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

ENT000318 Submitted: March 29, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of

Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)

ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:

Identified:

Admitted: Withdrawn:

Rejected: Stricken: Other: ENT000318-00-BD01 10/15/2012 10/15/2012

¥' 0 < 0 : v f '1"4< 0-o ........ <<tEntergy Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 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:

Robert Walpole Licensing Manager 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 Facility Radioactive Effluent Release Report: 2009 Docket No. 50-3, 50-247, & 50-286 Page 1 of 49 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 E Il= 3.05E-01 Mev/dis Ey= 6.28E-01 Mev/dis 2nd Quarter E Il= 3.20E-01 Mev/dis Ey= 7.25E-01 Mev/dis 3rd Quarter E Il= 1.74E-01 Mev/dis Ey= 1.34E-01 Mev/dis 4th Quarter E Il= 1.50E-01 Mev/dis Ey= 9.71E-02 Mev/dis Unit 3: 1st Quarter E Il= 2.04E-01 Mev/dis Ey= 1.43E-01 Mev/dis 2nd Quarter E Il= 3.33E-01 Mev/dis Ey= 7.34E-01 Mev/dis 3rd Quarter E Il= 4.36E-01 Mev/dis Ey= 1.18E+00 Mev/dis 4th Quarter E Il= 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.

b/c) lodines and Particulates Docket No. 50-3, 50-247, & 50-286 Page 3 of49 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.

5. Batch Releases Airborne:

Unit 1 and 2 Airborne Releases Number of Batch Releases Total Time Period (min Maximum Time Period min Average Time Period min Minimum Time Period min Unit 3 Airborne Releases Number of Batch Releases Total Time Period min Maximum Time Period min Average Time Period min Minimum Time Period min Liquid: Unit 1 and 2 Liquid Releases Number of Batch Releases Total Time Period min Maximum Time Period min Average Time Period min Minimum Time Period min Unit 3 Liquid Releases Number of Batch Releases Total Time Period min Maximum Time Period min . Average Time Period min Minimum Time Period min Average Stream Flow:

I:;: Qtr 2 43 49 3280 3470 125 236 76.3 70.9 4.00 27.0 Qtr 2. 21 35 2520 3450 419 174 120 98.5 3.00 4.00 Docket No. 50-3, 50-247, & 50-286 Page 4 of 49 .Qtr3 '.' Qtr 4':' 2009* . 62 64 218 4340 4750 15800 173 175 236 70.0 74.2 72.7 10.0 2.00 . 2.00 Qtr 3.* 1<' 0tr 4 ", ' '2009 35 40 131 5100 6120 17200 233 216 419 146 153 131 9.00 4.00 3.00 ' Qtr1 Qtr 2. . Qtr3. Qtr. 4G:.' : .':2009.:: 5 4 11 11 31 535 408 1120 1090 3160 133 107 114 106 133 107 102 102 99.2 102 87.0 95.0 92.0 93.0 87.0 *;*Qfr 1 Otr 2 Qtr 3 Qtr4/ 2009 38 33 23 *7 101 4780 3900 2500 782 12000 256 272 118 117 272 126 118 109 112 118 106 77.0 92.0 103 77.0 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 2007 2008 2008 2008 Quarter Fourth. First Second Third Flow lets) 53,970 135,500 74,600 33,110

6. Abnormal Releases a) Liquid General Groundwater Docket No. 50-3, 50-247, & 50-286 Page 5 of 49 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: Unit 2 liquid waste effluent flow rate meter, CT-971 Unit 2 Plant Vent flow rate meter, SV2-DPT U3 Primary Water Storage Tank level instrument, LT-1131 -Effected . Interval ' .. ' 09-18-09 15:51 to 12-16-09 09:45 (88.7 days) 10-08-09 16:30 to 01-01-10 00:00 (84.3 days in 2009) 12-19-09 21:53 to 01-01-10 00:00 (12.1 days in 2009, but 32.6 days total) Details Instrument failed regularly scheduled test. Parts were determined necessary.

After arrival on site, it was determined that these parts were not precisely "like and kind". After investigation and procurement of correct parts, the instrument was successfully tested and placed back in service. During this interval, flow rate measurement was estimated per aDCM and lower tier requirements using level instruments.

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