 TABLE 2B INDIAN POINT 3 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan - Dec 2009)

BATCH and CONTINUOUS RADIOACTIVE LIQUID EFFLUENT Batch Fission/Activation Products Units Qtr 1 Qtr2 Qtr3 Qtr4 2009 Ag-11()n a 9.70E-05 5.22E-OS 3.83E-06 O.OOE+OO 1.53E-04 Co-58 a O.OOEiOO 6.88E-04 4.08E-04 5.63E-05 1.15E-03 Co-60 a 1.87E-03 1. 62E-03 3.00E-04 9.36E-05 3.97E-03 Cr-51 a O.OOEiOO 3.36E-04 1.80E-05 O.OOE+OO 3.54E-04 Cs-137 a 9.91E-06 5.00E-OS 9.98E-06 1.51E-05 8.50E-05 Fe-55 a 7.26E-04 O.OOE+OO O.OOE+OO O.OOE+OO 7.26E-04 Mn-54 a 1.93E-05 9.81E-06 O.OOE+OO O.OOE+OO 2.91E-05 Nb-95 a O.OOEiOO 1.81E-OS 2.37E-06 O.OOE+OO 2.OSE-05 Ni-63 a 9.93E-04 4.28E-04 7.31E-04 3.17E-04 2.47E-03 Rb-88 a 1.29E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E-04 Str124 a O.OOEiOO 1. 95E-04 1.68E-05 O.OOE+OO 2. 12E-04 Str125 a 2.93E-05 6.71E-04 2.65E-04 3.25E-05 9.98E-04 Te-123m a O.OOEiOO 3. 58E-04 3.20E-06 O.oOE+OO 3.61E-04 Te-125m a O.OOEiOO 1.42E-02 5.06E-04 O.oOE+OO 1.47E-02 t( .T~~!,fcr ~~~x(

';?: ' /:jicL*' * .** ;'j:8!:Eo03i :i:1:~(,E~02..*.

';~:"'>

'\:i;; 2.35$:0:3 ;'5:14E~4: <:2:54E:.o2

" ""'"'V" /,"

Dissolved ara &ltrained Gas (Batch)

Xe-133 a 7.42E-03 6.33E-04 4.62E-04 4.50E-06 8.52E-03 Xe-133m a 7.57E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.57E-06 Xe-135 a 1.00E-06 2. 19E-06 O.OOE+OO O.OOE+OO 4. 18E-06 Caltinuous Releases (SG BlolMJown)

H-3 (only) a 11.78E-031 O.OOE+OO 11.45E-03 I 3.91 E-031 7.14E-031

'- irdicates < mda

Docket No. 50-3, 50-247, & 50-286 Page 21 of49 Indian Point Energy Centei (Units 1; 2, and 3)

RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2009

Docket No. SO-3, SO-247, & SO-286 Page 22 of49 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2009 to 12/31/2009 Percent Cutoff: 0 (all identified isotopes are included)

Waste Strea m : Resins, Filters, and Evap Bottoms C artidg e F ilte rs LWS Resin Plant Resin 8~120 U 1 West Pool 8-120 Waste Volume Curies % Error (Ci) 3 Class fe m Sh ip ped A 1.79E+02 S.07E+00 2.8SE+00 +/- 25 %

B 1.80E+02 S.10E+00 1.69E+02 +/- 25 %

C 2.46E+01 6.97E-01 1.1SE+01 +/- 25 %

All 3.84E+02 1.09E+01 1.84E+02 +/- 25 %

Waste Strea m Dry Active Waste DAW / Metals Waste Volume Curies % Error (Ci)

Class ft3 m3 Sh ip ped A S.00E+01 1.42E+00 1.46E-OS +/-25%

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

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

All S.00E+01 1.42E+00 1.46E -OS +/-25%

Waste Strea m Irradiated Components Waste Volume Curies % Error (Ci)

Class ft 3 m3 Sh ip ped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

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

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

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

Waste Strea m: Other Waste Waste Volume Curies % Error (Ci) 3 Class fe m Sh ip ped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

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

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

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

Waste Strea m : Su m of All 4 Categories Combined Packages:

Cartridge Filters U1 West Pool 8-120 LW S Resin DAW / Metals Plant Resin 8-120 Waste Volume Curies % Erro r (Ci) 3 Class fe m Shipped A 2.29E+02 6.48E+00 2.8SE+00 +/-25,%

B 1.80E+02 S.10E+00 1.69E+02 +/-25%

C 2.46E+01 6.97E-01 1.1SE+01 +/-25%

All 4.34E+02 1.23E+01 1.84E +02 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

Docket No. 50-3, 50-247, & 50-286 Page 23 of 49 Units 1 and 2 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2009 to 12/31/2009 Percent Cutoff: 0 Number of Shipments Mode of Transportation Destination 1 Hittman Transport Energy Solutions - Bear Creek 1 R & R Trucking Inc Studsvik Processing -

Memphis 3 Hittman Transport Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance Curies H-3 0.066% 1.88E-03 Mn-54 0.474% 1.35E-02 Fe-55 15.690% 4.47E-01 Co-58 0.288% 8.20E-03 Co-60 5.686% 1.62E-01 Ni-63 21.727% 6.19E-01 Sr-90 0.082% 2.35E-03 Cs-134 9.302% 2.65E-01 Cs-137 46.684% 1.33E+00 Total 2.85E+OO Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance Curies H-3 0.019% 3.18E-02 Mn-54 0.014% 2.39E-02 Fe-55 0.417% 7.06E-01 Co-57 0.015% 2.47E-02 Co-60 4.334% 7.34E+00 Ni-63 52.488% 8.89E+01 Sr-89 0.001% 1.79E-03 Sr-90 8.325% 1.41E+01 Sb-125 0.348% 5.89E-01 Cs-134 2.539% 4.30E+00 Cs-137 31.292% 5.30E+01 Ce-144 0.168% 2.84E-01 Pu-238 0.002% 2.61E-03 Pu-239 0.001% 1.15E-03 Pu-241 0.037% 6.19E-02 Am-241 0.002% 2.72E-03 Cm-242 0.000% 4.71 E-05 Cm-243 0.001% 1.20E-03 Total 1.69E+02

Docket No. 50-3, 50-247, & 50-286 Page 24 of 49 Resins, Filters, and Evap Bottoms Waste Class C Nuclide Name Percent Abundance Curies H-3 0.041% 4.75E-03 Mn-54 0.020% 2.35E-03 Fe-55 0.815% 9~37E-02 Co-57 0.020% 2.27E-03 Co-60 7.746% 8.91 E-01 Ni-63 61.725% 7.10E+00 Sr-89 0.000% 5.64E-05 Sr-90 0.775% 8.91E-02 Sb-125 0.682% 7.85E-02 Cs-134 4.738% 5.45E-01 Cs-137 23.299% 2.68E+00 Ce-144 0.073% 8.36E-03 Pu-238 0.003% 3.00E-04 Pu-239 0.001% 6.59E-05 Pu-241 0.061% 7.00E-03 Am-241 0.000% 5.10E-05 Cm-242 0.000% 3.27E-06 Cm-243 0.001% 1.57E-04 Total 1.15E+01 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies H-3 0.021% 3.84E-02 Mn-54 0.022% 3.98E-02 Fe-55 0.680% 1.25E+00 Co-57 0.015% 2.69E-02 Co-58 0.004% 8.20E-03 Co-60 4.567% 8.39E+00 Ni-63 52.585% 9.66E+01 Sr-89 0.001% 1.85E-03 Sr-90 7.730% 1.42E+01 Sb-125 0.363% 6.67E-01 Cs-134 2.782% 5.11E+00 Cs-137 31.029% 5.70E+01 Ce-144 0.159% 2.92E-01 Pu-238 0.002% 2.91E-03 Pu-239 0.001% 1.22E-03 Pu-241 0.038% 6.89E-02 Am-241 0.002% 2.77E-03 Cm-242 0.000% 5.04E-05 Cm-243 0.001% 1.35E-03 Total 1.84E+02

Docket No. 50-3, 50-247, & 50-286 Page 25 of 49 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies Co-60 1.188% 1.73E-07 Ni-63 45.996% 6.70E-06 Sr-90 14.554% 2.12E-06 Cs-137 38.032% 5.54E-06 Ce-144 0.210% 3.06E-08 Pu-238 0.001% 1.05E-10 Pu-239 0.001% 1.14E-10 Pu-241 0.016% 2.40E-09 Am-241 0.003% 3.75E-10 Cm-243 0.000% 2.62E-11 Total 1.46E-05 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies Co-60 1.188% 1.73E-07 Ni-63 45.996% 6.70E-06 Sr-90 14.554% 2.12E-06 Cs-137 38.032% 5.54E-06 Ce-144 0.210% 3.06E-08 Pu-238 0.001% 1.05E-10 Pu-239 0.001% 1.14E-10 Pu-241 0.016% 2.40E-09 Am-241 0.003% 3.75E-10 Cm-243 0.000% 2.62E-11 Total 1.46E-OS Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 0.066% 1.88E-03 Mn-54 0.474% 1.35E-02 Fe-55 15.690% 4.47E-01 Co-58 0.288% 8.20E-03 Co-60 5.686% 1.62E-01 Ni-63 21.727% 6.19E-01 Sr-90 0.083% 2.36E-03 Cs-134 9.302% 2.65E-01 Cs-137 46.684% 1.33E+00 Ce-144 0.000% 3.06E-08 Pu-238 0.000% 1.05E-10 Pu-239 0.000% 1.14E-10 Pu-241 0.000% 2.40E-09 Am-241 0.000% 3.75E-10 Cm-243 0.000% 2.62E-11 Total 2.8SE+OO

Docket No. 50-3, 50-247, & 50-286 Page 26 of 49 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 0.019% 3.18E-02 Mn-54 0.014% 2.39E-02 Fe-55 0.417% 7.06E-01 Co-57 0.015% 2.47E-02 Co-60 4.334% 7.34E+00 Ni-63 52.488% 8.89E+01 Sr-89 0.001% 1.79E-03 Sr-90 8.325% 1.41E+01 Sb-125 0.348% 5.89E-01 Cs-134 2.539% 4.30E+00 Cs-137 31.292% 5.30E+01 Ce-144 0.168% 2.84E-01 Pu-238 0.002% 2.61E-03 Pu-239 0.001% 1.15E-03 Pu-241 0.037% 6.19E-02 Am-241 0.002% 2.72E-03 Cm-242 0.000% 4.71E-05 Cm-243 0.001% 1.20E-03 Total 1.69E+02 Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies H-3 0.041% 4.75E-03 Mn-54 0.020% 2.35E-03 Fe-55 0.815% 9.37E-02 Co-57 0.020% 2.27E-03 Co-60 7.746% 8.91 E-01 Ni-63 61.725% 7.10E+00 Sr-89 0.000% 5.64E-05 Sr-90 0.775% 8.91E-02 Sb-125 0.682% 7.85E-02 Cs-134 4.738% 5.45E-01 Cs-137 23.299% 2.68E+00 Ce-144 0.073% 8.36E-03 Pu-238 0.003% 3.00E-04 Pu-239 0.001% 6.59E-05 Pu-241 0.061% 7.00E-03 Am-241 0.000% 5.10E-05 Cm-242 0.000% 3.27E-06 Cm-243 0.001% 1.57E-04 Total 1.1SE+01

Docket No. 50-3, 50-247, & 50-286 Page 27 of49 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 0.021% 3.84E-02 Mn-54 0.022% 3.98E-02 Fe-55 0.680% 1.25E+00 Co-57 0.015% 2.69E-02 Co-58 0.004% 8.20E-03 Co-60 4.567% 8.39E+00 Ni-63 52.585% 9.66E+01 Sr-89 0.001% 1.85E-03 Sr-90 7.730% 1.42E+01 Sb-125 0.363% 6.67E-01 Cs-134 2.782% 5.11E+00 Cs-137 31.029% 5.70E+01 Ce-144 0.159% 2.92E-01 Pu-238 0.002% 2.91E,03 Pu-239 0.001% 1.22E-03 Pu-241 0.038% 6.89E-02 Am-241 0.002% 2.77E-03 Cm-242 0.000% 5.04E-05 Cm-243 0.001% 1.35E-03 Total 1.84E+02

Docket No. 50-3, 50-247, & 50-286 Page 28 of 49 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2009 to 12/31/2009 Percent Cutoff: 0 (all identified isotopes are included)

Waste Strea m: Resins, Filters, and Evap Bottom s L W S Resin 14-170 Waste Volume Curies % Error (Ci)

Class fe m3 Shipped A 1.35E+02 3.82E+00 1.62E+00 +/- 25 %

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

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

All 1.35E+02 3.82E+00 1.62E +00 +/- 25 %

Waste Strea m Dry Active Waste U3 DAW B-25 So i/O eb ris B-25 Unit 3 OAW-20' Sealand 20' Intermodal Soil DAW 20' Shielded SeaLand Waste Volume Curies % Error (Ci)

Class fe m3 sti ip ped A 1.26E+04 3.57E+02 8.49E-01 +/-25%

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

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

All 1.26E+04 3.57E+02 8.49E-01 +/-25%

Waste Strea.m Irradiated Components Waste Volume Curies % Error (Ci)

Class fe m3 Sh ip ped A 0.0 OE +00 O.OOE+OO 0.0 OE +00 +/-25%

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

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

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

Waste Strea m Other Waste Combined Packages Waste Volume Curies % Error (Ci)

Class fe m 3

Sh ip ped A O.OOE+OO O.OOE+OO O.OOE+OO +/-25%

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

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

All O.OOE+OO O.OOE+OO O.OOE +00 +/-25%

Waste Strea m : Su m of All 4 Categories Unit 3 DAW 8-25 Soil/Debris 8-25 LW S Resin 14-170 20' Intermodal Soil DAW 20' Shielded SeaLand Waste Volume Curies % Error (Ci)

Class ft3 m3 Shipped A 1.27E+04 3.60E+02 2.4 7E +00 +/-25%

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

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

All 1.27E+04 .3.60E+02 2.4 7E +00 +/-25%

Combined Waste Type Shipment, Major Volume Waste Type Shown

Docket No. 50-3, 50-247, &50-286 Page 29 of 49 Unit 3 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream 01/01/2009 to 12/31/2009 Percent Cutoff: 0 Number of Shipments Mode of Transportation Destination 8 Hittman Transport Energy Solutions Bear Creek 3 R & R Trucking Inc Studsvik Processing Facility Resins, Filters, and Evap Bottoms Waste Class A Percent Nuclide Name Abundance Curies H-3 15.346% 2.48E-01 Mn-54 0.167% 2.70E-03 Fe-55 18.254% 2.95E-01 Co-57 0.074% 1.19E-03 Co-58 0.043% 7.03E-04 Co-60 17.635% 2.85E-01 Ni-63 36.074% 5.83E-01 Sr-90 0.003% 5.30E-05 Sb-125 2.525% 4.08E-02 Cs-134 2.358% 3.81E-02 Cs-137 7.116% 1.15E-01 Ce-144 0.325% 5.26E-03 Pu-238 0.002% 3.78E-05 Pu-239 0.001% 9.73E-06 Pu-241 0.072% 1.17E-03 Am-241 0.002% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.003% S.43E-OS Total 1.62E+OO Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Curies Abundance H-3 15.346% 2.48E-01 Mn-54 0.167% 2.70E-03 Fe-55 18.254% 2.9SE-01 Co-57 0.074% 1.19E-03 Co-58 0.043% 7.03E-04 Co-60 17.635% 2.85E-01 Ni-63 36.074% 5.83E-01 Sr-90 0.003% S.30E-05 Sb-125 2.525% 4.08E-02 Cs-134 2.358% 3.81E-02 Cs-137 7.116% 1.1SE-01 Ce-144 0.325% S.26E-03 Pu-238 0.002% 3.78E-05

Docket No. 50-3, 50-247, & 50-286 Page 30 of 49 Pu-239 0.001% 9.73E-06 Pu-241 0.072% 1.17E-03 Am-241 0.002% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.003% 5.43E-05 Total 1.62E+OO Dry Active Waste Waste Class A Nuclide Name Percent Curies Abundance H-3 0.483% 4.10E-03 C-14 0.031% 2.59E-04 Mn-54 0.397% 3.37E-03 Fe-55 27.691% 2.35E-01 Co-57 0.141% 1.20E-03 Co-58 30.754% 2.61 E-01 Co-60 18.028% 1.53E-01 Ni-63 20.856% 1.77E-01 Sr-90 0.015% 1.28E-04 Nb-95 0.016% 1.35E-04 Sb-124 0.033% 2.83E-04 Sb-125 0.109% 9.21E-04 Cs-134 0.197% 1.67E-03 Cs-137 1.249% 1.06E-02 Total 8.49E-01 Dry Active Waste Waste Class All Nuclide Name Percent Curies Abundance H-3 0.483% 4.10E-03 C-14 0.031% 2.59E-04 Mn-54 0.397% 3.37E-03 Fe-55 27.691% 2.35E-01 Co-57 0.141% 1.20E-03 Co-58 30.754% 2.61 E-01 Co-60 18.028% 1.53E-01 Ni-63 20.856% 1.77E-01 Sr-90 0.015% 1.28E-04 Nb-95 0.016% 1.35E-04 Sb-124 0.033% 2.83E-04 Sb-125 0.109% 9.21 E-04 Cs-134 0.197% 1.67E-03 Cs-137 1.249% 1.06E-02 Total 8.49E-01

Docket No. 50-3, 50-247, & 50-286 Page 31 of 49 Sum of All 4 Categories Waste Class A Nuclide Name Percent Curies Abundance H-3 10.226% 2.52E-01 C-14 0.011% 2.59E-04 Mn-54 0.246% 6.07E-03 Fe-55 21.506% 5.30E-01 Co-57 0.097% 2.39E-03 Co-58 10.631% 2.62E-01 Co-60 17.773% 4.38E-01 Ni-63 30.839% 7.60E-01 Sr-90 0.007% 1.81E-04 Nb-95 0.005% 1.35E-04 Sb-124 0.011% 2.83E-04 Sb-125 1.692% 4.17E-02 Cs-134 1.615% 3.98E-02 Cs-137 5.072% 1.25E-01 Ce-144 0.213% 5.26E-03 Pu-238 0.002% 3.78E-05 Pu-239 0.000% 9.73E-06 Pu-241 0.047% 1.17E-03 Am-241 0.001% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.002% 5.43E-05 Total 2.46E+OO

Docket No. 50-3, 50-247, & 50-286 Page 32 of49 Sum of All 4 Categories Waste Class All Nuclide Name Percent Curies Abundance H-3 10.226% 2.52E-01 C-14 0.011% 2.59E-04 Mn-54 0.246% 6.07E-03 Fe-55 21.506% 5.30E-01 Co-57 0.097% 2.39E-03 Co-58 10.631% 2.62E-01 Co-GO 17.773% 4.38E-01 Ni-63 30.839% 7.60E-01 Sr-90 0.007% 1.81 E-04 Nb-95 0.005% 1.35E-04 Sb-124 0.011% 2.83E-04 Sb-125 1.692% 4.17E-02 Cs-134 1.615% 3.98E-02 Cs-137 5.072% 1.25E-01 Ce-144 0.213% 5.26E-03 Pu-238 0.002% 3.78E-05 Pu-239 0.000% 9.73E-06 Pu-241 0.047% 1.17E-03 Am-241 0.001% 2.57E-05 Cm-242 0.000% 1.29E-06 Cm-243 0.002% 5.43E-05 Total 2.46E+OO

Docket No. 50-3, 50-247, & 50-286 Page 33 of 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT E. RADIOLOGICAL IMPACT ON MAN Jan 1, 2009 - Dec 31, 2009

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

! Page 34 of 49 RADIOLOGICAL IMPACT ON MAN Routine Effluent Dose Calculations:

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

An approved computer code is used to perform liquid and gaseous dose calculations according to the models and parameters presented in the Indian Point Offsite Dose Calculation Manual (ODCM). This information is stored in a database on site to enhance dose tracking information and management. Site airborne effluent dose calculations include annual average dispersion and deposition factors, averaged from data collected over approximate ten year periods. When new data is averaged (approximately every ten years) the modeling is updated and used in subsequent airborne effluent calculations.

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

Carbon-14 (C*14):

Concentrations and offsite dose from C-14 have been determined from data generated at IP3 from August 1980 to June 1982, during a study conducted by the NY State Department of Health (C. Kunz, later published and incorporated into NCRP 81). 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 rated electrical capacity, approximately 1000 MW(e) maintained for the entire year, and the given curies determined from the experiment, corrected for the fraction of C-14 determined to be in the Carbon Dioxide form, as doses are not expected from other forms (methane, etc). The resultant offsite doses are based upon this source term and the dose calculations described in Reg Guide 1.109 and the ODCM.

The annual dose to the maximally exposed individual (child) from gaseous releases of C-14 at IPEC (units 2 and 3) is 0.508 mrem to the critical organ (bone) and 0.102 mrem to the total body.

The annual dose to the maximally exposed individual (child) from typical liquid releases of C-14 is 0.0117 mrem to the critical organ (bone) and 0.00234 mrem to the total body. Due to the unique nature of C-14, and the extremely conservative bounding measurements performed, the combined offsite dose attributable to C-14 alone (liquid and airborne) is reported on the Dose to Man section cover page (and not in the tables that follow), specifically to avoid confusion.

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 49 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 ina 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 occupahcy 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 2009:

Routine Airborne Effluents 1 Units 1 and 2 2.28E-3 2.28E-3 Routine Liquid Effluents Units 1 and 2 9.00E-4 1.71E-3 Routine Airborne Effluents 1 Unit 3 3.36E-3 3.36E-3 Routine Liquid Effluents Unit 3 2.49E-4 4.S9E-4 Indian Point Energy Center IPEC 5.11 5.53 Total Dose, per 40 CFR 190 Note 1: Airborne dose in this table is conservatively represented as a sum of Iodine/Particulate Dose (mrem) and noble gas beta air energy (mrad, expressed as mrem) at the highest site boundary location, for purposes of demonstrating 40CFR190 compliance only.

Note 2: Groundwater curie and dose calculations are provided in Section H.

Note 3: The direct shine component from sources other than ISFSI are indistinguishable from background. ISFSI doses were determined from net integrated quarterly TLD readings at the identified critical site boundary locations, and comparing these values with ISFSI boundary and REMP TLDs. No occupancy factors were applied for this conservative assessment. Details of this evaluation are available on site.

Docket No. 50-3, 50-247, & 50-286 Page 36 of 49 INDIAN POINT UNITS land 2 NUCLEAR POWER PLANTS RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2009 Maximum exposed individual doses in mrem or mrad A. LlOU 10 DOSES Otr 1;, 1>:Ot,,2;>,: :hi;; ;,Qtr 3 :';: '.'. ":Ott4 ANNUAL Organ Dose (mrem) 3.02E-04 6.40E-04 5.70E-04 2.34E-04 1.71 E-03

!Applicable Limit (mrem) 5 5 5 5 10 Percent of Umit (%) 6.04E-03 1.28E-02 1.14E-02 4.68E-03 1.71 E-02 IAqeGroup Adult Child Child Child Child Critical Organ Bone Bone Bone Bone Bone Adult Total Body (mrem) 1.41 E-04 3.33E-04 2.74E-04 1.52E-04 9.00E-04 Applicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of Umit (%) 9.40E-03 2.22E-02 1.83E-02 1.01E-02 3.00E-02 B. AIRBORNE NOBLE GAS DOSES

"'Ot(1\<: '>>Otr.2'.' . '. Otr3,/.': :*'Otl'4 ANNUAL Gamma Air (mrad) 2.95E-05 1.14E-05 4.62E-05 2.69E-05 1.14E-04

~pplicable Limit (mrad) 5 5 5 5 10 Percent of Umit (%) 5.90E-04 2.28E-04 9.24E-04 5.38E-04 1.14E-03 Beta Air (mrad) 2.36E-05 8.35E-06 8.63E-05 5.88E-05 1.77E-04

~pplicable Limit (mrad) 10 10 10 10 20 Percent of U mit (%) 2.36E-04 8.35E-05 8.63E-04 5.88E-04 8.85E-04 C. AIRBORNE IODINE and PARTICULATE DOSES

- - - - Otr1.**.*.* ** *.** ****>Qti':2 . . g.. Qtr3;;' *1;'.Qtr4V~ ANNUAL Iodine/Part (mrem) 4.34E-04 5.73E-04 6.18E-04 4.72E-04 2.10E-03

!Applicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of U mit (%) 5.79E-03 7.64E-03 824E-03 6.29E-03 1.40E-02 ge Group Child Critical Organ Uver

Docket No. 50-3, 50-247, & 50-286 Page 37 of49 INDIAN POINT 3 NUCLEAR POWER PLANT RADIOLOGICAL IMPACT ON MAN JANUARY - DECEMBER 2009 Maximum exposed individual doses in mrem or mrad A. LlQU 10 DOSES

.::Qtr.*1 * **.**.i. ;.:.~ Qtr:2 i \;.: h,; Q~r3*** ',',

,.,Qtr.4{*., ANNUAL*

Organ Dose (mrem) 2.57E-04 1.67E-04 3.12E-05 1.37E-05 4.59E-04

~pplicable Limit (mrem) 5 5 5 5 10 Percent of U mit (%) 5.14E-03 3.34E-03 6.24E-04 2.74E-04 4.59E-03

~ge Group Adult Adult Adult Child Adult Critical Organ GI-LLI GI-LLI GI-LLI Bone GI-LLI

~dultTotal Body (mrem) 1.96E-04 2.89E-05 2.12E-05 3.10E-06 2.49E-04 IApplicable Limit (mrem) 1.5 1.5 1.5 1.5 3.0 Percent of U mit (%) 1.31 E-02 1.93E-03 1.41 E-03 2.07E-04 8.31 E-03 B. AIRBORNE NOBLE GAS DOSES Qtr1 . Qtr2 Qtr3 \.;::*qtr4;;: .. .ANNUAL" Gamma Air (mrad) 3.52E-05 1.07E-05 8.85E-06 1.34E-05 6.82E-05 Applicable Limit (mrad) 5 5 5 5 10 Percent of U mit (%) 7.04E-04 2.14E-04 1.77E-04 2.68E-04 6.82E-04 Beta Air (mrad) 1.18E-04 2.15E-05 1.49E-05 2.24E-05 1.77E-04 Applicable Limit (mrad) 10 10 10 10 20 Percent of U mit (%) 1.18E-03 2.15E-04 1.49E-04 2.24E-04 8.84E-04 C. AIRBORNE IODINE and PARTICULATE DOSES

>Qtr1 .. /qtr2 *.* * ***Cltr3 .'. qtrA s * : ANNUAL Iodine/Part (mrem) 5.92E-04 1.08E-03 8.20E-04 6.86E-04 3.18E-03 IApplicable Limit (mrem) 7.5 7.5 7.5 7.5 15 Percent of U mit (%) 7.89E-03 1.44E-02 1.09E-02 9.15E-03 2.12E-02 ge Group Child Critical Organ Uver

Docket No. 50-3, 50-247, & 50-286 Page 38 of 49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2009 - Dec 31, 2009 This data is stored onsite and is available in printed or electronic form.

Docket No. 50-3, 50-247, & 50-286 Page 39 of49 Indian Point Energy Center (Units 1, 2, and 3)

RADIOACTIVE EFFLUENT REPORT G. OFFSITE DOSE CALCULATION MANUAL, REMP SAMPLING LOCATIONS, PROCESS CONTROL PROGRAM, OR LAND USE CENSUS LOCATION CHANGES 2009 There was an additional GW well added to the REMP sampling locations, and two wells were reclassified as part of the Radiological Groundwater Monitoring Program in year 2009.

Details of the changes in the REMP are included in the ODCM and justification package, provided as an Addendum to this report.

There were no changes to the Land Use Census in year 2009.

There were no changes to the Process Control Program (PCP) in 2009.

There was one ODCM update in 2009.

In July, 2009 the station ODCM was upgraded to revision 2.

A complete copy of the revised IPEC ODCM, as well as the Rev 2 justification package, are provided in an Addendum to this report.

Docket No. 50-3, 50-247, & 50-286 Page 40 of 49 Indian Point Energy Center (Units 1, 2, and 3)

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

Jan 1, 2009 - Dec 31, 2009

Docket No. 50-3, 50-247, & 50-286 Page 41 of49 Summary of IPEG Groundwater and Storm Water Activity, 2009 The Unit 1 Spent Fuel, which had been considered the source of most of the groundwater contamination, was removed in 2008, to integrated spent fuel storage. This process demanded pool levels to be increased in April, 2008, for the defueling operation. During this evolution, the pool water was continuously demineralized and carefully monitored. After defueling, the pools were further processed with additional cleanup. For dewatering, two sets of composite samplers were installed, and the slow, permitted release was carefully integrated. Resin-specific cleanup systems were added during the pump down to the routine liquid effluent release line. The empty pools were then cleaned, closed, and covered.

As a result of aggressive processing before, during, and after the defueling operation, the effluent release from draining the pools (Sep, 2008) resulted in curies and mrem consistent with or slightly lower than routine monthly effluent. Stontium-90 releases, in particular, were essentially non-existent, because the pool water had been cleaned up for ni-onths prior draining.

Because the pool levels had to be increased for a time in 2008 (as mentioned. above), some increases in groundwater contamination were expected through 2009. Wells near the Unit 1 pools did in fact start to show somewhat elevated activitY in 2009, but by the end of the year, a clear downward trend was visible. Monitored Natural Attenuation is expected to continue.

The precipitation mass balance model applied in 2007 and 2008 was applied for offsite dose calculations in 2009. Hydraulic conductivity readings continued to validate the model throughout the year, and the USGS, as well as IPEC local MET data verified annual precipitation averaging 2.68 feet per year. No changes to the model were required.

Results of 2009 Groundwater and Storm water offsite dose evaluation The results of the assessment are shown on the following table. These dose values are again a small portion of the annual limits <<0.1 %), and were added to the Total Dose table in the opening summary of the Dose to Man section of this report (Section E).

Based on the above analysis, the total .GW and storm water Tritium released from IPEC was approximately 0.07 Curies in 2009, resulting in a total body dose of significantly less than 0.1 mrem (1.4E-7 mrem). It is evident that tritium alone, whether from ground water or routine effluents, does not arithmetically contribute to integrated offsite dose.

Strontium-90, Cesium-137, and Co-60 collectively contributed approximately 0.00025 curies to site effluent from the groundwater pathway. Combined groundwater releases from IPEC in 2009 (all radionuclides) resulted in a calculated annual dose of significantly less than 0.1 % of the annual limits for whole body and critical organ, as follows:

IPEC Groundwater and Storm Water Effluent Dose, 2009 0.000256 mrem to the total body, (0.0085% limit) 0.00103 mrem to the critical organ, adult bone (0.0103% limit)

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

Docket No. 50-3, 50-247, & 50-286 Page 42 of 49 2009 Northern Clean'Zone AdultDoses,inmrem t:~;,I§~:tQJkI;l!Ktl !,_B¢~EI'j;'j1g :{littYEBa: ;.TgJ#~Cjpy* *TI'IYRClID"r' 1',' KlDNEY:~. iIiIGlllfjj<3.4ii _QI+I1~lk::lI b;l~iZeilj;;' .

Hc3 1;;f,O,OOE+OO;, ;;'.4:64E~09;', 'SL'A:64E::09,',:F:'4:64E-09,4,64E-09h't, ;,,,:4!64E:'()9,;, ;:;,A~64E,:09' 4,45£t02; :

0'0'0£+00 :

'O.ooEfO'O .

,Sr-90 '.':O:OOE+OO):>O;OOE+OO: ' O:OOE+OO,',O,OOE-I{)O",: i'i:':O:OOE+OO O;OOE+OO;,: ;,::O.OOE+OO;~, '0:00£+00 ;

'0.00£+0'0. :

",,;.' totals:: O.OOE+OO . 4.64Ec 09 4.64E~09"'*' 4.64E;,()9 4.64E-09* 4.64E,.Q9 , 4,64E-09 {4,{15E:+02; .

Unit2 North

.I!>QJ;(3PvE,~~ 11IiiIBO~EE;;: .lHVERfiHit ;i;£;T,eT#BGDy:;;~i ~;I8YROIO:;: :~~IDI)JEY~ if"t;"lI1LJNG,.n EGlflilHPi.:; EU,czii;fy,: .

H"3 ;;'";*O.OOE+OO",'::"U2E:08"* b12E"08';X:; :;71'::12E-08n>'T12E~08' . :;t12F08"~,;* T'c1:12E"08',,' 4:63E+04' .

co:.60f:\O:OOE+OO'O.OOE-I{)O'O:OOE+OO r< ;\/O:OOE-I{)O' O.OOE+OO O.OOE+OO' -: ,,;,'O.OOE+OO '0;00£+00, .

Ni-63 :;"'O.OOEfOO<:' f:O.OOE-I{)OO:OOE+OO" 'O,OOE-I{)O;CO' 'X:"O,OOE+Oo;, OOOE+OO;' ":O'OOE+OO::' 'O.ooE+oo, :

Sr:gOO.OOE+OO,;' O:OOE+OO' I;,:: O:OOE+OO;/' (:V'O.OOE-I{)O, , O.OOE+OO "O:OOE,tOO:::: ;*O,OOE+OO:t 0.00£+00 4*26£+00 ;

!4!63E+04:

Unit 112

';i:, uCi':y%&

H-3 9.57E:l-03 co:.60 ,O.OOE+OO ::O.OOE+OO :'::::'O:OOE+OO ", O:OOE-I{)O O.OOE+OO::;: :,':;:'O.OOE+OO ' :YO.OOE+OO: . '0.00£+'00 Ni-63 .. 1.99Ei 05,i::: 9:61E-06 O.OOE-I{)O, O,OOE+OO~ ; f:O:OOE+OO' r,:4j~4E-06 :1:45£+'02 Sr-90 ii;,O.OOE+OO 1:;:::t::1.13E-04>~ OOOE-I{)O, 2:91E:l-'OJ

<: 8:54E:05 4.44E+O,1 ;

,totals' . 8,34E-04 . 3: 97F05 I:' .1.32E-05*;::, 1.98E-05 ' 19:74E+Ol Ufiif3 North Pi.;uczi Ai .

4:94E..,03

r'02E+'Ot,'

Ni-63 x,' :O.OOE+OO:';,O.OOE+OO';,;:;':;O:OOE+OO O.OOE-I{)O O.OOE+OO,,; . ';'.O:OOE-I{)OYi:;'\O;OOEfOO' 0:00£+0'0 ..

Sr-90 ":?:8::15E;05;O.OOE-I{)O; :,t'Z:OOE-05' ;," O.OOE-I{)O O.OOE+OO**'::;,O.OOE+OO~:':;; ; :Z;35E-06:: 4~94E+'OO i Cs-137. .t;:, O:OOE-+:OO :.::;i',;O:OOE+OO' V'O;OOE+OO O,OOE-I{)O., *O.OOE+OOY,,:A;::O:OOE,i-OO'!'. ;O.OOE-+:OO* 'O:ooE+oo 1:",'" ,;totals'; 8!15E705," 6.10E:07:. I', ZJ3E-05' '1. 13E-08 1:13E-081.13E'-08 1:36E-05 . 11196E+O:J! :

Unit3 South

.'$QJ9Re:2i .BONE. iWiiI1lVER?;\::J i"TTOIB.ODY,S! ~:rI:jY,ROIQ. HKlONEY;iAS! ;ifSi;{;UN<3l;i:;;;):; 'ri1f~Glclitilm' a:uCi!B:

H-3:*.LO, OOE+OO:) .';:, ,L22E~08:':' *1.22E-08.,. ;,:,'1;22E-08: ;:;. ,':0';122Ec08<' '; I" ,l22E"08'" . '(,,1 :ZZEc08 ::, :1:.04E+03 .

O.ooE+ooJ*

Ni-63 C:0:00E+00;;e:00E+00\i";,;:;;0:00EfOO!;" ';'O.OOE+QO; O:OOE+OO>;;, ,;;,;'O.OOE+OO:;" /:.:O.OOE+OO:;;; 'O.'ooE+oo: :

4'14E+'O.1 Cs.:.137 .O'OOE+OO/* :.:O:OOE-I{)O* 'O:OOE+oor ""'OOOE-I{)O:, ::1,,:; O:OOE+OO;'* O;OOE-I{)O':' ;O:OOE+/-OO':* 'O:ooE+'O'O .

totals1.09Ec04**: 1'.2ZE~08 .. 'Z,67E-05"1.22E-08. 1.2ZE-08 :1,22E-08 ' 3::15Ec06 !7iO,6E£O.ll

Southern Clean Zone,'

iiiJSQ;1;QRI:':S:; 1x.SONI:. i'l.\~~I~e:~;:tf;;) %&,\TOIElODY'" ;'THYROID:';: v;~KIDNEYia: ooU!JNG_ (;x'i\Gljli~Jt. f':4*::1/QiiBr:

H~3 . O:OOE+OO,,:' ;,:2;98E:08< ;'> 2.98E:08,;,'2.98E-08 ,,z.98Ec08 ,'. ',":2,98E:08;::' " 2.98Ec08';; 2:66£+'03, .

0:00£+00 Ni-63 O.OOE+OO' ,O,OOE+OO>; O,OOE+OO;'::i,; ;::):O'OOE+OO;;" ':O:OOE+OO" O.OOE+OO , ::O.o.OE;f001 '0:00£+'0'0 Sr-90: O:OOE'l:OO" jo,'.O:OOE-I{)O OOOE+OO. OOOE-I{)O'li;'*'O.OOE+OO: O:OOE+OO ", '::O.OOE+OO: 0:00£0+00 Cs"137 i: o.:o.OE+o.o. '*,:<O.o.OE+o.o.::;Oo.o.E+oo O,o.o.E+OO o.:o.o.E-I:OO ; o..ooE+o.O): .o..o.o.E+o.o. '0,00£:+00.

totals O.OOE+OO; 2.98E:08 2.98E-08" 2. 98E:'()8 2.98E-08: "2;98E-08, Z:98E'-08 . !2166E:+031 ;

Totals: AdUlt DoSes, in mrem H-30n1 X .',; O.OOE+,OO .' 1:37E-07 1.37E-OT 1.37E.:o7 .'. U7E-07,'** U7E-07 ,U7E:07 ;rotaf'uC;s ;

6.79E+04 H3

'all isotopes 11:03E-03,' 1.50E~04,;:;'2.56E-04 ;*1.37E-07 4.39E-05 1.47E-05: *3,68Ec05 1:02£+01 Co 1:45E';'02, NI

~:54E:+'01 Sr.

4:87£+'01 Cs

Docket No. 50-3, 50-247, & 50-286 Page 43 of 49 INDIAN POINT RADIOLOGICAL GROUNDWATER MONITORING PROGRAM 2009 Summary of Results The following pages represent a summary of isotopic radio-analytical data for all onsite groundwater testing performed at Indian Point in 2009, as required per the aDeM and NEI 07-07.

Docket No. 50-3, 50-247, & 50-286 Page 44 of 49 Tritium Summary page 1 of 3

P()sitive

Samples H~ Samples AvgPos MinPos M'axPos 1"2009 in 2009. Act Act Ad B-1 1 .1 8.B1E+02 ,B,81 E+02 8.B1 E+.02 LAF-Ob2~ 2 1, 1,BOE,+()2 1.BOE+02 1.BOE+02 IvfH-S .. , :3 3 1.1tE'+03 6:286+02: '1'.SOE+03 MW-I07 1 1 1.96E+02 1.~6,E+02: r.~9E+02

.MW.,.1r1 2 2 :3.08E+04 2;26E+04 ~3.89E:+04' IVIW<30-69; 6 6 1,Q7E+05 8 ..:20£;+04 1.p4E+05 MW...:30-B4 6 6 6.11E+03 4.69E+03 7.76E+03 IVIW.;3i,;49 7 -; 2.14E+04 7:366+02 4. 84 E:t-b,4

.I\IIW-3t""63' 7 7 1:99E+04 1,28E+04, :3.24E+04 MW:,31".B5 7 7 7.3tE+03 2.96E+03 1.BBE+04 MW;;~2.;14Jf 7 7 3:Q7E+02 1*9~E+Q2: 4.::>7E+02 MW~32-173, 7 7 7.4BE+02 4:31 Ef02 1.72E+03

.MW-3:2'-19Q; 1. i 2.11E+03 1.63E+O,3 2.69E+03

'MW';'32~59, 7 7 1.71E+04 B.85E+02' 6A3E+04 I\iJW~32-B5, 7 "1 B.16E+03 6;54E+()3: 9.16E+03

'MW~3a' 1 1 3.44E+04 3.44E+04. 3A4E+04 MW':'35 1 1 1.46E+03 1A6E+03 1.46E+03 JVIW"'36~24' 4 4 1.28E+03 2.37E+02 2.92E+o3 MW':'36,,41 3 3 1 ;05E+04 1.01E+04 1.13E+04 IVIW~36...;52 4 4 7.42E+Cl3 S:b6E+03. 8.61E+03 M\IV-37-22 4 4 4,60E+03 .3.85.E+03 ,~;27E+03 MW-'37-32 4 4. 4.66E+03 3,76E+03 5.48.E+03 MVV...:37...:40 4 4. 4.!51E+03 4.22E+03' 4.91E+Q3

.MW,,"37.;57 4 4 4:B1E+03 4.05E+03 '5.94E:l-03, MW;;39-1'02: :2 :2 2A4E+02 :2.20E+02; ,2.67E+02 MW.:.39-124 2 :2 2,:33E+02 1.98E+()2 ,2.68E+0,2 MVV;,39-183 2 1 :9.85E+01' 9.B56+O',1 9.85E+Q1*

MW.:.;3!3.,19?: 2 t 1 :O:S,E+Cl4 t.oSE+Q2! 1.q9.E+O~

MW..,39-67 2 2 3:90E+02 3;3BE+02 4A1E+02 JVIW':39-84 2 2: 2.J.4E+02 1.85E+Q2 :2A2E+b~

MW-AO..,100: 4 1 '2:62E+02 2:62E.f02* 2.62E+02

.MW-40-'12i 4 2 1.28E+02 1.04E+02' 1.52E+02 IVIW...;4Q-162, 4 t 1A2E+02 '1A2E+02! 1 ;42,EH)2 MW-AO-27 4 2 1.5BE+02 t.17E+02 1.9.8E+02 MW-4Cl~46 4 1. 1 :52E+02 t.52E+J)2 1.52E:+02

.MW-AO-B1 4 4 1.74E+02 9i11 E+01 2.31E+02 MW,.41:-40 3 3 5~01 E+02 3.1'56+02 6.17E+02

.I'v1W.,4t-~3 3 3 4:72E+02 4AOE+02 5.2E)E+Qg MW-42-49; 5 5 1.5BE+04 1.2BE+03 7.22E+0;4 MW,,4.2-7B' 4 4 4:27E+02 2,74E+02: 5.~fE+02 MW,,43-2B~ 3 2 2;44E+02 1 :73E+02 3;14E+02 M\N-43-62 3 1 1~96'E+0:2 1.96E+02 1.96E+02 MW-"44-102 4 4. '4;34E+02 2.57E+02 5.15E+02 IVIW'"44~'66 4 4 4. 94E:+-02 2.06Ef02 7.o44E'+02 tylW-45,.42 4 4 2.9e;E+03 1.. 4:1E+03 ?.~9E+03

Docket No, 50-3, 50-247, & 50-286 Page 45 of 49 Tritium Summary page 2 of 3

Positive

'#;$ampl,e~ H~3$ar11pl,e$; Avg;p()~, Mir(Pos' ivlaxPos vveliName 1i1~009' i!'l;:t(:jOS ,~Gt Act .,Act M\M45-'61 4 4 1 :336+03 '1:,1'~6+0~ 10466+03 MW4f3 4 .4 9.22E+02 7,566+02 1 ..106+()3 MW'A~-26 4 '-1 i;3':2$6+0;3 3; 19E+.03: '3;566+03 MW-':49-42,' :4 .4 2A96+03 2.256+03 2~686+03, MW~4$-65\ 4' 4 1 ;S,26+03 t.~4E+b3 1 :66E+'03 MW,;,50"o42' 4 4 :5;,196+02 2:,1'56+02; ,,1 ;066+0,3, MW-50~6,6 5 5 )2;956+03 2.30E+03; :30456+03 MW:,S1-'i04, 4 2 2j86+92, 1 :446+02 '2:916+02 MVV~5Y-4h' ' 4 3, 2.086+02 1:S56+02 2'.676+02

'MW+5f':19: 4 1 ,1;99£::+02 t,$96+02,1 .9~'6+02 MW,;,52"'11 l' t 5.196+02 5>196+02 5~196+02 MWL52-122i 'i i '1.156'+02 itSE+02: 1:156f02

,MW~52-1;62: T ~ 4:926+02 .(92'6+02 4:926+02 MW:,52-'t8 1; 1 , 2,29£::+02 *2.296...02 .2;.296+02 IVIVV-:52'-'181 :1' 1 1A76+02, 1A76+021.47'E+02 MW..52-48 1 1 1,436+02 10436f02; 1>436+02 MVv~5$120 '5 5 '5':256+03 5,()5E+03'5:6,5E+03 MW.,53".82, 4 4. '1;916~(j3 6.646f02 4~26E+03 M\N,:S4.'::123 4 4 6,516,+02 5~31E:+627.496+02 I\IIW~94'-144 4 4. 1.326+03 1.136+0~ 1.456+0~

MW~54:;173, 4 4' "1:816+03 1.576+'031 ;986+03 MW';54.,t~0 4' 4' 1.756+03 1,436:+03,2.01 6:+-0~

MV¥-54~37 4 .4 1.366f03 '1.t66+03 1.606fOqi

'MWi 54':S8, 4 4. 7,40E+02 $.$8E+02 8;386+02 MVV"55-24 4 4 1.296+03 1,:046+03 1:596+03

'MW.,55':3S: 4. 4 2.19E+()3 8.53E+02 2.8'3E+03 I\IIVv-':55-54 4 4' 6At6+03 5A76+03 7.~36+03 MW~56-5:3' 2 2 5,936+02 5.006+02i6~866+02 M\IV:,5i:i-83; 2 2 ;3.206+03 3.156+03 3,246t03

,MW.;57".f1 t 1, ,4~226+03 4.226+03 ,4:226+03 MW".57-,;ZO t 1: j;526+03 1;:526+03:1.526+03

'I\IIVV-:57'-4S 1 J 1.196+03 :1.196+0:3, L 19E,+03

~MW':'58,:'26' 3 3 :4:526+02 4,,136+02' '5.196+02 MVV,;58,-65 ~ '3 2.486:+-02 2i~:36+():2: .2~75£::f02 MW;60'-135, 4 4 3,416f02 3:176+02' 3.8~E+04 MW~66-154 4 4 4.446+02 4~69E+Q2; 5:.136~02 MW~60-t76 4 4 1 :006+03 ~:~66+02 1 .046+03 MW.,60-35 4 3 2.306+02 2.006:+:02, 2~60E;+02 r\ilW';150:.$3 ' 4. 2 '3:5:16+Q2 2.036+()2 4.99E+02 MW.,,60-,72 4 3 . 1.716:+:02 t.676+02' 1 ]36+02 I\IIW:-E)2-138' 4 4 J3;S,16+Q2 5.76E+02, f72E+0~

MW-6,2-'~8 4 A, 3:606+02 2.366+02 4.646+02 MW-62~182 4 4 :5;536+02 4.666+02 7.366+02 MW':'6l2;,;37, 4 4 3.566+02 2:1.76+02 A87E+()2 Mv\1,;62~53, 4 ;4 3.286:+-02 2.406+02 A.336':+:()2

Docket No. 50-3, 50-247, & 50-286 Page 46 of 49 Tritium Summary page 3 of 3 1# Positiv¢

Sample~ H~3 ;Samples AvgPo~ Min Pbs Max Po's Well Name in~,009 in 2009, Act Act' Act

'MW~!34",71 4 4 3 . ~9E+02 2,~9E+02, 4;78E+Q2 MW~62";92< 4 4 o4J4E+02 2.80E+02 6,086+02 MW-6j.;H2 4 4 ~t~oE+b2 *t37E+02: 4.96E+02 MW~63":121 4 4 '5;32E+02 4.:66E+02 ,6.23E+02 NlW-63.;163 4 4 :5:59E+02 4:36E+02 6.96E+02 "MW~~~,;174 4 4 4.67E+02 4.22E+02' 4.98E+02 MW~63-T8 4 '2 2:89E+02 1.97E+02' 3.80Et02 MW~63-34' 4 4 ,3.4$,E+02 ~;10E+02 4.2"OE+02 MW,,63-50: 4 4 '3.31E+02 2:98E+02 3.60E+02 MVV~63~93 4 4 2.68E+02 1".66E+02 3.40E+02

,MW~66,";2:1 5 4 6.66E+02 4,29E+02 9.51E+02 MV"'~66,-36i 4 4 '3.85E+03 3;05E+03 4.39E+03 MW'-67-10s: 4 4 1;96E+03 1;77E+03 ~2 . f2E+03 MW,,67-173 5 5 8:07E+02 673E+02 1.05E+03 M\/V'"67-219 4 4 1 .. 1~E+Q3. ~;:22E+02: 1.44E+0~

MW-6.7,,276 4 4 1 ~00E+03 9.t7E+02 1.10E+03 MW-67-323 4 4 .3.94E+02 3.6SE+()2 4.21 E+02 MW~67-340 4 4 9.Q7p+04 4);OE+02 5,;37E+02 MW,6.7-39 4 4 3.26E+03 2.69E+03 3.88E+03

,U1..:G$S ~ 3, 2.59E+03 1.97E+03 3.28E+03 U3-40: 4 4 4.55E+02 3.82E+02 4,82E+02 U,3~T1 4 4 4.49 E+02, ~;~8~+02, $j~E+P4 U3~T2 4 4 1 ,Q4E+0~ 8.94E+02 1J2E+03 Note 1: All results imi in:pCiI.L Note 2: A totalof431 sa'i"nples WerE~;analyzed for H~3 in 2009, with 3.85 positive' results. . . ",

N6te,'3: A sample 'is pp:sitive ifthe r¢siJlt is greater thari9r~quaLtQ~'

tirnes th~ 1 sigm,a uDcertainty.~ Th~~arget Moe is'200 pCi/L

Docket No. 50-3, 50-247, & 50-286 Page 47 of 49 Cobalt-50 Summary it: P()sitlve

Sampl~s, ~arnpl~s,Jn Avg,.P()~ Min Pos Ma.xPo~

Well Name in 2009 2009 Act Act Ac:t MW-42,.49 5 1 5.23E+00 5.23E+00 5.23E+00

MW-44-66 4 1 3'.()9E+bb 3.09E+OO .3. 09 EH).b MVV-63-163 4 1. 9:~'OE+QQ 6.80E+OO $.80(:+<;>0 Note 1: All results are inpCi/L N6te2: A t6talOf. 431 sa mph:fs Were analyzed f6f;Co~60 iii 200.9.

,with~;po?itiveJ~~ult~. '"

A sample :i~ P9sitive inhEf;resLJlt is greater tharrqr~qu~I't9 3 ti.rTl~s;tl1e 1 si9 rnCl uncertainty~ Th~t.arget M[)(} is'1$ pCilL Nickel-53 Summary

P'osJtive

Samples' Samples in Avg Pos MinPos MaxPos Well Name in 2009. 2009 Act Act Act MWA2"49' 5 5 6.49E+02 7.46 EtO.1 1. t6E+03., .

MW4$';2~ 4 1 2,318+01 2.3.1E+01 2.91'E+Q1 MW~67:-::r73 5 1 8.408+01 8.40E+01 8.406+01

MW.. S7~276' 4 ,1 2.21E+01 2:211:+:,01 2,ZtE+th No!e 1,: All resul,ts areinpGJ!L Note2: A total of 176 sarnples\N~re.a[lalyze.d fpr Ni..~~. i[l2009 with 8 positive. results'.

A s~mpleis pO$itive if fheJ¢slIltis gr,ea't~r tharlor ~qualto 3 times the 1 sigma*.uncertainty; The target MDe is,30 pCi/L

Docket No. 50-3, 50-247, & 50-286 Page 48 of 49 Strontium-gO Summary page 1 of 2

Positive t;t'Sampie.s ' Sr;;.gp S~mples AVQ Po~ Minpgs M~XPClS, Well Name ,in 2009 in 2009: A~t A,e,t ,Ad

,MV\f-t1l 2 2 1.51 E+OO' 8~46E~01 2~,17E+OO Mw'3tc49 7 1 5.58E;.01 5,58E~01 ~.~8E~p1.

MW31-~3 7: :3 7;67E~01 5;S9E':01 1.tOE+.OQ MW~32:85i 7 1 8.00E~Ot 8:00E~O,1 8.00E*01 MW~36-41 :3 3 SA3E+OO 4'.03E+OQ 7.12E+OO fI,i\N<3p';,52; 4 4' 3.50E+.OO 2AOE+OO 4.70E~OO MW+37';22 4 4 1.07E+O~ ,8.8tE+OO t,2.4E+01 M\1V+37~32 4 4 1.85E+01 1.11E+Ot 2.38E+O:1 MW~37-40 4 4 8;35E+,OO 1.11E+OO 1.69E+01 MW~37';57 4 4 2:63E+01 1.99E+01' 3;17E+01

'MW~39~1,02 :2 2 1.82E+OO' 1.24E+OO 2.40E+o6 M\N~39 .. 124 ~ 2 1.39E+OO ,9.1S~~01 t87E+Oq

'MW~39..;195' 2 1 6.89E*01 S:89E.:m 3.~9E~01 MW~39,,67 2 2 2.8SE+,OO 2.37E+OO 3,~5E+60

,MW-39"84 2 2 1.58E+OO 1 J1E+OO 2~O~E,..qq

'MW,,41-4Q' 3 :3 4.5SE+OO 4.00E+OO 5:38E+OO I\!1W-41-63': 3 3 3.S4E+OO :2.67E+00 4.08E+o6

'MW"'42-49' 5 '5, 3.09E+02 '4.8;~E+o6 f3.:. 7'7 E:+02 MW-43-62 ~ 3 ,9.3SE~01 S:~5E-01 124E+Og MW~44-t02 4 1 7.80E:'01 7',80E-:01 7.80E~01 MW-46' ' ;4 1 8.S0E~01 8:60E':01 8J~OE.. 01,

,MW-49"26' 4 4 1.,3SE+01 1.23E+o1 1:50E-i:01

'MW~49-42, 4 4' f.83E+01 1.74E+Q1 2:07E+01 M\I\I-49-65: 4 4 1..3,5E+01 1.J4E:+Ot 1.7~E+'01 MW~~O-42: 4 4 4.10E+OO 1.9E3E+OO 6;73E+Oq

.1\I1\iv~50';66; 5 5 2.78E+01 2A2E;+Ol 3.00E+O,1 MW~53-1'20' 5 4 2.77E+01 :2.37E+Ot 3:tQE-+:O.1 MW~53..;8:it 4 '1 2.30E+OO 2,jOE+QO 2:30E+OO

,MW7 54-1.23 4 4 4.54E+o6: 3.77E+OO 5:91 E+bb' M\I\I~54-144: 4 4' 1 :4SE+01 1.43E+01 1:51 E+O:1 MW~S4.;t73 4 4 8:85E+OQ 7.42E+OO 1:02E+O,1 MW-54..;190: 4 4: 1.9SE+O~ 1.90E+O'1 1.98E+01 MW-54-3T 4 4 5;90E+OO 5.~3E+OO S~35E+OO MW~5'4-'58 4 4, :r.i83E+OO 1.41 E+OO 2;'OOE;:bq.

MW~55';24; 4 4 2.0SE+01 1.~5E+01 3;07E+O,1 MW~55-35, 4' 4' 3.0SE.+01 1.71 E+01 4;*t4E+01

'MW~55-54; 4 4 2.64E+01 2AtE+of 3,27E+01 MW~56-83; 2 2 2,75E+OO 2.71 E+OO 2:78E+OQ'

,MW~57"11 1 1 4.72E+01 4.72E+Ot 4.72E+01 MW~57<20 1 1 2.71E+OQ 2:.7'7E+OO 2.77E+QO

,MW-57-4S' 1 1 2.25E+OO :,l2':25E+OO 2.25E~OO

'fii1W"S~-65 3 1 6,33E-01' 6(33 E.;O 1 6.~3E-Q+

,MW~E32-138, 4 4, 2.10E+OO 1 :31E+OO 2.83E+OO

'MW~62-18, 4 1 1;o9E+06 1.09E+QQ 1.09E+'OO

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

Positive

Samples, .Sr~90Samphi!s Avg Pos Min Pos Max Pas Well.*Name hi 2009' in 2009, Act Act Act MW63-121 4 1 7.30E-Ot 7.30E..:01 7.30E-01

.MW,g;3.,93 4 1 5.44E~01 S.44E':01 5,44E-()1 MW,.66..:36 4 4 9:31E+00 .6.82E+00 1..22E+01

.MVV.,67-105 4 2 6.Q1E~bf 5.33E~01 SA9E-01 MW"67~39.* 4 4 1;13E+01 6.37E+00 '1A2E+01 U1"CSS 3 .3 2.24E+01 1.41 E+01 3.56E+01 U3'-T 1. 4 1 1,04E+.QO 1;Q4E+QO LQ4.E+OQ U3;;T2 4 '1 1.76E+00 1.76E+00 1.76E+00, Note 1-; AILresutts arelh pOi/t.

N6te2*: AtotalofA3.1 sample's*Vi/ere*ahalyzed fOJSr~90 in 2009 With 14S>pqsitive resqfts, .. r _

Note 3: A sampfeispositive ifthed'esuft is greater than or equarto:3 tlr:nesthe 1 sigm<:l.unc~rt(linty; ThE! target MDCi.s'1pCi/L Cesium-137 Summary

Positive

Samples' Samples in AvgPos Min Pos Max Pos Wen Name in 2009 2009 Act Act Act

,MW30".84 S 1. 8.97E+00 8:97E+00 8.97E+00

'Mw-41'.:40, :3 1 4.2SE+ob 4.26E+.ob 4.2SE+DO MW':'42-49 S S 6.73E+04 S.42E+03 f.40E+OS MW~43~S2 ~ 1 f,18E+()i 1.181::+01 1;18E+01 IVIW-~3-82 4 1 7.7SE+.00 T7SE+00 7.76E+00

.MW,.55-24' 4 1 1.03E+01 1.03E+01 1'.03E+01 MW.:.57..:11 1 1 3.89E+00 3:89E+00 3.89E+00 MW.,SO-1.54 4 1 1.34'E+Q1 1.34E+01 1.34E+01 MW~6S-21 5 '1 B.99E+Ob ~:99E+()Q 8.99E+00*

MW-~7-173 5 ~. 1 ;:34E+01 1:34E+01 1.34E+Ol Nole.1: AIlr'Efsults are . iri pCi/L Note 2: Atotal of 431, samples were.analyzed forCs~137 in 2009 with 14 positive res.ults. . ,', ... . .

Note: 3: A sample is p()sitiv~ )fthe, result is' greater, than:orequal to 3

~ime.s.the 1 sigma uncertail'lty: TI1~' target IV! DC is' H~ pCijL"

ENCLOSURE 2 TO NL-10-045 2009 Offsite Dose Calculation Manual Changes and Justification Package ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 1, 2, AND 3 DOCKET NOS. 50-03, 50-247, AND 50-286 LICENSE NO. DPR-5, DPR-26, AND DPR-64

Entergy Nuclear Northeast t Indian Point Energy Center Units 1, 2, and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Rev. 2

(

\

WRITTEN BY:

REVIEWED BY:

OSRC REVIEW:

APPROVED BY:

EFFECTIVE DATE:

Table of Contents ii List of Tables and Figures vi Introduction viii PART 1- RADIOLOGICAL EFFLUENT CONTROLS D 1.0 USE AND APPLICATION D 1.1 Definitions D 1.1-1 D 1.2 Logical Connectors D 1.2-1 D 1.3 Completion Times D 1.2-1 D1.4 Frequency D 1.2-1 D2.0 SAFETY LIMITS (Not Used)

D 3.0 APPLICABILITY D 3.0 ODCM Limiting Condition for Operation (DLCO) D 3.0-1 D 3.0 ODCM Surveillance Requirement (DSR) D 3.0-2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluents Concentration D 3.1.1-1 D 3.1.2 Liquid Effluents Dose D3.1.2-1 D 3.1.3 Liquid Radwaste Treatment System D3.1.3-1 D 3.1.4 Liquid Holdup Tanks D 3.1.4-1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate D 3.2.1-1 D 3.2.2 Gaseous Effluents Dose - Noble Gas D 3.2.2-1 D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate D 3.2.3-1 D 3.2.4 Gaseous Radwaste Treatment System D 3.2.4-1 D 3.2.5 Ventilation Exhaust Treatment System D 3.2.5-1 D 3.2.6 Gas Storage Tanks D 3.2.6-1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1-1 D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2-1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose D 3.4.1-1 IPEC ODCM 11 Revision 2

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 D4.1 UNRESTRICTED AREA D4.1-1 05.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report D5.1-1 D 5.2 Radioactive Effluent Release Report D 5.2-1 D 5.3 Special Reports D 5.3-1 05.4 Major Changes to Radwaste Treatment Systems D 5.4-1 D 5.5 Process Control Program (PCP) D 5.5-1 D 5.6 Radiological Ground Water Monitoring Program (RGWMP) D 5.6-1 IPEC ODcM iii Revision 2

BASES PAGE B 03.0 APPLICABILITY 8 D3.0 ODCM Limiting Condition for Operation (DLCO) 8 D 3.0-1 8 D 3.0 aDCM Surveillance Requirement (DSR) 8 D 3.0-1 B 0 3.1 RADIOACTIVE LIQUID EFFLUENTS 8 D 3.1.1 Liquid Effluents Concentration 8 D 3.1.1-1 8 D 3.1.2 Liquid Effluents Dose 8 D 3.1.2-1 8 D 3.1.3 Liquid Radwaste Treatment System 8 D 3.1.3-1 8 D 3.1.4 Liquid Holdup Tanks 8 D 3.1.4-1 BD3.2 RADIOACTIVE GASEOUS EFFLUENTS 8 D 3.2.1 Gaseous Effluents Dose Rate 8 D 3.2.1-1 8 D 3.2.2 Gaseous Effluents Dose - Noble Gas 803.2.2-1 8 D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate 8 D 3.2.3-1 8 D 3.2.4 Gaseous Radwaste Treatment System 8 D 3.2.4-1 8 D 3.2.5 Ventilation Exhaust Treatment System 8 D 3.2.5-1 8 D 3.2.6 Gas Storage Tanks 8 D 3.2.6-1 BD3.3 INSTRUMENTATION 8 D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation 8D3.3.1-1 8 D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 8 D 3.3.2-1 B D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 803.4.1 Radioactive Effluents Total Dose 803.4.1-1 B D3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 803.5.1 Radiological Environmental Monitoring Program 8 D 3.5.1-1 8 D 3.5.2 Land Use Census 803.5.2-1 8 D 3.5.3 Interlaboratory Comparison Program 8 D 3.5.3-1 B D 3.6 SOLID RADIOACTIVE WASTE 8 D 3.6.1 Solid Radwaste Treatment System 8 D 3.6.1-1 IPEC aDCM IV Revision 2

PART II CALCULATIONAL METHODOLOGIES 1.0 RADIATION MONITORS AND SETPOINTS 1.1 Effluent Monitoring System Description 1 1.2 Setpoints for Airborne Effluent Monitors 1 1.3 Setpoints for Liquid Effluent Monitors 2 2.0 LIQUID EFFLUENT METHODOLOGY 2.1 Liquid Effluent Releases - General Information 6 2.2 Liquid Effluent Concentrations 9 2.3 Liquid Effluent Dose Calculation Requirements 12 2.4 Dose Methodology (Computer Calculation) 13 2.5 Backup Simplified Dose Methodology 16 2.6 Site-Specific Bio-Accumulation and Dose Factors 16 3.0 GASEOUS EFFLUENT METHODOLOGY 3.1 Gaseous Effluent Releases - General Information 25 3.2 Gaseous Effluent Dose Calculation Requirements 30 3.3 Dose Methodology (Computer Calculation) 31 3.4 Backup Simplified Dose Methodology 43 3.5 Calculation of Meteorological Dispersion Factors 46 3.6 Justification and Use of Finite Cloud Assumptions for Assessing SB Dose 51 4.0 TOTAL DOSE DETERMINATIONS 4.1 10CFR190 Dose Evaluation 100 4.2 Doses from Liquid Releases 100 4.3 Doses from Atmospheric Releases 100 4.4 Doses to MEMBERS OF THE PUBLIC Visiting the Site 101 5.0 LOWER LIMIT OF DETECTION 102 REFERENCES 104 APPENDICES Appendix A: Summary of Radiological Effluent Controls 107 Appendix B: Liquid Effluent Simplified Flow Diagram 108 Appendix C: Gaseous Effluent Simplified Flow Diagram 110 Appendix D: Steam Partition Factor Calculation (f ) 112 Appendix E: Allowed Diluted Concentration (ADC) 113 Appendix F: Conversion Factors for Liquid Effluent Monitors 114 Appendix G: Environmental Sampling Points 115 Appendix H: Interlaboratory Comparison Program 122 Appendix I: Calculation of Allowable Release Rates for Indian Point Units 2 and 3 123 Appendix J: Groundwater Flow and Offsite Dose Calculation Details 130 IPEC ODCM v Revision 2

LIST OF TABLES AND FIGURES PART 1- RADIOLOGICAL EFFLUENT CONTROLS Tables:

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 Figures:

4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE D 4.1-2 GASEOUS AND LIQUID EFFLUENTS 4.1-2 MAP DEFINING RELEASE POINTS D 4.1-3 IPEC ODCM . vi Revision 2

LIST OF TABLES AND FIGURES PART 11- CALCULATIONAL METHODOLOGIES 1-1 Unit 2 Effluent Radiation Monitor System Data 4 1-2 Unit 3 Effluent Radiation Monitor System Data 5 2-1 Site Related Adult Ingestion Dose Commitment Factors 18 2-2 Site Related Teen Ingestion Dose Commitment Factors 20 2-3 Site Related Child Ingestion Dose Commitment Factors 22 2-4 Bio-Accumulation Factors for Liquid Effluent Isotopes 24 3-1a Adult Inhalation Dose Factors 52 3-1b Teen Inhalation Dose Factors 54 3-1c Child Inhalation Dose Factors 56 3-1d Infant Inhalation Dose Factors 58 3-2 TBISkin GP Dose Factors, wI Half Life & Stable Element Transfer Data 60 3-3a Adult Ingestion Dose Factors 62 3-3b Teen Ingestion Dose Factors 64 3-3c Child Ingestion Dose Factors 66 3-3d Infant Ingestion Dose Factors 68 3-4 Total Body Dose Factors, Ki, from Noble Gas (Gamma) 70 3-5 Skin Dose Factors, Li, from Noble Gas (Beta) 71 3-6 Air Dose Factors, Mi, from Noble Gas (Gamma) 72 3-7 Air Dose Factors, Ni, from Noble Gas (Beta) 73 3-8 NG Dose Factors for Instantaneous and Time Average Mixtures at the SB 74 3-9 Locations of Site Boundary and Nearest Residence 75 3-10a Adult Inhalation Ri(l) 76 3-10b Teen Inhalation Ri(l) 78 3-10c Child Inhalation Ri(l) 80 3-10d Infant Inhalation Ri(l) 82 3-11a Adult Ingestion (Leafy Vegetable) Ri(V) 84 3-11b Teen Ingestion (Leafy Vegetable) Ri(V) 86 3-11c Child Ingestion (Leafy Vegetable) Ri(V) 88 3-12a Adult Grass-Cow-Milk Pathway Ri(C) 90 3-12b Teen Grass-Cow-Milk Pathway Ri(C) 92 3-12c Child Grass-Cow-Milk Pathway Ri(C) 94 3-12d Infant Grass-Cow-Milk Pathway Ri(C) 96 3-13 Total Body and Skin Ground Plane Dose Factors Ri(G) and Ri(S) 98 IPEC ODCM Vll Revision 2

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5. for both IPEC units 2 and 3. Previous revisions of each unit's ODCM have been combined to form a station ODCM. The IPEC ODCM consists of two parts:

1) Part I, Radiological Effluent Controls, (RECS) - previously, often referred to as the Radiological Effluent Technical Specifications, or RETS (Section 3.9 of original Unit 2 Technical Specifications, and Appendix B or original Unit 3 Technical Specifications).

2) Part II, Calculational Methodologies (previously often referred to as simply the "ODCM")

Part I, Radiological Effluent Controls, includes the Radiological Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5. It also includes descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by each unit's Technical Specifications.

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. At IPEC, this method includes the use of ten-year averaged 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.

The sources for criteria found in the ODCM and the Radiological Effluent Control SpeCifications include the following:

Liquid Effluent Release Rate: Diluted concentrations in the discharge canal are limited to ten times the EFFLUENT CONCENTRATIONS identified in 10CFR20 Appendix B.

Airborne Effluent Release Rate: Release rates are limited to corresponding dose rate limits from NUREG 0133 and 0472.

Integrated Radiological Effluent Dose: The design objectives of 10CFR50 Appendix I.

The ODCM and associated tracking software implements the methodology of

1) 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

2) 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. In some cases, site-specific data or reasonable simplifying assumptions are used and justified to permit formulation of more workable methodologies for implementing RECS dose calculation requirements.

IPEC ODCM Vlll Revision 2

Indian Point Energy Center Offsite Dose Calculation Manual PART I - RADIOACTIVE EFFLUENT CONTROLS

Definitions D 1.1 D 1.0 USE AND APPLICATION D 1.1 Definitions

NOT E----------------------------------------------------------

Terms defined in Technical Specifications and the following additional defined terms appear in capitalized type and are applicable throughout these specifications and bases.

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 all 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 ten times the PERMISSIBLE EFFLUENT CONCENTRATIONS specified in 10CFR20, Appendix B, CONCENTRATION Table 2, 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 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.

IPEC ODCM D1.1-1 Revision 2

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 the licensee(s).

SOLIDIFICATION SOLI 01 FICATION 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 rad ioactivity.

UNRESTRICTED An UNRESTRICTED AREA is any area at or beyond the SITE AREA BOUNDARY, access to which is not controlled by the licensee(s) for purposes of protection of individuals from exposure to radiation and radioactive materials. (See Figure 04.1-1)

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.

IPEC ODCM 01.1-2 Revision 2

Logical Connectors D 1.2 1.0 USE AND APPLICATION 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 IPEC ODCM D 1.2-1 Revision 2

APPLICABILITY D 3.0 D 3.0 ODCM Limiting Condition for Operation (DLCO) Applicability DLCO 3.0.1 DLCOs shall be met during the MODES or other specified condition in the Applicability, except as provided in DLCO 3.0.2.

DLCO 3.0.2 Upon discovery of a failure to meet a DLCO, the Required Actions of the associated Conditions shall be met, except as provided in DLCO 3.0.5.

If the DLCO 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.

DLCO 3.0.3 When a DLCO 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 DLCO or associated ACTIONS, and

b. Enter the circumstances into the Corrective Action Program.

NOT E-----------------------------------

DLCO 3.0.3.b shall be completed if DLCO 3.0.3 is entered.

Exceptions to this Specification are stated in the individual Specifications.

DLCO 3.0.4 Not Applicable to ODCM Specifications.

DLCO 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.

IPEC ODCM D 3.0-1 Revision 2

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 DLCO. 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 specified 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 DLCO 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 DLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

'IPEC ODCM D 3.0-2 Revision 2

Liquid Effluents Concentration 03.1.1 o 3.1 RADIOACTIVE LIQUID EFFLUENTS 03.1.1 Liquid Effluents Concentration DLCO 3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure 04.1-1) shall be limited to:

a. The MPCW concentrations as defined in 01.1 for radionuclides other than dissolved or entrained noble gases; and

b. 2 x 10-4 I-ICi/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 0 3.1.1-1 DSR3.1.1.2 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 0 3.1.1-1 are maintained within the limits of DLCO 3.1.1.

IPEe ODCM Page 3.1.1 - 1 Revision 2

Liquid Effluents Concentration D 3.1.1 TableD 3.1.1-1 (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 1E-5 Draindowns, Grab Sample 31 days Entrained Gases 31 days (h) 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)

Principal Gamma eg, SG Composite (d) Composite 7 days Emitters (c) 5E-7 Blowdown, U1 NCO, Mo-99, Ce-144 5E-6 U1 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-89, Sr-90 5E-8 92 days Fe-55 1E-6

3. Service Water Gamma and Beta Per liquid batch Grab Sample 31 days 31 days (in Radiologically emitters OJ releases, above.

Controlled Areas)

4. Turbine Hall Gamma and Beta Per liquid batch Drains, SG Composite (d) Composite 7 days emitters OJ releases, above.

Feedwater (i)

IPECODCM Page 3.1.1 - 2 Revision 2

liquid Effluents Concentration D 3.1.1 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 with 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 10-6IlCi/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 circumstances, the LLD may be increased in inverse proportion to the magnitude of the gamma yield (Le., 5 x 10-7/1 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 RECS Section D.1.1.

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

IPEC aDCM Page 3.1.1 - 3 Revision 2

Liquid Effluents Dose D 3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 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 D 4.1-1) 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 D 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.

IPEC ODCM D 3.1.2 - 1 Revision 2

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 0 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.

IPECODCM 03.1.2 -2 Revision 2

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.

IPEe ODCM D 3.1.2 - 3 Revision 2

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 COMPLETION 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 inoperability, (2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and I**

(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.

IPEC ODCM D 3.1.3 - 1 Revision 2

Liquid Holdup Tanks D 3.1.4 D 3.1 LIQUID EFFLUENTS D 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:

AND U2& U3 PWSTs A.2 Initiate measures to reduce 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months U2& U3 RWSTs content to within the limits.

U1 Waste Dist Storage Tanks AND U3 Monitor Tanks A.3 Describe the events leading to Prior to submittal of U3 CPF High/Low TDS Tanks the condition in the next Radioactive Outdoor Temporary Tanks 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) where radioactive liquid does not exceed the limit. is being added to the tanks, in accordance with the methodology and parameters of the ODCM IPECODCM D 3.1.4 - 1 Revision 2

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, ::;; 500 mrem/yr to the whole body and

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, ::;; 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.

IPEC ODCM D 3.2.1 -1 Revision 2

Gaseous Effluents Dose Rate D 3.2.1 Table D 3.2.1-1 (Page 1 of 2)

Radioactive Gaseous Waste Sampling and Analysis SAMPLE LOWER GASEOUS ANALYSIS SAMPLE LIMIT OF SAMPLE SAMPLE RELEASE FREQUENCY TYPE FREQUENCY ANALYSIS DETECTION TYPE (LLD) (a)

Principal Noble 1E-4

1. Waste Gas Grab Each Tank (h) Each Tank (h) Gas (NG)

Storage Tank Sample Gamma IlCilcc Emitters (b)

Principal NG Grab Each Purge (h) 1E-4 Purge Each Purge (h) Gamma Sample Emitters (b)

2. IlCilcc Vapor Containment Principal NG Press Grab . 1E-4 31 days (i) 31 days (i) Gamma Relief Sample IlCilcc Emitters (b)

Principal NG

3. Condenser Air Grab 1E-4 31 days 31 days Gamma Ejector Sample IlCi / cc Emitters (b)

Principal NG

4. Continuous Grab 1E-4 31 days (c) 31 days (c) Gamma Ventilation: Sample Emitters (b) IlCilcc

a. Main Plant H-3 1E-6 Continuous 31 days (e) H-3 Vent (unit 2) Specific Il Cilcc

b. Stack Vent Charcoal 1E-12 (unit 1) Continuous (f) 7 days (c), (g) 1-131 Sample Il Cilcc

c. Main Plant Principal Vent (unit 3) Gamma Particulate 1E-11 Continuous (f) 7 days (c), (9) Emitters (b)

d. Radioactive Sample (1-131, IlCilcc Machine Shop Others)

Vent (unit 3)

Composite 1E-11

e. Admin Bldg Particulate Continuous (f) 31 days Gross Alpha Vent (unit 3) Sample IlCilcc Composite 1E-11 Particulate Continuous (f) 92 days Sr-89 / Sr-90 Sample IlCilcc Noble Gases 1E-6 Noble Gas Continuous (f) Continuous (f) Gross Beta Monitor IlCilcc (d) or Gamma IPEC aDCM D 3.2.1 - 2 Revision 2

Gaseous Effluents Dose Rate D 3.2.1 Table D 3.2.1-1 (Page 2 of 2)

Radioactive Gaseous Waste Sampling and Analysis (a) The LLD is defined, for purposes of these Specifications, 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 with the methodology and parameters in the ODCM.

It should be recognized that the LLD is defined as an .5! priori (before the fact) limit representing the capability of a measurement system and not as an .5! 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. 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 Section D 5.2.

(c) !E following a shutdown, startup, or a thermal power change (within one hour) exceeding 15 percent of RATED THERMAL POWER, analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased by a factor of 3 or more, AND the noble gas monitor shows that effluent activity has increased by a factor of 3 or more THEN:

1) Sample the main 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 main 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) This value is the established Radiation Monitor sensitivity (minimum).

(e) Grab samples can be used as alternative to continuous sampling, provided the periodicity of these grab samples is increased from monthly to once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded, or at least once per 7 days when spent fuel is in the Spent Fuel Pool.

(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 Specifications D 3.2.1, D 3.2.2 and D 3.2.3.

(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, !E routine Iodine sampling indicates 1-131 in any of the listed continuous streams, THEN collect a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sample from the applicable vent (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) Complete prior to each release.

(i) Vapor Containment 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 adjusted by the noble gas radiation monitor reading for purposes of quantification of each release. Should the 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 Bo.TH the containment noble gas and particulate monitors be inoperable, two independent samples of the VC are required prior to a Pressure Relief.

IPECODCM D 3.2.1 - 3 Revision 2

Gaseous Effluent Dose - Noble Gas D 3.2.2 D 3;2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.2 Gaseous Effluent Dose - Noble Gas DLCO 3.2.2 The air dose from noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (Figure D 4.1-1) shall be limited to: . .

a. :::; 5 mrad to the whole body from gamma radiation and

10 mrad to the skin from beta radiation during any calendar quarter, and

b. :::; 10 mrad to the whole body from gamma radiation and

20 mrad to the skin from beta radiation during any calendar year.'

. APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.' The calculated air dose at A.1 Prepare and submit to the 30 days or beyond the SITE. NRC, pursuant to D 5.3, a BOUNDARY due to noble Special Report that gases released in gaseous (1) Identifies'the cause(s) effluents exceeds limits. for exceeding the limit(s) and (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 3.2.2.

IPEC ODCM D 3.2.2-1 Revision 2

Gaseous Effluent Dose - Noble Gas D 3.2.2 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 airborne effluents exceeds radiation from the units 2 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.

IPEC ODCM D 3.2.2 - 2 Revision 2

Gaseous Effluent Dose - Noble Gas D 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.2.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year.

IPEC ODCM D 3.2.2 ':' 3 Revision 2

Gaseous Effluent Dose - Iodine and Particulate o 3.2.3 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.3 Gaseous Effluent Dose - Iodine and Particulate DLCO 3.2.3 The dose to a MEMBER OF THE PUBLIC from 1-131 , tritium, and all radionuclides in particulate form with half-lives> 8 days, in gaseous effluents, released from each unit to areas at or beyond the SITE BOUNDARY (Figure 04.1-1) shall be limited to:

a. ::; 7.5 mrem to any organ during any calendar quarter, and

b. ~ 15 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The dose from 1-131, A.1 Prepare and submit to the 30 days tritium, and radioactive NRC, pursuant to 0 5.3, a material in particulate form Special Report that with half-lives> 8 days (1) Identifies the cause(s) released in gaseous for exceeding the limit(s) effluents at or beyond the SITE BOUNDARY 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 3.2.3.

IPEC ODCM 03.2.3 -1 Revision 2

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 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 B.2 Verify that the limits of DLCO Immediately 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.

IPECODCM D 3.2.3 - 2 Revision 2

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.3.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year for 1-131, tritium, and radioactive material in particulate form with half-lives> 8 days.

IPEC aDCM D 3.2.3 - 3 Revision 2

Gaseous Radwaste Treatment System D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System DLCO 3.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure D 4.1-1) would be:

a. > 0.2 mrad for gamma radiation; and

b. > 0.4 mrad for beta radiation in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 5.3, a without treatment. Special Report that includes the following:

AND (1) Identification of any Projected doses due to the inoperable equipment or gaseous effluent, from the subsystems and the unit, at and beyond the reason for the SITE BOUNDARY would inoperability, exceed limits.

(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 3.2.4.1 Project the doses due to gaseous effluents from each 31 days unit at and beyond the SITE BOUNDARY.

IPEC ODCM D 3.2.4 - 1 Revision 2

Ventilation Exhaust Treatment System D 3.2.5 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.5 Ventilation Exhaust Treatment System DLCO 3.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure D 4.1-1) would be:

a. > 0.2 mrad air dose from gamma radiation; and

b. > 0.4 mrad air dose from beta radiation in a 31 day period; or

c. > 0.3 mrem to any organ in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 5.3, a without treatment. Special Report that includes the following:

(1) Identification of any inoperable equipment or Projected doses due to subsystems and the gaseous effluent, from reason for the each unit, to areas at or inoperability, beyond the SITE BOUNDARY would (2) Action(s) taken to restore exceed limits. the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.5.1 Project the doses from gaseous releases from each 31 days unit to areas at and beyond the SITE BOUNDARY when the GASEOUS RADWASTE TREATMENT SYSTEMS are not being fully utilized.

IPEC ODCM D 3.2.5-1 Revision 2

Gas Storage Tanks o 3.2.6 o 3.2 GASEOUS EFFLUENTS o 3.2.6 Gas Storage Tanks DLCO 3.2.6 The radioactivity contained in each gas storage tank shall be limited to the following unit-specific curie levels of noble gas (considered as Xe-133):

Unit 2: ~ 29,761 Curies Unit 3: ~ 50,000 Curies APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits. radioactive material.

A.2 Reduce content to within the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.6.1 The quantity of radioactive material contained in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during each gas storage tank shall be determined to be addition of within the limits above, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months radioactive when radioactive materials are being added to the material to the tank in accordance with the methodology and tank parameters in the ODCM.

IPEC ODCM 03.2.6 -1 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DLCO 3.3.1 The unit-specific radioactive liquid effluent monitoring instrumentation channels shown in Table D 3.3.1-1 shall be OPERABLE with:

a. The minimum OPERABLE channel(s) in service.

h. The alarm/trip setpoints set to ensure that the limits of DLCO 3.1.1 are not exceeded.

APPLICABILITY: According to Table D 3.3.1-1 for the applicable unit.

ACTIONS

NOT E-------------------------------------------------------

Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. Liquid effluent monitoring A.1 Suspend the release of Immediately instrumentation channel radioactive liquid effluents alarm/trip setpoint less monitored by the affected conservative than required. channel.

OR A.2 Declare the channel Immediately inoperable.

OR Immediately A.3 Change the setpoint so it is acceptably conservative.

IPEC ODCM D 3.3.1 -1 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Enter the Condition Immediately channels inoperable. referenced in Table D 3.3.1-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

C. As required by Required C.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in release in Table D 3.3.1-1. accordance with Table D 3.1.1-1.

AND C.2 -----------N OTE ----------------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the Prior to initiating a release rate calculations and release discharge line valving.

D. As required by Required D.1 Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B.1 and referenced samples for radioactivity at a in Table D 3.3.1-1. limit of detection of at least AND 5 x 10-7 ~Ci/ml.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter IPEC ODCM D 3.3.1 - 2 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B.1 and samples for radioactivity at referenced in a limit of detection of at AND Table D 3.3.1-1. least 5 x 10.7 ~Cilml, when specific activity is Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 0.01 ~Ci/gm DOSE thereafter EQUIVALENT 1-131.

OR E.2 Collect and analyze grab 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months samples for radioactivity at a limit of detection of at AND least 5 x 10.7 ~Cilml, when specific activity is Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

s; 0.01 ~Ci/gm DOSE thereafter EQUIVALENT 1-131.

F. As required by Required F.1 ---------------NOTE ------------

Action B.1 and Pump performance curves 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months referenced in generated in place may be Table D 3.3.1-1. used to estimate flow. AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Estimate the flow rate during thereafter actual releases.

G. As required by Required G.1 Estimate tank liquid level. Immediately Action B.1 and referenced in AND Table D 3.3.1-1.

During liquid additions to the tank H. Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met. Release Report why the Release Report inoperability was not corrected in a timely manner.

IPEC ODCM D 3.3.1 - 3 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. Required Action and 1.1 Suspend liquid effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E, inoperable channel(s).

or F not met.

J. Required Action and J.1 Suspend liquid additions to Immediately associated Completion the tank monitored by the Time for Condition G not inoperable channel(s).

met.

SURVEILLANCE REQUIREMENTS

NOT E ---------------------------------------------------------------

Refer to Table D 3.3.1-1 to determine which DSRs apply for each function.

SURVEILLANCE FREQUENCY DSR 3.3.1.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DSR 3.3.1.2 Perform CHANNEL CHECK by verifying indication of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on any flow during periods of release. day on which continuous, periodic, or batch releases are made DSR 3.3.1.3 Perform SOURCE CHECK. Prior to release DSR 3.3.1.4 Perform SOURCE CHECK. 31 days DSR 3.3.1.5 Perform CHANNEL OPERATIONAL TEST 92 days IPEC ODCM D 3.3.1 - 4 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY DSR 3.3.1.6 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation (or control panel indications/display) occurs if the instrument indicates measured levels above the alarm/trip setpoint DSR 3.3.1.7 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate control room alarm annunciation (or control panel indications/display) occurs if any of the following conditions exist, instrument indicates measured levels above the alarm setpoint, instrument controls not set in operate mode.

DSR 3.3.1.8 Perform CHANNEL OPERATIONAL TEST 24 months DSR 3.3.1.9 Perform CHANNEL CALIBRATION 24 months IPEC ODCM D 3.3.1 - 5 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation 03.3.1 Table 0 3.3.1-1 (page 1 of3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS SURVEILLANCE INSTRUMENT FROM SPECIFIED PER REQUIREMENTS REQUIRED CONDITIONS INSTRUMENT ACTION B.1

1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release DSR 3.3.1.1

a. Unit 2 Liquid Radioactive (a) C DSR 3.3.1.3 Waste Effluent Line (R-54) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

b. Unit 2 Steam Generator Effluent (a) (i) E DSR 3.3.1.4 Blowdown Line (R-49) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

c. Unit 3 Liquid Radioactive (a) C DSR 3.3.1.3 Waste Effluent Line (R-18) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1 (h) d .. Unit 3 Condensate Polisher Facility (a) C DSR 3.3.1.4 (h)

(CPF) Waste Line (R-61) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

e. Unit 3 Steam Generator Effluent (a) (i) E DSR 3.3.1.4 Blowdown Line (R-19) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm but NOT Providing Automatic Termination of Release

a. Unit 1 or 2 Service Water or River Water Effluent Lines

- VC FCU (R-46 or R-53) DSR 3.3.1.1 (a) 1 (g) D DSR 3.3.1.4

- 21 CCW HX (R-39) DSR 3.3.1.7 (e)

- 22 CCW HX (R-40) DSR 3.3.1.9 (d)

- SBBPS HX (R-52)

DSR 3.3.1.1

b. Unit 1 Secondary Boiler (a) D DSR 3.3.1.4 DSR 3.3.1.7 (e)

Blowdown Effluent Line (R-51)

DSR 3.3.1.9 (d)

c. Unit 1 Sphere Foundation DSR 3.3.1.1 (a) D DSR 3.3.1.4 Drain Sump Effluent Line (R-62)

DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

d. Unit 3 Service Water Effluent Lines DSR 3.3.1.1

- SW for VC FCU return (a) 1 (g) D DSR 3.3.1.4 (R-16A or R~16B) DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

- SW for CCW Heat DSR 3.3.1.1 Exchanger (R-23) (a) D DSR 3.3.1.4 DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

IPECODCM 03.3.1 - 6 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 2 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SURVEILLANCE INSTRUMENT SPECIFIED PER FROM REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

3. Flow Rate Measurement Devices DSR 3.3.1.2

a. Unit 2 Liquid Radwaste (a) F DSR 3.3.1.5 Effluent Line DSR 3.3.1.9 (CT971-FRE, CT971-FIE)

b. Unit 2 Steam Generator DSR 3.3.1.2 Blowdown Effluent Line (a) (i) F DSR 3.3.1.5 (FI-1241 to FI-1244, and DSR 3.3.1.9 FT-1241 to FT-1244)

c. Unit 1 North Curtain Drain (a) F DSR 3.3.1.2 Effluent Line (f) DSR 3.3.1.9 (LW-FE-12)

d. Unit 1 Sphere Foundation (a) F DSR 3.3.1.2 Drain Sump (f) DSR 3.3.1.9 6/09 (FR-7874)

DSR 3.3.1.2

e. Unit 3 Liquid Radwaste (a) F DSR 3.3.1.5 Effluent Line DSR 3.3.1.9 (FE-1064, FI-1064)

DSR 3.3.1.2

f. Unit 3 Cond Polisher (CPF) (a) F DSR 3.3.1.5 Effluent Line (3LG-FIT-41, DSR 3.3.1.9 (3LG-FM-41,3LG-FR-41)

g. Unit 3 Steam Generator (a) (i) F DSR 3.3.1.2 Blowdown Effluent Line DSR 3.3.1.5 (FT-545 to 548, FIR-543,544) DSR 3.3.1.9

4. Tank Level Indicating Devices (c)

DSR 3.3.1.1 (b)

a. Unit 1 Waste Distillate (a) G DSR 3.3.1.5 Storage Tank #13 DSR 3.3.1.9 (CT967-L1E-1, L1E-2)

b. Unit 1 Waste Distillate DSR 3.3.1.1 (b)

Storage Tank #14 (a) G DSR 3.3.1.5 (CT974-L1E-1, L1E-2) DSR 3.3.1.9

c. Unit 2 Primary Water DSR 3.3.1.1 (b)

Storage Tank (a) G DSR 3.3.1.5 (LT-1131, L1-1131) DSR 3.3.1.9

d. Unit 2 Refueling Water (a) G DSR 3.3.1.1 (b)

Storage Tank (L1-920, L T-920, L T-5751) G)

e. Unit 3 Refueling Water (a) G DSR 3.3.1.1 (b)

Storage Tank (L1-920A, L1-920B) G)

IPEC aDCM D 3.3.1 -7 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 3 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SURVEILLANCE INSTRUMENT SPECIFIED PER FROM REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

4. Tank Level Indicating Devices (c) (continued)

DSR 3.3.1.1 (b)

f. Unit 3 Primary Water Storage (a) G DSR 3.3.1.8 Tank (LT-1131, LI-1131) DSR 3.3.1.9 DSR 3.3.1.1 (b)

g. Unit 3 Monitor Tank #31 (a) G DSR 3.3.1.8 (LI-181) DSR 3.3.1.9 DSR 3.3.1.1 (b)

h. Unit 3 Monitor Tank #32 (a) G DSR 3.3.1.8 (LI-180) DSR 3.3.1.9 DSR 3.3.1.1 (b)

Unit 3 CPF High Total (a) G DSR 3.3.1.8 Dissolved Solids Tank DSR 3.3.1.9 (h)

(3-LG-Ll-12)

DSR 3.3.1.1 (b)

j. Unit 3 CPF Low Total (a) G DSR 3.3.1.8 Dissolved Solids Tank DSR 3.3.1.9 (h)

(3-LG-Ll-22)

NOTES (a) Applicability is defined as anytime releases are being performed via this pathway. During periods of release, channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the specified action, for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, or CHANNEL OPERATIONAL TEST.

(b) During liquid addition to the associated tank.

(c) Tanks included in this Specification 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, as specified in RECS Section D 3.1.4.

(d) Radioactive calibration standards used for CHANNEL CALIBRATIONS shall be analyzed with instrumentation which is calibrated NIST traceable standards. Standards from suppliers who participate in approved measurement assurance activities with NIST are acceptable.

(e) Test will include: Low sample flow, no counts per minute failure, and alarm setpoint reached. The CHANNEL OPERATIONAL TEST does not include testing or trouble shooting, nor the performance of any equipment diagnostic capabilities provided with the monitor installation.

(f) Flow rate for these continuous intermittent release pathways is normally obtained from a flow totalizer on the system outlet.

(g) One instrument per operating Service Water system is required. For example, unit-specific VC FCU monitors are redundant and compensatory actions are only required when BOTH monitors are OOS for anyone unit. However, for Unit 2's CCW HX's (R-39 and R-40), the appropriate SW monitor is required to be in service anytime the effected loop is in service.

(h) Channel and Source Checks for R-61 in Unit 3's Condensate Polisher Facility (CPF) are required only during or after a primary to secondary leak, as defined in RECS Section 1. Surveillances on the flow meter and level instruments are performed to be prepared for this type of leak. The level instrument calibration is also required by the SPDES permit.

(i) Applicable for Continuous Steam Generator Blowdown to the environment only. These requirements are not applicable for Batch Steam Generator Draindowns.

0) Surveillance requirements for the RWST level instruments (CHECKS and CALIBRATIONS) are prescribed in Technical Specifications (Sections 3.3.3 and 3.5.4 for Unit 2 and Section 3.5.4 for Unit 3). However, the requirement for a daily channel check (when making additions to the tank, per earlier footnote b) is maintained in the ODCM per the original licensing bases (NUREG 0472) and the 10 curie rule.

IPEC ODCM D 3.3.1 - 8 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation 03.3.2 03.3 INSTRUMENTATION 03.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DLCO 3.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 0 3.3.2-1 shall be OPERABLE with:

a. The minimum OPERABLE channel(s) in service.

h. , The alarm/trip setpoints set to ensure that the limits of DLCO 3.2.1 are not exceeded.

APPLICABILITY: According to Table 0 3.3.2-1.

ACTIONS

NOTE ------------------------------------------------.:------

Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. Gaseous effluent A.1 Suspend the release of Immediately monitoring instrumentation radioactive gaseous channel alarm/trip setpoint effluents monitored by the less conservative than . affected channel.

required.

OR A.2 Declare the channel Immediately inoperable.

OR A.3 Change the setpoint so it is Immedi'ately acceptably conservative.

B. One or more channels B.1 Enter the Condition Immediately inoperable. referenced in Table 0 3.3.2-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

IPEC ODCM 03.3.2 -1 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation

.D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required Action B.1 and referenced C.1 Take grab samples. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in Table D 3.3.2-1.

AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Analyze samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time of activity. sampling completion D. As required by Required D.1 Estimate the' flow rate for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action B.1 and referenced the inoperable channel(s).

in Table D 3.3.2-1. AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter E. As required by Required E.1 Continuously collect 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action B.1 and referenced samples using auxiliary in Table D 3.3.2-1. sampling equipment as required in Table D 3.2.1-1.

F. As required by Required F.1 Determine the radioactive 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action B.1 and referenced content of the receiving in Table D 3.3.2-1. gas decay tank is in AND compliance with DLCO 3.2.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter

,IPEC ODCM D 3.3.2 - 2 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Analyze at least 2 Prior to initiating a .

Action B.1 and referenced independent. samples in gas decay tank in Table D 3.3.2-1, for gas accordance with release decay tank releases. Table D 3.2.1-1.

AND G.2 -----------N OTE ----------------

Verification Action will be performed by at least 2 separate technically qualified members of the faci lity staff.

Independently verify the Prior to initiating a release rate calculations and gas decay tank discharge line valving. release H. Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met. Release Report why the Release Report inoperability was not frequency corrected in a timely manner.

I. Required Action and 1.1 Suspend gaseous effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E inoperable channel(s).

or F not met.

J .. Required Action and J.1 Suspe.nd gaseous effluent Immediately associated Completion releases from Waste Gas

. Time for Condition G not Holdup System .

met.

K. As required by Required K.1 Take Noble Gas grab Prior to venting Action B.1 and referenced samples and analyze for Vapor Containment in Table D 3.3.2-1 (in . gross activity. (VC)

MODES 1-4 only).

K.2 Immediately suspend PURGING the VC.

IPEG ODCM D 3.3.2 - 3 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.3.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DSR 3.3.2.2 Perform CHANNEL CHECK. 7 days DSR 3.3.2.3 Perform SOURCE CHECK. Prior to release DSR 3.3.2.4 Perform SOURCE CHECK. 31 days*

DSR 3.3.2.5 Perform CHANNEL OPERATIONAL TEST. 92 days The test shall include 1) low sample flow, 2J no counts per minute failure, 3) a demonstration 0 the automatic isolation capability of this fcathwafr and that control room alarm annunciation or con rol panel indications/disPla Y occurs if the instrument indicates b

measured levels a ove the alarm/trip setpoint.

This test does NOT include testin~ of troubleshootin~

and equipment diagnostic capabl ities provided wit the monitor installation.

DSR 3.3.2.6 Perform CHANNEL OPERATIONAL TEST. 92 days The test shall include 1) low sample flow (except for Condenser Air Ejector monitors), 2~ no counts per minute failure, 3) a demonstration t at control room ,

alarm annunciation (or control panel indications or display) occurs if the instrument indicates measured levels above the alarmsetpoint, or the instrument controls are not set in operate mode.

This test does NOT include testin~ of troubleshootin~

and equipment diagnostic capabl ities provided wit the monitor installation.

DSR 3.3.2.7 Perform CHANNEL CALIBRATION. 24 months IPECODCM D 3.3.2-4 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 1 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1, 2, or 3) CONDITIONS INSTRUMENT ACTION B.1

1. Waste Gas Holdup System

a. Unit 2 Noble Gas DSR 3.3.2.1 Monitor, providing (b) 1 F DSR 3.3.2.4 Alarm, (R-SO) DSR 3.3.2.6 DSR 3.3.2.7 (c)

b. Unit 3 Noble Gas DSR 3.3.2.1 (b) 1 F DSR 3.3.2.4 Monitor, providing DSR 3.3.2.6 Alarm, (R-20) DSR 3.3.2.7 (c)

2. Condenser Air Evacuation System DSR 3.3.2.1

a. Unit 2 Noble Gas 1 C DSR 3.3.2.4 (a)

Activity, (R-4S) DSR 3.3.2.6 (d)

DSR 3.3.2.7 (c)

b. Unit 3 Noble Gas DSR 3.3.2.1 Activity, (R-1S)

(a) 1 C DSR 3.3.2.4 DSR 3.3.2.6 (d)

DSR 3.3.2.7 (c)

3. Vapor Containment Atmosphere

a. Unit 2 Noble Gas Activity Monitor, providing .

ALARM and automatic (a) 1 K DSR 3.3.2.4 termination of release (g)

(R-42)

b. Unit 3 Noble Gas Activity (a) 1 K DSR 3.3.2.4 Monitor, providing (g)

ALARM and automatic

. termination of release (R-12)

IPEC ODCM D 3.3.2 .. 5 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 2 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1,2, and 3 INSTRUMENT APPLICABILITY REQUIRED CONDITIONS REFERENCED SURVEILLANCE and OR OTHER CHANNELS APPLICABLE UNIT PER FROM REQUIREMENTS SPECIFIED REQUIRED (1,2, or 3) CONDITIONS INSTRUMENT ACTION B.1

4. Unit 2 Main Plant Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor (R-44) (a) & (b) 1 C&G DSR 3.3.2.4 DSR 3.3.2.5 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (SV2-DPT, SV2-1-DPT, SV2-DPI) DSR 3.3.2.7

e. Sample Flow-Rate Monitor (a) 1 D . DSR 3.3.2.1 (Chem Totalizer) DSR 3.3.2.7

5. Unit 3 Main Plant Vent Radiation Monitor:

a. Noble Gas Monitor(s) DSR 3.3.2.1 (a) & (b) 1 C&G DSR 3.3.2.4 (R-14 or R-27)

DSR 3.3.2.5 Other Monitoring Equipment: DSR 3.3.2.7 (c)

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (from R-27's Kurz probes and DSR 3.3.2.7 RMBO processing computer)

(a) 1 D DSR 3.3.2.1

e. Sample Flow-Rate Monitor DSR 3.3.2.7 (Chem Totalizer)

IPEC aDCM D 3.3.2 - 6 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 3 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1,2, or 3) CONDITIONS INSTRUMENT ACTION B.1

6. Unit 1 Stack Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor (R-60) (a) 1 C DSR 3.3.2.4 DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (SV1-DPT, SV1-FR) DSR 3.3.2.7

e. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chern Totalizer) DSR 3.3.2.7

7. Unit 3 Radioactive Machine Shop (RAMS) Vent Radiation Monitor: DSR 3.3.2.1 DSR 3.3.2.4

a. Noble Gas Monitor (R-59) (a) 1 C DSR3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (from R-59's RMBO processor) DSR 3.3.2.7

e. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chern Totalizer) DSR 3.3.2.7 IPEC aDCM D 3.3.2-7 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 4 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APpLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER* CHANNELS FROM .. REQUIREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1,2, or 3) CONDITIONS INSTRUMENT ACTION B.1

8. Unit 3 Admin Bldg Vent (f)

Radiation Monitor: DSR 3.3.2.1 DSR 3.3.2.4

a. Noble Gas Monitor (R-46) (a) 1 C DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Sample Flow-Rate Monitor (8) 1 D DSR 3.3.2.1 (Chern Totalizer) DSR 3.3.2.7 NOTES (a) During release via this pathway. Channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the specified action for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, or CHANNEL OPERATIONAL TEST.

(b) During waste gas holdup system operation (treatment for primary system off-gases).

(c) Radioactive Calibration Standards used for channei' 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 who participate in measurement assurance activities with NIST are acceptable.

(d) The CHANNEL OPERATIONAL TEST for the Condenser Air Ejector monitors does NOT require a loss of sample flow test.

(e) The main Plant Vents for Units 2 and 3 monitors the Fuel Storage Building vents, in addition to ventilation from the Primary Auxiliary Buildings.

(f)* The Unit 3 Admin Bldg Controlled Area ventilation system does NOT have an installed process flow meter.

Default fan flow is used in lieu of a measurement, per ODCM Part II, Section 3.1.11.

(g) Most surveillance requirements for Vapor Containment monitors are located in Technical Specifications, Section 3.3.6. Source checks, however, are NOT required per Technical Specifications. Since these checks are valuable to ensure accurate quantification of VC Pressure Reliefs (as described below), a monthly source check requirement is listed here, in addition to the requirements of Technical Specifications.

Grab samples of the Vapor Containment atmosphere are routinely collected at least monthly and compared to the gas monitor for use in quantification of VC Pressure Reliefs (by scaling the monitor reading for each release to the reading obtained at time of grab sample). If the noble gas monitor is inoperable,a grab samples shall be taken. and analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to performing a Pressure Relief. During containment building ventilation in Modes 5 or 6, continuous monitoring and automatic termination of release is not required. In this condition, one continuous* monitor at the Plant Vent is sufficient.

IPEC aDCM D 3.3.2 - 8 Revision 2

Radioactive Effluents Total Dose 03.4.1 o 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 03.4.1 Radioactive Effluents Total Dose DLCO 3.4.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to ~ 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to ~ 75 mrem.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Estimated dose or dose A.1 Verify the condition resulting Immediately commitment due to direct in doses exceeding these radiation and the release limits has been corrected.

of radioactive materials in liquid or gaseous effluents exceeds the limits.

B. Required Action and B.1 --------------N OTE -------------

associated Completion This is the Special Report Time not met. required by 0 3.1.2, 0 3.2.2, or 0 3.2.3 supplemented with the following.

Submit a Special Report, 30 days pursuant to 0 5.3, including a request for a variance in accordance with the provisions of 40 CFR 190.

This submission is considered a timely request, and a variance is granted until staff action on the request is complete.

IPEC ODCM 03.4.1 - 1 Revision 2

Radioactive Effluents Total Dose D 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.4.1.1 Perform a cumulative dose calculation due to 12 months radioactive material in gaseous and liquid effluents to determine compliance with DLCO 3.4.1.

IPEC ODCM . D 3.4.1 - 2 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Monitoring Program DLCO 3.5.1 The Radiological Environmental Monitoring Program shall be conducted as specified In Table D 3.5.1-1.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Prepare and submit to the In accordance with Environmental Monitoring NRC in the Annual the Annual Program not conducted as Radiological Environmental Radiological specified in Operating Report, a Environmental Table D 3.5.1-1. description of the reasons Operating Report for not conducting the frequency program as required and the plans for preventing a recurrence.

B. Level of radioactivity in an B.1 ------------N 0 TES-------------

environmental sampling 1. Only applicable if the medium at a specified radioactivity/radionuclides location exceeds the are the result of plant reporting levels of effluents.

Table D 3.5.1-2 when averaged over any 2. For radionuclides other calendar quarter. than those in Table D 3.5.1-2, this report shall OR indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

IPEC ODCM D 3.5.1 -1 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME More than one of the Prepare and submit to the 30 days radionuclides in Table NRC, pursuant to D 5.3, a D 3.5.1-2 are detected in Special Report that the environmental (1) Identifies the cause(s) for sampling medium and exceeding the limit(s) and Concentration 1 + (2) Defines the corrective reporting level 1 actions to be taken to reduce radioactive concentration 2 + ... ~ 1.0 .. effluents so that the reporting level 2 potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Radionuclides other than Specifications D 3.1.2, those in Table D 3.5.1-2 D 3.2.2, or D 3.2.3.

are detected in an environmental sampling OR medium at a specified location which are the B.2 ------------NOTE S-------------

result of plant effluents and 1.0nly applicable if the the potential annual dose radioactivity/radionuclides to a MEMBER OF THE are not the result of plant PUBLIC from all effluents.

radionuclides is ~ the calendar year limits of 2. For radionuclides other Specifications D 3.1.2, than those in Table D 3.2.2 or D 3.2.3. D 3.5.1-2, this report shall indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

In accordance with Report and describe the the Annual condition in the Annual Radiological Radiological Environmental Environmental Operating Report. Operating Report frequency IPEC ODCM D 3.5.1 - 2 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or fresh leaf~ C.1 Identify specific locations 30 days vegetation samp es for obtaining replacement unavailable from one or sam~les ana add them to more of the sample the adiological locations required by Environmental Monitoring Table D 3.5.1-1. Program.

AND C.2 Delete the specific 30 days locations from which samples were unavailable from the Radiol~ical Environmental onitoring

. Program.

-AND C.3 Pursuant to D 5.2, submit In accordance with in the next Radioactive the Radioactive Effluent Release Report Effluent Release documentation for a Report change in the ODCM reflectin~ the new location s) with supporting information identifyinibthe cause of the unavaila ility of samples and {ustifying the selection of he new location(s) for obtaining samples.

D. Environmental samples D.1 Ensure all efforts are made Prior to the end of required in Table D 3.5.1-1 to complete corrective the next sampling are unobtainable due to action(s). period samplin equipment malfuncU Ions. AND D.2 Report all deviations from In accordance with the sam~ling schedule in the the Annual Annual adlological Radiological Environmental perating Environmental Report. Operating Report IPEC ODCM D 3.5.1 - 3 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Samples required by Table E.1 Choose suitable alternative 30 days D 3.5.1-1 not obtained in media and locations for the the media of choice, at the pathway in q'uestion.

most desired location, or at the most desired time.

E.2 Make appropriate 30 days substitutions in the Radiological Environmental Monitoring Program.

AND E.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a Report change in the ODCM reflecting the new location(s) with supporting information identifying the cause of t'he unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

IPEC ODCM D 3.5.1 ~4 Revision 2

Radiological Environmental Monitoring* Program D 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.1.1 Collect and analyze radiological environmental In accordance with monitoring samples pursuant to the requirements of Table D 3.5.1-1 Table D 3.5.1-1 and the detection capabilities required by Table D 3.5.1-3.

IPEC aDCM D 3.5.1 - 5 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 1 of 3)

Radiological Environmental Monitoring Program EXPOSURE NUMBER SAMPLING AND PATHWAY OF COLLECTION TYPE AND FREQUENCY AND/OR SAMPLES SAMPLE FREQUENCY OF ANALYSIS SAMPLE STATIONS LOCATIONS (a)

1. Direct 41 routine (1 ) An inner ring of stations Quarterly Gamma dose quarterly Radiation monitoring (DR1-DR16), one in each stations (b) meteorological sector in (DR1-DR41) the general area of the SITE BOUNDARY (2) An outer ring of stations (DR17-DR32), one in each meteorological sector in the 6 to 8 km range from the site (3) The balance of the stations (DR33-DR41), should be placed in special interest areas such as population centers, nearby re!jiidences, schools, and in one or two areas to serve as control stations

2. Airborne 5 locations (1 ) 3 samples (A1-A3) from Continuous sampler Radioiodine canister:

Radioiodine (A1-A5) locations close to the site' operation with sample Analyze weekly for 1-131 and boundary in different collection weekly or Particulates sectors, of the highest more frequently if Particulate sampler:

calculated annual average (1 ) Analyze for gross beta ground level D/Q required by dust loading radioactivity ;:::: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change (2) 1 sample (A4) from the (d).

vicinity of an established year-round community (2) Perform gamma isotopic having the highest analysis on each sample calculated annual average (e) in which gross beta ground level D/Q activity is > 10 times the previous yearly mean of (3) 1 sample (A5) from a control samples.

control location, approximately 15-30 km (3) Gamma isotopic analysis distant, and in the least of composite sample (e) prevalent wind direction (c) (by location) once per 3 months.

3. Waterborne

a. Surface (f) 1 sample Upstream (Wa1) Composite sample (1 ) Gamma isotopic (used as a Control Station) over a one month analysis of each sample period (g) (e) once per month.

1 sample* Downstream (Wa2)

(2) Composite and analyze for H-3 quarterly.

b. Drinking 1 sample Nearest water supply (Wb1) Grab sample: Monthly (1 ) Gross beta and gamma isotopic analyses(e) of each sample monthly.

(2) Composite and analyze for H-3*quarterly.

IPEC aDCM D 3.5.1 - 6 Revision'2

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 2 of 3)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY SAMPLING AND ANDIOR NUMBER OF SAMPLE COLLECTION TYPE AND FREQUENCY OF SAMPLE SAMPLES LOCATIONS (a) FREQUENCY ANALYSIS

3. Waterborne (continued)

c. Soil 2 samples Downstream area (Wc1) Twice per year at least 90 Gamma isotopic (e) from with existing or potential days apart and Sr-90 analyses Shoreline recreational value of each sample, semi-annually.

Upstream area (Wc2) control sample

d. Ground 1 sample Monitoring Well, SWof Semi-Annually Gamma isotopic (e),

Water Site Boundary (Lafarge) H-3, Ni-63, and Sr-90 6/09 analyses of each sample, semi-annually.

4. Ingestion

a. Milk (i) 3 samples from In 3 locations (la1-la3) milch animals within 5 km having the at MILK highest dose potential SAMPLING (human consumption)

LOCATIONS Twice per month when If there are none, animals are on pasture; then 1 sample In each of 3 areas (la1-la3) monthly at other times Gamma isotopic (e) and from milch 5 to 8 km distance, if 1-131 analyses of each animals at available, where doses are sample.

MILK SAMPLING calculated to be > 1mrem LOCATIONS per year (h) 1 sample from At a control location (la4), Concurrently, with a MILK approximately 15 to 30 km indicator locations SAMPLING distant, and in the least LOCATION prevalent wind direction

b. Fish and (1) 1 sample each In the vicinity of a plant Invertebrates from edible discharge area (lb1) portions of Sample in season, commercially or Gamma isotopic, recreationally or Ni-63, and Sr-90 important analyses of each species Semiannually sample (e) if sample is not seasonal (2) 1 sample of the If available in areas not same species influenced by plant discharge (lb2)

IPEC ODCM D 3.5.1 -7 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 3 of 3)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY SAMPLING AND AND/OR NUMBER OF SAMPLE COLLECTION TYPE AND FREQUENCY SAMPLE SAMPLES LOCATIONS (a) FREQUENCY OF ANALYSIS

4. Ingestion Grown nearest to each (continued) (1) Samples of 3 of 2 different offsite different kinds locations of highest

c. Food of broad leaf predicted annual Products vegetation (edible average ground level or inedible) (j) D/Q if milk sampling is Monthly Gamma isotopic (e) not performed (lc1-lc2) when available and 1-131 analyses (2) 1 sample of Grown 15 to 30 km each of the distant in the least similar broad prevalent wind direction leaf vegetation. if milk sampling is not performed (lc3)

(a) The code letters in parenthesis, e.g., DR1, A1 refer to sample locations specified in ODeM, Part II. Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent, shall be provided for each and every sample location in Table D 3.5.1-1. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position on Environmental Monitoring, 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 D5.1.

(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. Each of the 40 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 instrument for measuring and recording dose rate continuously. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; 2 or more phosphors in a packet are considered as 2 or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(c) The purpose of these samples 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, which provide valid background data, may be substituted.

(d) Airborne particulate sample filters shall be analyzed for gross beta activity 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.

(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" samples shall be taken near the intake structures as described in the ODeM. The

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

(g) In this program, a composite sample is one in which the quantity (aliquot) 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 ODeM.

(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 leaf 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.

IPEC aDCM D 3.5.1 - 8 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-2 (page 1 of 1)

Reporting Levels for Radioactivity in Environmental Samples **

AIRBORNE FOOD RADIONUCLIDE WATER FISH MILK PARTIUCLATE OR PRODUCTS ANALYSIS (pCi/L) GASES (pCi/m3) (pCi/kg, wet) (pCi/L)

(pCi/kg, 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 Ni-63 *** 300 1,000 Zn-65 300 20,000 Sr-90 *** 8* 40 Zr-95 400 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 8a-140 200 300 La-140 200 300 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

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

Sr-90 12 pCi/L 1-131 20 pCi/L These reporting levels are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment, per References 45 and 46.

IPEC aDCM D 3.5.1 - 9 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-3 (page 1 of 2)

Detection Capabilities for Environmental Sample Analysis (a) (e)

LOWER LIMIT OF DETECTION (LLDl (b) (c)

FOOD SOIL or AIRBORNE FISH RADIONUCLIDE WATER MILK PRODUCTS SEDIMENT PARTIUCLATE 9,R (pCi/kg, ANALYSIS (pCi/L) (pCi/L) (pCi/kg, wet) (pCilkg, dry)

GASES (pCi/m ) wet)

Gross Beta 4 0.01 H-3 2,000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Ni-63 (f) 30 100 Zn-65 30 260 Sr-90 (f) 1 5 5000 Zr-95 15 Nb-95 15 1-131 1 (d) 0.07 1 60 Cs-134 . 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 15 15 La-140 15 15 IPEC ODCM D 3.5,1 -10 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-3 (page 2 of 2)

Detection Capabilities for Environmental Sample Analysis Table Notation (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 Specification 0 5.1.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

(c) 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.

It should be recognized that the LLD is defined as an 2 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. 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 0 5.1.

(d) These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 for H-3 and 15 for 1-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

(f) Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment, per References 45 and 46.

IPEC aDCM D 3.5.1 - 11 Revision 2

Land Use Census D.3.5.2 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.2 Land Use Census DLCO 3.5.2 A land use census shall:

a .. Be conducted.

b. Identify 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> 50 m2 (500 ft2) 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 a garden census, per Table D 3.5.1-1, part4.c.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Land use census identifies A.1 Identify the new location(s) In accordance with locaticm(s) that yields a in the next Radioactive the Radioactive calculated dose, dose Effluent Release Report. Effluent Release commitment, or D/Q value Report greater than the values currently being calculated in DSR 3.2.3.1.

IPEC ODCM D3.5.2 -1 Revision 2

Land Use Census D 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Land use census identifies B.1 Add the new location(s) to . 30 days location(s) that yields a the Radiological calculated dose, or dose Environmental Monitoring commitment (via the same Program.

exposure pathway) a factor greater than 2 than at a location from which samples are currently B.2 Delete the sampling After October 31 of being obtained in location(s), excluding the the year in which the accordance with control station location, land use census was Table D 3.5.1-1. having the lowest conducted calculated dose, dose_

commitment(s) or D/Q

. value, via the same exposure pathway, from the Radiological Environmental Monitoring Program.

B.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a change Report in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

IPEC ODCM D 3.5.2 - 2 Revision 2

Land Use Census D 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.2.1 Conduct the land use census during the growing 366 days season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

DSR3.5.2.2 Report the results of the land use census in the In accordance with Annual Radiological Environmental Operating Report. the Annual Radiological Environmental Operating Report IPEC ODCM D 3.5.2 - 3 Revision 2

Interlaboratory Comparison Program 035.3 03.5 RADIOLOGICAL ENVIRONMENTAL MONITORING o 3.5.3 Interlaboratory Comparison Program DLCO 3.5.3 The Interlaboratory Comparison Program shall be described in the ODCM.

Ana!yses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Analyses not performed as A.1 Report the corrective In accordance with required. actions taken to prevent a the Annual recurrence to the NRC in Radiological the Annual Radiological Environmental Environmental Operating Operating Report Report:

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.3.1 Report a summary of the results obtained as part of In accordance with the Interlaboratory Comparison Program in the the Annual Annual Radiological Environmental Operating Report.' Radiological Environmental Operating Report IPEC ODCM 03.5.3 - 1 Revision 2

Solid Radwaste Treatment System .

D3.6.1 D 3.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System DLCO 3.6.1 The appropriate equipment of the Solid Radwaste Treatment System shall be in operation process wet radioactive wastes in accordance with the Process Control Program.

APPLICABILITY: During solid radwaste processing ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive solid waste A.1 Suspend shipments of Immediately does not comply with solid radioactive waste.

Process Control Program requirements.

IPEC ODCM D 3.6.1 - 1 Revision 2

Solid Radwaste Treatment System D 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.6.1.1 Verify solidification of specimens in accordance with Prior to each the Processing Control Program. shipment DSR 3.6.1.2 Record the following information for each class of Prior to each solid waste (as defined by 10 CFR Part 61) shipment shipped offsite during the Radioactive Effluent Release Report period:

a. Container volume,

b. total curie quantity (specify determined by

. measurement or estimate),

c. principal radionuclides (specify 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).

IPEC ODCM D 3.6.1 - 2 Revision 2

UNRESTRICTED AREA 04.1 04.0 DESIGN FEATURES o 4.1 UNRESTRICTED AREA 04.1.1 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.

A map representing the UNRESTRICTED AREA is shown in Figure 04.1-1 Information which will allow identification of structures and release points for radioactive gaseous and liquid effluents is shown in Figure 0 4.1-2.

04.1.2 For the purpose of satisfying 10 CFR Part 20, the "Restricted Area" is the same as the "Exclusion Area" defined in the FSARs.

IPEC ODCM 04.1 - 1 Revision 2

UNRESTRICTED AREA D 4.1 Figure 04.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS PLANT TRUE: 'NORTH NORTH .'. ~,,'

. ~ROAOWAY POft.lP~:

~

EXCLUSION. AREA-~"

'BOUNDARY~

I~r~i'---"""'----'-'--f------c.._ J tLECTRItAi..

swtrcBv~D U~,lIt 3; INtAt(E~

UNIT 3:

6/09 DISCHARGE~

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:

J:

GA$. PIPElIl'I.E '345 KV TRANSMISSION LINE B~()AOWAY PROPERTY LINE" ., .

EASEUENT/

EXCLlJSION ,AREA BOUNDARY .'

IPEC aDCM D 4.1 - 2 Revision 2

UNRESTRICTED AREA D 4.1 Figure D 4.1-2 MAP DEFINING RELEASE POINTS 0: GASEOUS EFF,LlJEN:r RE,LEA.SE POINT A I 'RWStO o ,

i N

DISCHARGE CANAL U-3 TURBINE BLDG.

!U-1TURBINE BLDG.

U-2 TURBINE BLDG_

U'1 INTAKE STRUCTURE SGli;FTv'*,;~,>;;"'STEAMGENERATOR BLO,WDOWN'FLASH TANKNENT 1li'""'~!*rrV;*;\SECO't.lDf'.R'Y~OI,LER BLOW~Q~~~~.RlfICJlTiON

'Cf"~4tJ'7*~~~0';lC?~tt~~'~~~c~~~~;;~~~~T;~;*.t~L : ' :, ....~.,:J;~(~.'{,

@~~~~~~~~~.t~~~~~

IPEC ODCM D 4.1 - 3 Revision 2

Annual Radiological Environmental Operating Report D 5.1 D 5.0 ADMINISTRATIVE CONTROLS D 5.1 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. Per the Technical Specification Reporting Requirements, 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.

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 D 3.5.1 and the plans for preventing recurrence.

A discussion of environmental sample measurements that exceed the reporting levels of Table D 3.5.1-2 but are not the result of plant effluents. .

A discussion of all deviations from the. sampling schedule of Table D 3.5.1-1.

A discussion of the contributing factors for cases in which the LLD required by Table D 3.5.1-3 was not achievable.

A discussion of identifiable nuclide peaks, including those of nuclides specified in Table D 3.5.1.:3.

The results of the land use census.

The corrective actions taken to prevent a recurrence if the Interlaboratory Comparison Program is not being performed as required.

The results of licensee participation in the Interlaboratory Comparison Program.

IPEC ODCM D 5.1 - 1 .Revision 2

Radioactive Effluent Release Report D5.2 D 5.0 ADMINISTRATIVE CONTROLS D 5.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include:

a. 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 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.

b. 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 magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution 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 onsite in a file that shall be provided to the NRC upon request

c. An assessment of the offsite radiation doses due to the radioactive liquid and gaseous effluent releases from the unit or station during the previous calendar year. This assessment shall include potential offsite dose determined with data collected from the Radiological Ground Water Monitoring Program (RGWMP).

d. 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 (Figure D 4.1-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports.

Gaseous pathway doses are determined from sampling and measurements at the exhaust points, coupled with the use of annual-averaged meteorological data collected from a period of live data to verify its validity. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

IPEC ODCM D 5.2-1 Revision 2

Radioactive Effluent Release Report D 5.2 D 5.2 Radioactive Effluent Release Report (continued)

e. The following information for each class of solid waste (in compliance with 10 CFR Part 61) shipped offsite during the report period:

1. Container volume,

2. total curie quantity (specify whether determined by measurement or estimate),

3. principal radionuclides (specify whether determined by measurement or estimate), .

4. source of waste and processing employed (e.g.,dewatered spent resin, compacted dry-waste, evaporator bottoms),

5. type of container (e.g., LSA, Type A, Type B, Large Quantity), and

6. solidification agent or absorbent (e.g., cement, urea formaldehyde).

f. 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.

g. A summary of data collected for the RGWMP, per D5.6 and NEI 07 Industry Ground Water Protection Initiative.

h. Any changes made during the reporting period to the Process Control Program (PCP) and to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification D 3.5.2.

IPEC ODCM D 5.2 - 2 Revision 2

Special Reports D 5.3 D 5.0 ADMINISTRATIVE CONTROLS D 5.3 Special Reports Special reports shall be submitted to the NRC Regional Administrator of the Region I Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the applicable Specification:

a. Radioactive Effluents (Specifications D 3.1, D 3.2 and D 3.4)

b. Radiological Environmental Monitoring (Specification D 3.5)

IPEC ODCM D 5.3-1 Revision 2

Major Changes to Radioactive Waste Systems

. D 5.4 D 5.0 ADMINISTRATIVE CONTROLS D 5.4 Major Changes to Radioactive Waste Systems Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Reportfor the period in which the change was made. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59, .

b. sufficient detailed information to totally support the reason forthe change without benefit of additional or supplemental information,

c. a detailed description of the equipment, components and processes involved and the interfaces with other plant systems, d 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,

e. . an evaluation of the change, whi9h shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto,

f. 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 in which the changes are to be made;

g. an estimate of the exposure to plant operating personnel as a result of the change,and

h. documentation of the fact that the change was reviewed and found acceptable by the OSRC ..

IPEC ODCM D 5.4-1 Revision 2

Process Control Program D 5.5 D 5.0 ADMINISTRATIVE CONTROLS D 5.5 Process Control Program Licensee initiated changes to the Process Control Program (PCP):

a. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

1. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,

2. a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes, and

3. documentation of the fact that the change has been reviewed and found acceptable by the OSRC.

b. Shall become effective upon review and acceptance by the OSRC.

D 5.6 Radiological Ground Water Monitoring Program (RGWMP)

The purpose of the RGWMP is to monitor, investigate, and characterize any contamination of groundwater from licensed radioactive material at Indian Point Energy Center (lPEC).

a. The program is also required in order to meet the following objectives:

The Nuclear Energy Institute Groundwater Protection Initiative (NEI-07-07),

American Nuclear Insurers Guideline for unmonitored releases (ANI 07-01),

EPRI Groundwater Protection Guidelines, (report #1015118, Nov 2007),

NRC Information Notice 2006-13, Groundwater Contamination Due to Undetected Leakage of Radioactive Water,

IPEC commitments to the NRC, Entergy Letter NL-06-033, "Current Status/Future Plans Regarding Onsite Groundwater Contamination at IPEG",

6/09

IPEC commitments to the NRC, Entergy Letter NL-08-079, "Remediation and Long Term Monitoring of Site Groundwater".

b. Specific monitoring objectives of the program include:

Monitoring the status of any known radiological groundwater plumes,

Detecting and quantifying previously unidentified sources of groundwater contamination, such as spills or leaks from a radioactively contaminated system, structure, or component,

Providing data to calculate potential offsite doses to a member of the public,

Monitoring and evaluating the long term effectiveness of remediation or intervention.

IPEC ODCM D 5.5-1 Revision 2

Radiological Ground Water Monitoring Program D 5.5 D 5.0 ADMINISTRATIVE CONTROLS D 5.6 Radiological Ground Water Monitoring Program (RGWMP) (continued)

c. Investigation and characterization activities are performed to evaluate and understand any groundwater contamination once it has been identified, or an event (such as a spill or leak) with the potential to contaminate the groundwater to levels above the investigation levels has occurred. Specific investigation and characterization objectives of the program in<;lude:

Determining the source(s) of groundwater contamination (eg, leaking radioactive components or systems, radioactive spills, or legacy soil/bedrock contamination),

Determining the locations;.extent, and concentrations of groundwater contamination (eg, plume definition),

6/09

Evaluating necessary corrective or investigative actions, utilizing the Corrective Action Program.

d. Station procedures shall include detailed information regarding the following:

The purpose and scope of the program, as defined above,

Location and periodicities of samples,

Required radionuclides for analysis, including limits of detection,

Guidance for communication of abnormal results,

Guidance regarding the generation of periodic summary reports.

e. Elements of the RGWMP program that intersect the REMP shall be included in the Annual Radiological Environmental Operating Report, per D 5.1.

f. An evaluation of the EFFLUENT impact, and a summary of the sample data from the RGWMP shall be included in the annual Radiological Effluent Release Report, as identified in ODCM D 5.2. . . .

IPECODCM D*5.5 - 2 Revision 2

Indian Point Energy Center Offsite Dose Calculation Manual Part I (REeS)

BASES

Applicability B 0 3.0 3.0 APPLICABILITY BASES DLCOs 3.0.1, 3.0.2, and 3.0.5, and DSRs 3.0.1, 3.0.2, and 3.0.3 reflect parallel requirements in the Technical Specifications. Refer to Technical Specification Bases for appropriate discussions.

ODCM Specification DLCO 3.0.3, in lieu of imposing a plant shutdown as paralleled in Technical Specifications, requires: (a) an Action to initiate efforts to restore compliance with the ODCM or associated Actions; and (b) an Action that requires entering the circumstances into the Corrective Action Program (CAP). These requirements ensure that the appropriate actions continue to be focused on and that the circumstances concerning failure to comply with the ODCM Actions would be reviewed. This review will be conducted in accordance with the procedural guidance for CAP Notifications.

There are no ODCM 3.0 Specifications that parallel Technical Specification LCO 3.0.4 or SR 3.0.4. Restrictions in entering MODES or other specified conditions in the Applicability have historically not been applied to ODCM Specifications. There are also no ODCM 3.0 Specifications that parallel Technical Specification LCO 3.0.6 and LCO 3.0.7, which allow for exceptions and revisions of other Technical Specifications. They are not applicable to the ODCM since it is not permitted to allow the ODeM to revise a Technical Specification.

(Note, currently no identified ODeM DLCOs support Technical Specification systems; however, this discussion is presented to address the philosophy that would be applied.) An allowance similar to Technical Specification LeO 3.0.6 does not apply to the ODeM. When a Technical Specification supported system LCO is discovered to be not met solely due to a ODeM support system DLCO not met, appropriate Technical Specification ACTIONS are required to be entered immediately. This applies even in instances where the ODCM contains a delay prior to declaring a Technical Specification supported system inoperable. In this case, certain ODeM inoperabilities may not directly impact the OPERABILITY of the Technical Specification supported system and delayed declaration of inoperability of the supported system is acceptable. In other cases, discovered support system inoperabilities that directly result in supported system inability to perform the safety function, should result in immediate declaration of inoperability of the supported system. .

Technical Specification LCO 3.0.7 has no parallel in the ODCM since it provides for explicit changes to specified Technical Specifications by the Section 3.1.8 Specifications. However, in the event that LCO 3.0.7 provides for changes to the Technical Specification MODE definitions by the Section 3.1.8 Specifications, the revised MODE definitions apply to all plant references, including ODCM references.

IPEC ODCM B 03.0-1 Revision 2

Liquid Effluent Concentrations

. B D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluent Concentrations BASES It is expected that the release of radioactive materials in liquid and gaseous effluents to UNRESTRICTED AREAS will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20 and should be as low as reasonably achievable (ALARA) in accordance with the requirement of 10 CFR 50.36a. While providing reasonable assurance that the design objectives will be met, these Specifications permit the flexibility of operation, compatible with considerations of health and safety, to ensure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels, but still less than ten times the effluent concentration limits (EC's) .

specified in 10 CFR Part 20. It is expected that using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive materials in liquid and gaseous wastes as low as reasonably achievable, releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience, taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with 10 CFR Part 50.36a.

The Indian Point site is a multiple-unit site. There exist shared radwaste treatment systems and shared effluent release points. Where site limits must be met, the effluents of all the units will be combined to determine site compliance. For instances where unit-specific information may be required for radwaste processed or released via a shared system, the effluents shall be proportioned among the units sharing the system(s) in accordance with the methods and agreements set forth in the ODCM.

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the EFFLUENT*

CONCENTRATIONS specified in 10 CFR Part 20. This limitation provides additional 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 1,10 CFR Part 50, to a member of the public and (2) the limits of 10 CFR Part 20.1302 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

This specification applies to the release of liquid effluents from all units on site.

IPEC ODCM B 0 3.1.1- 1 Revision 2

Liquid Effluents Dose D 3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.2 Liquid Effluents Dose BASES This Specification is provided to implement the requirements of Sections II.A, liLA and IV.A of Appendix I, 10 CFR Part 50. The DLCO implements the guides set forth in Sectionll.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 Ito assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable".

Also, for fresh water sites to UNRESTRICTED AREA 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 concentration 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 ODCM 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 equations specified in the ODCM 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 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.

In addition to the limiting conditions for operation, the reporting requirements specify that the licensee shall identify the cause whenever the dose from the release of radioactive materials in liquid waste effluent exceeds the above limits and describe the proposed program of action to reduce such releases to design objective levels on a timely basis ..

IPEC ODCM B D 3.1.2 - 1 Revision 2

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System BASES This Specification requires that the licensee maintain and operate appropriate equipment installed in the liquid waste systems, when necessary, to provide assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This Specification implements the requirements of 10 CFR 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 to 10 CFR Part 50 for liquid effluents.

IPEC ODCM B D 3.1.3 - 1 Revision 2

Liquid Holdup Tanks D 3.1.4 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks BASES The tanks listed in this Specification include 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. These tanks include the following: .

a. Refueling Water Storage Tanks

b. Primary Water Storage Tanks

c. 13 Waste Distillate Storage Tank

d. 14 Waste Distillate Storage Tank

e. 31 Monitor Tank

f. 32 Monitor Tank

g. Unit 3 CPF High Total Dissolved Solids Tank

h. Unit 3 CPF Low Total Dissolved Solids Tank

i. Any Outside Temporary Tank Restricting the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of any such tank's contents, the resulting concentration would be less than the limits of 10 CFR 20 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

IPECODCM B D 3.1.4-1 Revision 2

Gaseous Effluents Dose Rate D 3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate BASES 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 II.A 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 mrem/year 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.

This Control applies to the release of gaseous effluents from all units at the site.

IPEC ODCM B D 3.2.1 -1 Revision 2

Gaseous Effluents Dose - Noble Gas o 3.2.2 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.2 Gaseous Effluents Dose - Noble Gas BASES This Specification is provided to implement the requirements of Sections II.B, liLA, and IV.A of Appendix I to 10 CFR Part 50. The DLCO implements 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 to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The 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 form Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the 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 unit on site.

IPEC ODCM B 03.2.2 - 1 Revision 2

Gaseous Effluents Dose - Iodine and Particulate o 3.2.3 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.3 Gaseous Effluents Dose - Iodine and Particulate BASES This Specification is provided to implement the requirements of Section II.C, liLA and IV.A of Appendix I to 10 CFR Part 50. The DLCOs 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 to UNRESTRICTED AREAS will be kept "as low as reasonably achievable."

The ODCM calculational methods specified in the 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 thatthe 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 specifications for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuCiide 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 (applied where applicable), and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B 03.2.3-1 Revision 2

Gaseous Radwaste Treatment System D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System BASES This Specification requires that the appropriate portions of the Gaseous Radwaste Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Specification 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 Specification applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.4 - 1 Revision 2

Ventilation Exhaust Treatment System o 3.2.5 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.5 Ventilation Exhaust Treatment System BASES This Specification requires that the appropriate portions of the. Ventilation Exhaust Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Specification 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 Il.e of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from each reactor on site.

IPEC aOCM B 03.2.5 - 1 Revision 2

Gas Storage Tanks D 3.2.6 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.6 Gas Storage Tanks BASES The tanks included in this Specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by other specifications to a quantity that is less than the quantity that provides assurance that, in the event of an uncontrolled release of the tank's 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 assurances that, in the event of an uncontrolled release of the tank's 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 Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981, and NUREG 0133.

IPECODCM B D 3.2.6 - 1 Revision 2

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation BASES The radioactive liquid effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with methods set forth in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the EFFLUENT CONCENTRATION values specified in 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. 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.

IPEC ODCM B D 3.3.1 - 1 Revision 2

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 D 3.3 INSTRUMENTATION D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in 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 release rates corresponding to effluent dose rates of 0.5 Rem/yr whole body, and 3.0 Rem/yr to the skin.

This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.

IPEC ODCM B D 3.3.2 - 1 Revision 2

Radioactive Effluents Total Dose D 3.4.1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose BASES This Specification is provided to meet the dose limitation of 40 CFR Part 190 that has been incorporated into 10 CFR Part 20 by 46 FR 18525. The Specification requires the preparation and submittal of a special report whenever the calculated doses from plant-generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ,except the thyroid, which shall be limited to less than or equal to 75 mrem.

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 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 contribution 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, the special report 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 be a 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 Part 20, as addressed in Specifications D 3.1.1 and D 3.2.1. 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 nuclear fuel cycle.

IPEC ODCM B D 3.4.1 - 1 Revision 2

Radiological Environmental Monitoring Program D 3.5.1 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Radiological Environmental Monitoring Program BASES The radiological environmental monitoring program required by this specification 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.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. Program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 0 3.5.1-3 are considered optimum for routine environmental measurements in industrial laboratories.

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.

IPEC ODCM B D 3.5.1 - 1 Revision 2

Land Use Census D 3.S.2 D 3.S RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.S.2 Land Use Census BASES This specification 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 SO.

Restricting the census to gardens of greater than SO'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 .

IPEC ODCM B D 3.S.2-1 Revision 2

Interlaboratory Comparison Program D 3.5.3 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.3 Interlaboratory Comparison Program BASES 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 (developed using the guidance in Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April 1975) in order to demonstrate that the results are valid Jor the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

IPECODCM B D 3.5.3-1 Revision 2

Solid Radwaste Treatment System D 3.6.1 D 3.6 SOLID RADWASTE TREATMENT SYSTEM D 3.6.1 Solid Radwaste Treatment System BASES This Specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the process control program may include, but are not limited to, waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

IPEC ODCM B D 3.6.1 -1 Revision 2

-INDIAN POINT ENERGY CENTER OFFSITE DOSE CALCULATION MANUAL ODCM PART II - CALCULATIONAL METHODOLOGIES Revision 2

ODCM Part II - Calculational Methodologies 1.0 RADIATION MONITORS AND SETPOINTS 1.1 Effluent Monitoring System Description Information regarding effluent radiation monitor function and setpoint bases is provided in Tables 1-1 and 1-2. Additionally, Appendices Band C show a schematic of release pathways, including the relative position and application of these monitors.

1.2 Setpoints for Airborne Effluent Monitors Setpoints for airborne (gaseous) monitors are based on the permissible discharge rate as calculated in Section 3 of the ODCM, Part II, and shown in Appendix I. These setpoints are inherently conservative due to the assumed mixture (Table 3-8). They are tiered in such a way as to ensure proper (higher) authentication is obtained as the selected limit (and expected release rate) increases.

The Annual Limit is used to conservatively establish initial setpoints for routine operation.

For releases associated with unit shutdown, etc, additional permission may be obtained to apply the quarterly or instantaneous values, per Section 3.1.8. This method ensures operational control of releases, while precluding approaching the limits of D3.2.1.

The methodology identified in Section 3 and Appendix I is used to generate the following release rate limits (radiation monitor setpoint calculations only use the noble gas rates):

Conservative Permissible Discharge Rates (J.1Ci/sec) lodine/Particulate* Noble Gases T~l:1e of Limit Basis Unit 2 Unit 3 Unit 2 Unit 3 Annual Average ODCM, Part II, App I 4.01E-2 4.0SE-2 7.20E+3 3.S7E+3 Quarterly Average ODCM, Part II, App I 8.02E-2 8.10E-2 1.44E+4 7.14E+3 Instantaneous RECS 03.2.1 and App I 1.38E+1 1.38E+1 7.00E+4 7.00E+4

Half-lives greater than 8 days 1.2.1 The Plant Vent Wide Range Gas Monitor (R-27) reads in !-lCi/sec. Therefore, at unit 3, the alarm setpoints are set directly in !-lCi/sec. (Unit 2 does not apply alarm setpoints to R-27).

1.2.2 If the monitor reads and alarms in !-lCi/cc, the maximum alarm set point is calculated as follows:

S =D / [(F) * (4.72E+2)] where; S =Maximum alarm setpoint in !-lCi/cc D = Permissible discharge rate in !-lCi/sec F = Vent duct flow in fe/min 4.72E+2 = unit conversion factor (28317 cceminlfee60sec)

IPEC ODCM Page 1 of 136 Revision 2

aDCM Part II - Calculational Methodologies 1.2.3 If the monitor reads and alarms in cpm, then the maximum alarm setpoint is calculated as follows:

S = 0 I [(F) * (4.72E+2) * (CF)]

where:

S, 0, F, and 4.72E+2 are defined in the previous step CF =Rad Monitor Conversion Factor (/-lCi/cc per net cpm) 1.2.4 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.

1.2.5 During normal operation, the main plant vent is the only significant release point at either unit. 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.

If necessary, release rates may be apportioned (per 10CFR20 applicability to a site, rather than anyone unit) for maximum operational flexibility such that one unit "borrows" routine apportionment from the other unit. This evolution is controlled by station procedures, which require direct communication with the Shift Managers and the Chemistry Department.

1.3 Setpoints for Liquid Effluent Monitors 1.3.1 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 a!?cordance with 10CFR20.1302(2)(i).

1.3.2 Monitor setpoints are inherently conservative due to the routine use of determining dilution from Circulating Water Pumps at the applicable unit only.

In actuality, both Circulating and Service Water systems for the entire site contribute to site dilution.

IPEC aDCM Page 2 of 136 Revision 2

ODCM Part II - Calculational Methodologies 1.3.3 For monitors that read and alarm in /lCi/ml, setpoints are calculated as follows:

S = [(ADC) (F)] / [f] = Maximum alarm setpoint in /lCi/ml where:

F= Available discharge canal dilution flow for this release, in gpm f = calculated allowable release rate in gpm (Section 2.2.6)

ADC = The Allowed Diluted Concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (both gamma and beta emitters). This term is necessary to correct the MPCW due to the relatively insignificant effect of beta emitters on the radiation monitor, as desgibed in Section 2.2.6.

1.3.4 Alert or Warn 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 or Warn setpoint in /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.

Alert or Warn setpoints for other monitors are typically initially established at approximately 75% of the Alarm value.

IPEC ODCM Page 3 of 136 Revision 2

ODCM Part II - Calculational Methodologies TABLE 1 -1 Unit 2 Effluent Radiation Monitor System Data CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS RANGE EFFLUENT CONTROL FUNCTIONS 1E-7 to 1E-2 R-42 Containment Gas Monitor 72' Fan Bldg Containment Ventilation Isolation J..lCi/cc 1E-7 to 1E-2 Shuts RCV-014 (isolating gas tanks), stops VC R-44 Plant Vent Radiogas Monitor 88' Fan Bldg J..lCi/cc release fans and shuts VC vent/purge valves.

In-line detector on the air ejector 1 E-6 to 1E-1 Alarm diverts air ejector exhaust to VC and R-45 Condenser Air Ejector Monitor exhaust header J..lCi/cc secures steam to priming air ejector re-heaters.

Waste Gas Disposal System None. RECS 03.2.6 is assured by setpoint R-50 98' PAB 0.1 to 1E5 Ci Monitor basis per ODCM Part II, Sec 3.1.12.

Plant Vent Wide-Range Drawn from inside Plant Vent, 1E-7 t01 E+5 None. PV Concentration and release rate R-27 Monitor to 85' BAB J..lCi/cc information only, for accident applications.

Unit 1 Stack Vent Unit 1 Nuclear Services Bldg 1 E-7 to 1E-2 R-60 None Radiogas Monitor 100' Elevation J..lCi/cc Adjacent to service water return Fan Cooler Unit Service 1E-7 to 1E-2 R-46 / 53 line from V.C. fan cooler units and None Water Return J..lCi/cc motor coolers Component Cooling System Adjacent to line monitors on each 1E-6 to 1E-2 None. Setpoints are not based on effluent.

R-47 pump outlet pump outlet J..lC i/m I They are for ALARA and information only.

Component Cooling Heat 1E-7 to 1E-2 R-39 / 40 Exchanger Service Water 80' PAB None J..lCi/cc Monitors Waste Disposal Liquid Effluent 1E-7 to 1E-2 R-54 In-line monitor on 70' CSB Terminates Distillate Tank releases on alarm Monitor J..lCi/cc 1E-6 to 1E+2 R-49 SG Blowdown Monitor 15' Transformer Yard Housing Closes blowdown isolation valves J..lCi/cc Sec Boiler Blowdown 1E-7 to 1E-2 R-51 43' Superheater Bldg None Purification J..lCilcc Sec Boiler Blowdown 1E-7 to 1E-2 R-52 33' Superheater Bldg None Purification Sys SW J..lCi/cc IPECODCM Page 4 of 136 Revision 2

aDCM Part II - Calculational Methodologies TABLE 1 - 2 Unit 3 Effluent Radiation Monitor System Data CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS RANGE EFFLUENT CONTROL FUNCTIONS Samples drawn from 32 and 35 R-12 Containment Gas Monitor Containment Fan Coolers 1E-7 to 1E-1 /-lCi/cc Containment Ventilation Isolation In Plant Vent at approximately Secures waste gas tank release and R-14 Plant Vent Radiogas Monitor 1E-6 to 1E-1 /-lCi/cc Containment Ventilation Isolation 105' elevation On alarm, diverts air ejector exhaust to In-line detector on the air ejector VC and secures steam to priming air R-15 Condenser Air Ejector Monitor 1E-6 to 1E+O /-lCi/cc exhaust header ejectors re-heaters Waste Gas Disposal System Adjacent to line, on suction to None. This setpoint is based on limiting R-20 Monitor waste gas compressors 1E-2 to 1E+3 /-lCi/cc 50,000 Ci per tank, per RECS D3.2.6.

Plant Vent Wide-Range Secure waste gas tank release and R-27 Drawn from inside Plant Vent 1E-7 to 1E+5 /-lCi/cc Containment Ventilation Isolation Monitor 4th Floor Administration Building 1E+1 to 1E+6 cpm Administration Building Vent Monitor Exhaust Plenum for (typically 5.0E-8 to R-46 Radiogas Monitor None Controlled Areas 5.0E-2 IlCi/cc)

RAMS Building Vent Radiogas 55' RAMS Building Monitor R-59 Monitor Exhaust Plenum 1E-6 to 1E+2 /-lCi/cc None Adjacent to service water return Fan Cooler and Motor Cooler line from V.C. fan cooler units and 1E-7 to 1E-1 /-lCi/cc None R-16 AlB Service Water Return motor coolers Component Cooling System Adjacent to line monitors on each None. These setpoints are not based on R-17 AlB 1E-6 to 1E-1 /-lCi/ml pump outlet pump outlet effluent and are for information only.

Component Cooling Heat Adjacent to line, mounted on SW Exchanger Service Water return from Component Cooling 1E-7 to 1E-1 /-lCi/cc R-23 None Monitor Heat Exchanger Waste Disposal Liquid Effluent In-line monitor on monitor tank Terminates monitor tank release on alarm 1E-7 to 1E-1 /-lCi/cc R-18 Monitor recirc pump discharge PAB blowdown room monitors Closes blowdown isolation valves and SG SG Blowdown Monitor 1E-6 to 1E+2 /-lCi/cc sample valves R-19 steam generator blown Recirc line of HTDS/LTDS tanks Terminates HTDS or LTDS tank release.

CPF Regen Waste Release in CPF (used when primary to Applicable only in a primary to secondary 1E-7 to 1E-1 /-lCi/cc R-61 Monitor secondary leakage exists). leak, as defined in RECS D1.1.

IPEC aDCM Page 5 of 136 Revision 2

ODCM Part II - Calculational Methodologies 2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Information 2.1.1 A completed and properly authorized Liquid Radioactive Waste Permit is required prior to performing any BATCH release (a release of known volume and activity from an isolated source).

2.1.2 All activity determinations for liquid radioactive effluents are performed in such a manner as to be representative of the activity released to the river.

2.1.3 The radioactivity in liquid waste tanks shall be continuously monitored during release except as allowed by RECS D3.3.1. If the flowmeter is inoperable, the flow shall be estimated every four hours by difference in tank level or by discharge pump curves.

2.1.4 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.

2.1.5 Steam Generators or other CONTINUOUS releases shall be quantified and included in effluent reports, but do not require a pre-release permit. Continuous releases are typically quantified from periodic sampling and the* use of radiation monitoring. In Modes 4-6, however, SG Draindowns are typically quantified in BATCH mode.

2.1.6 Assurance that the combined liquid releases from Units 2 and 3 maintain compliance with 10CFR20 is provided by administrative controls which include an administrative minimum dilution of 100,000 gpm for any batch release, and routine use of unit-specific dilution flow for each permitted release.

Upon agreement between both Shift Managers, however, 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. When applying this shared policy, the Shift Managers require the details and duration of this evolution in writing at both CRS work stations.

2.1.7 Steam Generator Blowdown activity is determined by composite samples 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 the RECS. Due to appropriate compositing, total blowdown flow is then routinely multiplied by average concentrations to determine the actual effluent contribution from Steam Generator Blowdown.

2.1.8 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.

2.1.9 The discharge canal flow rate is determined by the use of pump flow characteristics curves. Actual monthly average flow rates and total gallons of dilution are determined by Programs and Components and delivered to Chemistry on a monthly basis. Unit 2 circulator pumps are operated at either low or high speed (approximately 88,000 to 140,000 gpm). Unit 3 circulator pumps have a variable speed capacity, and can produce a range from 65,000 to 140,000 gpm.

IPEC ODCM Page 6 of 136 Revision 2

ODCM Part II - Calculational Methodologies 2.1.10 Radioactivity content in outdoor tanks is to be limited to less than 10 curies, excluding tritium and noble gas, as per RECS D3.1.4.. 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 j.1Ci / curie = 7.3 x 10-3 j.1Ci / ml 358,500gal x 3785ml / gal 6

PWST: 10 curies x 10 j.1Ci / curie = 1.6 xl 0- 2 j.1Ci / ml 165,000gals x 3785mll gal.

31 & 32 Monitor Tanks (Unit 3):

10 curies x 106 j.1Ci / curie . 1

- - - - - - - - - = 2.2 x 10- j.1Ci / ml 11,750gals x 3785ml / gal 13 & 14 Waste Distillate Storage Tanks (Units 1/2):

10 curies x lO\lCi / curie 1

- - - - - - - - - = 1.1 x 10- )lCi! ml 23,577 gals x 3 785ml / gal Unit 3's Condensate Polisher High and Low Total Dissolved Solids Tanks:

10 curies x 106 j.1Ci / curie 2

- - - - - - - - - = 4.4 x 10- j.1Ci / ml 60,000gals x 3785ml / gal Outside Temporarv Tanks:

10 curies x 10-6 j.1Ci / curie

= j.1Ci / ml Volume (gal) x 3785ml / gal Integrated curies in a tank can similarly be determined by calculating the curies added from known inlet concentrations and volumes, which would then be combined with previously determined tank curie levels.

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.

IPEC ODCM Page 7 of 136 Revision 2

aDCM Part II - Calculational Methodologies 2.1.11 Turbine hall drains (from sumps in the five foot elevation for units 2 and 3) 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, however their effluent contribution should be evaluated.

Quantification of effluents is performed on this pathway during a Primary to Secondary Leak, as defined by RECS D1.1. In these cases, releases from this pathway would be quantified by periodic sampling multiplying the source term by a determination of the release rate to the river, generally bounded by secondary system loss or make-up rate.

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 D3.1.3. In this case, water at Unit 3 can be directed to the Condensate Polishing Facility prior to release. At Unit 2, a temporary processing" skid will need to be applied, or water directed to the Secondary Boiler Blowdown Purification System, or other installed cleanup system.

Activity released via this pathway is determined as follows:

Turbine Hall J (FeedwaterJ (steam Plant SG BlowdownJ Drain

( Effluent Activity

= Specific

Makeup - Rate to the Activity Rate River 2.1.12 Carbon 14 is released at a rate of .07 curies per GW(e)/yrwith 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.

2.1.13 Several normally non-radioactive systems are periodically analyzed for radioactivity.

Examples include Unit 3's Condensate Polisher regenerant waste tank, the Spent Fuel Pool Auxiliary Heat Exchanger Secondary Cooling Systems (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.

2.1.14 The Unit 3 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.

IPEC aDCM Page 8 of 136 Revision 2

ODCM Part II - Calculational Methodologies 2.1.15 Due to the addition of Hafnium control rods at Unit 3, an offsite dose may need to be calculated for Hafnium isotopes in waste pathways. In the absence of site-specific bioaccumulationand dose factors for Hafnium, factors for Zirconium are used, as .

suggested in ICRP 30. Should these calculations become necessary, they will be performed per the following sections, and manually added to other totals.

2.1.16 Investigations from the Radiological Ground Water Monitoring Program (RGWMP) have resulted in a determination of liquid effluent. A quantification and dose assessment of radioactive groundwater and 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 arid collective storm drain pathways are provided from modeling by hydrologists. Initially, a general precipitation mass balance model was applied to assess groundwater flow rates (Reference 32). During calendar year 2007, this model was calibrated usingan independent Darcy's Law model. Future determinations will continue to use a combination of these models at various depths, over effected zones, as discussed in Appendix J, Groundwater Flow and Offsite Dose Calculation Details.

Dilution flow is directly measured in the Discharge Canal, for any water directed there. For storm or 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 is applied. As discussed in Reference 33, this dilution is equivalent to 5.83E1 0 gallons per year, or 1.11 E5 gallons per minute.

Dose calculations are otherwise then completed per the following sections.

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 D3.1.1.

2.2.2 Compliance with the instantaneous limits of 10CFR20 is achieved by allocating dilution flow on a per unit basis, as described in Section 2.1.6. Compliance with 10CFR50 (quarterly and annual limitations) is assured by completing a monthly report which summarizes the time-average releases from the site.

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. At Unit 2, this duration is determined from station procedures with every batch release. At Unit 3, 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 tanks in lieu of the actual calculation:

11750 gals

2 Tank Volumes

=-------- -

39 u

. nours ~ 4 nours u

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.

IPECODCM Page 9 of 136 Revision 2

aDCM Part II - Calculational Methodologies 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, 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) * (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 compliance with RECS D3.1.1. The discharge canal concentration of radionuclides must be maintained less than those identified as limits (10 times the EC's of 10CFR20). The noble gas limit has been specified as 2E-4 uCi/ml.

These criteria are normally assured by using an Allowed Diluted 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 ADC= MPCWt:

CG or Totalactivity CG+CB

where:

ADC =Allowed diluted concentration in uCi/ml IPEC aDCM Page 10 of 136 Revision 2

ODCM Part II - Calculational Methodologies MPCWt = Maximum permissible concentration in water for all isotopes (beta & gamma), in uCi/ml, as defined in RECS, 01.1, as follows:

MPCWt Ci and MPCWi = Concentration and MPCW for each isotope CB =The concentration of the non gamma emitters, in uCilml 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

c. After the tank has been sampled, the Allowed Diluted Concentration is determined, per the equations above.

d. A determination of other liquid radioactive discharges is evaluated. If other releases are in progress at an affected unit, the radioactive concentrations and discharge rates are included to determine a potentially new required dilution factor.

e. Available dilution flow may be adjusted by physically using more pumps or altering an allocation fraction. Additionally, if required, release rate can be adjusted to comply with diluted concentration limits with existing dilution flow. Typically, however, these measures are not required.

f. 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 IPEC ODCM Page 11 of 136 Revision 2

aDCM Part II - Calculational Methodologies

g. The permissible discharge rate is calculated 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 J.1Ci/ml B = Adjusted dilution flow from the unit, in gpm, from Step 2.2.6.d, above, as follows:

Note: With no "other" releases, B simply ,

becomes the A vailable Dilution Flow.

2.3 Liquid Effluent Dose Calculation Requirements 2.3.1 RECS D3.1.2 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 anyorgan.

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.

c) 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 RECS D3.4.1.

2.3.2 RECS D3.1.3 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. 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

]

=

Current Month Dose + Previous months' Dose

+/-

[ mlajo.r d p anne 1

number of months used evolutions The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

IPEC aDCM Page 12 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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 near IPEC is considered to be fresh water when in reality it is a tidal estuary and never completely fresh. Observed average chlorosity at IPEC has ranged as high as2.5 gm/liter or about 13% sea water and 87% fresh water.

Hence, use of the Hudson River for fresh 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 IPEC). 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, RECS D3.1.2 reporting regulations for a 3 mile downstream limit do not apply. There is no exposures from ingestion of drinking water.

Thus, at IPEC, 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).

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 a time period:

m n D(T) = Ii=!

[Air *I k=l (dtk)(Cik)(Fk )]

Where:

m = The total number of isotopes released.

D(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 C ik 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.)

C ik = 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.

IPEC ODCM Page 13 of 136 Revision 2

ODCM Part II - Calculational Methodologies AiT = The site related ingestion dose commitment factor to the total body or any organ for each 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 C ik 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 AiTterms.

The term Fk is a total dilution factor and is determined as follows:

F = Liquid Radioact ive Waste Flow k [Discharge Structure Exit Flow

Applicable Facto r]

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" (a mixing factor in the near field), is 5.0.

For permitting and initial assessment of liquid effluent releases, Fk is first determined with dilution flow concurrent with applicable releases (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 AiT for 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 AiT for the total body and critical organ of the maximum exposed individual for Adult, Teen and Child doses.

Most factors needed in the equation were obtained from Regulatory Guide 1.109 with the following exceptions (see Section 2.6 and Ref 2,12,13, 14, and 25):

The fish and invertebrate bioaccumulation factors (BFi and Bl i) for Cesium, Niobium, Silver, and Antimony, were determined locally.

IPEC ODCM Page 14 of 136 Revision 2

aDCM Part II - Calculational Methodologies 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 summary dose factor is as follows:

AiT = K[(UF)BF; + (UI)BIJDf Where:

AiT = Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, mrem/hr per IlCilml.

K = Units conversion factor, 114155 = (1 E6pCi/uCi) * (1 E3ml/kg) 8760 hr/yr 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 pCi/1 from Table A-1 of Regulatory Guide 1.109.

UI = kg/yr invertebrate consumption from Table E-5 of Regulatory Guide 1.109:

5.0 Adult 1.7 Child 3.8 Teen o Infant Bli = Salt Water Invertebrates Bioaccumulation factor for nuclide, i, in pCi/kg per pCi/1 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.

IPEC has compiled AiT 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 IPEC. In addition, the values for Antimony, Silver, Cesium, and Niobium are site specific as previously discussed.

IPEC aDCM Page 15 of 136 Revision 2

ODCM Part II - Calculational Methodologies 2.5 Backup Simplified Dose Methodology 2.5.1 An alternate computer method which completely complies with Section 2.4 is available should the primary computer system be inoperable.

2.5.2 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 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 three facts; 1) the Hudson River at IPEC is not completely fresh, 2) the Bioaccumulation Factor for salt water is 40 (Ref. 2), and 3) the behavior of Cesium in the Hudson is a complex phenomenon, as dis,cussed below.

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 13if the Regulatory Guide values were used.

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.

IPEC ODCM Page 16 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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 IPEG 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.

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 Te-123m dose factors are not listed in Reg. Guide 1.109. Since this isotope is identified from potentially failed secondary startup sources and previously identified at IPEC, ingestion dose factors were derived from ICRP 30 and calculated per Ref 34.

2.6.6 In summary, with the exception of the bioaccumulation and dose factors discussed above, all remaining factors applied at IPEG are defined in Reg Guide 1.109 for a combination of fresh water fish and salt water invertebrates. .

IPEC ODCM Page 17 of 136 Revision 2

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.B2E-Ol 2.B2E-Ol 2.B2E-Ol 2.B2E-Ol 2.B2E-Ol 2.B2E-Ol BE-7 3.29E-Ol 7.45E-Ol 3.69E-Ol O.OOE+OO 7.B3E-Ol O.OOE+OO 1.28E+02 NA-24 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.0BE+02 4.08E+02 4.0BE+02 P-32 4.96E+07 3.0BE+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 2.5BE+OO 9.50E-Ol 5.72E+OO 1.OBE+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 1.73E+02 O.OOE+OO 4.36E+03 FE-55 3.2lE+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+Ol 1.20E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 6.65E+02 CU-64 O.OOE+OO 9.0BE+Ol 4.26E+Ol 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+Ol O.OOE+OO 4.27E+02 O.OOE+OO 9.87E+Ol BR-B3 O.OOE+OO O.OOE+OO 4.05E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 5.84E+Ol BR-84 O.OOE+OO O.OOE+OO 5.25E+Ol 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-B6 O.OOE+OO 1. OlE+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-ll 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+Ol 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-Ol 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 l.68E-Ol Y-91 8.89E+Ol 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+OO O.OOE+OO 4.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO . 5. 36E+04 ZR-95 1.63E+OO 5.22E-Ol 3.54E-Ol O.OOE+OO 8.20E-Ol 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+OO O.OOE+OO 2.65E+OO O.OOE+OO 1.63E+04 MO-99 O.OOE+OO 1.28E+02 2.43E+Ol O.OOE+OO 2.90E+02 O.OOE+OO 2.97E+02 TC-99M 1.59E-02 4.50E-02 5.73E-Ol O.OOE+OO 6.84E-Ol 2.21E-02 2.66E+Ol TC-IOI 1.64E-02 2.36E-02 2.32E-Ol O.OOE+OO 4.25E-Ol 1.21E-02 7.09E-14 RU-I03 1.lOE+02 O.OOE+OO 4.74E+Ol O.OOE+OO 4.20E+02 O.OOE+OO 1.2BE+04 RU-I05 9.16E+00 O.OOE+OO 3.62E+00 O.OOE+OO 1.18E+02 O.OOE+OO 5.60E+03 RU-I06 1.64E+03 O.OOE+OO 2.07E+02 O.OOE+OO 3.16E+03 O.OOE+OO 1.06E+05 AG-llOM 4.5BE+02 4.23E+02 2.51E+02 O.OOE+OO 8.32E+02 O.OOE+OO 1.73E+05 SB-122 3.47E+Ol 7.99E-Ol 1.20E+Ol 5.38E-Ol O.OOE+OO 2.08E+Ol l.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 SB-125 3.11E+02 3.47E+OO 7.40E+Ol 3.16E-Ol O.OOE+OO 2.40E+02 3.42E+03 IPEC aDCM Page 18 of 136 Revision 2

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 TE-125M 2.72E+03 9.87E+02 3.65E+02 8.19E+02 1.11E+04 O.OOE+OO 1.09E+04 TE-127M 6.88E+03 2.46E+03 8.38E+02 1.76E+03 2.79E+04 O.OOE+OO 2.31E+04 TE-127 1.12E+02 4.01E+01 2.42E+01 8.28E+01 4.55E+02 O.OOE+OO 8.82E+03 TE-129M 1.17E+04 4.36E+03 1.85E+03 4.01E+03 4.88E+04 O.OOE+OO 5.88E+04 TE-129 3.19E+01 1.20E+01 7.77E+00 2.45E+01 1.34E+02 O.OOE+OO 2.41E+01 TE-131M 1.76E+03 8.60E+02 7.16E+02 1.36E+03 8.71E+03 O.OOE+OO 8.53E+04 TE-131 2.00E+01 8.36E+00 6.32E+00 1.65E+01 8.77E+01 O.OOE+OO 2.83E+00 TE-132 2.56E+03 1.66E+03 1.55E+03 1.83E+03 1.60E+04 O.OOE+OO 7.83E+04 1-130 4.88E+01 1.44E+02 5.68E+01 1.22E+04 2.24E+02 O.OOE+OO 1.24E+02 1-131 2.68E+02 3.84E+02 2.20E+02 1.26E+05 6.58E+02 O.OOE+OO 1.01E+02 1-132 1.31E+01 3.50E+01 1.23E+01 1.23E+03 5.58E+01 O.OOE+OO 6.58E+00 1-133 9.16E+01 1.59E+02 4.86E+01 2.34E+04 2.78E+02 O.OOE+OO 1.43E+02 1-134 6.84E+00 1.86E+01 6.64E+00 3.22E+02 2.95E+01 O.OOE+OO 1.62E-02 1-135 2.86E+01 7.48E+01 2.76E+01 4.93E+03 1.20E+02 O.OOE+OO 8.45E+01 CS-134 4.14E+04 9.84E+04 8.04E+04 O.OOE+OO 3.18E+04 1.06E+04 1.72E+03 CS-136 4.33E+03 1.71E+04 1.23E+04 O.OOE+OO 9.51E+03 1.30E+03 1.94E+03 CS-137 5.30E+04 7.25E+04 4.75E+04 O.OOE+OO 2.46E+04 8.18E+03 1.40E+03 CS-138 3.67E+01 7.25E+01 3-.59E+01 O.OOE+OO 5.33E+01 5.26E+00 3.09E-04 BA-139 6.47E+00 4.61E-03 1.89E-01 O.OOE+OO 4.31E-03 2.61E-03 1.15E+01 BA-140 1.35E+03 1.70E+00 8.87E+01 O.OOE+OO 5.78E-01 9.73E-01 2.79E+03 BA-141 3.14E+00 2.37E-03 1.06E-01 O.OOE+OO 2.21E-03 1. 35E-03 1.48E-09 BA-142 1.42E+00 1.46E-03 8.93E-02 O.OOE+OO 1.23E-03 8.27E-04 2.00E-18 LA-140 1.58E+00 7.95E-01 2.10E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.83E+04 LA-142 8.07E-02 3.67E-02 9.15E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+02 CE-141 3.23E+00 2.18E+00 2.48E-01 O.OOE+OO 1.01E+00 O.OOE+OO 8.35E+03 CE-143 5.69E-01 4.21E+02 4.66E-02 O.OOE+OO 1. 85E-01 O.OOE+OO 1. 57E+04 CE-144 1.68E+02 7.04E+01 9.04E+00 O.OOE+OO 4.17E+01 O.OOE+OO 5.69E+04 PR-143 5.80E+00 2.33E+00 2.88E-01 O.OOE+OO 1. 34E+00 O.OOE+OO 2.54E+04 PR-144 1.90E-02 7.88E-03 9.65E-04 O.OOE+OO 4.45E-03 O.OOE+OO 2.73E-09 ND-147 3.97E+00 4.59E+00 2.74E-01 O.OOE+OO 2.68E+00 O.OOE+OO 2.20E+04 W-187 2.98E+02 2.49E+02 8.71E+01 O.OOE+OO O.OOE+OO O.OOE+OO 8.16E+04 NP-239 3.53E-02 3.47E-03 1.91E-03 O.OOE+OO 1.08E-02 O.OOE+OO 7.12E+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 1.21E+02 2.01E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.07E+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 4.05E-02 1.02E-02 3.74E-03 O.OOE+OO 1.20E-02 O.OOE+OO 3.78E+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 3.29E+01 2.15E+01 1.32E+01 2.88E+01 2.08E+02 O.OOE+OO 3.65E-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 IPEC aDCM Page 19 of 136 Revision 2

aDCM Part II -:- 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 3.5SE-01 S.02E-01 4.01E-01 O.OOE+OO S.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+OO 2.47E+OO 9.73E-01 6.34E+OO 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.SlE+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.S3E+04 2.S7E+05 CO-5S O.OOE+OO 5 .. 10E+02 1.lSE+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.04E+03 CO-60 O.OOE+OO 1.4SE+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 2.1SE+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+Ol 4.4SE+Ol 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 3.24E+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 BR-S3 O.OOE+OO O.OOE+OO 4.41E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-S.4 O.OOE+OO O.OOE+OO 5.55E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-S5 O.OOE+OO O.OOE+OO 2.34E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-S6 O.OOE+OO 1. 09E+05 5.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 RB-SS O.OOE+OO 3.12E+02 1.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-05 RB-S9 O.OOE+OO 2.01E+02 1. 42E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-07 SR-S9 2.79E+04 O.OOE+OO S.OOE+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.33E+03 SR-90 5.27E+05 O.OOE+OO 1. 30E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.4SE+04 SR-91 5.12E+02 O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+03 SR-92 1.94E+02 O.OOE+OO S.25E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.93E+03 Y-90 6.57E+OO O.OOE+OO 1.77E-01 O.OOE+OO O.OOE+OO 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+OO Y-91 9.64E+01 O.OOE+OO 2.58E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.95E+04 Y-92 5.S0E-01 O.OOE+OO 1.6SE-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+04 Y-93 1.S4E+OO O.OOE+OO 5.03E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.61E+04 ZR-95 1.68E+OO 5.29E-01 3.64E'-Ol O.OOE+OO 7.7SE-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+OO 2.70E+OO 1.48E+OO O.OOE+OO 2.61E+OO 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 2.9SE+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+OO O.OOE+OO 3.82E+OO 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 S.50E+04 AG-110M 4.45E+02 4.22E+02 2.56E+02 O.OOE+OO 8.04E+02 O.OOE+OO 1.1SE+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+OO 1.99E+02 1.16E+OO O.OOE+OO 4.45E+02 1. 03E+04 SB-125 3.27E+02 3.5SE+OO 7.64E+01 3.11E-01 O.OOE+OO 2.S5E+02 2.53E+03 IPEC aDCM Page 20 of 136 Revision 2

aDCM Part II - 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 TE-l25M 2.96E+03 1. 07E+03 3.96E+02 8.28E+02 O.OOE+OO O.OOE+OO 8.75E+03 TE-l27M 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.l9E+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 1-132 1.37E+01 3.58E+01 1.29E+01 1. 21E+03 5.64E+01 O.OOE+OO 1.56E+01 1-133 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 1-135 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 CS-138 3.93E+01 7.54E+01 3.77E+01 O.OOE+OO 5.57E+01 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-142 1. 52E+00 1.52E-03 9.33E-02 O.OOE+OO 1.28E-03 1.01E-03 4.65E-12 LA-140 1.67E+00 8.20E-01 2.18E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+04 LA-142 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+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+01 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 ND-147 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 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 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 IPEC aDCM Page 21 of 136 Revision 2

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-01 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+OO 2.70E+OO 7.37E-01 4.92E+OO 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 O.OOE+OO 3.07E+04 1.lOE+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 7.23E+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+OO 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+OO SR-89 3.63E+04 O.OOE+OO 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+03 SR-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+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+03 Y-90 8.79E+OO 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+OO 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+OO O.OOE+OO 6.69E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+04 ZR-95 2.10E+OO 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-02 O.OOE+OO 2.63E-02 O.OOE+OO 2.77E+03 NB-95 5.75E+OO 2.24E+OO 1.60E+OO O.OOE+OO 2.10E+OO 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-01 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+OO 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-110M 5.24E+02 3.54E+02 2.83E+02 O.OOE+OO 6.59E+02 O.OOE+OO 4.21E+04 SB-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+OO 2.29E+02 1.44E+OO O.OOE+OO 3.63E+02 4.09E+03 SB-125 4.22E+02 3.25E+OO 8.85E+01 3.91E-01 O.OOE+OO 2.35E+02 1. OlE+03 IPEC aDCM Page 22 of 136 Revision 2

ODCM 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+Ol 3.21E+01 6.00E+03 1.04E+02 O.OOE+OO 5.16E+Ol 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+Ol 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 9.79E-01 9.50E+02 BA-141 4.51E+00 2.53E-03 1.47E-01 O.OOE+OO 2.19E-03 1.48E-02 2.57E+00 BA-142 1.97E+00 1.42E-03 1.10E-01 O.OOE+OO 1.15E-03 8.35E-04 2.57E-02 LA-140 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+01 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 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 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 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 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 IPECODCM Page 23 of 136 Revision 2

aDCM Part II - 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 l.OOOE+02 BE-7 2.000E+OO 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-l29 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-131 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 1-130 1.500E+01 5.000E+01 CO-58 5.000E+01 1.000E+03 1-131 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 l.700E+03 1-135 l.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-136 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-138 2.240E+02 2.240E:+-02 BR-85 4.200E+02 3.100E+00 BA-139 4.000E+OO 1.000E+02 RB-86 2.000E+03 1.700E+01 BA-140 4.000E+OO 1.000E+02 RB-88 2.000E+03 1.700E+01 BA-141 4.000E+OO 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 SR-91 3.000E+01 2.000E+01 CE-141 1.000E+OO 6.000E+02 SR-92 3.000E+01 2.000E+01 CE-143 1.000E+OO 6.000E+02 Y-90 2.500E+01 1.000E+03 CE-144 1.000E+00 6.000E+02 Y-91M 2.500E+Ol 1.OOOE+03 PR-143 2.500E+Ol 1. OOOE+03 Y-91 2.500E+01 1.00OE+03 PR-144 2.500E+01 1.000E+03 Y-92 2.500E+Ol 1.00OE+03 ND-147 2.500E+01 1.000E+03 Y-93 2.500E+Ol 1.000E+03 W-187 1.200E+03 3.000E+Ol ZR-95 3.300E+OO 8.000E+01 NP-239 1.000E+Ol 1.OOOE+01 ZR-97 3.300E+OO 8.000E+Ol K-40 O.OOOE+OO O.OOOE+OO NB-95 3.000E+02 1.OOOE+02 CO-57 5.000E+01 1.000E+03 MO-99 1.000E+01 1.OOOE+Ol SR-85 O.OOOE+OO O.OOOE+OO TC-99M 1.500E+Ol 5.000E+Ol Y-88 O.OOOE+OO O.OOOE+OO TC-IOl 1.500E+01 5.000E+Ol NB-94 3.000E+02 1.OOOE+02 RU-103 1.000E+01 1.000E+03 NB-97 3.000E+02 1.OOOE+02 RU-I05 1.000E+01 1.OOOE+03 CD-109 O.OOOE+OO O.OOOE+OO RU-106 1.OOOE+01 1.000E+03 SN-1l3 O.OOOE+OO O.OOOE+OO AG-llOM 2.300E+00 5.000E+03 BA-133 O.OOOE+OO O.OOOE+OO SB-122 1.000E+OO 3.000E+02 TE-134 4.000E+02 1.00OE+02 SB-124 1.OOOE+OO 3.000E+02 CE-139 O.OOOE+OO O.OOOE+OO SB-125 1.000E+OO 3.000E+02 HG-203 O.OOOE+OO O.OOOE+OO Bio-Accumu1ation Factors and DFi's for Noble Gases 0 IPEC aDCM Page 24 of 136 Revision 2

ODCM Part II - Calculational Methodologies 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Releases - General Information 3.1.1 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, containment purge, or any other batch release.

3.1.2 Since Indian Point is a two unit site, the derived instantaneous f.lCi/sec limits for each unit, (Section 3.2) were derived from an actual site limit (Appendix I). The time-average limits are "per reactor", and applicable to each unit.

3.1.3 During Modes 4 through 6, there is no flowpath for a release from the Condenser Air Ejector. During these intervals, when there is no actual release pathway, the monthly grab sample described in RECS D3.2.1 is not required.

3.1.4 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 other pathways (see Appendix C).

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. Therefore, allocation of portions of the allowable release rate to these various release points during routine operation is not warranted.

If, on the other hand, the instantaneous release rate is being considered for the Plant Vent, then ALL release points should be considered when establishing alarm setpoints, 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.

A containment purge permit may be closed, with the release reclassified as continuous building ventilation, when activity in containment is sufficiently reduced to that level which, if released for 31-days, would remain BELOW the dose projection limits.

However, when plant conditions change, such that releases to containment are likely, a new permit should be evaluated.

3.1.6 Assurance that the combined gaseous releases from Units 2 and 3 do not exceed limits of Section 3.2.1 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 I.

IPECODCM Page 25 of 136 Revision 2

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 unique releases that may require the site limit for release rate. To better control these evolutions, written agreement to the apportionment is generally kept with each unit's CRS and included on applicable permits for the duration.

3.1.8 Conservative release rate limitations have been established to ensure compliance with 10CFR20, and to aid in controlling time average dose limits. The annual average release rate limit (Appendix I) shall normally be used for calculating limitations on discharge. If this limitation is unduly restrictive, other release rates may be allowed, per Appendix I, and summarized below:

Quarterly Average Site Operations Manager I designee Default Instantaneous General Manager, Plant Operations I designee ODCM Instantaneous GMPO and Chemistry Superintendent I designee As described in Appendix I, the ODCM instantaneous limit provides a maximum release rate with an actual or suspected isotopic mixture, back-calculated from the actual10CFR20 limit (500 mrem/yr for the site). The calculations for the use of this limit should be verified within the Chemistry department. The default interval in which to determine the proximity to this limit (uCi/sec or mrem/yr) is one hour or less.

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. The containment noble gas monitors (R-42 for Unit 2 and R-12 for Unit 3) are used in conjuction with expected flow rates to determine a release rate. The effluent noble gas monitor in the plant vent is also used to verify total unit release rate remains below the current authorized limit.

3.1.10 Composite Particulate Samples Continuous building ventilation exhaust points are sampled continuously for Iodine and Particulate. Media is replaced weekly, with composite filters prepared for vendor lab analyses monthly.

3.1.11 Flow rate measurement for the Continuous Building Ventilation systems is typically obtained from the installed process monitor or nearby instrument. When the process flow rate instrument is OOS, estimates are performed every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per the RECS, to allow appropriate quantification of continuous airborne effluent. The estimates are typically performed by summing the exhaust flow rates (or design flow rate) from any operable fans. Unit 3's PV flow may be estimated from a backup instrument.

Unit 3's Admin Bldg does NOT have a flow rate instrument (design flow of 12500 cfm is used). The process flow rate monitor surveillance requirements specified in the RECS are not applicable for the Unit 3 Admin Building.

IPEC ODCM Page 26 of 136 Revision 2

aDCM Part II - Calculational Methodologies 3.1.12 Gas Storage Tank Activity Limits The quantity of radioactivity in each gas storage tank is limited to 50,000 Ci of noble gas, Xenon-133 equivalent, per RECS D3.2.6. The source of this requirement is NUREG 0133 (Section 5.6.1) for both units. However, the parameters used in the given equation are applied differently at each unit, as defined in the FSARs and summarized in the following discussion:

Unit 2:

(500mrem)* 3.15E+7 sec/yr Q133= 3 = 29,761 Ci (IE6j.1Ci/Ci)(294mrem-m 3 / j.1Ci- yr)(1.81E-3 sec/m ) .

Where; 294 mrem-m3/IlCi-yr = the Xe-133 WB dose factor, RG 1.109, table B-1 (K).

1.81 E-3 sec/m 3 = Design Basis Accident X/Q from Indian Point 2 FSAR An actual curie limit is calculated by substituting the actual mixture Keff into the equation above. For example, the Keff for the accident mix computed using Table 14.2-5 of the FSAR is 476 mrem-m3/IlCi-yr. Thus, the actual activity limit (for an expected mixture of radionuclides, not just Xe-133) is: .

(500mrem)

3.15E + 7 sec/ yr Q133= 3 = 18,300 Ci (IE 6 j.1Ci/ Ci)(4 76 mrem - m 3 / j.1Ci - yr )(1. 81E - 3 sec/ m )

Similar calculations could be performed with actual Keff and X/Q data.

As demonstrated above, the setpoints calculated from NUREG 0133 modeling assume Xe-133 equivalent and no tank interconnections (29,761 Ci of Xe-133 equivalent or 18,300 Ci for an expected accident mixture).

However, the tanks are, in fact, generally interconnected, requiring a more conservative approach. The unit 2 FSAR (14.2.3) has established a specific gas decay tank limit of 6,000 Ci each. This value is based on the original RECS required 29,761 curies of Xe-133 equivalent, divided into 4 large and all 6 small gas decay tanks. Given the actual atmospheric volume of the tanks (525 fe for each large and 40 fe for each small), the total volume is approximately 4.5 tanks:

29,761

=.- = 6,000 C.. .

Xe-133 Equivalent 4.5 The RECS required gas storage tank radiation monitor (R-50), is therefore set to alarm at 6,000 curies. Warn setpoints are established by procedure, usually with consideration for measured tank contents and anticipated release rate.

IPEC aDCM Page 27 of 136 Revision 2

aDCM Part II -Calculational Methodologies In the event R-50 becomes inoperable, but a depressurized sample can be taken, the quantity limits can still be verified. Compliance with the appropriate curie limit in a tank is assured if the following inequality holds:

[A1m < 14.7 (0) or [A1eq < 14.7 (0133)

(14.7 + P)V (14.7 + P)V Where:

[A1m == total measured depressurized sample concentration (/-lCi/cc)

[A1eq == Xe-133 equivalent measured depressurized sample concentration (/-lCilcc)

V ~ tank volume (cc) P == tank pressure (psig) o == activity limit for selected mix (/-lCi) 0133 == dose equivalent Xe133 limit(/-lCi)

Unit 3:

. (500mrem)* 3.15E+7 seclyr Olt= = 50,000 Ci (lE6JlCi I Ci)(294mrem - m 3 I JlCi - yr)(l.03E - 3 secl m 3 )

Where; 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 This limit assumes 100% Xe-133 as per NUREG 0133. Utilizing the Ki from an expected mixture during RCS degasification (787 mrem-m3 per uCi-yr), the gas tank conservative administrative limit should becomes:

. (500mrem)* 3.15E+7 sec/yr Olt= = 19,400 Ci (IE6/lCi I Ci)(787mrem - m 3 I /lCi - yr)(l.03E - 3 sec/m 3 )

There are two methods available to ensure that the activity in the gas storage tank is within the conservative administrative limit:

1.94E+4*IE6/lCi/Ci

;---------;:--'------ =117E

. + 2 /lC'I 1 cc 525fe * (164.7 Psia]

2.83E4cc/ft 3 14.7psia

1. The total gaseous activity will normally be limited to less than 117 /-lei/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 /-lCi/cc. It allows for control of waste gas tank curie content by limiting the input concentration to 117 /-lCi/cc, thereby limiting the curies to 19,400.

IPEC aDCM Page 28 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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.

Gas releases may also occur from the gas space atop liquid holdup tanks. The basis for assuring these tanks comply with the curie limits for noble gas is Technical Specification 3.4.16, which limits Reactor Coolant to :::; 1 IlCi/gm Dose Equivalent lodine-131. Using the assumptions discussed in each unit's FSAR, the potential total curies of noble gas in the liquid holdup tanks is limited to less than the conservative limit for the Gas Storage Tanks.

3.1.13 The activity released via the blowdown flash tank vent is determined by obtaining the steam generator blowdown activity (tritium, noble gas, and iodine), 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 1".

3.1.14 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 CO 2form. While quantifiable based on the GW(e) per year, C-14 is exempt from the dose limits specified in the RECS. Nonetheless, 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. The airborne effluent dose calculation from C-14 emissions is performed using the fraction of carbon 14 released in the CO 2 form (26%).

3.1.15 The Unit 3 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 IlCi/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 IlCilml. No action

. is required if the inlet noble gas concentration is less than 2E-3 IlCi/ml. This gas release will be quantified by calculating the difference (in IlCi'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 separate 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.

Unit 2's Waste Distillate Storage Tanks are vented inside the Unit 1* facility, so there is no similar airborne release pathway from these tanks.

IPEC ODCM Page 29 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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 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 Slowdown), an Iodine partition factor (per Section 3.1.13), 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.

3.1.18 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 orother 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 3.1.13.

3.1.19 The Unit 3 Monitor Tank vents, both unit 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 RECS D3.2.1 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/yr to the total body and less than or equal to 3000 rt:lrem/yr to the skin; and b) For Iodine 131, H-3, and radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

These are SITE limits and normally apportioned appropriately between the units to simplify assurance of compliance with the RECS. The methodologies for performing these calculations are discussed in Sections 3.3.1 and 3.3.2, respectively.

3.2.2 RECS Section D3.2.2 requires that the air dose due to noble gas 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.

IPEC ODCM Page 30 of 136 Revision 2

ODCM Part II - Calculational Methodologies 3.2.3 RECS Section 03.2.3 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.

If either of the air dose or iodine/particulate dose cumulative limits is exceeded by a factor of two or more, then a cumulative dose evaluation is required from all contributions of direct radiation at the site boundary per RECS 03.4.1.

3.2.4 RECS 03.2.4 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.

RECS 03.2.4 requires that for each reactor unit, the appropriate portions of the 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.

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 d J

= +/- p anne

[ 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.

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, The site release rate is split to 50% per each unit, in terms of uCi/sec. Converted to actual mrem/yr dose rate, Unit 2's portion is 44.6%, with Unit 3 being allocated 55.4% (Unit 3 is slightly closer to the site boundary where dose rates are calculated).

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aDCM Part II - Calculational Methodologies 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 I. 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 that these are default unit portions of a site release rate limit. The entire site limit can be applied to anyone site, when required, per Section 3.1 and Appendix I).

~ [(Ki) * (%) * (Qi)] :5. unit specific mrem/yr whole body limit

~ [(Li + 1.lMi)*(%) * (Qi)] :5. unit specific skin limit, mrem/yr Where:

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per /-lCi/m 3 (unit-specific 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 /-lCi/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 /-lCi/m 3 (unit-specific 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 /-lCi/m 3 , per Table 3-7.

Qi = The release rate of radionuclides, i, in gaseous effluent for all release points in /-lCi/sec.

(X/Q) = For all vent releases, the highest calculated annual averaged relative concentration at the critical receptor (at a unit-specific distance and direction, in sec/m 3 , as shown on Page 1 of Appendix I).

The Ki, Li, Mi, and Ni factors were obtained from Table 8-1 of Regulatory Guide 1.109 and are included in this document as Tables 3-4,3-5,3-6, and 3-7 respectively. The gamma dose factgors (Ki and Mi) have a unit-specific finite cloud correction factor included, as discussed in Sections 3.5 and 3.6.

Unit specific dose rate limits, as stated in Appendix I are as follows:

Unit 2: mrem/yr whole body =234, skin limit =1194 mrem/yr Unit 3: mrem/yr whole body =266, skin limit = 1806 mrem/yr IPEC aDCM Page 32 of 136 Revision 2

aDCM Part II - Calculational Methodologies 3.3.1.2 These equations can also be expressed in the following manner:

(K) rQt) (X I Q) = mrem/yr dose to whole body (L + 1.1M)(X I Q)( Qt) =mrem/yr dose to skin Where:

Qt = The release rate of all noble gases summed together in )lei/sec, Le., the sum of all QL n

K = (l/Qt) L cQi) (Ki) i=1 n

L (1/Qt) L Q i) (Li) i=1 n

M (1/Qt) L Q i) (Mi) i=1 n

N (11 Qt) L (Q i) Ni) i=!

The values of K, L, M, and N are listed in Table 3-8 for the unrestricted area boundary, for both units.

3.3.2 Instantaneous Dose Rates 131. Part w/>8 day t% and H-3 !

The equation developed in this section is used to meet the calculational requirements of RECS 03.2.1. The critical organ is considered to be the child thyroid as stated in the RECS bases (803.2.1). Different dispersion factors are applied to the critical sector of the unrestricted area boundary for units 2 and 3. Therefore, while 50% of the site release limit (in Ci/sec) is applied to each unit, 32.8% of the limit is applied to Unit 2 and 67.2% to Unit 3 (per Appendix I). 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 for this dose rate determination, due to insignificant contribution compared to the inhalation pathway.

Utilizing the above assumptions, the dose rate equation reduces to the following:

L (Pi * (X/Q)

Qi) must be less than the unit-specific mrem/yr limit Where:

Unit-specific limits are 497 mrem/yr for Unit 2 and 1003 mrem/yr for Unit 3.

Pi = The dose parameter for radionuclides other than noble gases for the inhalation pathway in mrem/yr per )lCi/m 3 . These parameters (per Section 3.3.2.1) are calculated separately for each isotope, age group, and organ.

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aDCM Part II - Calculational Methodologies Qi = The release rate of radionuclide 131 and particulates, i, in gaseous effluents for all release points in /-lCi/sec.

X/Q = The unit-specific annual average dispersion parameter for the inhalation pathway at the controlling location due to all vent releases, per Section 3.5 and Appendix I.

3.3.2.1 Calculation of PiOn): Inhalation Dose Factor Pi (inhalation) =K' (BR) DFAi (mrem/yr per /-lCi/m 3 )

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-Tthrough 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 RECS 03.2.2. All noble gas releases at IPEC are assumed to be mixed mode unless indicated otherwise. Because the limits are in measured air dose (mrad), the magnitude of a measured effect is the same for all age groups.

Dispersion parameters are discussed in Section 3.5.

3.3.3.2 Equations for calculating the air 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 sector (a unit-specific location identified in Appendix I). These equations reduce to the following:

gamma air mrad = 3.17 E -8*L:Mi [(XlQ)(Qi) + (x/q) ('li) + (x/qmt)(,}imt)]

i beta air mrad = 3.17 E - 8*L:Ni [(XlQ) (Qi) + (x/q) ('li) + (x/qmt) ('li mt )]

Where:

Air dose limits are as follows:

Any Calendar Quarter Any Calendar Year Gamma Air Smrad 10 mrad Beta Air 10 mrad 20 mrad IPEC aDCM Page 34 of 136 Revision 2

aDCM Part II - Calculational Methodologies (X/Q) =The highest calculated annual average relative concentration for the unrestricted area boundary at the controlling sector for long term releases (greater than SOO hrs/yr or 1S0 hrs/qtr or as noted in 3.1.16), per Appendix I.

(x/q) = The relative concentration for the unrestricted area boundary for short term releases (equal to or less than SOO hrs/yr or 1S0 hrs/qtr and not random as defined in NUREG 0133, Section 3.3). This value is calculated as per Section 3.S.

(x/qmt)=The relative concentration for the unrestricted area boundary for ground level releases from Unit 3 Monitor Tanks at the critical receptor, in sec/m 3 , per* Section 3.S.3.

Mi = The weighted air dose factor due to gamma emission for each identified noble gas radionuclide in mrad/yr per f.lCi/m 3 .

This factor is unit-specific, per Table 3-6.

Ni = The weighted air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per f.lCi/m 3 .

qi mt = The total releases of noble gas radionuclides in Monitor Tank vents in f.lCi. 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 short term releases (equal to or less than SOO hrs/yr or 1S0 hrs/qtr and not random as defined in NUREG 0133, Section 3.3) from all vents, in f.lCi. 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 SOO hrs/yr or 1S0 hrs/qtr or as noted in 3.1.16) from all vents in f.lCi.

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 8-1 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 and therefore unit-specific.

3.3.4 Time Averaged Dose - Radioiodine 131. Part w/tY:! >8 days. and Tritium 3.3.4.1 The equations in this section are used to meet the calculational requirements of RECS D3.2.3.

IPEC aDCM Page 3S of 136 Revision 2

aDCM Part II - Calculational Methodologies 3.3.4.2 The pathways considered in this analysis are as follows:

'.J Pathwax~: }t;.: . , i.

'..: ::'~" Receptor"

....*... ., "," f; Inhalation, Ground Plane, Primary, Nearest Resident, per App I Vegetative Ingestion Inhalation, Ground Plane, Secondary Receptor at 5 mile, Vegatative, Cow;.Milk applied per the annual Land Use Census Ingestion The land use census identifies a high degree of commercial, industrial, and residential land usage in the area, and as such, the meat ingestion pathway is not considered.

Doses from the cow-milk pathway are included only if the applicable annual census has defined the pathway applicable. The methodology in nonetheless included here.

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:

(3.17 E - 08 )

L (Ri (W Oi + w qi) < 7.5 mrem in a calendar quarter (3.17 E - 08 )

L (Ri (W Oi + w qi ) < 15 mrem in a calendar year 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

~Ci. 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

~Ci. 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 applicable receptor for long term releases as defined in Section 3.1.16 and Appendix I.

w - The vent dispersion or deposition parameter for estimating the dose to an individual at the applicable receptor for short term releases as calculated as in Section 3.5 and defined in Section 3.1.16 and Appendix I.

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.

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ODCM Part II - Calculational Methodologies 3.3.4.4 Utilizing the assumptions contained in Section 3.3.4.3, these equations for the nearest resident and the 5-mile cow secondary receptor reduce to the following:

DN=(3.17E-8) ~)Ri(I)* [Wn(in)Oi + wn(in)qi]+ (Ri(G)+ Ri(V))*[Wn(dep)Oi +wn(dep)qi))

i DS=(3.17E-8) ~)Ri(I)* [Ws(in)Oi + ws(in)qi]+(Ri(G)+Ri(c)+Ri(V))* [Ws(dep)Oi + ws(dep)qi))

i Where:

DN = total dose at the nearest residence, in mrem DS = total dose at the 5-mile cow secondary receptor, in mrem.

Wn(in) = The highest calculated annual average dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area, as defined in Appendix I.

wn(in) = The dispersion parameter Wn(in), corrected for short term releases, as defined in Appendix I.

Wn(dep)= The highest calculated annual average deposition parameter for the nearest residence in the unrestricted area, as defined in Appendix I, for all isotopes except Tritium, which uses the X/Q value instead (Wn(in>>.

wn(dep)= The deposition parameter Wn(dep), corrected for short term releases, as defined in Appendix I.

Ws(in) = The highest calculated annual average dispersion parameter for the inhalation pathway at the 5-mile cow secondary receptor per Appendix I.

ws(in) = The dispersion parameter Ws(in), at the 5-mile cow secondary receptor, corrected for short term releases, as defined in Appendix I.

Ws(dep)= The highest calculated annual average deposition parameter for the 5-mile cow secondary receptor, as defined in Appendix I, for all isotopes except Tritium, which uses the X/Q value instead (Ws(in>>.

ws(dep)= The deposition parameter Ws(dep), at the 5-mile cow secondary receptor, corrected for short term releases, as defined in Appendix I.

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).

'iii = 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, defined in Section 3.3.4.5.

Ri (G): Ground plane pathway factor for each radionuclide, i, defined in Section 3.3.4.5. .

Ri (V): Vegetation pathway factor for each radionuclide, i, defined in Section 3.3.4.5.

Ri (C): Cow-Milk pathway factor for each radionuclide, i, defined in Section 3.3.4.5.

IPEC ODCM Page 37 of 136 Revision 2

aDCM Part II - Calculational Methodologies 3.3.4.5 Calculation of Dose Factors 3.3.4.5.a Calculation of Ri (I) (XlQ) Inhalation Pathway Factor Ri (I) (X/Q) = K'[(BR) a] [(DFAi) a](mrem/yr per I-lCi/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-5)

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.

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)(l- e(-kit)) m 2 *mrem/ yr RI( G)(D / Q) = Ki uCi/sec Where:

K' = A constant of conversion, 106 pCi/I-lCi.

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/m2).

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 3-13.

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aDCM Part II - Calculational Methodologies 3.3.4.S.c Calculation of Ri(V)(D/Q) - Vegetation Pathway Factor For non-Tritium isotopes:

Ri(V)(DIQ) = K:(r) *(DFLi)a*[(UaL)jL*e(-kitL) + (UaS)!g*e(-kith)]

YV(kl +kw)

Where:

K' = Constant of conversion, 106 pCi/IlCi r = Dimensionless correction factor for Iodine and Particulate from Table E-15 of Reg Guide 1.109: 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 .

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) (X/Q) = K'K"[(UaL)fL +(UaS)fg](DFLi)a (O.75)(O.5/H) (mrem/yr per IlCilm3)

Where:

K" = A constant of unit conversion, 1000 gm/kg IPEC aDCM Page 39 of 136 Revision 2

aDCM Part II - Calculational Methodologies 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 3-3a through 3-3d and Ri(V) values are listed in Table 3-11a through 3-11c.

Ri(V) Parameters Are From The Following Sources:

PARAMETER VALUE Reg Guide 1.109 Table r (dimensionless) 1.0 for iodines & 0.2 for part. E-15 (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 (dimensionless) 0.76 E-15 tL (seconds) 8.6E4 (1 day) E-15 th (seconds) 5.18E6 (60 days) E-15 Yv (kg/m2) 2.0 E-15 IPEC aDCM Page 40 of 136 Revision 2

aDCM Part II - Calculational Methodologies 3.3.4.S.d Calculation of Ri(c)(D/Q) - Grass-Caw-Milk Pathway Factor (applied only as required by the Land Use Census)

Ri(e) (D/Q) K(QF)(Uap)(Fm)(r)(DFLi)a *([!Pfs + 1- fpfs]

e(-kilh>>)

e(-kitj)

e(-kitj) ki+kw Yp Ys Where:

K' = Constant of conversion, 106 pCilJ,lCi QF = Cow's consumption rate in kg/day (wet weight)

Uap= Receptor's milk consumption rate for age (a) in liters/yr.

Yp = Agricultural productivity by unit area of pasture grass in kg/m 2

Ys = Agricultural productivity by unit area of stored feed in kg/m 2

Fm = Stable element transfer coefficients in dayslliters, Table_2-2.

r = Fraction of deposited activity retained on cow's feed grass.

(DFLi)a= The maximum organ ingestion dose for the radionuclide, I, for the receptor in age group (a) in mrem/pCi. Values are from Tables E-11 through E-14 of Regulatory Guide 1.109 and are listed in Tables 3-3a through 3-3d.

ki = Decay constant for the radionuclide in sec-1

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).

tf = The transport time from pasture, to cow, to milk, to receptor in sec.

th = The transport time from pasture, to harvest, to cow, to milk, to receptor, in sec.

fp = Fraction of the year that the cow is on pasture.

fs = Fraction of the cow feed that is pasture grass while the cow is on pasture.

Note: The values of Ri (c) are listed in Table 3-12a-d.

The concentration of Tritium in milk is based on the airborne concentration rather than the deposition. Therefore,.the Ri (c) is based on X/Q:

Ri (c) (X/Q) = K'K" (Fm) (QF) (Uap) (DFLi) a 0.75 (0.5/H) (mrem/yr per J.lCi/m 3 )

Where:

K" = A constant of unit conversion, 103 m/kg; IPEC aDCM Page 41 of 136 Revision 2

ODCM Part II - Calculational Methodologies H = Absolute humidity of the atmosphere in gm/m 3 ;

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; Other parameters and values are given above. The value of H may be considered as 8 grams/meter (NUREG 0133, PAGE 27) in lieu of site specific information.

Ri(c) Parameters Are Taken From The Following Sources:

PARAMETER VALUE TABLE R.G. 1.109 r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Fm (days/liter) Each stable element E-1 Uap (liters/year) - infant 330 E-5

- child 330 E-5

- teen 400 E-5

- adult 310 E-5 (Dfli) a (mrem/pCi) Each radionuclide E-11 to E-14 Yp (kg/m2) 0.7 E-15 Ys (kg/m2) 2.0 E,.15 tf (seconds) 1.73E5 (2 days) E-15 th (seconds) 7.78E6 (90 days) E-15 Qf (kg/day) 50 E-15 fs Assumed to be unity fp Assumed to be unity Stable Element Transfer data is listed in Table 3-2 (Reg Guide 1.109, Table E-1).

The (DFLi)a values for 4 age groups are given in Tables 3-3a through 3-3d.

IPEC ODCM Page 42 of 136 Revision 2

ODCM Part II - 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: While true instantaneous rates and limits generally apply, a one hour average can be chosen as the defining interval for determining process radiation monitor response or release rate determinations.

3.4.1.1 This section describes the alternative calculational methods to meet the requirements of Section 3.2.1 and the calculational results per Section 3.3.1.

3.4.1.2 To determine an acceptable noble gas instantaneous release rate in f.lCi/sec, a standard isotopic mixture of noble gas is 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 weighted values of K, L, M, and N is determined using the technique presented in paragraph 3.3.1.2, and the Ki, Li, Mi, and Ni values from Tables 3-4 through 3-7. The data and results of this calculation are shown in Table 3-8.

3.4.1.3 Utilizing the equations from Paragraph 3.3.1.2 and the values from Table 3-8, conservative IPEC maximum (site) release limits for all noble gases in f.lCi/sec are calculated in Appendix I, page 2.

The resulting calculations establish a default instantaneous noble gas release rate limit of 140,000 f.lCi/sec for the site, split equally between the units for conservativism. While both Units 2 and 3 originally apply the instantaneous limit at 70,000 f.lCi/sec, anyone unit can use up to nearly 100% of the site limit, should it become necessary.

Generally, as these limits begin to apply, actual sample data is used to determine the true instantaneous limit associated with 10CFR20 requirements, for both whole body and skin dose rate, as shown in Appendix I.

3.4.1.4 For individual release rate determinations, alternate computer codes and/or a procedurally driven hand calculation template serve as back up methodologies should the primary computer method be inoperable. These methods comply with calculations in Section 3.3.

3.4.2 Instantaneous Dose Rates-I-131. Particulates w/t% >8 days. & H-3 3.4.2.1 This section describes the alternative calculational method to meet the requirements of Section 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.

IPEC ODCM Page 43 of 136 Revision 2

aDCM Part II - Calculational Methodologies 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 a) 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 b) VC iodines and long lived particulates are less than 1E-7 f.lCi/cc.

Both these conditions have historically been the case, assuring that noble gas activity continues to be more limiting.

3.4.2.3 Backup instantaneous dose rate calculations can be performed with an alternate computer code or by formatted hand calculations which 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 either unit's Plant Vent (PV) mixed mode releases, and the potential Unit 3 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:

PVKi = (Ki) * (X IQ)PV and MTKi = (Ki) * (X I Q)MT PVLi = (Li) * (X I Q)PV and MTLi = (Li)*(XIQ)MT PV Mi = (Mi) * (X I Q)PV and MTMi = (Mi) * (XIQ)MT PV Ni = (Ni) * (X I Q)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 f.lCilm3 (unit-specific finite cloud correction used).

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide in mrem/yr per f.lCi/m3.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per f.lCi/m3 (unit-specific finite cloud correction used).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per f.lCi/m 3.

IPEC aDCM Page 44 of 136 Revision 2

ODCM Part II - Calculational Methodologies (X/Q)PV = The highest calculated annual average dispersion parameter for the noble gas pathway at the unrestricted area boundary, applicable to plant vent mixed mode releases, per Appendix I.

(X/Q)MT = The highest calculated annual average X/Q for ground level monitor tank noble gas release pathway, 5.00E-5 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:

PV Kt = ~)Ki * (Ci / Ct)]

PV Lt = L [Li * (Ci / Ct)]

PV Mt = L[Mi * (Ci / Ct)]

PV Nt = L[Ni*(Ci / Ct)]

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 PV or 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 approved alternate computer codes to compute all or part of the dose calculation.

3.4.3.4 Resultant doses are compared 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'lh. 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.

IPEC ODCM Page 45 of 136 Revision 2

ODCM Part II - Calculational Methodologies 3.4.4.2 If the primary computer method is inoperable, dose calculations can be performed by 1) an alternate computer code which complies with Section 3.3.4, using all identified Iodine and Particulate isotopes; or 2) hand calculations (via a formalized departmental procedure) which comply with Section 3.3.4.

3.4.4.3 Quarterly and annual Iodine, Particulate, and Tritium dose contributions are summed and compared to 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.

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 Safety (Draft Regulatory) Guide 1.23 (Ref. 18).. The data recovery index for these periods was in excess of 99%.

Comparison of the new meteorological data (1992 to 2002) with previous data (1981 to 1990) 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.

IPEC ODCM Page 46 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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 I.

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 5.00E-5 sec/m 3 (concentration X/Q per Ref. 21). This value is specific only to the Unit 3 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, a hypothetical grass-cow-milk pathway and its dispersion and deposition factors are included, but turned on or off according to the applicable annual Land Use Census. Dispersion and deposition parameters for these locations were calculated using the models and data described in Sec. 3.5.2, and are*

represented as:

Wn(in) = The highest calculated annual average dispersion parameters for the inhalation pathway for the nearest residence in the unrestricted area, per Attachment I.

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 I. For Tritium in the vegetation pathway, Wn(in) is used.

Ws(in) = The highest calculated annual average dispersion parameters for the inhalation pathway at the 5-mile cow secondary receptor, per Attachment I.

Ws(dep)= The highest calculated annual average deposition parameters for the cow-milk, vegetation, and ground plane pathways at the 5-mile secondary receptor, per Attachment I. For Tritium at this location, Ws(in) is used.

NOTE: For the monitor tank pathway, iodines and particulates are effectively removed by demineralization, therefore deposition parameters for this pathway are not applicable.

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.

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ODCM Part II - Calculational Methodologies 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 = [NTOTALl8760]m Where:

F = The non-dimensional correction factor used to convert annual average dispersion or deposition factors to short term dispersion or deposition factors.

NTOTAL = The total duration of a short-term release (or releases) in hours, during a chosen reporting period.

10g(ANMX / F15MX) m =

10g(8760) 8760 = The total number of hours in a year.

ANMX = The calculated historical average dispersion (sec/m3) 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 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 1O-year hourly meteorological data. They are documented in detail in Reference 17.

Note that in line with the guidance in NUREG-0133, 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 ODCM 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.

IPEC ODCM Page 48 of 136 Revision 2

aDCM 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/m 3 1.590E-4 sec/m 3 ANMX = 2.219E-6 sec/m 3 4.470E-6 sec/m 3 log(ANMX / F15MX) m= = - 0.391 - 0.393 log(8760)

F= [NTOTAU8760]..o*391 [NTOTAU8760rO.393 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/m 3 log(ANMX / F15MX) m= - 0.428 -0.427 log(8760)

F= [NTOTAU8760rO. 428 [NTOTAU8760rO. 427 c) Nearest Residence Deposition:

IPEC aDCM Page 49 of 136 Revision 2

aDCM Part II - Calculational Methodologies o2 F15MX = 3.995E-7 m*2 4.019E-7 m o2 ANMX = 7.517E-9 mo2 7.451 E-9 m m=

log(ANM¥ / F15M¥) = _ 0.438 -0.439 log(8760)

F= [NTOTALl8760rO. 438 [NTOTALl8760rO. 439 IPEC aDCM Page 50 of 136 Revision 2

aDCM Part II - Calculational Methodologies d) 5-mile Inhalation:

Same for both Units 2 and 3 F15MX = 6.192E-6 sec/m 3 ANMX = 7.223E-7 sec/m 3 log(ANMX / F15MX) m= -0.237 log(8760)

F = [NTOTALl8760rO.237 e) 5-mile Deposition:

Same for both Units 2 and 3 F15MX = 9.501 E-9 m-2 ANMX = 1.350E-9 m-2 log(ANMX / F15MX) m=

log(8760)

= - 0.215 F = [NTOTALl8760rO. 215 f) The slopes (Urn") for ground level short term correction factors can be calculated in a similar fashion, from ground level data found in Reference 17. For example:

Unit 2 Unit 3 Site Boundary Noble Gas: -0.390 -0.397 Nearest Resident Inhalation: -0.427 -0.427 Nearest Resident Deposition: -0.455 -0.455 5-mile Inhalation: -0.235 -0.235 5-mile Deposition: -0.212 -0.212 IPEC aDCM Page 51 of 136 Revision 2

ODCM Part II - Calculational Methodologies 3.6 Justification for and Use of Finite Cloud Assumption for Assessing Site Boundary 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 IPEC site boundary.

For the Unit 3 Monitor Tank pathway (ground release concentration X/Q), 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 X/Q value may be used as described in Reference 21.

IPEC ODCM Page 52 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-1a ADULT INHALATION DOSE FACTORS (mrem 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+OO 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-10 2.29E-11 O.OOE+OO 1. 63E-10 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-10 2.62E-11 1.14E-11 O.OOE+OO O.OOE+OO 7.00E-07 1.54E-06 Cu-64 O.OOE+OO 1.83E-10 7.69E-11 O.OOE+OO 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 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-13 O.OOE+OO 5.27E-12 1.15E-07 2.04E-09 Br-83 O.OOE+OO O.OOE+OO 3.01E-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.90E-OS Br-84 O.OOE+OO O,OOE+OO 3.91E-OS 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 2.4lE-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.1SE-19 Rb-89 O.OOE+OO 3.20E-08 2.12E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-21 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-05 Sr-91 7.74E-09 O.OOE+OO 3.13E-10 O.OOE+OO O.OOE+OO 4.56E-06 2.39E-05 Sr-92 S.43E-10 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-91m 3.26E-11 O.OOE+OO 1.27E-12 O.OOE+OO O.OOE+OO 2.40E-07 1.66E-10 Y-91 S.78E-05 O.OOE+OO 1.S5E-06 O.OOE+OO O.OOE+OO 2.13E-04 4.81E-05 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.lSE-OS O.OOE+OO 3.26E-10 O.OOE+OO O.OOE+OO 6.06E-06 5.27E-05 Zr-9S 1.34E-OS 4.30E-06 2.91E-06 O.OOE+OO 6.77E-06 2.21E-04 1.S8E-OS Zr-97 1.21E-08 2.45E-09 1. 13E-09 O.OOE+OO 3.7lE-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 S.26E-07 O.OOE+OO 9.67E-07 6.31E-OS 1.30E-OS Mo-99 O.OOE+OO 1.51E-OS 2.87E-09 O.OOE+OO 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 O.OOE+OO 5.52E-12 9.S5E-08 S.20E-07 Tc-101 S.22E-1S 7.52E-15 7.38E-14 O.OOE+OO 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 O.OOE+OO 8.23E-08 O.OOE+OO 7.29E-07 6.31E-OS 1.38E-OS Ru-10S 9.88E-11 O.OOE+OO 3.89E-11 O.OOE+OO 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 O.OOE+OO 1. 09E-06 O.OOE+OO 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.3SE-06 1.2SE-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-OS 1.58E-06 6.7SE-09 O.OOE+OO 2.18E-04 1.26E-05 IPEC aDCM Page 53 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-la ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-12Sm 4.27E-07 1.9SE-07 S.S4E-OS 1. 3lE-07 1.SSE-06 3.92E-OS S.S3E-06 Te-127m 1.SSE-06 7.2lE-07 1. 96E-07 4.lIE-07 S.72E-06 1.20E-04 1.S7E-OS Te-127 1.7SE-lO S.03E-ll 3.S7E-ll 1.32E-lO 6.37E-IO S.14E-07 7.l7E-06 Te-129m 1.22E-06 S.S4E-07 1. 9SE-07 4.30E-07 4.S7E-06 1.4SE-04 4.79E-OS Te-129 6.22E-12 2.99E-12 1.SSE-12 4.S7E-12 2.34E-ll 2.42E-07 1.96E-OS Te-13lm S.74E-09 S.4SE-09 3.63E-09 6.SSE-09 3.S6E-OS 1.S2E-OS 6.9SE-OS Te-13l 1.39E-12 7.44E-13 4.49E-13 1.l7E-12 S.46E-12 1.74E-07 2.30E-09 Te-132 3.2SE-OS 2.69E-OS 2.02E-OS 2.37E-OS 1.S2E-07 3.60E-OS 6.37E-OS 1-130 S.72E-07 1.6SE-06 6.60E-07 1.42E-04 2.6lE-06 O.OOE+OO 9.6lE-07 1-131 3.lSE-06 4.47E-06 2.S6E-06 1. 49E-03 7.66E-06 O.OOE+OO 7.SSE-07 1-132 1.4SE-07 4.07E-07 1. 4SE-07 1. 43E-OS 6.4SE-07 O.OOE+OO S.OSE-OS 1-133 1.OSE-06 1.SSE-06 S.6SE-07 2.69E-04 3.23E-06 O.OOE+OO 1.lIE-06 1-134 S.OSE-OS 2.l6E-07 7.69E-OS 3.73E-06 3.44E-07 O.OOE+OO 1.26E-lO I-13S 3.3SE-07 S.73E-07 3.2lE-07 S.60E-OS 1.39E-06 O.OOE+OO 6.S6E-07 Cs-134 4.66E-OS 1. 06E-04 9.l0E-OS O.OOE+OO 3.S9E-OS 1.22E-OS 1.30E-06 Cs-136 4.SSE-06 1.S3E-OS 1.3SE-OS O.OOE+OO 1.07E-OS 1.S0E-06 1.46E-06 Cs-137 S.9SE-OS 7.76E-OS S.3SE-OS O.OOE+OO 2.7SE-OS 9.40E-06 1.0SE-06 Cs-13S 4.14E-08 7.76E-OS 4.0SE-08 O.OOE+OO 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-lO S.32E-14 3.42E-12 O.OOE+OO 7.7BE-14 4.70E-07 1.12E-07 Ba-140 4.8SE-06 6.13E-09 3.2lE-07 O.OOE+OO 2.09E-09 1.S9E-04 2.73E-OS Ba-14l 1. 2SE-ll 9.41E-IS 4.20E-13 O.OOE+OO S.7SE-IS 2.42E-07 1.4SE-17 Ba-142 3.29E-12 3.38E-IS 2.07E-13 O.OOE+OO 2.S6E-IS 1.49E-07 1.96E-26 La-140 4.30E-08 2.l7E-08 S.73E-09 O.OOE+OO O.OOE+OO 1.70E-OS S.73E-OS La-142 8. S4E-ll 3.88E-ll 9.6SE-12 O.OOE+OO O.OOE+OO 7.9lE-07 2.64E-07 Ce-14l 2.49E-06 1.69E-06 1.9lE-07 O.OOE+OO 7.S3E-07 4.S2E-OS 1.SOE-OS Ce-143 2.33E-08 1.72E-08 1.9lE-09 O.OOE+OO 7.60E-09 9.97E-06 2.S3E-OS Ce-144 4.29E-04 1.79E-04 2.30E-OS O.OOE+OO 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 S.SOE-OS O.OOE+OO 2.70E-07 3.SlE-OS 2.S0E-OS Pr-144 3.76E-12 1.S6E-12 1.9lE-13 O.OOE+OO S.SlE-13 1.27E-07 2.69E-18 Nd-147 6.S9E-07 7.62E-07 4.S6E-OS O.OOE+OO 4.4SE-07 2.76E-OS 2.16E-OS W-187 1. 06E-09 8.8SE-IO 3.l0E-lO O.OOE+OO O.OOE+OO 3.63E-06 1. 94E-OS Np-239 2.87E-OS 2.82E-09 1.SSE-09 O.OOE+OO S.7SE-09 4.70E-06 1.49E-OS K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-S7 O.OOE+OO S.6SE-OS 8.39E-OS O.OOE+OO O.OOE+OO 4.62E-OS 3.93E-06 Sr-8S 4.00E-06 O.OOE+OO 9.70E-OS O.OOE+OO O.OOE+OO 6.00E-OS 7.60E-06 Y-SS 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 2.7BE-ll 7.03E-12 2.S6E-12 O.OOE+OO 8.l8E-12 3.00E-07 3.02E-OS Cd-l09 O.OOE+OO 4.90E-OS 1.60E-06 O.OOE+OO 4.70E-OS 9.l0E-OS 8.20E-06 Sn-1I3 8.20E-06 2.70E-07 S.60E-07 1.70E-07 O.OOE+OO 1.20E-04 1.SOE-06 Ba-133 9.S0E-06 4.20E-07 2.S0E-06 O.OOE+OO 2.l0E-09 1. 90E-04 1. OOE-OS Te-134 3.S4E-12 3.22E-12 1.S7E-12 3.44E-12 2.18E-ll 4.34E-07 2.97E-ll 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 IPEC aDCM Page 54 of 136 Revision 2

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 H-3 O.OOE+OO 1. S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-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-OS 8.9SE-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.l6E-OS Cr-S1 O.OOE+OO O.OOE+OO 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.7SE-07 Mn-S4 O.OOE+OO 6.39E-06 1. OSE-06 O.OOE+OO 1.S9E-06 2.48E-04 8.3SE-06 Mn-S6 O.OOE+OO 2.12E-10 3.1SE-11 O.OOE+OO 2.24E-10 1.90E-06 7.18E-06 Fe-SS 4.18E-06 2.98E-06 6.93E-07 O.OOE+OO O.OOE+OO 1.SSE-OS 7.99E-07 Fe-S9 1.99E-06 4.62E-06 1.79E-06 O.OOE+OO O.OOE+OO 1.91E-04 2.23E-OS Co-S8 O.OOE+OO 2.S9E-07 3.47E-07 O.OOE+OO O.OOE+OO 1.68E-04 1.19E-OS Co-60 O.OOE+OO 1. 89E-06 2.48E-06 O.OOE+OO O.OOE+OO 1.09E-03 3.24E-OS Ni-63 7.2SE-OS S.43E-06 2.47E-06 O.OOE+OO O.OOE+OO 3.84E-OS 1.77E-06 Ni-6S 2.73E-10 3.66E-11 1.S9E-11 O.OOE+OO O.OOE+OO 1.17E-06 4.S9E-06 Cu-64 O.OOE+OO 2.S4E-10 1.06E-10 O.OOE+OO 8.01E-10 1.39E-06 7.68E-06 Zn-6S 4.82E-06 1.67E-OS 7.80E-06 O.OOE+OO 1.08E-OS 1.SSE-04 S.83E-06 Zn-69 6.04E-12 1.1SE-11 8.07E-13 O.OOE+OO 7.S3E-12 1.98E-07 3.S6E-OS Br-83 O.OOE+OO O.OOE+OO 4.30E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-S4 O.OOE+OO O.OOE+OO S.41E-OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S 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-OS 1.0SE-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.21E-06 Rb-88 O.OOE+OO 6.82E-OS 3.40E-08 O.OOE+OO O.OOE+OO O.OOE+OO 3.6SE-1S 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 S.43E-OS O.OOE+OO 1.S6E-06 O.OOE+OO O.OOE+OO 3.02E-04 4.64E-OS Sr-90 1.3SE-02 O.OOE+OO 8.3SE-04 O.OOE+OO O.OOE+OO 2.06E-03 9.S6E-OS Sr-91 1.10E-08 O.OOE+OO 4.39E-10 O.OOE+OO O.OOE+OO 7.S9E-06 3.24E-OS Sr-92 1.19E-09 O.OOE+OO S.08E-11 O.OOE+OO O.OOE+OO 3.43E-06 1.49E-OS Y-90 3.73E-07 O.OOE+OO 1.00E-08 O.OOE+OO O.OOE+OO 3.66E-OS 6.99E-OS 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-OS O.OOE+OO 2.21E-06 O.OOE+OO O.OOE+OO 3.67E-04 S .11E-OS Y-92 1.S4E-09 O.OOE+OO S.36E-11 O.OOE+OO O.OOE+OO 3.35E-06 2.06E-OS Y-93 1.69E-08 O.OOE+OO 4.65E-10 O.OOE+OO O.OOE+OO 1.04E-05 7.24E-05 Zr-9S 1.82E-OS 5.73E-06 3.94E-06 O.OOE+OO 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.S7E-09 O.OOE+OO S.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-OS 4.03E-09 O.OOE+OO 5.14E-08 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-103 2.63E-07 O.OOE+OO 1.12E-07 O.OOE+OO 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 O.OOE+OO 5.42E-11 O.OOE+OO 1.76E-10 2.27E-06 1.13E-OS Ru-106 1.23E-05 O.OOE+OO 1.55E-06 O.OOE+OO 2.38E-05 2.01E-03 1.20E-04 Ag-llOm 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-OS 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 IPEC aDCM Page 55 of 136 Revision 2

ODCM 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-IO 1.14E-I0 5.52E-11 1.77E..,10 9.10E-I0 1.40E-06 1.01E-05 Te-129m 1. 74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-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 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-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 4.43E-06 6.14E-06 3.30E-06 1.83E-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 O.OOE+OO 8.28E-08 9.84E-09 3.38E-11 Ba-139 1. 67E-I0 1.18E-13 4.87E-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 2.68E-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 1.58E-05' Ce-143 3.32E-08 2.42E-08 2.70E-09 O;OOE+OO 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 O.OOE+OO 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 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 2.28E-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-08 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-85 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 6.70E-05 1.60E-04 8.60E-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 8.00E-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 IPEC ODCM Page 56 of 136 Revision 2

ODCM 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 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 P-32 7.04E-04 3.09E-OS 2.67E-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-OS Cr-S1 O.OOE+OO O.OOE+OO 4.17E-OB 2.31E-OB 6.S7E-09 4.S9E-06 2.93E-07 Mn-S4 O.OOE+OO 1.16E-OS 2.S7E-06 O.OOE+OO 2.71E-06 4.26E-04 6.19E-06 Mn-S6 O.OOE+OO 4.4BE-10 B.43E-ll O.OOE+OO 4.52E-J,O 3.SSE-06 3.33E-OS Fe-SS 1.2BE-OS 6.BOE-06 2.10E-06 O.OOE+OO O.OOE+OO 3.00E-OS 7.7SE-07 Fe-S9 S.S9E-06 9.04E-06 4.S1E-06 O.OOE+OO O.OOE+OO 3.43E-04 1.91E-OS Co-SB O.OOE+OO 4.79E-07 B.SSE-07 O.OOE+OO O.OOE+OO 2.99E-04 9.29E-06 Co-60 O.OOE+OO 3.SSE-06 6.12E-06 O.OOE+OO O.OOE+OO 1.91E-03 2.60E-OS Ni-63 2.22E-04 1.2SE-OS 7.S6E-06 O.OOE+OO O.OOE+OO 7.43E-OS 1.71E-06 Ni-6S B.OBE-10 7.99E-ll 4.44E-ll O.OOE+OO O.OOE+OO 2.21E-06 2.27E-OS Cu-64 O.OOE+OO S.39E-10 2.90E-10 O.OOE+OO 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.lSE-OS 3.06E-OS 1.90E-OS O.OOE+OO 1.93E-OS 2.69E-04 4.41E-06 Zn-69 1. B1E-ll 2.61E-ll 2.41E-12 O.OOE+OO 1. SSE-ll 3.B4E-07 2.7SE-06 Br-S3 O.OOE+OO O.OOE+OO 1.2BE-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-S4 O.OOE+OO O.OOE+OO 1.4BE-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-SS O.OOE+OO O.OOE+OO 6.B4E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-S6 O.OOE+OO S.36E-OS 3.09E-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.16E-06 Rb-SS O.OOE+OO 1.S2E-07 9.9OE-OS O.OOE+OO O.OOE+OO O.OOE+OO 4.66E-09 Rb-S9 O.OOE+OO 9.33E-OS 7.S3E-OB O.OOE+OO O.OOE+OO O.OOE+OO S .llE-10 Sr-B9 1.62E-04 O.OOE+OO 4.66E-06 O.OOE+OO O.OOE+OO S.S3E-04 4.S2E-OS Sr-9O 2.73E-02 O.OOE+OO 1.74E-03 O.OOE+OO O.OOE+OO 3.99E-03 9.2BE-05 Sr-91 3.2BE-OS O.OOE+OO 1.24E-09 O.OOE+OO O.OOE+OO 1.44E-OS 4.70E-OS Sr-92 3.S4E-09 O.OOE+OO 1. 42E-10 O.OOE+OO O.OOE+OO 6.49E-06 6.SSE-OS Y-9O 1.11E-06 O.OOE+OO 2.99E-OB O.OOE+OO O.OOE+OO 7.07E-OS 7.24E-OS Y-91m 1.37E-10 O.OOE+OO 4.9SE-12 O.OOE+OO O.OOE+OO 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+OO 6.S9E-06 O.OOE+OO O.OOE+OO 7.10E-04 4.97E-OS Y-92 S.SOE-09 O.OOE+OO 1.S7E-10 O.OOE+OO O.OOE+OO 6.46E-06 6.46E-OS Y-93 S.04E-OB O.OOE+OO 1.3BE-09 O.OOE+OO O.OOE+OO 2.01E-OS 1.0SE-04 Zr-9S 5.13E-OS 1.13E-OS 1.00E-OS O.OOE+OO 1.61E-OS 6.03E-04 1.6SE-OS Zr-97 S.07E-08 7.34E-09 4.32E-09 O.OOE+OO 1.0SE-OS 3.06E-OS 9.49E-OS Nb-9S 6.3SE-06 2.4SE-06 1.77E-06 O.OOE+OO 2.33E-06 1.66E-04 1.00E-OS Mo-99 O.OOE+OO 4.66E-08 1.1SE-08 O.OOE+OO 1.06E-07 3.66E-OS 3.42E-OS Tc-99m 4. SlE-13 9.41E-13 1. S6E-ll O.OOE+OO 1.37E-ll 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2. 91E-13 O.OOE+OO 3.92E-13 1. SBE-07 4.41E-09 Ru-103 7.SSE-07 O.OOE+OO 2.90E-07 O.OOE+OO 1.90E-06 1.79E-04 1. 21E-OS Ru-10S 4.13E-10 O.OOE+OO 1.S0E-10 O.OOE+OO 3.63E-10 4.30E-06 2.69E-OS Ru-106 3.6SE-OS O.OOE+OO 4.S7E-06 O.OOE+OO 4.97E-OS 3.87E-03 1.16E-04 Ag-llOm 4.56E-06 3.08E-06 2.47E-06 O.OOE+OO S.74E-06 1.4BE-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.SSE-OS 2.00E-07 S.41E-06 3.41E-08 O.OOE+OO 8.76E-04 4.43E-OS Sb-125 2.66E-OS 2.0SE-07 S.S9E-06 2.46E-08 O.OOE+OO 6.27E-04 1.09E-OS IPEe ODCM Page 57 of 136 Revision 2

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 Te-125m 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-I0 2.57E-I0 1. 65E-I0 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 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 O.OOE+OO 1.38E-06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.OOE+OO 7.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 O.OOE+OO 8.65E-07 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+OO 1. 48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 O.OOE+OO 2.58E-07 1-135 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 3.14E-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 5.29E-11 2.95E-14 1. 72E-12 O.OOE+OO 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 O.OOE+OO 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 O.OOE+OO O.OOE+OO 4.94E-05 6.10E-05 La-142 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 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 O.OOE+OO 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 O.OOE+OO 3.17E-04 3.23E-03 1. 05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 O.OOE+OO 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 O.OOE+OO 2.64E-12 4.23E-07 5.32E-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. 11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 O.OOE+OO 2.63E-08 1.57E-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 3.58E-06 Sr-85 1.20E-05 O.OOE+OO 3.20E-06 O.OOE+OO O.OOE+OO 1. 50E-04 5.50E-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-I0 2.08E-11 9.73E-12 O.OOE+OO 2.31E-11 9.24E-07 7.51E-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-05 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 IPEC aDCM Page 58 of 136 Revision 2

aDCM Part II - 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.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 P-32 1.4SE-03 8.03E-OS S.S3E-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.1SE-OS Cr-Sl O.OOE+OO O.OOE+OO 6.39E-08 4.11E-08 9.4SE-09 9.l7E-06 2.SSE-07 Mn-S4 O.OOE+OO 1.81E-OS 3.S6E-06 O.OOE+OO 3.S6E-06 7.l'4E-04 S.04E-06 Mn-S6 O.OOE+OO 1.l0E-09 1.S8E-10 O.OOE+OO 7.86E-10 8.9SE-06 S.12E-OS Fe-SS 1.41E-OS 8.39E-06 2.38E-06 O.OOE+OO O.OOE+OO 6.21E-OS 7.82E-07 Fe-S9 9.69E-06 1.68E-OS 6.77E-06 O.OOE+OO O.OOE+OO 7.2SE-04 1.77E-OS Co-S8 O.OOE+OO 8.71E-07 1.30E-06 O.OOE+OO O.OOE+OO S.SSE-04 7.9SE-06 Co-60 O.OOE+OO S.73E-06 8.41E-06 O.OOE+OO O.OOE+OO 3.22E-03 2.28E-OS Ni-63 2.42E-04 1.46E-OS 8.29E-06 O.OOE+OO O.OOE+OO 1.49E-04 1.73E-06 Ni-6S 1.71E-09 2.03E-10 8.79E-ll O.OOE+OO O.OOE+OO S.80E-06 3.S8E-OS Cu-64 O.OOE+OO 1. 34E-09 S.S3E-10 O.OOE+OO 2.84E-09 6.64E-06 1.07E-OS Zn-6S 1.38E-OS 4.47E-OS 2.22E-OS O.OOE+OO 2.32E-OS 4.62E-04 3.67E-OS Zn-69 3.8SE-ll 6.91E-ll S .13E-12 O.OOE+OO 2.87E-ll 1.OSE-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 O.OOE+OO O.OOE+OO O.OOE+OO Br-8S 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-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.l7E-06 Rb-88 O.OOE+OO 3.98E-07 2.0SE-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.OOE+OO O.OOE+OO O.OOE+OO 4.B7E-08 Sr-S9 2.84E-04 O.OOE+OO S.1SE-06 O.OOE+OO O.OOE+OO 1.4SE-03 4.S7E-OS Sr-90 2.92E-02 O.OOE+OO 1.8SE-03 O.OOE+OO O.OOE+OO 8.03E-03 9.36E-OS Sr-91 6.83E-OS O.OOE+OO 2.47E-09 O.OOE+OO O.OOE+OO 3.76E-OS S.24E-OS Sr-92 7.S0E-09 O.OOE+OO 2.79E-1O O.OOE+OO O.OOE+OO 1.70E-05 1.OOE-04 Y-90 2.35E-06 O.OOE+OO 6.30E-OS O.OOE+OO O.OOE+OO 1.92E-04 7.43E-05 Y-91m 2.91E-1O 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-OS O.OOE+OO O.OOE+OO 1.75E-03 S.02E-OS Y-92 1.17E-08 O.OOE+OO 3.29E-10 O.OOE+OO O.OOE+OO 1.7SE-OS 9.04E-OS Y-93 1.07E-07 O.OOE+OO 2.91E-09 O.OOE+OO O.OOE+OO S.46E-05 1.l9E-04 Zr-9S 8.24E-OS 1. 99E-OS 1.4SE-OS O.OOE+OO 2.22E-OS 1.2SE-03 1.SSE-OS Zr-97 1.07E-07 1. 83E-08 8.36E-09 O.OOE+OO 1.8SE-08 7.88E-OS 1.00E-04 Nb-9S 1.12E-OS 4.S9E-06 2.70E-06 O.OOE+OO 3.37E-06 3.42E-04 9.0SE-06 Mo-99 O.OOE+OO 1.l8E-07 2.31E-08 O.OOE+OO 1.89E-07 9.63E-OS 3.48E-OS Tc-99m 9.98E-13 2.06E-12 2.66E-ll O.OOE+OO 2.22E-ll S.79E-07 1.4SE-06 Tc-1Ol 4.6SE-14 S.88E-14 S.80E-13 O.OOE+OO 6.99E-13 4.l7E-07 6.03E-07 Ru-103 1.44E-06 O.OOE+OO 4.8SE-07 O.OOE+OO 3.03E-06 3.94E-04 1.1SE-OS Ru-1OS 8.74E-1O O.OOE+OO 2.93E-10 O.OOE+OO 6.42E-1O 1.12E-OS 3.46E-OS Ru-106 6.20E-OS O.OOE+OO 7.77E-06 O.OOE+OO 7.61E-OS 8.26E-03 1.17E-04 Ag-llOm 7.13E-06 S.16E-06 3.S7E-06 O.OOE+OO 7.80E-06 2.62E-03 2.36E-OS 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-OS 3.97E-07 B.S6E-06 7.l8E-OB O.OOE+OO 1.89E-03 4.22E-OS Sb-12S 3.69E-OS 3.41E-07 7.7BE-06 4.4SE-08 O.OOE+OO 1.l7E-03 LOSE-OS IPEC aDCM Page 59 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-ld INFANT INHALATION DOSE FACTORS (mrem 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-127m 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-129m 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-131m 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 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+OO 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+OO 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 O.OOE+OO 1.36E-06 1-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 O.OOE+OO 1.54E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 O.OOE+OO 9.21E-07 1-135 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-140 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':'140 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 0.00£+00 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-113 6.00E-05 1.60E-06 3.60E-06 1. 30E-06 O.OOE+OO 7.80E-04 1.20E-06 Ba-133 1.90E-04 1.70E-06 1.30E-05 O.OOE+OO 8.90E-09 9.10E-04 7.70E-06 Te-134 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 IPEC aDCM Page 60 of 136 Revision 2

ODCM 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 D 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 D 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 D 1. 20E-03 8.00E-09 9.40E-09 Co-58 70.800 D 1.00E-03 7.00E-09 8.20E-09 Co-60 5.27l Y 1. 00E-03 1.70E-08 2.00E-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 1.70E-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-10 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 D 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 8.30E-09 Sr-92 2.710 H 8.00E-04 9.00E-09 1. 00E-08 Y-90 2.667 D 1.00E-05 2.20E-12 2.60E-12 Y-91m 0.829 H 1.00E-05 3.80E-09 4.40E-09 Y-91 58.510 D 1.00E-05 2.40E-11 2.70E-11 Y-92 3.54.0 H 1. 00E-05 1.60E-09 1.90E-09 Y-93 10.100 H 1. 00E-05 5.70E-10 7.80E-10 Zr-95 63.980 D 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 D 2.50E-03 5.10E-09 6.00E-09 Mo-99 2.750 D 7.50E-03 1.90E-09 2.20E-09 Tc-99m 6.020 H 2.50E-02 9.60E-10 1.10E-09 Tc-101 0.237 H 2.50E-02 2.70E-09 3.00E-09 Ru-103 39.280 D 1.00E-06 3.60E-09 4.20E-09 Ru-105 4.440 H 1. 00E-06 4.50E-09 5.10E-09 Ru-106 368.200 D 1.00E-06 1.50E-09 1.80E-09 Ag-110m 249.900 D 5.00E-02 1.80E-08 2.10E-08 Sb-122 2.700 D 1.50E-03 O.OOE+OO O.OOE+OO Sb-124 60.200 D 1. 50E-03 1.30E-08 1. 50E-08 Sb-125 2.770 Y 1. 50E-03 3.10E-09 3.50E-09 IPEC ODCM Page 61 of 136 Revision 2

ODCM 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 D 1.00E-03 3.50E-11 4.80E-11 Te-127m 109.000 D 1.00E-03 1.10E-12 1.30E-12 Te-127 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-10 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 2.7QE-09 Ba-140 12.740 D 4.00E-04 2.10E-09 2.40E-09 Ba-141 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-10 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-113 115.100 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. 20E-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 IPECODCM Page 62 of 136 Revision 2

aDCM Part II - 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-B9 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-I0 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-04 Y-91m 9.09E-ll O.OOE+OO 3.52E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-I0 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-ll O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-05 Y-93 2.68E-09 O.OOE+OO 7.40E-ll 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-I0 1.55E-10 O.OOE+OO 5.12E-10 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-10 6.98E-10 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-103 1.85E-07 O.OOE+OO 7.97E-08 O.OOE+OO 7.06E-07 O.OOE+OO 2.16E-05 Ru-105 1.54E-08 O.OOE+OO 6.08E-09 O.OOE+OO 1.99E-07 O.OOE+OO 9.42E-06 Ru-106 2.75E-06 O.OOE+OO 3.48E-07 O.OOE+OO 5.31E-06 O.OOE+OO 1.78E-04 Ag-llOm 1.60E-07 1.48E-07 8.79E-OB O.OOE+OO 2.91E-07 O.OOE+OO 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.BOE-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 1.38E-06 1.97E-05 IPEC aDCM Page 63 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+OO 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+OO 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-05 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+OO 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 7.53E-07 3.63E-04 4.31E-06 O.OOE+OO 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+OO 2.51E-10 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-05 O.OOE+OO 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.l4E-05 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 4.65E-13 Ba-139 9.70E-08 6.91E-ll 2.84E-09 O.OOE+OO 6.46E-ll 3.92E-ll 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 O.OOE+OO 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-ll 1.59E-09 O.OOE+OO 3.31E-ll 2.02E-ll 2.22E-17 Ba-142 2.13E-08 2.19E-ll 1.34E-09 O.OOE+OO 1.85E-ll 1. 24E-ll 3.00E-26 La-140 2.50E-09 1. 26E-09 3.33E-10 O.OOE+OO O.OOE+OO O.OOE+OO 9.25E-05 La-l42 1.28E-10 5.82E-ll 1. 45E-ll O.OOE+OO O.OOE+OO O.OOE+OO 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+OO 2.94E-09 O.OOE+OO 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 O.OOE+OO 5.37E-10 O.OOE+OO 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 O.OOE+OO 1.21E-07 O.OOE+OO 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 O.OOE+OO 2.13E-09 O.OOE+OO 4.03E-05 Pr-144 3.01E-ll 1.25E-ll 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-10 O.OOE+OO 4.25E-09 O.OOE+OO 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E-05 Np-239 1.19E-09 1. 17E-10 6.45E-ll O.OOE+OO 3.65E-10 O.OOE+OO 2.40E-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 1.75E-07 2.91E-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 5.22E-ll 1.32E-ll 4.82E-12 O.OOE+OO 1. 54E-ll O.OOE+OO 4.87E-08 Cd-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 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 O.OOE+OO 3.59E-ll 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 IPEC aDCM Page 64 of 136 Revision 2

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 B.B7E-09 4.43E-09 O.OOE+OO 9.40E-09 O.OOE+OO 1.0BE-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 1.7lE-OS 1.07E-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-OS Cr-Sl O.OOE+OO O.OOE+OO 3.60E-09 2.OOE-09 7.B9E-lO S.14E-09 6.0SE-07 Mn-S4 O.OOE+OO S.90E-06 1.17E-06 O.OOE+OO 1.76E-06 O.OOE+OO 1.2lE-OS Mn-S6 O.OOE+OO 1.SBE-07 2.BlE-OB O.OOE+OO 2.OOE-07 O.OOE+OO 1.04E-OS Fe-SS 3.7BE-06 2.6BE-06 6.2SE-07 O.OOE+OO O.OOE+OO 1. 70E-06 1.l6E-06 Fe-S9 S.B7E-06 1.37E-OS S.29E-06 O.OOE+OO O.OOE+OO 4.32E-06 3.24E-OS Co-SB O.OOE+OO 9.72E-07 2.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-OS Co-60 O.OOE+OO 2.BlE-06 6.33E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-OS Ni-63 1.77E-04 1.2SE-OS 6.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.99E-06 Ni-6S 7.49E-07 9.S7E-OB 4.36E-OB O.OOE+OO O.OOE+OO O.OOE+OO S.19E-06 Cu-64 O.OOE+OO 1.1SE-07 S.41E-OB O.OOE+OO 2.91E-07 O.OOE+OO B.92E-06 Zn-6S S.76E-06 2.OOE-OS 9.33E-06 O.OOE+OO 1.2BE-OS O.OOE+OO B.47E-06 Zn-69 1.47E-OB 2.BOE-OB 1.96E-09 O.OOE+OO 1.B3E-OB O.OOE+OO S.16E-OB Br-B3 O.OOE+OO O.OOE+OO S.74E-OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-B4 O.OOE+OO O.OOE+OO 7.22E-OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-BS O.OOE+OO O.OOE+OO 3.0SE-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-B6 O.OOE+OO 2.9BE-OS 1.40E-OS O.OOE+OO O.OOE+OO O.OOE+OO 4.4lE-06.

Rb-BB O.OOE+OO B.S2E-OB 4.S4E-OB O.OOE+OO O.OOE+OO O.OOE+OO 7.30E-1S Rb-B9 O.OOE+OO S.SOE-OB 3.B9E-OB O.OOE+OO O.OOE+OO O.OOE+OO B.43E-17 .

Sr-B9 4.40E-04 O.OOE+OO 1.26E-OS O.OOE+OO O.OOE+OO O.OOE+OO S.24E-OS Sr-90 B.30E-03 O.OOE+OO 2.OSE-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-04 Sr-91 B.07E-06 O.OOE+OO 3.21E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-OS Sr-92 3.0SE-06 O.OOE+OO 1.30E-07 O.OOE+OO O.OOE+OO O.OOE+OO 7.77E-OS Y-90 1.37E-OB 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 S.39E-09 O.OOE+OO O.OOE+OO O.OOE+OO B.24E-OS Y-92 1.21E-09 O.OOE+OO 3. SOE-ll O.OOE+OO O.OOE+OO O.OOE+OO 3.32E-OS Y-93 3.B3E-09 O.OOE+OO 1.0SE-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 Zr-9S 4.12E-OB 1. 30E-OB B.94E-09 O.OOE+OO 1.9lE-OB O.OOE+OO 3.00E-OS Zr-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+OO 7.11E-lO O.OOE+OO 1.27E-04 Nb-9S B.22E-09 4.S6E-09 2.S1E-09 O.OOE+OO 4.42E-09 O.OOE+OO 1.9SE-OS Mo-99 O.OOE+OO 6.03E-06 1.1SE-06 O.OOE+OO 1.3BE-OS O.OOE+OO 1. OBE-OS Tc-99m 3.32E-10 9.26E-10 1.20E-OB O.OOE+OO 1.3BE-OB S.14E-lO 6.0BE-07 Tc-101 3.60E-lO S.12E-10 S.03E-09 O.OOE+OO 9.26E-09 3.12E-10 B.7SE-17 Ru-103 2.SSE-07 O.OOE+OO 1.09E-07 O.OOE+OO B.99E-07 O.OOE+OO 2.13E-OS Ru-10S 2.1BE-OB O.OOE+OO B.46E-09 O.OOE+OO 2.7SE-07 O.OOE+OO 1.76E-OS Ru-106 3.92E-06 O.OOE+OO 4.94E-07 O.OOE+OO 7.S6E-06 O.OOE+OO 1.BSE-04 Ag-110m 2.0SE-07 1.94E-07 1.1SE-07 O.OOE+OO 3.70E-07 O.OOE+OO S.4SE-OS Sb-122 3.30E-07 6.42E-09 9.64E-OS 4.19E-09 O.OOE+OO 2.06E-07 6.92E-OS Sb-124 3.S6E-06 7.12E-OS 1.SlE-06 B.79E-09 O.OOE+OO 3.37E-06 7.S1E-OS Sb-12S 2.4SE-06 2.7lE-OS S.79E-07 2.36E-09 O.OOE+OO 2.16E-06 1.92E-OS IPEe aDCM Page 65 of 136 Revision 2

ODCM Part II - 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.B3E-06 1.3BE-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.lSE-06 2.30E-06 3.92E-OS O.OOE+OO 2.4lE-OS Te-127 1.SBE-07 S.60E-OB 3.40E-OB 1.09E-07 6.40E-07 O.OOE+OO 1.22E-OS Te-129m 1.63E-OS 6.0SE-06 2.SBE-06 S.26E-06 6.B2E-OS O.OOE+OO 6.l2E-OS Te-129 4.4BE-OB 1.67E-OB 1.09E-OB 3.20E-OB 1.BBE-07 O.OOE+OO 2.4SE-07 Te-13lm 2.44E-06 1.17E-06 9.76E-07 1. 76E-06 1.22E-OS O.OOE+OO 9.39E-OS Te-13l 2.79E-OB 1.lSE-OB B.72E-09 2.lSE-OB 1.22E-07 O.OOE+OO 2.29E-09 Te-132 3.49E-06 2.21E-06 2.0BE-06 2.33E-06 2.12E-05 O.OOE+OO 7.00E-05 1-130 1.03E-06 2.9BE-06 1.19E-06 2.43E-04 4.S9E-06 O.OOE+OO 2.29E-06 1-131 S.BSE-06 B.19E-06 4.40E-06 2.39E-03 1.4lE-OS O.OOE+OO 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-OS 1.lSE-06 O.OOE+OO 3.lBE-07 1-133 2.0lE-06 3.4lE-06 1.04E-06 4.76E-04 S.9BE-06 O.OOE+OO 2.SBE-06 1-134 1.46E-07 3.B7E-07 1.39E-07 6.4SE-06 6.l0E-07 O.OOE+OO S.lOE-09 I-13S 6.l0E-07 1.S7E-06 S.B2E-07 1.0lE-04 2.4BE-06 O.OOE+OO 1.74E-06 Cs-134 B.37E-OS 1.97E-04 9.l4E-OS O.OOE+OO 6.26E-OS 2.39E-OS 2.4SE-06 Cs-136 B.S9E-06 3.3BE-OS 2.27E-OS O.OOE+OO 1.B4E-OS 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 S.19E-OS O.OOE+OO S.07E-OS 1.97E-OS 2.12E-06 Cs-13B 7.76E-OB 1.49E-07 7.4SE-OB O.OOE+OO 1.l0E-07 1.2BE-OB 6.76E-ll Ba-139 1.39E-07 9.7BE-ll 4.05E-09 O.OOE+OO 9.22E-ll 6.74E-ll 1. 24E-06 Ba-140 2.B4E-05 3.4BE-OB 1.B3E-06 O.OOE+OO 1.lBE-OB 2.34E-OB 4.3BE-OS Ba-14l 6.71E-OB S.OlE-ll 2.24E-09 O.OOE+OO 4.6SE-ll 3.43E-ll 1.43E-13 Ba-142 2.99E-OB 2.99E-ll 1.B4E-09 O.OOE+OO 2. S3E-ll 1.99E-ll 9.lBE-20 La-140 3.4BE-09 1.71E-09 4.SSE-lO O.OOE+OO O.OOE+OO O.OOE+OO 9.B2E-OS La-142 1.79E-lO 7.9SE-ll 1. 9BE-ll O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-06 Ce-14l 1.33E-OB B.BBE-09 1.02E-09 O.OOE+OO 4.lBE-09 O.OOE+OO 2.S4E-OS Ce-143 2.3SE-09 1. 71E-06 1.9lE-lO O.OOE+OO 7.67E-lO O.OOE+OO S .l4E-OS Ce-144 6.96E-07 2.BBE-07 3.74E-OB O.OOE+OO 1.72E-07 O.OOE+OO 1.7SE-04 Pr-143 1.3lE-OB S.23E-09 6.S2E-lO O.OOE+OO 3.04E-09 O.OOE+OO 4.3lE-OS Pr-144 4.30E-ll 1.76E-ll 2.lBE-12 O.OOE+OO 1.OlE-ll O.OOE+OO 4.74E-14 Nd-147 9.3BE-09 1.02E-OB 6.11E-lO O.OOE+OO S.99E-09 O.OOE+OO 3.6BE-OS W-IB7 1.46E-07 1.l9E-07 4.l7E-OB O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-OS Np-239 1. 76E-09 1.66E-lO 9.22E-ll O.OOE+OO S.2lE-lO O.OOE+OO 2.67E-OS K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-S7 O.OOE+OO 2.3BE-07 3.99E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 Sr-BS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-BB 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-ll 1. B3E-ll 6.6BE-12 O.OOE+OO 2.l4E-ll 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-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 4.47E-OB 2.B7E-OB 3.00E-OB 3.67E-OB 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 IPEC ODCM Page 66 of 136 Revision 2

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 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-05 1.33E-05 O.OOE+OO O.OOE+OO 7.74E-06 2.78E-05 Co-58 O.OOE+OO 1.80E-06 5.51E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.05E-05 Co-60 O.OOE+OO 5.29E-06 1.56E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.93E-05 Ni-63 5.38E-04 2.88E-05 1. 83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 O.. OOE+OO O.OOE+OO O.OOE+OO 2.56E-05 Cu-64 O.OOE+OO 2.45E-07 1.48E-07 O.OOE+OO 5.92E-07 O.OOE+OO 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 O.OOE+OO 2.30E-05 O.OOE+OO 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-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-85 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 5.11E-05 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-05 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 3.65E-08 O.OOE+OO 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 O.OOE+OO 1.45E-09 O.OOE+OO 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 O.OOE+OO 8.23E-09 O.OOE+OO 1.62E-05 Mo-99 O.OOE+OO 1.33E-05 3.29E-06 O.OOE+OO 2.84E-05 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-101 1.07E-09 1.12E-09 1. 42E-08 O.OOE+OO 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 O.OOE+OO 2.81E-07 O.OOE+OO 1. 84E-06 O.OOE+OO 1.89E-05 Ru-105 6.45E-08 O.OOE+OO 2.34E-08 O.OOE+OO 5.67E-07 O.OOE+OO 4.21E-05 Ru-106 1.17E-05 O.OOE+OO 1.46E-06 O.OOE+OO 1. 58E-05 O.OOE+OO 1.82E-04 Ag-11 Om 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 1.45E-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-05 Sb-125 7.15E-06 5.51E-08 1.50E-06 6.63E-09 O.OOE+OO 3.98E-06 1.71E-05 IPEC aDCM Page 67 of 136 Revision 2

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 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 2.41E-05 O.OOE+OO 1.01E-04 Te-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 I-US 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-10 1.30E-10 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 IPEC ODCM Page 68 of 136 Revision 2

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.S1E-08 O.OOE+OO 3.34E-08 O.OOE+OO 1.11E-06 Na-24 1.01E-OS 1.01E-OS 1.01E-OS 1.01E-OS 1.01E-OS 1. OlE-OS 1.01E-OS P-32 1.70E-03 1.00E-04 6.S9E-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.30E-OS Cr-S1 O.OOE+OO O.OOE+OO 1.4lE-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-S4 O.OOE+OO 1.99E-OS 4.S1E-06 O.OOE+OO 4.41E-06 O.OOE+OO 7.31E-06 Mn-S6 O.OOE+OO 8.18E-07 1.41E-07 O.OOE+OO 7.03E-07 O.OOE+OO 7.43E-OS Fe-SS 1.39E-OS B.98E-06 2.40E-06 O.OOE+OO O.OOE+OO 4.39E-06 1.14E-06 Fe-S9 3.08E-OS S.3BE-OS 2.12E-OS O.OOE+OO O.OOE+OO 1.S9E-OS 2.S7E-OS Co-S8 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-OS 2.SSE-OS O.OOE+O.O O.OOE+OO O.OOE+OO 2.S7E-OS Ni-63 6.34E-04 3.92E-OS 2.20E-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.9SE-06 Ni-6S 4.70E-06 S.32E-07 2.42E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.0SE-OS Cu-64 O.OOE+OO 6.09E-07 2.82E-07 O.OOE+OO 1.03E-06 O.OOE+OO 1.2SE-OS Zn-6S 1.84E-OS 6.31E-OS 2.91E-OS O.OOE+OO 3.06E-OS O.OOE+OO S.33E-OS Zn-69 9.33E-08 1.68E-07 1.2SE-08 O.OOE+OO 6.98E-08 O.OOE+OO 1.37E-OS 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-8S 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-OS O.OOE+OO O.OOE+OO O.OOE+OO 4.3SE-06 Rb-88 O.OOE+OO 4.98E-07 2.73E-07 o.,OOE+OO O.OOE+OO O.OOE+OO 4.8SE-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.S1E-03 O.OOE+OO 7.20E-OS O.OOE+OO O.OOE+OO O.OOE+OO S .16E-OS Sr-90 1.8SE-02 O.OOE+OO 4.71E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.31E-04 Sr-91 S.OOE-OS O.OOE+OO 1.81E-06 O.OOE+OO O.OOE+OO O.OOE+OO S.92E-OS Sr-92 1.92E-OS 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-OS Y-92 7.6SE-09 O.OOE+OO 2.1SE-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-9S 2.06E-07 S.02E-08 3.S6E-OB O.OOE+OO S.4lE-08 O.OOE+OO 2.S0E-OS Zr-97 1.48E-08 2.S4E-09 1.16E-09 O.OOE+OO 2.S6E-09 O.OOE+OO 1.62E-04 Nb-9S 4.20E-OB 1.73E-08 1.00E-08 O.OOE+OO 1.24E-08 O.OOE+OO 1.46E-OS Mo-99 O.OOE+OO 3.40E-OS 6.63E-06 O.OOE+OO S.OBE-OS O.OOE+OO 1.12E-OS Tc-99m 1.92E-09 3.96E-09 S.10E-08 O.OOE+OO 4.26E-08 2.07E-09 1.lSE-06 Tc-101 2.27E-09 2.86E-09 2.83E-OB O.OOE+OO 3.40E-OB 1. S6E-09 4.86E-07 Ru-103 1.48E-06 O.OOE+OO 4.9SE-07 O.OOE+OO 3.08E-06 O.OOE+OO 1. 80E-OS Ru-10S 1.36E-07 O.OOE+OO 4.S8E-08 O.OOE+OO 1.00E-06 O.OOE+OO S.41E-OS Ru-106 2.4lE-OS O.OOE+OO 3.01E-06 O.OOE+OO 2.8SE-OS O.OOE+OO 1.B3E-04 Ag-llOm 9.96E-07 7.27E-07 4.B1E-07 O.OOE+OO 1.04E-06 O.OOE+OO 3.77E-OS Sb-122 2.10E-06 3.BSE-08 6.13E-07 3.14E-08 O.OOE+OO 1.09E-06 7.6SE-OS Sb-124 2.14E-OS 3.1SE-07 6.63E-06 S.6BE-08 O.OOE+OO 1.34E-OS 6.60E-OS Sb-12S 1.23E-OS 1.19E-07 2.S3E-06 1.S4E-08 O.OOE+OO 7.72E-06 1.64E-OS IPEC aDCM Page 69 of 136 Revision 2

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 O.OOE+OO O.OOE+OO 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+OO 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 2.50E-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+OO 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+OO 3.81E-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+OO 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+OO 1.51E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+OO 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+OO 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+OO 1. 84E-06 1-135 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 Ba-141 4.25E-07 2.91E-I0 1. 34E-08 O.OOE+OO 1.75E-10 1. 77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-I0 9.06E-09 O.OOE+OO 8.81E-11 9.26E-11 7.59E-07 La-140 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-I0 1. 38E-11 O.OOE+OO 3.84E-11 O.OOE+OO 4.93E-06 Nd-147 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 0.00£+00 0.00£+00 3.69£-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 0.00£+00 O.OOE+OO 3.92E-06 Sr-85 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 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 0.00£+00 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO 0.00£+00 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 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO IPEC aDCM Page 70 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-4 Total Body Dose Factors Ki From Noble Gases (gamma)

Gamma Finite Cloud Correction Factor**

Nuclide TB factor

x (pCi/uCi) x Unit2 Unit 3 = U2 Ki *** U3 Ki ***

Kr-83m 7.56E-08 1E+6 8.86E-01 5.78E-01 6.70E-02 4.37E-02 Kr-85m 1.17E-03 1E+6 7.49E-01 4.46E-01 8.76E+02 5.22E+02 Kr-85 1.61 E-05 1E+6 6.73E-01 3.85E-01 1.08E+01 6.19E+OO Kr-87 5.92E-03 1E+6 5.68E-01 3.09E-01 3.36E+03 1.83E+03 Kr-88 1.47E-02 1E+6 5.40E-01 2.88E-01 7.93E+03 4.23E+03 Kr-89 1.66E-02 1E+6 5.60E-01 3.03E-01 9.30E+03 5.03E+03 Kr-90 1.56E-02 1E+6 5.97E-01 3.29E-01 9.31E+03 5.13E+03 Xe-131m 9.15E-05 1E+6 8.67E-01 5.62E-01 7.94E+01 5.14E+01 Xe-133m 2.51E-04 1E+6 8.17E-01 5.12E-01 2.05E+02 1.29E+02 Xe-133 2.94E-04 1E+6 8.86E-01 5.78E-01 2.60E+02 1.70E+02 Xe-135m 3.12E-03 1E+6 6.75E-01 3.87E-01 2.11E+03 1.21E+03 Xe-135 1.81E-03 1E+6 7.60E-01 4.55E-01 1.38E+03 8.24E+02 Xe-137 1.42E-03 1E+6 6.46E-01 3:65E-01 9.18E+02 5.18E+02 Xe-138 8.83E-03 1E+6 5.75E-01 3.14E-01 5.07E+03 2.77E+03 Ar-41 8.84E-03 1E+6 5.89E-01 3.21 E-01 5.21E+03 2.84E+03

From Reg Guide 1.109. Table B-1 (mrem/yr per pCi/m3)

- The finite cloud correction factor is described in Section 3.6

- - Ki (mrem/yr per uCi/m 3 )

IPECODCM Page 71 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-5 Skin Dose Factors Li From Noble Gases (beta)

Beta Skin*

Nucline Dose Factor x (pCi/uCi) = U**

Kr-83m O.OOE+OO 1E+6 O.OOE+OO Kr-85m 1.46E-03 1E+6 1.46E+03 Kr-85 1.34E-03 1E+6 1.34E+03 Kr-87 9.73E-03 1E+6 9.73E+03 Kr-88 2.37E-03 1E+6 2.37E+03 Kr-89 1.01 E-02 1E+6 1.01E+04 Kr-90 7.29E-03 1E+6 7.29E+03 Xe-131m 4.76E-04 1E+6 4.76E+02 Xe-133m 9.94E-04 1E+6 9.94E+02 Xe-133 3.06E-04 1E+6 3.06E+02 Xe-135m 7.11E-04 1E+6 7.11E+02 Xe-135 1.86E-03 1E+6 1.86E+03 Xe-137 1.22E-02 1E+6 1.22E+04 Xe-138 4.13E-03 1E+6 4.13E+03 Ar-41 2.69E-03 1E+6 2.69E+03

From Reg Guide 1.109, Table B-1 (mrem/yr per pCi/m3)

- Li (mrem/yr per uCi/m 3)

IPEC aDCM Page 72 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-6 Air Dose Factors Mi From Noble Gases (gamma)

Gamma Finite Cloud Correction Factor**

Nuclide factor

x (pCi/uCi) x Unit 2 Unit 3 U2 Mi *** U3 Mi ***

Kr-83m 1.93E-05 1E+6 8.86E-01 5.78E-01 1.71E+01 1.12E+01 Kr-85m 1.23E:.03 1E+6 7.49E-01 4.46E-01 9.21 E+02 5.49E+02 Kr-85 1.72E-05 1E+6 6.73E-01 3.85E-01 1.16E+01 6.62E+OO Kr-87 6.17E-03 1E+6 5.68E-01 3.09E-01 3.50E+03 1.91E+03 Kr-88 1.52E-02 1E+6 5.40E-01 2.88E-01 8.20E+03 4.37E+03 Kr-89 1.73E-02 1E+6 5.60E-01 3.03E-01 9.69E+03 5.24E+03 Kr-90 1.63E-02 1E+6 5.97E-01 3.29E-01 9.73E+03 5.36E+03 Xe-131m 1.56E-04 1E+6 8.67E-01 5.62E-01 1.35E+02 8.77E+01 Xe-133m 3.27E-04 1E+6 8.17E-01 5.12E-01 2.67E+02 1.68E+02 Xe-133 3.53E-04 1E+6 8.86E-01 5.78E-01 3.13E+02 2.04E+02 Xe-135m 3.36E-03 1E+6 6.75E-01 3.87E-01 2.27E+03 1.30E+03 Xe-135 1.92E-03 1E+6 7.60E-01 4.55E-01 1.46E+03 8.74E+02 Xe-137 1.51E-03 1E+6 6.46E-01 3.65E-01 9.76E+02 5.51E+02 Xe-138 9.21E-03 1E+6 5.75E-01 3.14E-01 5.29E+03 2.89E+03 Ar-41 9.30E-03 1E+6 5.89E-01 3.21 E-01 5.48E+03 2.99E+03

From Reg Guide 1.109, Table B-1 (mrad/yr per pCi/m3)

- The finite cloud correction factor is described in Section 3.6 3

- - Mi (mrad/yr per uCi/m )

IPEC ODCM Page 73 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-7 Air Dose Factors Ni From Noble Gases (beta)

Beta

Nucline Factor x (pCiluCi) = Ni**

Kr-83m 2.88E-04 1E+6 2.88E+02 Kr-85m 1.97E-03 1E+6 1.97E+03 Kr-85 1.95E-03 1E+6 1.95E+03 Kr-87 1.03E-02 1E+6 1.03E+04 Kr-88 2.93E-03 1E+6 2.93E+03 Kr-89 1.06E-02 1E+6 1.06E+04 Kr-90 7.83E-03 1E+6 7.83E+03 Xe-131m 1.11E-03 1E+6 1.11 E+03 Xe-133m 1.48E-03 1E+6 1.48E+03 Xe-133 1.05E-03 1E+6 1.05E+03 Xe-135m 7.39E-04 1E+6 7.39E+02 Xe-135 2.46E-03 1E+6 2.46E+03 Xe-137 1.27E-02 1E+6 1.27E+04 Xe-138 4.75E-03 1E+6 4.75E+03 Ar-41 3.28E-03 1E+6 3.28E+03

From Reg Guide 1.109, Table B-1 (mrad/yr per pCi/m 3 )

- Ni (mrad/yr per uCi/m 3 )

IPEC ODCM Page 74 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3 - 8 NOBLE GAS DOSE FACTORS For Instantaneous and Time Average Mixtures at the Site Boundarv. Units 2 and 3 Radionuclide Instantaneous Time Average Mix (%) Mix (%)

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-135m 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 Units dose factors dose factors K = 1507 K = 849 mremlyr per uCi/m3 K = 237 K = 153 L = 1310 L = 1310 mremlyr per uCi/m3 L =540 L = 540 M= 1601 M = 905 rnrad/yr per uCi/m3 M = 281 AT = 181 N = 1977 /i= 1977 rnrad/yr per uCi/m3 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 I.

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 I.

IPEC ODCM Page 75 of 136 Revision 2

ODCM Part II - Calculational Methodologies TABLE3-9 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCE Distance Distance Distance Sector to Site to Site to nearest Boundary Boundary residence, by from Unit 2 from Unit 3 from Unit 1 compass Plant Vent, Plant Vent, superheater, point in meters in meters in meters N RIVER RIVER 1788.1 NNE RIVER RIVER 3111.3 NE 550 636 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.

IPEC ODCM Page 76 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-10a 3

ADULT INHALATION Ri (I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG 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 1.70£+05 5.06E+05 Y-91m 2.61E-01 O.OOE+OO 1.02E-02 O.OOE+OO O.OOE+OO 1.92£+03 1.33E+00 Y-91 4.62E+05 O.OOE+OO 1.24E+04 O.OOE+OO O.OOE+OO 1.70£+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 O.OOE+OO 2.61E+00 O.OOE+OO O.OOE+OO 4.85£+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 5.05£+05 1.04E+05 Mo-99 O.OOE+OO 1.21E+02 2.30E+01 O.OOE+OO 2.91E+02 9.12£+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-11 Ru-103 1.53E+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-110m 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 IPECODCM Page 77 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-10a 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-l27 1.40E+00 6.42E-Ol 3.10E-Ol 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+01 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-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 1-130 4.58E+03 1. 34E+04 5.28E+03 1.14E+06 2.09E+04 O.OOE+OO 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 O.OOE+OO 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 1-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO 1.01E+00 1-135 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-137 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-Ol 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+Ol 2.57E+03 O.OOE+OO 1.67E+Ol 1.27E+06 2.18E+05 Ba-141 1.00E-Ol 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-l40 3.44E+02 1.74E+02 4.58E+01 O.OOE+OO O.OOE+OO 1.36E+05 4.58E+05 La-l42 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+Ol O.OOE+OO 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43£+06 1.43E+06 1. 84E+05 0.00£+00 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 0.00£+00 7.05E-03 1. 02E+03 2.15E-08 Nd-147 5.27E+03 6.10£+03 3.65E+02 O.OOE+OO 3.56E+03 2.21E+05 1.73E+05 w-187 8.48E+00 7.08E+00 2.48£+00 0.00£+00 0.00£+00 2.90E+04 1.55E+05 Np-239 2.30£+02 2.26E+01 1. 24E+Ol O.OOE+OO 7.00E+01 3.76E+04 1.19£+05 K-40 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 0.00£+00 0.00£+00 O.OOE+OO Co-57 O.OOE+OO 6.92E+02 6.71E+02 O.OOE+OO O.OOE+OO 3.70£+05 3.14£+04 Sr-85 3.20E+04 O.OOE+OO 7.76E+05 O.OOE+OO O.OOE+OO 4.80E+05 6.08£+04 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 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 6.56£+04 Sn-113 6.56E+04 2.16E+03 4.48E+03 1.36£+03 O.OOE+OO 9.60E+05 1.20E+04 Ba-133 7.60E+04 3.36E+03 2.00£+04 0.00£+00 1.68E+01 1.52E+06 8.00E+04 Te-134 3.07£-02 2.58E-02 1.26E-02 2.75E-02 1.74E-01 3.47E+03 2.38E-Ol Ce-139 0.00£+00 0.00£+00 0.00£+00 0.00£+00 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 IPECODCM Page 78 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-10b 3

TEEN INHALATION Ri (I) (mrem/yr per uCi/m )

Isotope BONE LIVER 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 2.74E+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 O.OOE+OO O.OOE+OO 2.94E+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-110m 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 1.72E+04 7.04E+01 O.OOE+OO 2.74E+06 9.92E+04 IPEC aDCM Page 79 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-l0b 3

TEEN INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-l25m 4.88E+03 2.24E+03 6.67E+02 1. 40E+03 O.OOE+OO 5.36E+05 7.50E+04 Te-127m 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-131m 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-l31 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1. 51E+01 Te-l32 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1. 95E+03 4.49E+05 4.63E+05 I-l30 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+0-5 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 I-l34 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+OO 2.04E+01 I-l35 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 6.95E+03 Cs-l34 5.02E+05 1.l3E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-l36 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.10E+05 1.78E+04 1. 09E+04 Cs-l37 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21E+05 8.48E+03 Cs-l38 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+01 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 Ba-142 3.70E-02 3.70E-05 2.27E-03 O.OOE+OO 3.l4E-05 1.91E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6.26E+01 O.OOE+OO O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-01 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+01 O.OOE+OO 8.64E+01 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.l3E+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 6.49E+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-01 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-113 1. 20E+05 3.76E+03 7.76E+03 2.32E+03 O.OOE+OO 1.60E+06 1.20E+04 Ba-l33 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+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 IPEC aDCM Page 80 of 136 Revision 2

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+01 2.43E+01 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-01 O.OOE+OO 1.67E+00 1.31E+04 1.23E+05 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+05 6.33E+03 Ni-65 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 9.58E+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 5.48E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 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+05 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO 5.62E+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+05 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+05 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+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 Y-92 2.04E+01 O.OOE+OO 5.81E-01 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 Y-93 1.86E+02 O.OOE+OO 5.11E+00 O.OOE+OO O.OOE+OO 7.44E+04 3.89E+05 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+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 Mo-99 O.OOE+OO 1.72E+02 4.25E+01 O.OOE+OO 3.92E+02 1.35E+05 1.27E+05 Tc-99m 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51E+02 4.81E+03 Tc-101 8.10E-05 8.51E-05 1.08E-03 O.OOE+OO 1.45E-03 5.85E+02 1.63E+01 Ru-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+00 O.OOE+OO 5.55E-01 O.OOE+OO 1.34E+00 1.59E+04 9.95E+04 Ru-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 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-122 O.OO~+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 IPEC aDCM Page 81 of 136 Revision 2

ODCM 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 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 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+00 9.51E-01 6.10E-01 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 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.S5E+04 Te-131m 1.34E+02 5.92E+01 5.07E+01 9.77E+01 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 1.77E+03 3.77E+05 1.38E+05 1-130 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 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 O.OOE+OO 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 I-US 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-Ol 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 2.9lE-05 1.64E+03 2.74E+00 La-140 6.44E+02 2.2SE+02 7.5SE+Ol O.OOE+OO O.OOE+OO 1.83E+05 2.26E+OS La-142 1.29E+00 4.llE-01 1.29E-Ol O.OOE+OO O.OOE+OO 8.70E+03 7.59E+04 Ce-14l 3.92E+04 1.9SE+04 2.90E+03 O.OOE+OO 8.S5E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+Ol O.OOE+OO 8.36E+Ol 1.l5E+05 1. 27E+05 Ce-144 6.77E+06 2.l2E+06 3.61E+05 O.OOE+OO 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.5SE+03 9.14E+02 O.OOE+OO 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.8SE-02 3.00E-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73E+03 6.8lE+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.l0E+04 Np-239 4.66E+02 3.34E+01 2.35E+Ol O.OOE+OO 9.73E+Ol 5.8lE+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-Ol 7.70E-02 3.60E-02 O.OOE+OO 8.S5E-02 3.42E+03 2.78E+04 Cd-l09 O.OOE+OO 7.03E+05 2.96E+04 O.OOE+OO 6.29E+05 1.11E+06 3.00E+04 Sn-1l3 1.4lE+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.lIE-Ol 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 IPECODCM Page 82 of 136 Revision 2

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-01 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 3.21E+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+Ol 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+Ol 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+01 O.OOE+OO 4.61E-01 O.OOE+OO O.OOE+OO 2.45E+04 1. 27E+05 Y-93 1.50E+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-106 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1. 16E+07 1.64E+05 Ag-11Om 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+01 O.OOE+OO 1.64E+06 1.47E+04 IPEC aDCM Page 83 of 136 Revision 2

ODCM 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 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-l27 2.23E+04 9.53E-01 4.89E-01 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-01 3.00E+03 2.63E+04 Te-131m 1.07E+02 5.50E+01 3.63E+01 8.93E+01 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 1-130 6.36E+03 1. 39E+04 5.57E+03 1.60E+06 1.53E+04 O.OOE+OO 1.99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 O.OOE+OO 1.06E+03 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 O.OOE+OO 1.90E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 1-134 9.21E+02 1. 88E+03 6.65E+02 4.45E+04 2.09E+03 0.00£+00 1.29£+03 1-135 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+01 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+01 O.OOE+OO O.OOE+OO 1.68E+05 8.48E+04 La-142 1.03E+00 3.77E-01 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+01 O.OOE+OO 5.64E+01 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+01 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+01 1. 88E+01 O.OOE+OO 6. 62E+01 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 IPEC ODCM Page 84 of 136 Revision 2

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+01 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 O.OOE+OO 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-110m 1.05E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+OT 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 4.07E+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 IPEC aDCM Page 85 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-l1a 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+OB O.OOE+OO 3.B6E+OB Te-127m 3.49E+OB 1. 25E+OB 4.26E+07 B.92E+07 1.42E+09 O.OOE+OO 1.17E+09 Te-127 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+OB 9.3BE+07 3.9BE+07 B.63E+07 1.05E+09 O.OOE+OO 1.27E+09 Te-129 7.62E-04 2.B7E-04 1.B6E-04 5.B5E-04 3.20E-03 O.OOE+OO 5.75E-04 Te-131m 9.12E+05 4.46E+05 3.72E+05 7.06E+05 4.52E+06 O.OOE+OO 4.43E+07 Te-131 1.50E-15 6.27E-16 .4.74E-16 1. 23E-15 6.57E-15 O.OOE+OO 2.13E-16 Te-132 4.30E+06 2.7BE+06 2.61E+06 3.07E+06 2.6BE+07 O.OOE+OO 1.32E+OB 1-130 3.92E+05 1.16E+06 4.57E+05 9.B1E+07 1.B1E+06 O.OOE+OO 9.96E+05 1-131 B.OBE+07 1.16E+OB 6.62E+07 3.79E+10 1.9BE+OB O.OOE+OO 3.05E+07 1-132 5.76E+01 1. 54E+02 5.39E+01 5.39E+03 2.45E+02 O.OOE+OO 2.B9E+01 1-133 2.09E+06 3.63E+06 1.l1E+06 5.33E+OB 6.33E+06 O.OOE+OO 3.26E+06 1-134 9.65E-05 2.62E-04 9.3BE-05 4.54E-03 4.17E-04 O.OOE+OO 2.29E-07 I-US 3.90E+04 1.02E+05 3.77E+04 6.73E+06 1.64E+05 O.OOE+OO 1.15E+05 Cs-134 4.67E+09 1.l1E+I0 9.0BE+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+OB Cs-136 4.24E+07 1.6BE+OB 1.21E+OB O.OOE+OO 9.32E+07 1.2BE+07 1.90E+07 Cs-137 6.36E+09 B.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.B1E+OB 1.6BE+OB Cs-13B 3.91E-l1 7.73E-ll 3.B3E-l1 O.OOE+OO 5.6BE-ll 5.61E-12 3.30E-16 Ba-139 2.6BE-02 1.91E-05 7.B6E-04 O.OOE+OO 1.79E-05 1. OBE-05 4.76E-02 Ba-140 1.2BE+OB 1.61E+05 B.3BE+06 O.OOE+OO 5.46E+04 9.20E+04 2.63E+OB Ba-141 1. 15E-21 B.70E-25 3.B9E-23 O.OOE+OO B.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 1.9BE+03 9.9BE+02 2.64E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.33E+07 La-142 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+OB Ce-143 9.98E+02 7.3BE+05 B.16E+01 O.OOE+OO 3.25E+02 O.OOE+OO 2.76E+07 Ce-144 3.29E+07 1.3BE+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 W-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.B9E+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 O.OOE+OO Sn-l13 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 3.56E-08 2.33E-08 1.43E-08 3.l1E-08 2.25E-07 O.OOE+OO 3.95E-l1 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 IPEC aDCM Page 86 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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.S9E+03 2.S9E+03 2.S9E+03 2.S9E+03 2.S9E+03 2.S9E+03 Be-7 l.43E+OS 3.20E+OS l.60E+OS O.OOE+OO 3.39E+OS O.OOE+OO 3.90E+07 Na-24 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS P-32 l.6lE+09 9.97E+07 6.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1. 3SE+08 Cr-S1 O.OOE+OO O.OOE+OO 6.17E+04 3.43E+04 1. 3SE+04 8.81E+04 1.04E+07 Mn-S4 O.OOE+OO 4.S4E+08 9.01E+07 O.OOE+OO 1.36E+08 O.OOE+OO 9.32E+08 Mn-S6 O.OOE+OO 1.43E+01 2.SSE+OO O.OOE+OO 1.81E+01 O.OOE+OO 9.44E+02 Fe-SS 3.26E+08 2.31E+08 S.39E+07 O.OOE+OO O.OOE+OO 1.47E+08 1.00E+08 Fe-S9 1.79E+08 4.18E+08 1.61E+08 O.OOE+OO O.OOE+OO 1.32E+08 9.88E+08 Co-S8 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 S.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 Ni-63 1. 61E+10 1.13E+09 S.4SE+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+08 Ni-6S S.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+OS Zn-6S 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. S6E-OS 1.09E-06 O.OOE+OO 1.02E-OS O.OOE+OO 2.87E-OS 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 2.2SE-ll O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S 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 4.0SE+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. 2SE-26 8.82E-27 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E-3S Sr-89 1. SlE+10 O.OOE+OO 4.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+09 Sr-90 7.S1E+ll O.OOE+OO 1.8SE+ll O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+10 Sr-91 2.8SE+OS 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-91m 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+OS O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+09 Y-92 8.60E-Ol O.OOE+OO 2.49E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.36E+04 Y-93 l.S9E+02 O.OOE+OO 4.36E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.86E+06 Zr-9S 1.72E+06 S.43E+OS 3.73E+OS O.OOE+OO 7.98E+OS O.OOE+OO 1.2SE+09 Zr-97 3.12E+02 6.18E+01 2.8SE+01 O.OOE+OO 9.37E+01 O.OOE+OO 1.67E+07 Nb-9S 1.93E+OS 1.07E+OS S.89E+04 O.OOE+OO 1.04E+OS O.OOE+OO 4.S7E+08 Mo-99 O.OOE+OO S.6SE+06 1.08E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.01E+07 Tc-99m 2.74E+OO 7.63E+OO 9.89E+01 O.OOE+OO 1.14E+02 4.24E+OO S.OlE+03 Tc-101 7.64E-31 1.09E-30 1.07E-29 O.OOE+OO 1.97E-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 S.69E+08 Ru-10S S.OOE+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 S.97E+08 O.OOE+OO 1.48E+10 Ag-llOm 1.S2E+07 1.43E+07 8.72E+06 O.OOE+OO 2.74E+07 O.OOE+OO 4.03E+09 Sb-122 3.03E+OS S.89E+03 8.8SE+04 3.8SE+03 O.OOE+OO 1.89E+OS 6.3SE+07 Sb-124 1.S4E+08 2.84E+06 6.02E+07 3.S0E+OS O.OOE+OO 1. 34E+08 3.11E+09 Sb-12S 2.14E+08 2.34E+06 S.00E+07 2.04E+OS O.OOE+OO 1.86E+08 1.66E+09 IPEC ODCM Page 87 of 136 Revision 2

aDCM Part II - Calculational Methodologies 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 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 4.12E+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 1.14E-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 7.80E+05 1-131 7.69E+07 1.08E+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+Ol 1-133 1.94E+06 3.29E+06 1.00E+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 1.43E+OS O.OOE+OO 1.00E+05 Cs-134 7.10E+09 1.67E+10 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 1. 47E+07 1.37E+07 Cs-137 1.01E+10 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 1. 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+01 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 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 2.00E-06 4.95E-07 1.81E-07 O.OOE+OO 5.'79E-07 O.OOE+OO 1.18E-02 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 3.23E-08 2.07E-08 2.17E-08 2.65E-08 1.98E-07 O.OOE+OO 1.20E-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 IPEC aDCM Page 88 of 136 Revision 2

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 H-3 O.OOE+OO 4.0lE+03 4.0lE+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 Be-7 3.37E+OS S.72E+05 3.77E+05 O.OOE+OO S.63E+05 O.OOE+OO 3.20E+07 Na-24 3.73E+OS 3.73E+OS 3.73E+OS 3.73E+OS 3.73E+05 3.73E+OS 3.73E+OS P-32 3.37E+09 1.S8E+08 1.30E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.31E+07 Cr-S1 O.OOE+OO O.OOE+OO 1.17E+OS 6.S0E+04 1. 78E+04 1.19E+OS 6.21E+06 Mn-S4 O.OOE+OO 6.6SE+08 1.77E+08 O.OOE+OO 1.86E+08 O.OOE+OO S.S8E+08 Mn-S6 O.OOE+OO 1.88E+01 4.24E+OO O.OOE+OO 2.27E+01 O.OOE+OO 2.72E+03 Fe-SS 8.01E+08 4.2SE+08 1.32E+08 O.OOE+OO O.OOE+OO 2.40E+08 7.87E+07 Fe-S9 3.97E+08 6.42E+08 3.20E+08 O.OOE+OO O.OOE+OO 1.86E+08 6.68E+08 Co-S8 O.OOE+OO 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 3.9SE+10 2.11E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+08 Ni-6S 1.0SE+02 9.89E+OO S.77E+OO 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 S.16E+OS Zn-6S 8.12E+08 2.16E+09 1.3SE+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 Zn-69 1.S1E-OS 2.18E-05 2.02E-06 O.OOE+OO 1. 32E-OS O.OOE+OO 1.37E-03 Br-83 O.OOE+OO O.OOE+OO S.37E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.82E-ll 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 4.S2E+08 2.78E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.91E+07 Rb-88 O.OOE+OO 4.37E-22 3.04E-22 O.OOE+OO O.OOE+OO O.OOE+OO 2.1SE-23 Rb-89 O.OOE+OO 1.64E-26 1.46E-26 O.OOE+OO O.OOE+OO O.OOE+OO 1.43E-28 Sr-89 3.S9E+10 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+09 Sr-90 1.24E+12 O.OOE+OO 3.1SE+ll O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 Sr-91 S.24E+OS 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.S6E+07 Y-91m 8.91E-09 O.OOE+OO 3.24E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.74E-OS Y-91 1.86E+07 O.OOE+OO 4.99E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+09 Y-92 1.S8E+OO O.OOE+OO 4.S3E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.S8E+04 Y-93 2.93E+02 O.OOE+OO B.04E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.37E+06 Zr-9S 3.B6E+06 B.48E+OS 7.SSE+OS O.OOE+OO 1.21E+06 O.OOE+OO B.84E+OB Zr-97 S.70E+02 8.24E+01 4.86E+01 O.OOE+OO 1.18E+02 O.OOE+OO 1.2SE+07 Nb-9S 4.12E+05 1.60E+OS 1.1SE+OS O.OOE+OO 1.S1E+OS O.OOE+OO 2.97E+OB Mo-99 O.OOE+OO 7.71E+06 1.91E+06 O.OOE+OO 1.6SE+07 O.OOE+OO 6.3BE+06 Tc-99m 4.71E+OO 9.24E+OO 1.S3E+02 O.OOE+OO 1.34E+02 4.69E+OO S.26E+03 Tc-101 1.41E-30 1. 47E-30 1. B7E-29 O.OOE+OO 2.S1E-29 7.7BE-31 4.6BE-30 Ru-103 1.S3E+07 O.OOE+OO S.BBE+06 O.OOE+OO 3.BSE+07 O.OOE+OO 3.96E+08 Ru-105 9.16E+01 O.OOE+OO 3.32E+01 O.OOE+OO B.05E+02 O.OOE+OO 5.9BE+04 Ru-106 7.4SE+08 O.OOE+OO 9.30E+07 O.OOE+OO 1.01E+09 O.OOE+OO 1.16E+10 Ag-llOm 3.21E+07 2.17E+07 1.73E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.SBE+09 Sb-122 S.SBE+OS B.24E+03 1.64E+OS 7.16E+03 O.OOE+OO 2.27E+OS 4.30E+07 Sb-124 3.S2E+OB 4.S6E+06 1. 23E+08 7.73E+OS O.OOE+OO 1.9SE+08 2.20E+09 Sb-12S 4.99E+OB 3.84E+06 1.OSE+OB 4.63E+05 O.OOE+OO 2.7BE+OB 1.19E+09 IPEG aDCM Page 89 of 136 . Revision 2

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+01 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+10 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-142 4.11E-39 2.96E-42 2.29E-40 O.OOE+OO 2.39E-42 1.74E-42 5.36E-41 La-140 3.25E+03 1.14E+03 3.83E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.17E+07 La-142 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-144 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 IPEC aDCM Page 90 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-l2a ADULT GRASS/COW/MILK PATHWAY Ri(C) 2 3 m

mrem/yr per uCi/s~c (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 Be-7 1.65E+03 3.73E+03 1.85E+03 O.OOE+OO 3.92E+03 O.OOE+OO 6.44E+05 Na-24 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 P-32 1.71E+10 1. 06E+09 6.61E+08 O.OOE+OO O.OOE+OO O;OOE+OO 1.92E+09 Cr-51 O.OOE+O.O O.OOE+OO 2.86E+04 1.71E+04 6.30E+03 3.79E+04 7.19E+06 Mn-54 O.OOE+OO 8 .. 41E+06 1.61E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.58E+07 Mn-56 O.OOE+OO 4.15E-03 7.36E-04 O.OOE+OO 5.27E-03 O.OOE+OO 1.32E-01 Fe-55 2.51E+07 1.74E+07 4.05E+06 O.OOE+OO O.OOE+OO 9.68E+06 9.95E+06 Fe-59 2.97E+07 6.98E+07 2.67E+07 O.OOE+OO O.OOE+OO 1.95E+07 2.33E+08 Co-58 O.OOE+OO 4.71E+06 1.06E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.55E+07 Co-60 O.OOE+OO 1.64E+07 3.62E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 Ni-63 6.73E+09 4.66E+08 2.26E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.73E+07 Ni-65 3.70E-01 4.81E-02 2.19E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+00 Cu-64 O.OOE+OO 2.38E+04 1.12E+04 O.OOE+OO 6.01E+04 O.OOE+OO 2.03E+06 Zn-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+OO 2.92E+09 O.OOE+OO 2.75E+09 Zn-69 5.18E-12 9.91E-12 6.89E-13 O.OOE+OO 6.44E-12 O.OOE+OO 1.49E-12 Br-83 O.OOE+OO O.OOE+OO 9.72E-02 O.OOE+OO O.OOE+OO *O.OOE+OO 1.40E-01 Br-84 O.OOE+OO O.OOE+OO 1.61E-23 O.OOE+OO O.OOE+OO O.OOE+OO 1.26E-28 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE:I"OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.59E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.12E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+08 Sr-90 4.68E+10 O.OOE+OO 1. 15E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+09 Sr-91 2.89E+04 O.OOE+OO 1.17E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.38E+05 Sr-92 4.88E-01 O.OOE+OO 2.11E-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.68E+00 Y-90 7.07E+01 O.OOE+OO 1.90E+00 O.OOE+OO O.OOE+OO O.OOE+OO 7.49E+05 Y-91m 5.98E-20 O.OOE+OO 2.32E-21 O.OOE+OO O.OOE+OO O.OOE+OO 1.76E-19 Y-91 8.59E+03 O.OOE+OO 2.30E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.73E+06 Y-92 5.58E-05 O.OOE+OO 1.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO 9.77E-01 Y-93 2.23E-01 O.OOE+OO 6.17E-03 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+03

. Zr-95 9.43E+02 3.02E+02 2.05E+02 O.OOE+OO 4.75E+02 O.OOE+OO 9.59E+05 Zr-97 4.33E-01 8.74E-02 4.00E-02 O.OOE+OO 1.32E-01 O.OOE+OO 2.71E+04 Nb-95 8.26E+04 4.60E+04 2.47E+04 O.OOE+OO 4.54E+04 O.OOE+OO 2.79E+08 Mo-99 O.OOE+OO 2.48E+07 4.71E+06 O.OOE+OO 5.61E+07 O.OOE+OO 5.74E+07 Tc-99m 3.32E+00 9.38E+00 1.20E+02 O.OOE+OO 1.43E+02 4.60E+00 5.55E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.02E+03 O.OOE+OO 4.38E+02 O.OOE+OO 3.88E+03 O.OOE+OO 1.19E+05 Ru-105 8.57E-04 O.OOE+OO 3.38E-04 O.OOE+OO 1. 11E-02 O.OOE+OO 5.24E-01 Ru-106 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.94E+04 O.OOE+OO 1.32E+06 Ag-110m 5.82E+07 5.39E+07 3.20E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.20E+10 Sb-122 2.24E+05 5.16E+03 7.73E+04 3.47E+03 O.OOE+OO 1.35E+05 8.52E+07 Sb-124 2.57E+07 4.87E+05 1.01E+07 6.25E+04 O.OOE+OO 2.00E+07 7.31E+08 Sb-125 2.04E+07 2.28E+05 4.86E+06 2.08E+04 O.OOE+OO 1. 58E+07 2.25E+08 IPEC aDCM Page 91 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-l2a ADULT GRASS/COW/MILK PATHWAY Ri(C) 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 1.63E+07 5.90E+06 2.1BE+06 4.90E+06 6.63E+07 O.OOE+OO 6.50E+07 Te-127m 4.5BE+07 1.64E+07 5.5BE+06 1.17E+07 1.B6E+OB O.OOE+OO 1. 54E+OB Te-l27 6.53E+02 2.34E+02 1.41E+02 4.B4E+02 2.66E+03 O.OOE+OO 5.l5E+04 Te-129m 6.02E+07 2.25E+07 9.53E+06 2.07E+07 2.51E+OB O.OOE+OO 3.03E+OB Te-129 2.B2E-10 1.06E-10 6.BBE-ll 2.l7E-10 1.19E-09 O.OOE+OO 2.l3E-10 Te-13lm 3.61E+05 1.77E+05 1.47E+05 2.BOE+05 1. 79E+06 O.OOE+OO 1.75E+07 Te-l3l 3.60E-33 1.51E-33 1.14E-33 2.96E-33 1.5BE-32 O.OOE+OO 5.l0E-34 Te-132 2.40E+06 1.55E+06 1.46E+06 1.72E+06 1.50E+07 O.OOE+OO 7.35E+07 I-l30 4.20E+05 1.24E+06 4.B9E+05 1.05E+OB 1.93E+06 O.OOE+OO 1.07E+06 1-131 2.96E+OB 4.23E+OB 2.43E+OB 1.39E+ll 7.26E+OB O.OOE+OO 1.12E+OB I-l32 1.64E-Ol 4.39E-Ol 1.54E-Ol 1.54E+Ol 7.00E-Ol O.OOE+OO B.25E-02 I-l33 3.B7E+06 6.73E+06 2.05E+06 9.B9E+OB 1.17E+07 O.OOE+OO 6.05E+06 1-134 2.02E-12 5.4BE-12 1. 96E-12 9.49E-ll B.71E-12 O.OOE+OO 4.77E-15 I-l35 1.2BE+04 3.36E+04 1.24E+04 2.22E+06 5.39E+04 O.OOE+OO 3.80E+04 Cs-l34 5.65E+09 1.35E+1O 1.lOE+lO O.OOE+OO 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.46E+08 O.OOE+OO 5.77E+08 7.90E+07 1.18E+08 Cs-137 7.38E+09 1.01E+1O 6.61E+09 O.OOE+OO 3.43E+09 1.l4E+09 1.95E+08 Cs-l3B 9.04E-24 1.79E-23 8.B5E-24 O.OOE+OO 1.31E-23 1.30E-24 7.62E-29 Ba-l39 3.92E-08 2.79E-ll 1.15E-09 O.OOE+OO 2.61E-ll 1. 58E-ll 6.94E-08 Ba-140 2.68E+07 3.37E+04 1.76E+06 O.OOE+OO 1.15E+04 1.93E+04 5.52E+07 Ba-14l O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.52E+OO 2.2BE+00 6.02E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+05 La-142 9.34E-12 4.25E-12 1. 06E-12 O.OOE+OO O.OOE+OO O.OOE+OO 3.l0E-08 Ce-14l 4.84E+03 3.28E+03 3.72E+02 O.OOE+OO 1.52E+03 O.OOE+OO 1. 25E+07 Ce-143 4.l6E+Ol 3.07E+04 3.40E+OO O.OOE+OO 1.35E+Ol O.OOE+OO 1.15E+06 Ce-144 3.58E+05 1.50E+05 1.92E+04 O.OOE+OO B.87E+04 O.OOE+OO 1.2lE+08 Pr-143 1.58E+02 6.33E+Ol 7.83E+OO O.OOE+OO 3.66E+Ol O.OOE+OO 6.92E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 9.42E+Ol 1.09E+02 6.51E+OO O.OOE+OO 6.36E+Ol O.OOE+OO 5.22E+05 W-187 6.56E+03 5.48E+03 1.92E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+06 Np-239 3.68E+OO 3.62E-Ol 2.00E-Ol O.OOE+OO 1.13E+OO O.OOE+OO 7.43E+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 1.28E+06 2.l3E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.25E+07 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 3.29E-12 8.32E-l3 3.04E-l3 O.OOE+OO 9.71E-13 O.OOE+OO 3.07E-09 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-l33 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 8.90E-19 5.83E-19 3.57E-19 7.78E-19 5.63E-18 O.OOE+OO 9.87E-22 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 IPEC aDCM Page 92 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-l2b TEEN GRASS/COW/MILK PATHWAY Ri(C) 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 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 Be-7 3.0SE+03 6.S3E+03 3.41E+03 O.OOE+OO 7.23E+03 O.OOE+OO S.31E+OS Na-24 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 4.26E+06 P-32 3.1SE+1O 1.9SE+09 1.22E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.6SE+09 Cr-S1 O.OOE+OO O.OOE+OO 4.99E+04 2.77E+04 1.09E+04 7.13E+04 S.39E+06 Mn-S4 O.OOE+OO 1.40E+07 2.7SE+06 O.OOE+OO 4.1SE+06 O.OOE+OO 2.S7E+07 Mn-S6 O.OOE+OO 7.36E-03 1.31E-03 O.OOE+OO 9.31E-03 O.OOE+OO 4.S4E-01 Fe-SS 4.4SE+07 3.16E+07 7.36E+06 O.OOE+OO O.OOE+OO 2.00E+07 1.37E+07 Fe-S9 S.lSE+07 1.21E+OS 4.67E+07 O.OOE+OO O.OOE+OO 3.S1E+07 2.S6E+OS Co-SS O.OOE+OO 7.94E+06 1. S3E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.09E+OS Co-60 O.OOE+OO 2.7SE+07 6.26E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.62E+OS Ni-63 1. lSE+lO S.3SE+OS 4.01E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1. 33E+OS Ni-6S 6.77E-01 S.6SE-02 3.94E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.69E+OO Cu-64 O.OOE+OO 4.2SE+04 2.00E+04 O.OOE+OO 1.07E+OS O.OOE+OO 3.29E+06 Zn-6S 2.11E+09 7.31E+09 3.41E+09 O.OOE+OO 4.6SE+09 O.OOE+OO 3.10E+09 Zn-69 9.SSE-12 1. S2E-ll 1.27E-12 O.OOE+OO 1.19E-ll O.OOE+OO 3.3SE-ll Br-S3 O.OOE+OO O.OOE+OO 1.79E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-S4 O.OOE+OO O.OOE+OO 2.SSE-23 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-SS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-S6 O.OOE+OO 4.73E+09 2.22E+09 O.OOE+OO O.OOE+OO O.OOE+OO 7.00E+OS Rb-SS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-S9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-S9 2.67E+09 O.OOE+OO 7.66E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.1SE+OS Sr-90 6.61E+lO O.OOE+OO 1.63E+lO O.OOE+OO O.OOE+OO O.OOE+OO 1. S6E+09 Sr-91 S.31E+04 O.OOE+OO 2.11E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.41E+OS Sr-92 S.94E-01 O.OOE+OO 3.S1E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.2SE+01 Y-90 1. 30E+02 O.OOE+OO 3.S0E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+06 Y-91m 1.lOE-19 O.OOE+OO 4.19E-21 O.OOE+OO O.OOE+OO O.OOE+OO S.17E-18 Y-91 1.S8E+04 O.OOE+OO 4.24E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.48E+06 Y-92 1. 03E-04 O.OOE+OO 2.9SE-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.S3E+OO Y-93 4.12E-01 O.OOE+OO 1.13E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.26E+04 Zr-9S 1.6SE+03 S.20E+02 3.SSE+02 O.OOE+OO 7.6SE+02 O.OOE+OO 1.20E+06 Zr-97 7.SSE-01 1.S6E-01 7.19E-02 O.OOE+OO 2.37E-01 O.OOE+OO 4.22E+04 Nb-9S 1.41E+OS 7.82E+04 4.30E+04 O.OOE+OO 7.S8E+04 O.OOE+OO 3.34E+OS Mo-99 O.OOE+OO 4.47E+07 S.S2E+06 O.OOE+OO 1.02E+OS O.OOE+OO S.OlE+07 Tc-99m S.76E+OO 1.61E+01 2.0SE+02 O.OOE+OO 2.39E+02 S.92E+OO 1.OSE+04 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.SlE+03 O.OOE+OO 7.74E+02 O.OOE+OO 6.3SE+03 O.OOE+OO 1. SlE+OS Ru-1OS 1.S6E-03 O.OOE+OO 6.07E-04 O.OOE+OO 1.97E-02 o :OOE+OO 1.26E+OO Ru-106 3.7SE+04 O.OOE+OO 4.73E+03 O.OOE+OO 7.24E+04 O.OOE+OO 1.SOE+06 Ag-llOm 9.63E+07 9.11E+07 S.S4E+07 O.OOE+OO 1.74E+OS O.OOE+OO 2.S6E+lO Sb-122 4.77E+OS 9.29E+03 1.39E+OS 6.06E+03 O.OOE+OO *2.9SE+OS 1.OOE+OS Sb-124 4.SSE+07 S.44E+OS 1.79E+07 1.04E+OS O.OOE+OO 4.00E+07 9.26E+OS Sb-12S 3.6SE+07 3.99E+OS S.S3E+06 3.4SE+04 O.OOE+OO 3.1SE+07 2.S3E+OS IPEC aDCM Page 93 of 136 Revision 2

aDCM Part" - Calculational Methodologies Table 3-l2b TEEN GRASS/COW/MILK PATHWAY Ri(C) 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 3.00E+07 1.08E+07 4.02E+06 8.39E+06 O.OOE+OO O.OOE+OO 8.86E+07 Te-127m 8.44E+07 2.99E+07 1.00E+07 2.01E+07 3.42E+08 O.OOE+OO 2.10E+08 Te-l27 1.21E+03 4.29E+02 2.60E+02 8.35E+02 4.90E+03 O.OOE+OO 9.34E+04 Te-129m 1.10E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 O.OOE+OO 4.13E+08 Te-129 5.20E-10 1.94E-10 1.26E-10 3.71E-10 2.18E-09 O.OOE+OO 2.84E-09 Te-131m 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.29E+06 O.OOE+OO 2.53E+07 Te-131 6.58E-33 2.71E-33 2.06E-33 5.07E-33 2.88E-32 O.OOE+OO 5.40E-34 Te-132 4.29E+06 2.72E+06 2.56E+06 2.87E+06 2.61E+07 O.OOE+OO 8.61E+07 1-130 7.38E+05 2.14E+06 8.53E+05 1. 74E+08 3.29E+06 O.OOE+OO 1.64E+06 1-131 5.37E+08 7.52E+08 4.04E+08 2.19E+11 1.29E+09 O.OOE+OO 1.49E+08 1-132 . 2. 91E-01 7.62E-Ol 2.74E-Ol 2.57E+Ol 1.20E+00 O.OOE+OO 3.32E-Ol 1-133 7.07E+06 1.20E+07 3.66E+06 1.67E+09 2.10E+07 O.OOE+OO 9.07E+06 1-134 3.58E-12 9.50E-12 3.41E-12 1.58E-I0 1. 50E-11 O.OOE+OO 1. 25E-13 1-135 2.28E+04 5.87E+04 2.18E+04 3.78E+06 9.27E+04 O.OOE+OO 6.51E+04 Cs-134 9.82E+09 2.31E+I0 1.07E+I0 O.OOE+OO 7.34E+09 2.80E+09 2.87E+08 Cs-136 4.47E+08 1.76E+09 1.18E+09 O.OOE+OO 9.57E+08 1.51E+08 1.42E+08 Cs-137 1.34E+10 1.78E+10 6.20E+09 O.OOE+OO 6.06E+09 2.35E+09 2.53E+08 Cs-138 1.64E-23 3.15E-23 1.57E-23 O.OOE+OO 2.33E-23 2.71E-24 1.43E-26 Ba-139 7.24E-08 5.09E-11 2.11E-09 O.OOE+OO 4.80E-11 3.51E-11 6.46E-07 Ba-140 4.84E+07 5.93E+04 3.12E+06 O.OOE+OO 2.01E+04 3.99E+04 7.46E+07 Ba-l41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 8.12E+00 3.99E+00 1.06E+00 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+05 La-142 1.69E-11 7.49E-12 1. 86E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E-07 Ce-141 8.88E+03 5.93E+03 6.81E+02 O.OOE+OO 2.79E+03 O.OOE+OO 1.70E+07 Ce-l*:J3 7.64E+01 5.56E+04 6.21E+00 O.OOE+OO 2.49E+Ol O.OOE+OO 1.67E+06 Ce-144 6.58E+05 2.72E+05 3.54E+04 O.OOE+OO 1.63E+05 O.OOE+OO 1.66E+08 Pr-143 2.90E+02 1.16E+02 1.44E+Ol O.OOE+OO 6.73E+Ol O.OOE+OO 9.54E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.81E+02 1.97E+02 1.18E+Ol O.OOE+OO 1.16E+02 O.OOE+OO 7.11E+05 W-187 1.20E+04 9.78E+03 3.43E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.65E+06 Np-239 7.03E+00 6.63E-01 3.68E-Ol O.OOE+OO 2.08E+00 O.OOE+OO 1.07E+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 2.25E+06 3.76E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.19E+07 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 5.99E-12 1.49E-12 5.43E-13 O.OOE+OO 1.74E-12 O.OOE+OO 3.55E-08 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 1.59E-18 1.02E-18 1. 06E-18 1. 30E-18 9.72E-18 O.OOE+OO 5.89E-20 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 IPEC aDCM Page 94 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-12c CHILD GRASS/COW/MILK PATHWAY Ri(C) 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 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 Be-7 7.49E+03 1.27E+04 8.38E+03 O.OOE+OO 1.25E+04 O.OOE+OO 7.11E+05 Na-24 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 8.85E+06 P-32 7.78E+10 3.64E+09 3.00E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+09 Cr-51 O.OOE+OO O.OOE+OO 1.02E+05 5.65E+04 1. 54E+04 1.03E+05 5.40E+06 Mn-54 O.OOE+OO 2.10E+07 5.59E+06 O.OOE+OO 5.88E+06 O.OOE+OO 1.76E+07 Mn-56 O.OOE+OO 1.28E-02 2.90E-03 O.OOE+OO 1. 55E-02 O.OOE+OO 1.86E+00 Fe-55 1. 12E+08 5.93E+07 1. 84E+07 O.OOE+OO O.OOE+OO 3.35E+07 1.10E+07 Fe-59 1.20E+08 1.94E+08 9.68E+07 O.OOE+OO O.OOE+OO 5.64E+07 2.02E+08 Co-58 O.OOE+OO 1.21E+07 3.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.07E+07 Co-60 O.OOE+OO 4.32E+07 1.27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+08 Ni-63 2.96E+10 1.59E+09 1.01E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1. 07E+08 Ni-65 1.66E+00 1.56E-01 9.10E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E+01 cu-64 O.OOE+OO 7.46E+04 4.51E+04 O.OOE+OO 1. 80E+05 O.OOE+OO 3.50E+06 Zn-65 4.13£+09 1.10E+10 6.85E+09 O.OOE+OO 6.94E+09 O.OOE+OO 1.93E+09 Zn-69 2.35£-11 3.39E-11 3.13E-12 O.OOE+OO 2.06E-11 O.OOE+OO 2.14E-09 Br-83 0.00£+00 O.OOE+OO 4.40E-01 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Br-84 0.00£+00 O.OOE+OO 6.51E-23 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 0.00£+00 8.77E+09 5.39E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.64E+08 Rb-88 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 6.62£+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.56E+08 Sr-90 1.12£+11 O.OOE+OO 2.83E+10 O.OOE+OO 0.00£+00 O.OOE+OO 1.51E+09 Sr-91 1.30E+05 O.OOE+OO 4.92E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.88E+05 Sr-92 2.18E+00 O.OOE+OO 8.75E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.13E+01 Y-90 3.21£+02 O.OOE+OO 8.60E+00 O.OOE+OO O.OOE+OO O.OOE+OO 9.15E+05 Y-91m 2.68£-19 O.OOE+OO 9.74E-21 O.OOE+OO O.OOE+OO O.OOE+OO 5.24E-16 Y-91 3.90E+04 O.OOE+OO 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E+06 Y-92 2.53£-04 O.OOE+OO 7.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.31E+00 Y-93 1.01E+00 O.OOE+OO 2.78E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1. 51E+04 Zr-95 3.83E+03 8.42E+02 7.50E+02 O.OOE+OO 1.21E+03 O.OOE+OO 8.79E+05 Zr-97 1.92E+00 2.77E-01 1.64E-01 O.OOE+OO 3.98E-01 O.OOE+OO 4.20E+04 Nb-95 3.18E+05 1.24E+05 8.85E+04 O.OOE+OO 1.16E+05 O.OOE+OO 2.29E+08 Mo-99 O.OOE+OO 8.13£+07 2.01E+07 O.OOE+OO 1.74E+08 O.OOE+OO 6.73E+07 Tc-99m 1.32E+01 2.59£+01 4.29E+02 O.OOE+OO 3.76E+02 1.32E+01 1.47E+04 Tc-101 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 0.00£+00 Ru-103 4.28E+03 0.00£+00 1.65E+03 O.OOE+OO 1.08E+04 O.OOE+OO 1.11E+05 Ru-105 3.82E-03 0.00£+00 1.39E-03 O.OOE+OO 3.36E-02 O.OOE+OO 2.49E+00 Ru-106 9.24£+04 0.00£+00 1.15E+04 O.OOE+OO 1.25E+05 O.OOE+OO 1.44E+06 Ag-110m 2.09£+08 1.41£+08 1.13E+08 O.OOE+OO 2.63E+08 O.OOE+OO 1.68E+10 Sb-122 1.17E+06 1.73£+04 3.44E+05 1.50E+04 O.OOE+OO 4.77E+05 9.02E+07 Sb-124 1.09£+08 1.41£+06 3.80E+07 2.39E+05 O.OOE+OO 6.02E+07 6.78E+08 Sb-125 8.69E+07 6.70£+05 1.82E+07 8.06E+04 O.OOE+OO 4.84E+07 2.08E+08 IPECODCM Page 95 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-12c CHILD GRASS/COW/MILK PATHWAY Ri (C) 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-12sm 7.3SE+07 2.00E+07 9.S4E+06 2.07E+07 O.OOE+OO O.OOE+OO 7.12E+07 Te-127m 2.0SE+OS s.60E+07 2.47E+07 4.97E+07 s.93E+OS O.OOE+OO 1.6SE+OS Te-127 2.9SE+03 S.02E+02 6.3SE+02 2.06E+03 S.47E+03 O.OOE+OO 1.16E+Os Te-129m 2.71E+OS 7.sSE+07 4.21E+07 S.7sE+07 7.97E+OS O.OOE+OO 3.31E+OS Te-129 1.2SE-09 3.sSE-10 3.04E-1O 9.1sE-10 3.7sE-09 O.OOE+OO 7.9SE-OS Te-131m 1.60E+06 s.s3E+Os s.S9E+Os 1.14E+06 s.3sE+06 O.OOE+OO 2.24E+07 Te-131 1.62E-32 4.93E-33 4.S1E-33 1.24E-32 4.S9E-32 O.OOE+OO S.49E-32 Te-132 1.02E+07 4.s3E+06 s.4SE+06 6.60E+06 4.21E+07 O.OOE+OO 4.s7E+07 1-130 1.73E+06 3.49E+06 1.S0E+06 3.S4E+OS s.22E:+-06 O.OOE+OO 1.63E+06 1-131 1.30E+09 1. 31E+09 7.4sE+OS 4.33E+l1 2.1sE+09 O.OOE+OO 1.17E+OS 1-132 6.S9E-01 1.27E+00 s.S2E-01 s.S7E+01 1.94E+00 O.OOE+OO 1.49E+00 1-133 1. 72E+07 2.12E+07 S.03E+06 3.94E+09 3.s4E+07 O.OOE+OO S.s6E+06 1-134 S.4SE-12 1. sSE-ll 7.2sE-12 3.62E-10 2.41E-ll O.OOE+OO 1.04E-ll I-US s.40E+04 9.72E+04 4.60E+04 S.61E+06 1.49E+Os O.OOE+OO 7.40E+04 Cs-134 2.26E+lO 3.72E+1O 7.S4E+09 O.OOE+OO 1.lsE+1O 4.13E+09 2.00E+OS Cs-136 1.01E+09 2.77E+09 L 79E+09 O.OOE+OO 1. 4SE+09 2.20E+OS 9.74E+07 Cs-137 3.22E+lO 3.09E+lO 4.ssE+09 O.OOE+OO 1.0lE+lO 3.62E+09 1.93E+OS Cs-13S 3.9SE-23 s.s3E-23 3.s1E-23 O.OOE+OO 3.S9E-23 4.19E-24 2.ssE-23 Ba-139 1.78E-07 9.s0E-ll s.16E-09 O.OOE+OO S.29E-ll s.s9E-ll 1.03E-Os Ba-140 1.17E+OS 1.02E+Os 6.S2E+06 O.OOE+OO 3.33E+04 6.10E+04 s.92E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.94E+01 6.S0E+OO 2.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.S9E+Os La-142 4.07E-ll 1. 30E-ll 4.06E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.s7E-06 Ce-141 2.19E+04 1.09E+04 1.62E+03 O.OOE+OO 4.7SE+03 O.OOE+OO 1.36E+07 Ce-143 1.S7E+02 1.02E+Os 1.47E+01 O.OOE+OO 4.26E+01 O.OOE+OO 1.49E+06 Ce-144 1.62E+06 s.09E+Os S.66E+04 O.OOE+OO 2.S2E+Os O.OOE+OO 1.33E+OS Pr-143 7.1SE+02 2.16E+02 3.s6E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7.7sE+Os Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 4.4sE+02 3.60E+02 2.79E+01 O.OOE+OO 1.9SE+02 O.OOE+OO s.70E+Os W-1S7 2.91E+04 1. 72E+04 7.73E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.42E+06 Np-239 1.73E+01 1.24E+OO S.73E-01 O.OOE+OO 3.s9E+OO O.OOE+OO 9.19E+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 3.S4E+06 7.77E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+07 Sr-Ss O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-SS 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 1.46E-ll 2.63E-12 1.23E-12 O.OOE+OO 2.92E-12 O.OOE+OO S.12E-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-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 3.77E-1S 1.70E-1S 2.26E-1S 2.9SE-1S 1.s7E-17 O.OOE+OO 1.72E-17 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 IPEC aDCM Page 96 of 136 Revision 2

aDCM Part II - Calcuiational Methodologies Table 3-12d INFANT GRASS/COW/MILK PATHWAY Ri(C) 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 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 Be-7 1.43E+04 3.00E+04 1.59E+04 O.OOE+OO 2.12E+04 O.OOE+OO 7.05E+05 Na-24 1.54E+07 1.54E+07 1. 54E+07 1. 54E+07 1.54E+07 1.54E+07 1.54E+07 P-32 1.60E+ll 9.43E+09 6.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E+09 Cr-51 O.OOE+OO O.OOE+OO 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 Mn-54 O.OOE+OO 3.90E+07 8.84E+06 O.OOE+OO 8.64E+06 O.OOE+OO 1.43E+07 Mn-56 O.OOE+OO 3.14E-02 5.42E-03 O.OOE+OO 2.70E-02 O.OOE+OO 2.85E+OO Fe-55 1.35E+08 8.73E+07 2.33E+07 O.OOE+OO O.OOE+OO 4.27E+07 1.llE+07 Fe-59 2.24E+08 3.92E+08 1. 54E+08 O.OOE+OO O.OOE+OO 1.16E+08 1. 87E+08 Co-58 O.OOE+OO 2.42E+07 6.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.04E+07 Co-60 O.OOE+OO 8.82E+07 2.08E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+08 Ni-63 3.49E+lO 2.16E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1. 07E+08 Ni-65 3.50E+OO 3.97E-Ol 1. 80E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 3.02E+Ol Cu-64 O.OOE+OO 1.86E+OS 8.S9E+04 O.OOE+OO 3.14E+OS O.OOE+OO 3.81E+06 Zn-6S S.SSE+09 1.90E+IO 8.78E+09 O.OOE+OO 9.23E+09 O.OOE+OO 1.61E+IO Zn-69 5.00E-ll 9.00E-ll 6.70E-12 O.OOE+OO 3.74E-ll O.OOE+OO 7.34E-09 Br-83 O.OOE+OO O.OOE+OO 9.34E-Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.26E-22 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S 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 2.23E+IO 1.lOE+IO O.OOE+OO O.OOE+OO O.OOE+OO 5.69E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1. 26E+IO O.OOE+OO 3.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+08 Sr-90 1. 22E+ll O.OOE+OO 3.10E+IO O.OOE+OO O.OOE+OO O.OOE+OO 1.S2E+09 Sr-91 2.72E+OS O.OOE+OO 9.83E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+05 Sr-92 4.64E+OO O.OOE+OO 1.72E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 5.00E+Ol Y-90 6.80E+02 O.OOE+OO 1.82E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 9.39E+05.

Y-91m S.67E-19 O.OOE+OO 1.93E-20 O.OOE+OO O.OOE+OO O.OOE+OO 1.89E-lS Y-91 7.33E+04 O.OOE+OO 1.95E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.25E+06 Y-92 5.38E-04 O.OOE+OO 1.51E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1. 03E+Ol Y-93 2.16E+OO O.OOE+OO 5.87E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.70E+04 Zr-95 6.80E+03 1.66E+03 1.18E+03 O.OOE+OO 1.79E+03 O.OOE+OO 8.26E+OS Zr-97 4.06E+OO 6.97E-Ol 3.18E-Ol O.OOE+OO 7.03E-Ol O.OOE+OO 4.45E+04 Nb-9S 5.94E+OS 2.45E+OS 1.41E+05 O.OOE+OO 1.7SE+05 O.OOE+OO 2.06E+08 Mo-99 O.OOE+OO 2.08E+08 4.05E+07 O.OOE+OO 3.11E+08 O.OOE+OO 6.85E+07 Tc-99m 2.75E+Ol 5.67E+Ol 7.30E+02 O.OOE+OO 6.10E+02 2.96E+Ol 1.65E+04 Tc-lOl O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 8.67E+03 O.OOE+OO 2.90E+03 O.OOE+OO 1.80E+04 O.OOE+OO 1.05E+05 Ru-105 8.05E-03 O.OOE+OO 2.71E-03 O.OOE+OO 5.92E-02 O.OOE+OO 3.20E+OO Ru-106 1.90E+05 O.OOE+OO 2.38E+04 O.OOE+OO 2.25E+05 O.OOE+OO 1.44E+06 Ag-llOm 3.86E+08 2.82E+08 1.86E+08 O.OOE+OO 4.03E+08 O.OOE+OO 1.46E+lO Sb-122 2.51E+06 4.59E+04 7.31E+05 3.75E+04 O.OOE+OO 1.30E+06 9.13E+07 Sb-124 2.09E+08 3.08E+06 6.49E+07 5.56E+05 O.OOE+OO 1. 31E+08 6.46E+08 Sb-125 1. 50E+08 1.45E+06 3.08E+07 1.87E+05 O.OOE+OO 9.38E+07 1.99E+08 IPEC aDCM Page 97 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-12d INFANT GRASS/COW/MILK PATHWAY Ri(C) 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 1.51E+08 5.04E+07 2.04E+07 5.07E+07 O.OOE+OO O.OOE+OO 7.18E+07 Te-127m 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+OO 1.70E+08 Te-127 6.32E+03 2.12E+03 1.36E+03 5.14E+03 1.54E+04 O.OOE+OO 1.33E+05 Te-129m 5.57E+08 1. 91E+08 8.58E+07 2.14E+08 1.39E+09 O.OOE+OO 3.33E+08 Te-129 2.72E-09 9.37E-10 6.35E-10 2.28E-09 6.77E-09 O.OOE+OO 2.17E-07 Te-131m 3.38E+06 1.36E+06 1.12E+06 2.75E+06 9.35E+06 O.OOE+OO 2.29E+07 Te-131 3.43E-32 1.27E-32 9.62E-33 3.06E-32 8.76E-32 O.OOE+OO 1.38E-30 Te-132 2.11E+07 1.04E+07 9.75E+06 1.54E+07 6.53E+07 O.OOE+OO 3.87E+07 1-130 3.55E+06 7.81E+06 3.13E+06 8.75E+08 8.58E+06 O.OOE+OO 1.67E+06 I-131 2.72E+09 3.20E+09 1.41E+09 1. 05E+12 3.74E+09 O.OOE+OO 1.14E+08 1-132 1.43E+00 2.90E+00 1.03E+00 1.36E+02 3.24E+00 O.OOE+OO 2.35E+00 I-133 3.63E+07 5.28E+07 1. 55E+07 9.60E+09 6.21E+07 O.OOE+OO 8.93E+06 1-134 1.76E-11 3.60E-11 1. 28E-11 8.40E-10 4.03E-11 O.OOE+OO 3.73E-11 I-135 1.12E+05 2.23E+05 8.14E+04 2.00E+07 2.49E+05 O.OOE+OO 8.08E+04 Cs-134 3.65E+10 6.80E+10 6.87E+09 O.OOE+OO 1.75E+10 7.18E+09 1.85E+08 Cs-136 1.97E+09 5.79E+09 2.16E+09 O.OOE+OO 2.31E+09 4.72E+08 8.80E+07 Cs-137 5.15E+10 6.02E+10 4.27E+09 O.OOE+OO 1.62E+10 6.55E+09 1.88E+08 Cs-138 8.39E-23 1.36E-22 6.61E-23 O.OOE+OO 6.80E-23 1.06E-23 2.18E-22 Ba-139 3.79E-07 2.51E-10 1.10E-08 O.OOE+OO 1.51E-10 1.52E-10 2.40E-05 Ba-140 2.40E+08 2.40E+05 1.24E+07 O.OOE+OO 5.71E+04 1.48E+05 5.91E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.06E+01 1.60E+01 4.12E+00 O.OOE+OO O.OOE+OO O.OOE+OO l.88E+05 La-142 8.55E-11 3.14E-11 7.51E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5.33E-06 Ce-141 4.34E+04 2.64E+04 3.11E+03 O.OOE+OO 8.15E+03.0.00E+00 1.37E+07 Ce-143 3.97E+02 2.63E+05 3.00E+01 O.OOE+OO 7.67E+01 O.OOE+OO 1.54E+06 Ce-144 2.33E+06 9.52E+05 1. 30E+05 O.OOE+OO 3.85E+05 O.OOE+OO 1. 33E+08 Pr-143 1.49E+03 5.55E+02 7.36E+01 O.OOE+OO 2.06E+02 O.OOE+OO 7.84E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 8.81E+02 9.05E+02 5.55E+01 O.OOE+OO 3.49E+02 O.OOE+OO 5.74E+05 W-187 6.12E+04 4.26E+04 1.47E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+06 Np-239 3.66E+01 3.27E+00 1. 85E+00 O.OOE+OO 6.53E+00 O.OOE+OO 9.46E+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 8.95E+06 1.46E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3 .. 05E+07 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 IPECODCM Page 98 of 136 Revision 2

aDCM Part II - Calculational Methodologies Table 3-13 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 1.802E-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+I0 2.53E+10 Ni-63 2.290E-I0 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 3.78E+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-I0 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 2.324E-04 1. OOE+05 1.16E+05 Y-91 1.371E-07 1.07E+06 1. 21E+06 Y-92 5.439E-05 1.80E+05 2.14E+05 Y-93 1.906E-05 1.83E+05 2.51E+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-l0l 8.136E-04 2.04E+04 2.26E+04 Ru-l03 2.042E-07 1.08E+08 1.26E+08 Ru-l05 4.337E-05 6.36E+05 7.21E+05 Ru-l06 2.179E-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 7.935E-09 2.34E+09 2.64E+09 IPEC aDCM Page 99 of 136 Revision 2

ODCM Part II - Calculational Methodologies Table 3-13 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 1.3S3E-07 1.55E+06 2.13E+06 Te-127m 7.360E-OS 9.16E+04 1.0SE+05 Te-127 2.059E-05 2.9SE+03 3.2SE+03 Te-129m 2.3SSE-07 1.9SE+07 2.31E+07 Te-129 1.660E-04 2.62E+04 3.10E+04 Te-131m 6.41SE-06 S.03E+06 9.46E+06 Te-131 4.621E-04 2.92E+04 3.45E+07 Te-132 2.462E-06 4.23E+06 4.9SE+06 1-130 1.55SE-05 5.51E+06 6.69E+06 1-131 9.97SE-07 1.72E+07 2.09E+07 1-132 S.371E-05 1. 25E+06 1.46E+06 1-133 9.257E-06 2.45E+06 2.9SE+06 1-134 2.196E-04 4.47E+05 5.30E+05 1-135 2.913E-05 2.53E+06 2.95E+06 Cs-134 1.066E-OS 6.S6E+09 S.00E+09 Cs-136 6.124E-07 1.50E+08 1.70E+OS Cs-137 7.327E-10 1.03E+10 1.20E+10 Cs-13S 3.5SSE-04 3.59E+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-l40 4.781E-06 1.92E+07 2.1SE+07 La-142 1.249E-04 7.36E+05 S.S4E+05 Ce-141 2.468E-07 1.37E+07 1.54E+07 Ce-143 5.835E-06 2.31E+06 2.63E+06 Ce-144 2.822E-OS 6.95E+07 S.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-1S7 8.056E-06 2.36E+06 2.74E+06 Np-239 3.399E-06 1.71E+06 1.98E+06 K-40 1. 717E-1 7 O.OOE+OO O.OOE+OO Co-57 2.961E-OS 1.8SE+OS 2.07E+OS Sr-S5 1.237E-07 O.OOE+OO O.OOE+OO Y-88 7.523E-OS 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-OS O.OOE+OO O.OOE+OO Sn-1l3 6.970E-08 O.OOE+OO O.OOE+OO Ba-133 2.047E-09 O.OOE+OO O.OOE+OO Te-134 2.764E-04 2.22E+04 2.66E+04 Ce-139 5.S2SE-OS O.OOE+OO O.OOE+OO Hg-203 1.722E-07 O.OOE+OO O.OOE+OO IPEC ODCM Page 100 of 136 Revision 2

ODCM Part II - Calculational Methodologies 4.0 TOTAL DOSE DETERMINATIONS 4.1 40CFR 190 Dose Evaluation Per RECS D3.4, the direct radiation component for potential offsite dose is routinely determined and reported, along with doses from effluent. Radiological Support has determined bounding calculations (using References 26 through 29) as follows:

Direct Radiation Dose =VC + IRWSF + SGM + ISFSI + RMHAs where; VC = The Vapor Containment structures IRWSF = The Interim Radioactive Waste Storage Facility SGM = The Steam Generator Mausoleums (both units)

ISFSI = The Dry Cask Storage Facility, once active RMHA = Radioactive Material Handling Areas, as posted, summed Other structures or tanks are included as determined by Rad Support. The calculations in References 26 through 29 were performed in order to meet the requirements of the annual effluent report, and 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 10CFR20 ... "

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.

ISFSI dose rate calculations and specification are bounded by a conservatively applied maximum annual dose of 17 mrem at the site boundary. This special bounding criteria ensure that combined offsite doses (effluent and direct shine) are in compliance with 40CFR190.

4.2 Doses From Liquid Releases Doses to real individuals can be determined with the same (maximum individual) methodology described in the ODCM, but with more realistic assumptions with regard to dilution, diet, and occupenncy. Actual radionuclide concentrations in foodstuffs can be applied per the Radiological Environmental Monitoring Program (REMP), such that more accurate doses are determined from actual intakes, rather than models only.

4.3 Doses From Atmospheric Releases Similarly, real individual methodology can be substituted for maximum individual modeling for airborne releases. Specific dose transfer factors can be used in lieu of weighted dose transfer factors. Information on the location and occupancy of real individuals, as well as more precise meteorological information and the consumption of foodstuffs, can be employed to re-calculate more accurate doses. The REMP can also provide actual concentrations to apply for a more accurate determination than modeling alone.

IPEC ODCM Page 101 of136 Revision 2

ODCM Part II - Calculational Methodologies Data from the land use census can be used to either extend times from food production to consumption, or otherwise show that the exposure of the critical receptors is reduced.

Also, estimates of direct exposure through calculation may be supplanted by REMP results, since these are often more indicative of the true impact at specific locations. Default values used in NUREG-0133 and Reg Guide 1.109 methodology can be supplanted by more specific values if there has been sufficient science and pedigree involved in their determination.

4.4 Doses to MEMBERS OF THE PUBLIC Visiting the Site Per the RECS Bases, and the discussion regarding gaseous effluent dose rate, visiting MEMBERS OF THE PUBLIC will receive negligible dose from plant effluents, 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 / 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 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.

IPEC ODCM Page 102 of 136 Revision 2

aDCM Part II - Calculational Methodologies 5.0 LOWER LIMIT OF DETECTION (LLDl 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 * ~1 +(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 ~Ci) 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 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.

IPEC aDCM Page 103 of 136 Revision 2

ODCM Part II - 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. Chern.

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) energy 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 mustbe defined, which has been identified as the Critical Level. Following an experimental observation, one must decide whether or not a 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 II 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 tiTs)0.5 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.2 for Lc determination at less than 0.05, the equation for the LLD (which places .2 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 RECS. This calculation, if necessary, will be performed on a case by case basis.

IPEC ODCM Page 104 of 136 Revision 2

ODCM Part II - Calculational Methodologies 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-SMM-CY-001, "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. Kerns 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.

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ODCM Part II - Calculational Methodologies

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).

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-0000 1, "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 (2/17/72) (Safety Guide 23 and and proposed revision 1 to the Reg Guide).

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, "IP3-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, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors."

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. International 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".

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ODCM Part II - Calculational Methodologies

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.

34~ Indian Point Technical Specifications (all units).

35. Indian Point Final Safety Analysis Reports (all units).

36. 10CFR20, "Standards for Protection Against Radiation."

37. 40CFR190, "Environmental Rad Protection Standards for Nuclear Power Operations."

38. 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."

39. G. Knoll, "Radiation Detection and Measurement," (1979)

40. TS (RS) 92-24, "Ingestion Dose Factor Methodology."

41. NPG (RS) 92-88, "Process and Effluent Monitor Energy Calibration."

42. NPG (RS) 92-97, "Effective Stack Height for Blowdown Flash Tank Vent."

43. IPEC-CHM-05-022, "Alternative Methods for Liq Rad Monitor Setpoints / Conv Factors."

44. . IPEC Chemistry Department Procedures 0-CY-2730 and 0-CY-2740, Airborne and Liquid Radioactive Effluents.

45. IPEC-CHM-06-026, Reporting Levels and Lower Limits of Detection for Sr-90 in REMP.

46. IPEC-CHM-08-008, Reporting Levels and Lower Limits of Detection for Ni-63 in REMP.

IPEC ODCM Page 107 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIX A

SUMMARY

of RADIOLOGICAL EFFLUENT CONTROLS (RECS)

LIQUID: AIRBORNE:

Dose The diluted concentration of ~ach Rate isotope in UNRESTRICTED AREAS Dose rate is limited at or beyond the SITE BOUNDARY to:

is limited to ten times the ECs of 10CFR20, defined as the Maximum

500 mrem/yr whole body, per site, for noble gases; Permissible Concentrations (MPCw)

3000 mrem/yr to the skin, per site, for noble gases; identified per Section D1.1. The

1500 mrem/yr to any organ, per site for iodine-131 ,

diluted concentration of dissolved or tritium, or 8 day particulates.

entrained noble gases is limited to 2E-4 uCi/ml.

Cumulative Dose commitment to any member Air Dose at the SITE BOUNDARY is limited to:

Dose of public in UNRESTRICTED 5 mrad per quarter and 10 mrad per year for noble AREAS is limited to:

gases, gamma air dose;

1) In any calendar quarter, 1.5 10 mrad per quarter and 20 mrad per year for noble mrem to the total body and 5 gases, beta air dose.

mrem to any organ.

2) In a calendar year, 3 mrem to Maximum Individual Dose to a Member of the Public at the total body and 10 mrem to the nearest resident is limited to 7.5 mrem per qtr and any organ. 15 mrem per yr for Iodine, H-3, & 8 day particulates to any organ.

Dose Projection Projection of liquid effluent doses Projection of airborne effluent doses shall be computed shall be computed at least every 31 at least every 31 days. If projected doses exceed days. If projected doses exceed:

0.2 mrad gamma air dose, 0.06 mrem total body, or 0.4 mrad beta air dose, or 0.2 mrem critical organ, 0.3 mrem to any organ at the nearest residence, clean-up treatmen~ systems are clean-up treatment systems are required to be required to be operational and operational.

applied to future releases.

TOTAL DOSE:

(includes all effluents, plus direct shine from holding pens, or ISFSI, etc) 25 mrem/yr, all sources, whole body or any organ except thyroid, 75 mrem/yr, all sources, thyroid.

IPEC aDCM Page 108 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIX B (Page 1 of 2)

UNITS 1 and 2 LIQUID EFFLUENT SIMPLIFIED FLOW DIAGRAM I 6/09 80-10, Roof & Floor Drains, SeD, etc Discharge Canal ~

}-----r---I~ U1 Foundation Drain }---.

R-49 Sec Boiler Service Water R-52 Blowdown HX Pllrifir.::ltinn SG water

-51 North Curtain Drain R-62 wI totalizer Sphere Foundation Drain Sumo 13 WDST R-54 SW 14 WDST R-47 (:::~::}"""""-'"'-'-I'-------,

SW IE Bulletin 80-10*

Including Storm Drains, Condensate, roof drains, and Groundwater Hudson River

IE Bulletin 80-10 systems include House Service Boiler Blowdown and other Aux Condensate, Service Water Return, Unit 1 Foundation Drain, Utility Tunnel Sump, etc. 6/09 These and other systems are monitored per the IPEC 80-10 compliance program. Any identified effluent is evaluated for inclusion in integrated totals.

IPEC aDCM Page 109 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIX B (Page 2 or 2)

UNIT 3 LIqUID EFFLUENT SIMPLIFIED FLOW DIAGRAM Flash Tank Venl see Fiqure 3-1 Ip ,#'1 Waste Processing b:

Steam Generator' slowdown

¢ S

(4),

H A

R

)-----' -["""J Polisher G

E Turbine,Hall Drains

____.Monitor TankVent Waste, I ' Se~Figure 3-1 HOldup Waste Tanks Processing Monitor Tanks Fan Cooler

't.:Jnff' ,

1....._ _ _ _..... Service

~_ _ _ _~' VVarer ~-------~----~--------T-------------~'

FCU Motor R R CqOI~rs Component Cooling Water

,I r ,~_-r---I Component Cooling HeatEXchan\Jer Service, Water L--.:,component

'Cooling Water Storm Drains; Grbund Water, and 80-10 ii, To Hudson River' IPEC aDCM Page 110 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIXC (Page 1 of 2)

UNITS 1 and 2 GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM I 6/09 Containment Pressure Relief Containment Purge Unit 2 Vent - -......*~IIcR;--:4:4"---** atmosphere

22 Aux Feed Pump Vent, SG Atmospherics, or Safeties 1--. atmosphere Fuel Storage Building Steam Generators R-49

-I R-45 containment ..

R-5976 I-------------.~ atmosphere MOB Exhaust

1 Unit 2 SG Slowdown Flash Tank BID Flash Tank -------------i.~ atmosp h ere Vent (Unit 2)

Unit 1 SG Slowdown 1----+ BID Flash Tank ------------t_~ atmosphere Flash Tank Vent (Unit l,forSBBPS)

CSB Exhaust NS B Exhaust Unit I Stack ----I.~ atmosphere Unit I Annulus E~haust House Service Boilers IPEC aDCM Page 111 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIXC (Page 2 of 2)

UNIT 3 GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM Batch Release Vents Cont.

Release Monitor Point Tanks Liquid Cont.

Waste Release Point Recirc See

'-----__<11--'---+ River Figure 2-1 (on high alarm) r--

I I

I PV I

___ IL __

I I

I Fill RCV-014 Waste Gas Cont.

Tanks Release Point Fuel Storage Building Cont.

Release Radioactive Point Machine Shop Trubine Cont.

Administration Release Building Points

32 Aux Feed Pump Excess Steam Vent Main Steam Atmospherics and Safeties SIG BID STEAM

32 Aux GEN Generator Feed Pump Blow-down FlashTank to to BDR River IPEC aDCM Page 112 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX 0 STEAM PARTITION FACTOR CALCULATION (f)

The Steam Partition Factor f for the Unit 2 flash tank vent is given by:

For the secondary boiler blowdown purification system flash tank, the factor f is calculated by:

f = hSD - 291 895 Where; hSD is the enthalpy of blowdown liquid, as taken from SOP 15.1, "Calorimetric

=

Thermal Power Calculation," in STU/Ibm. A typical value 500 STU/Ibm.

180 or 291 is the enthalpy of condensed water in each flash tank, in STU/Ibm 970 or 895 is the enthalpy of associated with the latent heat of vaporization in each tank, in STU/Ibm f = A multiplicative factor used to determine the curies of H-3 escaping the flash tank vent, as follows:

f

SGSD activity (uCi/ml)

SGSD flowrate (gpm)

3785 ml/gal

min = uCi released from vent (1-0

SGSD activity (uCi/ml)

SGSD flowrate (gpm)

3785 ml/gal

min = Liquid uCi released IPEC ODCM Page 113 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIX E ALLOWED DILUTED CONCENTRATION (ADC)

The Allowed Diluted Concentration (ADC) is derived and calculated as follows:

ADC= MPCWt

CG or ADC= MPCWt

CG or Total activity CGtCB Where; ADC = Allowed diluted concentration in IlCilml MPCWt = Maximum permissible concentration in water for all isotopes (beta &

gamma), in uCi/ml, as defined in RECS D3.1.1, as follows:

ICi MPCWt = _-:--,-i_ _-:-

II (CYMPCWi)

Where; Ci and MPCWi = Concentration and MPCW for each isotope CB = The concentration of the non gamma emitters, in IlCi/cc CG = The concentration of the gamma emitters in uCi/ml Applications of ADC:

If simultaneous liquid radioactive discharges are being performed from one unit, dilution flows may need to be re-apportioned. This may be performed by allocation or by calculation. The required dilution flow is calculated as follows:

E = Dr*CG ADC where; Dr = Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm The permissible discharge rate is then calculated as follows:

ADC*B.

D CG Where:

D = Permissible discharge rate in gal/min B = Adjusted dilution flow (Available - E, above), in gpm Note that when there are no other releases (E=O), B simply becomes the available dilution flow.

IPEC aDCM Page 114 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX F CONVERSION FACTORS FOR LIQUID EFFLUENT MONITORS Monitor conversion factors are derived from circulating a representative sample (or NIST traceable fluid) through the monitor until a stable reading is obtained. The conversion factor is then determined by quantifying the uCi/cc (by gamma spectroscopy or known activity) and dividing this value by the net cpm displayed on the monitor.

Fluid may be recirculated within the monitoring system, or introduced into a closed loop, to provide elevated, stable readings on the monitor. This fluid should be representative of the expected nuclide mixture in the system, as the conversion factor is energy-dependent.

When the process fluid itself is of sufficient activity to provide this function, it is this fluid that is measured and applied to develop a typical conversion factor.

When the process fluid is usually free of contamination, NIST traceable fluid must be injected into the sample chamber to accomplish this task.

Once the sample chamber is providing a stable reading, an alequate of the fluid is measured by gamma spectroscopy to determine the average energy and the monitor's conversion factor.

Conversion Factors for effluent monitors are maintained by Chemistry and updated when standard mixtures change which would warrant an improved average energy representation.

If desired, a more robust method can be applied per Reference 43.

IPEC ODCM Page 115 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXG (Page 1 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATION /

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 0.32 mi - 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 0.88 mi-SSW DR11/53 White Beach 0.92 mi- SW DR12/74 West Shore Drive - South 1.59 mi-WSW DR13/76 West Shore Drive - North 1.21 mi-W DR14/78 Rt. 9W, across from RlS #14 1.2 mi-WNW DR15/80 Rt. 9W - South of Ayers Road 1.02 mi- NW DR16/82 Ayers Road 1.01 mi - NNW DR17/58 Ht. 9D - 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 4.97 mi-SW DR28/81 Palisades Parkway, Lake Welch Exit 4.96 mi-WSW DR29/77 Palisades Parkway 4.15 mi-W DR30/79 Anthony Wayne Park 4.57mi:....WNW DR31/75 Palisades Parkway 4.65mi-NW DR32/83 Rt. 9W Fort Montgomery 4.82 mi-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 & 6th 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 20.7mi-N DR41/27 Croton Point 6.36 mi - SSE

Control Station IPEC ODCM Page 116 of 136 Revision 2

ODCM Part II - Calculational Methodologies.

APPENDIXG (Page 2 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATION/

STATION LOCATION DISTANCE Airborne A1/4 Algonquin Gas Line 0.28 mi -SW A2/94 IPEC 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 20.7 mi - 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 0.92 mi-SW Wc2/50 *Manitou Inlet 4.48 mi - NNW Exposure Pathway/Sample: 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 (la1 -la4).

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 tp 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 IPEC ODeM Page 117 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXG (Page 3 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATION/ SAMPLE 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 Wa1/9 *Plant Inlet (Hudson River Intake) 0.16 mi - W 7 Wa2/10 Discharge Canal (Mixing Zone) 0.3 mi -WSW 7,8 DR7/14 Water Meter House 0.3 mi - SE 3

- /17 Off Verplanck 1.5 mi - SSW 8,9,10 DR38/20 Cortlandt Yacht Club (AKA 1.5 mi-S 3 Montrose Marina)

Ib2,A5,DR40,lc3/23 *Roseton 20.7mi-N 1,2,3,4,5,11,12 Ib1/25 where available, downstream N/A 12 DR41/27 Croton Point 6.36 mi - 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 Peekskill Gas Holder Building 1.84 mi - NE 1,2,11 Wc2/50 *Manitou Inlet 4.48 mi- NNW 10 Wc1, DR11/53 White Beach 0.92 mi-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. 9D 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 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 IPEC ODCM Page 118 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXG (Page 4 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATION/ SAMPLE STATION LOCATION DISTANCE TYPES DR25/71 Warren Avenue - Haverstraw 4.83 mi-S 3 DR26/72 Railroad Ave. & 9W - Haverstraw 4.53 mi -SSW 3 DR27/73 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 4.65 mi- NW 3 DR13/76 West Shore Drive - North 1.21 mi-W 3 DR29/77 Palisades Parkway 4.15 mi-W 3 DR14/78 Rte. 9W, across from R/S #14 1.2 mi-WNW 3 DR30/79 Anthony Wayne Park 4.57 mi-WNW 3 DR15/80 Rte. 9W - South of Ayers Road 1.02 mi - NW 3 DR28/81 Palisades Parkway, Lake Welch Exit 4.96 mi-WSW 3 DR16/82 Ayers Road 1.01 mi - NNW 3 DR32/83 Rte. 9W - Fort Montgomery 4.82 mi-NNW 3

- /84 *Cold Spring 10.88 mi - N 8,9,10

- /85 Quality Control 6 DR6/88 Reuter-Stokes Pole #6 0.32 mi - ESE 3 DR35/89 Highland Ave. & Sprout Brook Road (near 2.89 mi - NNE 3 rock cut)

DR3/90 Charles Point 0.88 mi - NE 3 DR24/92 Warren Rd. - Cortlandt 3.84 mi - SSE 3 A2,lc2/94 IPEC Training Center 0.39 mi-S 1,2,4,5 A3,lc1/95 Meteorological Tower 0.46 mi - SSW 1,2,4.5 GW/106 Lafarge Monitoring Well 0.63 mi -SW 13 6/09

Control Station ** Items are in excess of RECS requirements Sample types are:

1. Air particulates 8. H.R. bottom sediment

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. Groundwater well

7. Hudson River (H.R.) water IPEC ODCM Page 119 of 136 . Revision 2

ODCM Part 11- Calculational Methodologies APPENDIXG (Page 5 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS Within Two Miles of Indian Point N

~

lonai Island

_. R.,

ocklari9QOur;jty 1 mile:

~ey:

Icff-*Btoatlleaf y~ge(ation A~ - VVatetpprne: "$u rface(t-l R)Wa#: <:>-HRShprelihe:sbii yve¥!;

o -;[:lireciR9di?tionSarnpl~, L()cafion PR# Ib1.,. Fish* andl hvertebrates' DI- AirtlC:>Tne., P9diculate;anCf Radioioqin¢.'A# (Vilh¢re .ava) 19 bl,edownstFearn)'

IPEC ODCM Page 120 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXG (Page 6 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS Greater Than Two Miles from Indian Point R.()s~t9nj2ti.7m{ N}: N' III@

Upstream: Ib2 ic3

.~

Or~ng~ County Putnam County Bear Mountain Bridge

~ ):

"qJ)

Westct1est~r

~; C:QunW smlle.s, Rdtklc3nd County Key: 0 .,[jirectRadiationSampleLocationDR# Ic3.- BrCladleaf *vegetation o .- Airborne Sampling L?G~tiQnA#i :Q - Waterborne:Drinkih~fWb#**

<>"> Huds'on River ShorelineSoiLWC# Ib2'~ FiSh: and Invertebrates, (wbereavailable upstream)

IPEC ODCM Page 121 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXG (Page 7 of 7)

ENVIRONMENTAL SAMPLING POINTS ADDITIONAL SAMPLING LOCATIONS 6/09 N

Rdiiefon (20.7 mi. N):'23."'p * ~

Qrang~CQunt)l Putnclm :GOUJ1ty

-Cold:Spring,(.10:8SmLN~ :S4 :

Bear MoLintain Brid~e 10:+

17:' T,

<>~----~~~~

29: III .----4;:

Roqkland :County HudSon. °8;*dw River 5 miles Key: 11- Air :ParticLllateac.RRdioiodine <> -HR .Shorelihe,Sbii

.~.- AquatiQN~getation +-:Soil

. . - HR Bottom Sedirnent GVV- MonitoririgWelljSW of p - Precipitation Site Boundary dw;.*D rinkingWater IPEC ODCM Page 122 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX H INTERLABORATORY COMPARISON PROGRAM Laboratories used for analysis of samples to support the Radiological Environmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program or comparable program with an approved vendor (EPA, NIST, etc).

Samples of various media containing known activities of radionuclides are sent to participating laboratories for analyses. Results of the analyses are compared to the known values.

While laboratory results may be reported in terms of normalized deviations from a known value (generally.:!:. 3 sigma), the results are evaluated for acceptance criteria using the NRC's standardized comparison requirements for agreement found in the site quality control procedures (as a function of resolution).

Annual results of the interlab participation, along with resolution and agreement criteria, are summarized in the Annual Environmental Operating Report.

IPEC ODCM Page 123 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIX I Page 1 of 7 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Primary Assumptions:

Units 2 and 3 effective dose factors (KLMN) are equivalent, except for unit-specific finite cloud correction factors, which represent different recirculation contribution, as required.

For instantaneous release calculations, the default (initial) condition is for each unit to share (50-50) in the application of the site's 10CFR20 limit (converted to uCi/sec from mrem/yr).

The following data represent long-term meteorological factors. Short term correction, if applicable, should be applied to these values, as discussed in Section 3.5, and Reference 17.

5-miles Unit 1 or 2 Site Nearest Receptor Down Valley, Release Points Boundary Resident Haverstraw Concentration 2.219E-06 1.030E-06 7.22E-07 X/Q (sec/m3) [SSW, 755 m] [SSW, 1574 m]

Primary Vent Releases Deposition 1.407E-08 7.517E-09 1.35E-09 D/Q (m*2) [SSW, 755 m [S,1133m]

Concentration 2.873E-05 5.158E-06 7.22E-07 X/Q (sec/m3) [SSW, 440 m] [SSW, 1374 m]

Ground Level Releases Deposition 8.759E-08 1.878E-08 1.35E-09 D/Q (m*2) [SSW, 440 m [S, 933 m]

5-miles Unit 3 Site Nearest Receptor Down Valley, Release Point Boundary Resident Haverstraw Concentration 4.473E-06 1.016E-06 7.22E-07 X/Q (sec/m3) [SW, 350 m] [SSW, 1574 m]

Primary Vent Deposition 2.599E-08 7.451E-09 Releases 1.35E-09 D/Q (m* 2) [SSW, 480 m] [S, 1133 m]

Concentration 6.980E-05 5.158E-06 7.22E-07 X/Q (sec/m3) [SSW, 250 m] [SSW, 1374 m]

Ground Level Releases Deposition 2.012E-07 1.878E-08 1.35E-09 D/Q (m o2 ) [SSW, 250 m] [S, 933 m]

IPEC aDCM Page 124 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIX I Page 2 of 7 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 X/Q 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 2 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 Note:

b) IP3 worst sector X/Q =4.47E-6 sec/m3 3

Units 2 and 3 effective c) IP3 K-bar for instantaneous mixture = 849 mrem* m dose factors (KLMN) flO .yr are equivalent, except d) IP2 worst sector X/Q . = 2.22E-6 sec/m3 for site-specific finite cloud correction, as

3 e) IP2 K-bar for instantaneous mixture =1507 mrem m defined in Table 3-8.

flO. yr f) Q = !-lCi/sec Solve for Q:

Q [ (X/Q 3) (K bar3) + (X/Q2) (K bar2)] = 500 mrem/yr Q [(4.47E-6) (849) + (2.22E-6) (1507)] = 500 mrem/yr Therefore, without performing any specific calculations for an actual release, the default back-calculated instantaneous release rate (Q) for either unit =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.

IPEC aDCM Page 125 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX I Page 3 of 7 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 X/Q = 4.47E-6 sec/m3 e 3 c) IP3 (Li + 1.1 Mi) = 2306 mrem m

. j.lCi e yr d) IP2 X/Q for SSW sector = 2.22E-6 sec/m3 mrem e m 3 e) IP2 (Li + 1.1 Mi) = 3071 j.lCi e yr f) Q = uCi/sec Solve for Q:

Q [(X/Qh (Li + 1.1 Mih + (X/Qh (Li + 1.1 Mih] = 3,000 mrem/yr Q [(4.47E-6) (2306) + (2.22E-6) (3071)] =3,000 mrem/yr Q = 1.75E+5 /lCi/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:

. mrem e m 3 (7.00E+4 /lCI/sec) (2.22E-6 sec/m3) (1507 . ) = 234 mrem/yr j.lO e yr Indian Point 3:

. 3 mrem e m 3 (7.00E+4 /lCI/sec) (4.47E-6 sec/m ) (849 . ) = 266 mrem/yr j.lO e yr The less restrictive skin dose rate limit for each unit (information only):

mremem 3 Unit 2: (1.75E+5 uCi/sec) (2.22E-6 sec/m3) (3071 . ) = 1194 mrem/yr j.lO e yr mremem 3 Unit 3: (1.75E+5 uCi/sec) (4.47E-6 sec/m3) (2306 . ) = 1806 mrem/yr j.lO e yr IPECODCM Page 126 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX I Page 4 of 7 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. X/Q for Unit 2 = 2.22E-6 sec/m 3 , (Q = release rate uCi/sec)

4. X/Q for Unit 3 =4.47E-6 sec/m 3 , (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 3 N = 1254 N = 1254 mrad/yr per uCi/m J II. Calculation of Quarterly Release Rates:

a) for gamma dose: (Q )*[(M)(X/Q)] less than or equal to 5 mrad/qtr b) for beta dose: (Q )*[(N)(X/Q)] less than or equal to 10 mrad/qtr unit 2 unit 3 5mrad / qtr gamma dose rate Q= = 3.21 E+4 /lCi/sec 2.47E+4/lCi/sec (1/ 4yr)(M)(X / Q) lOmrad / qtr beta dose rate Q = = 1.44E+4 /lCi/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.

IPEC ODCM Page 127 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX I Page 5 of 7 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE INSTANTANEOUS RELEASE RATE for 1-131 & Particulates wI T~ > 8 DAYS)

Given: Wv(in): X/Q at the Site Boundary for IP3 = 4.47E-6 sec/m 3 Wv(in): X/Q at the Site Boundary for IP2 = 2.22E-6 sec/m 3 Pl(c) = 1.62 E7 mreml yr 3

JiCil m 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 I yr . mrem I yr IP3: (Q )PI(c)(Wv(in))3 = Q

1.62E7 . 3 4.47E-6 s/m 3 = Q

72.4 --~

JiCl I m JiCi I sec

. . mremlyr . mremlyr IP2: (Q )PI(c)(Wv(in))2 =Q

1.62E7 3 2.22E-6 s/m 3 = Q

36.0 ---'---

JiCi I m JiCi I sec The sum equals: (108) ( Q) mrem/yr per uCi/sec Limit is 1500 mrem/yr per site:

Therefore: 108

Q mrem I yr = 1500 mrem/yr JiCi I sec Q = 1.38E+1 J.1Ci/sec (for each unit) 3 mrem sec IP3 Dose Contribution: 1.38E+1 JiCi*1.62£7 m *4.47£_6 =1003 mrem/yr sec yr JiCi m3 3

IP2 Dose Contribution: 1.38E+1 JiCi

1.62£7 mrem m

2.22£ _ 6 sec = 497 mrem/yr sec yr JiCi m3

---:-~:----

Sum = 1500 mrem/yr (Approximately a 67 133 percent dose split for IP3 and IP2 respectively).

IPEC ODCM Page 128 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX I Page 6 of 7 ALLOWABLE QUARTERLY and ANNUAL IODINE/PARTICULATE RELEASE RATES 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:

Unit 2 Unit 3 X/Q (in sec/m3 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) flCilm mreml yr RG = 1.72E+7 m 2

"--, ground plane dose factor for 1-131 (for both units) flCi / sec RV(c) = 4.75E+10 m2 mreml yr ,child thyroid vegetation dose factor for 1-131 (for both units) flCi /sec Calculating the allowable time average release rate by solving the following equation for Q:

Q [(Rlc)(X/Q) + (RG)(D/Q) + (RVc)(D/Q)] = limit in mrem/yr Unit 2 Unit 3 Q (Rlc)(X/Q) in mrem/yr per uCi/sec = 16.7

Q 16.5

Q Q (RG) (D/Q) 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:

(Quarterly Limit) (Annual Limit)

. mrem/ yr (IP2) Q

374 . = 30 mrem/yr; 8.02E-2 IlCi/sec 4.01 E-2 IlCi/sec flO/sec

. mrem/yr (IP3) Q

371 . =30 mrem/yr; 8.10E-2 IlCi/sec 4.05E-2 IlCi/sec flCi/sec (Annual limits are ~quarterly limits, or .15 mrem to any organ/yr)

IPEC ODCM Page 129 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX I Page 7 of 7 ALLOWABLE QUARTERLY and ANNUAL IODINE/PARTICULATE RELEASE RATES DOSE LIMITS AT THE 5-MILE SECONDARY RECEPTOR (when applied)

Dose factors for the infant, 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 is on the infant age group at this location. When applied (as required by the applicable current Land Use Census), this pathway may be approximately four times more limiting than the Primary Receptor. The back-calculated release rate for Iodine and PartiCUlate are as follows:

Units 2 or 3 X/Q (in sec/m3 at 5-miles down valley) 7.22E-7 D/Q (in m-2 at 5-miles down valley) 1.35E-9 RI(i) =1.48E+7 mrem I y; , infant thyroid inhalation dose factor for 1-131 (for both units) j.1Ci I m mreml yr .

RG = 2.10E+7 m2 ----'--, g round plane dose factor for 1-131 (for both units) j.1Ci I sec RC(i) =1.05E+ 12 m 2 mrem I yr , infant thyroid cow-milk dose factor for 1-131 (for both units) j.1Cil sec (there is no vegetative pathway for the infant)

Calculating the allowable time average release rate by solving the following equation for Q:

Q [(Rli)(X/Q) + (RG)(D/Q) + (RCi)(D/Q)] = limit in mrem/yr Units 2 or 3 Q (Rli)(X/Q) in mrem/yr per uCi/sec = 10.7

Q Q (RG) (D/Q) in mrem/yr per uCi/sec = 0.028

Q Q (RCi)(D/Q) in mrem/yr per uCi/sec = 1412

Q The sum for each unit ( X ~ Q ) in mrem/yr per uCi/sec. 1428

Q Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr).

Solving for Q yields the following limits, at either unit (Quarterly Limit) (Annual Limit)

. mremlyr Q

1428 = 30 mrem/yr; 2.10E-2 !lCi/sec 1.05E-2 !lCi/sec j.1Ci I sec (Annual limits are Y:z quarterly limits, or 15 mrem to any organ/yr)

IPEC ODCM Page 130 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXJ Page 1 of 6 GROUNDWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Overview:

Site hydrologists have verified the overall direction of groundwater flow at IPEC to be ultimately into the Hudson River. From this established understanding, two independent models are applied to determine groundwater f10wrates from the site into the river, the precipitation mass balance and the Darcy's Law models.

The precipitation mass balance model applied prior to 2007 was enhanced and further validated for 2007 and beyond by a calibration process involving the Darcy's Law model. A total of six zones on site (described below) are evaluated 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-canallpost-canal differentiation of flow values in each zone.

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. Average concentrations are used, and based on multiple samples, generally at least one per quarter per elevation per well. The additional wells, and the instrumentation installed therein, also provides further definition of groundwater elevations to enhance the Darcy's Law calibration of the precipitation mass balance model. The hydrology portion of the final model was produced by IPEC's hydrological consultant, GZA GeoEnvironmental, Inc. The specific processes for release and dilution flow evaluation are defined in the following text.

The precipitation mass balance model partitions the precipitation falling on the watershed catchment area (Le., 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 / 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.

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.

IPEC ODCM Page 131 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIXJ Page 2 of 6 GROUNDWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS

3. 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.

Prior to 2007, the net precipitation infiltration rates resulting in groundwater flow were adopted directly 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 general groundwater flow areas.

These groundwater flow values were subsequently refined in 2007 using the relative flow values computed with the Darcy's Law model. The gradients (changes in hydraulic pressure with distance) throughout the site were 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 compared 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 activities; 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:

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 I 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;

Unit3 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.

IPEC ODCM Page 132 of 136 Revision 2

ODCM Part II - Calculational Methodologies APPENDIX J Page 3 of 6 GROUNDWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Overall, the partitioning is established for groundwater and storm water, including recharge rates where storm drains and ground water communicate. In 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, determined from hydraulic pressure differences 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.

Source Terms:

Concentrations of identified radionuclides for all Zones (from quarterly groundwater sampling data from Monitoring Wells and the accumulated Storm Drain sample data) are then applied for routine offsite dose cacluations per ODCM Part II, Section 2. All wells and storm drains are analyzed for gamma spectroscopy and tritium by liquid scintillation. Additionally, groundwater analyses are completed for beta emitters, such as Ni-63 and Sr-90. Quarterly results from effected wells in the effluent locations are evaluated to compute an average source term for each area or zone.

If a result is below MOC (whether positive or negative) it was not included in the computed average. This computed average is therefore biased high (more conservative from a dose computation perspective) relative to an average computed using all of the data, which would be more representative of actual conditions (values below MDC and non-detected "zero values" are equally valid results for the groundwater activity levels at certain locations/times).

More specifically, the average is based on only those results above MDCfor any location that 6/09 had at least one identified value above MDC. However, if all the sampling locations assigned to a given stream tube provided results below the MDC, 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). This procedure results in a high, but conservative bias to the dose computations.

Ground Water and Storm Drain Source Term selection to the canal is as follows:

Monitoring Wells, Monitoring Wells, Streamtube Manholes upper zone lower zone Northern NA Background Background Clean Zone Unit 2 MW-S2-11 MW-S2-18 MW-S2-64 MW-S2-122 None MW-S2-48 MW-S2-162 MW-S2-181 North MW-36-24 MW-36-41 MW-32-92 MW-32-140 Units MW-36-S2 MW-SO-42 MW-32-16S MW-32-196 MH-4A MW-SO-66 MW-S4-37 MW-S3-120 MW-S4-S8 1/2 MW-S7-11 MW-S7-20 MW-S4-123 MW-S4-144 MW-S7-4S MW-S4-173 MW-S4-190 Unit 3 MW-S4-S8 MW-S4-123 MW-S8-26 CB-14, CB-34 MW-S8-6S MW-S4-144 MW-S4-173 North MW-S4-190 Unit 3 U3-T2 MW-44-102 MW-41-63 B8 U3-Tt U3-4D South MW-40-27 MW-40-81 MW-40-100 Southern C1, D1, E6, MW-40-46 MW-40-127 MW-40-162 Clean Zone E10, E13 MW-51~40 MW-51-104 MW-51-135 MW-S1-79 MW-S1-163 MW-S1-189 IPEC ODCM Page 133 of 136 Revision 2

aDCM Part II - Calculational Methodologies APPENDIXJ Page 4 of 6 GROUNDWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Ground Water and Storm Drain Source Term selection directly to the river is as follows:

Monitoring Wells, Monitoring Wells, Streamtube Manholes upper zone lower zone Northern NA Background Background Clean Zone MW-60-35 MW-37-22 MW-60-53 MW-60-72 Unit 2 MH-1 MW-49-26 MW-60-135 MW-60-154 MW-37-32 North MH-12 MW-49-42 MW-60-176 MW-37-22 MW-37-32 MW-67-105 MW-67-173 Units MW-49-26 MW-49-42 MH-14 MW-49-65 MW-66-21 MW-67-219. MW-67-276 1and 2 MW-67-323 MW-67-340 MW-66-36 MW-67-39 MW-62-18 MW-62-37 MW-62-92 MW-62-138 Unit 3 MW-62-53 MW-62-71 MW-62-182 MW-63-112 CB-15 MW-63-18 MW-63-34 MW-63-121 MW-63-163 North MW-63-50 MW-63-93 MW-63-174 Unit 3 MW-41-63 MW-44-102 none U3-T1 U3-T2 U3-4D South MW-40-81 MW-40-100 Southern MW-40-27 MW-40-46 MW-40-127 MW-40-162 C2 MW-51-40 MW-51-79 MW-51-104 MW-51-135 Clean Zone MW-51-163 MW-51-189 Flow Rates:

Determination of flow rates to the canal and the river through each zone depend on infiltration rates as well as rainfall and measured hydraulic pressure differences. The infiltration rate in non-paved areas (or building areas) was computed at 0.87 feet/year, and consistent with 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 IPEC area is recorded each year, and averages approximately 3 feet per year. A long-term onsite meteorological average should be used for a starting point in determining annual effluent flow rate. All precipitation falling on paved/building areas is 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 to ensure conservativism in the model. Some of the Stormwater, however, naturally recharges the groundwater.

The following values are currently applied in the flow model:

Percent of Stormwater Flow Streamtube Recharging Groundwater Northern Clean Zone 0%

Unit 2 North 50%

Unit 1/2 30%

Unit 3 North 50%

Unit 3 South 1%

Southern Clean Zone 1%

IPEC aDCM Page 134 of 136 Revision 2

aDCM Part II - Calculational Methodologies

\

APPENDIXJ Page 5 of 6 GROUNDWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS Known extration rates from existing pathways need to be subtracted from the zones applicable to these specific pathways, as follows:

Five gallons per minute (gpm) from the Unit 2 Footing Drain is removed from the Unit 2 North streamtube.

Five gpm from the Unit 1 North Curtain Drain and 2.5 gpm from the Unit 1 Chemical Systems Building Foundation Drain are removed from the Unit 1/2 streamtube.

Seven and a half gpm from the Unit 1 Chemical Systems Foundation Drain are removed from the Unit 3 North streamtube Beyond the known flow and/or extraction rates, the model uses Darcy's Law to determine the flow contours for each of the six zones. Groundwater elevation contours and measurements of hydraulic conductivity are developed from the wells on site, recognizing that flow is perpendicular to the contours. This effort also provides knowledge of facility-specific flow paths. Measurments of pressure differential are then applied (per Darcy's Law) to determine flow rate:

Where:

Q is groundwater flow (cubic feeUday). This value is calculated.

K is the hydraulic conductivity (ftlday). This value is a log normal average of hydraulic conductivity values measured within the appropriate portion of the streamtube. In other words, the ease of which flow can be forced through sub-surface media.

A is the cross sectional area through which groundwater is moving (ft2).

is the change in head over a distance (ftlft) , or a measure of the pressure driving the flow. This value is calculated for the shallow and deep zones both upgradient and downgradient of the canal.

The data above was applied to calibrate the precipitation mass balance model in 2007 and will be similarly applied in subsequent dose determination, with potential minor updates in pararmetes, such as the change in head (I) defined above, as the model is further refined. This calibration routine consists of the following steps, as they applied in the 2007 effluent determination:

1) Groundwater elevation data was downloaded from transducers and/or recorded manually with an electronic water level indicator or equivalent. Following download, the data was reduced and evaluated by the site Hydrologists.

2) A period of time was selected to evaluate the groundwater at key elevations and positions along all three axes, such that the maximum number of working transducers were included.

Evaluations were also optimized by selecting readings during low-low tide on the targeted day.

IPEC aDCM Page 135 of 136 Revision 2

ODCM Part II .:. . Calculational Methodologies APPENDIXJ Page 6 of 6 GROUNDWATER FLOW AND OFFSITE DOSE CALCULATION DETAILS

3) Two sets of groundwater contours were prepared. Shallow groundwater contours were drawn based on groundwater elevation data collected generally at elevations higher than 40 feet below top of bedrock. Deep groundwater contours were drawn based on groundwater elevation data from sampling locations deeper than 40 feet below the top of rock, although preference was given to data from the upper portion of that zone.

4) Using the groundwater contours within each streamtube, the groundwater flux was calculated within each zone using Darcy's Law as described above.

5) The total flow, both upgradient and downgradient of the Discharge Canal, was summed separately. The difference between these flows constitutes that groundwater which is recharging the Discharge Canal.

6) The total flow downgradient of the Discharge Canal discharges into the Hudson river.

7) The percentage of groundwater flow in the upper and lower zones of each streamtube was calculated for proportioning of groundwater flow in the upper and lower zones in the Precipitation Mass Balance Model.

NOTE:

The groundwater contours used for the Darcy's Law calibration of the precipitation mass balance model have been based on data collected during Quarter 2 of calendar year 2007. Seasonal variations in precipitation and runoff were expected to cause variations in I the groundwater contours for individual quarterly monitoring rounds. Quarterly data was 6/09 collected and reviewed to evaluate if an update to the model would be required. To date, the small variation in groundwater flow has not warranted a model recalibration. However, once the complete set of quarterly groundwater contours have been collected, that quarter which provides the highest release rate (Le. those with the steepest gradients observed from Quarter 2, 2007 to at least Quarter 2, 2009 ) will be used to generate a conservative recalibration of the Precipitation Mass Balance Model.

8) A final determination of offsite dose can be performed with the previously compiled data (dilution flow, effluent flow rates, and source terms) using an integrated dose calculation model (electronic Excel spreadsheet) identified in Reference 44. This spreadsheet, called the Master Groundwater Dose Calculator, is available from Chemistry Management.

The distribution of flow rates to the canal and the river, from each zone, is determined within this asset as a result of calibrations of the rainfall model with Darcy's Law and transducer data. Its purpose is to bound the effluent flow rate in a conservative fashion, until there is evidence of a need to recalibrate the precipitation mass balance method.

Averaged or conservative assessments of source term are entered for each zone from a list of required input locations (wells or drains in each effected area).

Dose calculations are performed with this information per ODCM Part II, Section 2.4, in the same fashion as other liquid effluents.

IPEC ODCM Page 136 of 136 Revision 2

IPEC ODCM, Revision 2 Justification Package

IPEC COMBINED ODCM Rev 2 Justification Package Prepared by: Steven Sand ike Brief Summary of Changes June,2009 The station ODCM was upgraded to revision 2, with changes summarized below:

ODCM Part I 1 Modified Table 03.3.1-1, Section 3d, to update SFOS totalizer flow instrument with new plant 10 number.

2 Added Lafarge well to REMP, Section 3.5, reclassifying MW 40 and 51 as RGWMP only.

3 Modified the format of Section 05.6 to more closely follow previous examples of outline format, and add two new sources of information: (ANI 07-01 and the EPRI GW Guidelines).

ODCM Part II 4 Added REMP sample point at Lafarge in Appendix G, and reclassified MW 40 and 51 as RGWMP only.

5 Modified Appendix J definition of the GW dose model with data from 2008.

6 Added detail to Appendices Band C, to indicate 80-10 and other pathways of interest.

Each of the above changes 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

IPEC COMBINED ODCM Rev 2 Justification Package item # 1 of 6 June, 2009 OBJECTIVE:

Modify Table 03.3.1-1, Section 3d, to update SFOS totalizer flow instrument with new plant 10 number.

DESCRIPTION OF CHANGES:

Modified Table 03.3.1-1, Section 3d, to reflect new instrument 10 # ( FR-7874) replacing the old instrument 10 for the Sphere Foundation Drain Sump flow totalizer that was replaced in 2008 (CR-IP2-2008-03074 and ER-06-2-043).

IMPACT:

None.

JUSTIFICATION:

A new instrument was required to improve the reliability of this measurement. While the new instrument provides essentially the same functionality, the precise instrument that had been in use could not be purchased new. Hence, a new instrument 10 was assigned per ER-06-2-043.

IPEC COMBINED ODCM Rev 2 Justification Package item # 2 of6 June, 2009 OBJECTIVE:

Add Lafarge well to REMP, Section 3.5 and reclassifying MW 40 and 51 as RGWMP only.

DESCRIPTION OF CHANGES:

Added Lafarge well to REMP, Table 3.5.1-1, Section 3d, in place of using MW-40 and MW-51. Updated Figure D4.1-1 to remove depiction of these Monitoring Wells, which remain in RGWMP, but are removed from REMP.

IMPACT:

None. The Monitoring Well at Lafarge was refurbished in 2008 in order to support this improvement.

JUSTIFICATION:

An off-site Monitoring well was deemed a better method to determine potential migration of contamination offsite (REMP) than the previous on-site wells near the training building. Monitoring Wells 40 and 51 remain an important part of the Radiological Groundwater Monitoring Program, but are no longer classified as fulfilling a REMP purpose. In 2008, Entergy funded an upgrade to the well at Lafarge such that it would function as a legitimate "Monitoring Well", and could be added to the REMP in 2009. This well and it's ability to implement the REMP are in keeping with REMP definitions in NUREG 1301.

IPEC COMBINED ODCM Rev 2 Justification Package item # 3 of 6 June, 2009 OBJECTIVE:

Modify the format of Section 05.6 to more closely follow previous examples of outline format and add two new sources of information: (ANI 07-01 and the EPRI GW Guidelines).

DESCRIPTION OF CHANGES:

Modified the format of Section 05.6 to use letter designations for the sub-headers under Section 05.6. Added, under the section for objectives (a), references to two new documents: ANI 07-01 and the EPRI GW Guidelines.

IMPACT:

None JUSTIFICATION:

Typographical improvements. The new documents were added to ensure inclusive bases.

IPEC COMBINED ODCM Rev 2 Justification Package item #4 of6 June, 2009 OBJECTIVE:

Add a REMP sample point at Lafarge in Appendix G, and remove MW 40 and 51 from REMP.

DESCRIPTION OF CHANGES:

Added REMP sample point at the Lafarge Monitoring Well in Appendix G, page 4 of 7, as ID: GW1106.

Removed MW 40 and 51 from this list of REMP sample points. They are maintained in the Radiological Groundwater Monitoring Program (RGWMP). Modified page 7 of 7 to depict the new sample point.

IMPACT:

REMP sampling lower tier procedures were previously updated to include sampling at Lafarge.

No further changes to procedures are required to implement this upgrade to the program.

JUSTIFICATION:

An off-site Monitoring well was deemed a better method to determine potential migration of contamination offsite (REMP) than the previous on-site wells near the training building. Monitoring Wells 40 and 51 remain an important part of the Radiological Groundwater Monitoring Program, but are no longer classified as fulfilling a REMP purpose. In 2008, Entergy funded an upgrade to the well at Lafarge such that it would function as a legitimate "Monitoring Well", and could be added to the REMP in 2009. This well and it's ability to implement the REMP are in keeping with REMP definitions in NUREG 1301

IPEC COMBINED ODCM Rev 2 Justification Package item # 5 of6 June, 2009 OBJECTIVE:

Modify Appendix J, pages 2 and 6, describing the data applied to define the IPEC GW offsite dose model.

DESCRIPTION OF CHANGES:

Modified the description of the use of source term data near minimum detectable levels, and the note on page 6 of Appendix J, to clarify how 2008 data was applied to fine-tune the offsite dose model to it's current conservative calibration.

IMPACT:

None. Lower tier Chemistry procedure 0-CY-2740 was updated in 4th quarter 2008 to reflect the latest model calibration.

JUSTIFICATION:

The Groundwater contractors (GZA) provided feedback for groundwater contours on a quarterly basis through 2 nd quarter 2009, and included the most conservative assessment of this data into the model to calibrate the Darcy's Law validation of the Precipitation Mass Balance model on site. The set of contours providing the highest release rate was used, as defined by the steepest gradients in ground water measurements observed from 2006 to mid-2009. Details of the calibration are included in the GZA final report for 2008 and provide a basis for any further calibration, should a more conservative contour be identified in any future annual report.

IPEC COMBINED ODCM Rev 2 Justification Package item # 6 of 6 June, 2009 OBJECTIVE:

Add detail to Appendices Band C, to indicate 80-10 and other pathways of interest.

DESCRIPTION OF CHANGES:

J Added detail to Appendix B, page 1 (units 1 and 2 liquid effluent pathways) and Appendix C, page 1 (units 1 and 2 airborne effluent pathways) to be more complete, including 80-10 and other pathways of interest.

IMPACT:

None JUSTIFICATION:

These improvements are clerical and conform to similar efforts for the Unit 3 sketches (Attachments Band C, pages 2). Both unit release pathway sketches now indicate Groundwater and key 80-10 pathways, as well as all key routine effluent.

ML12338A695

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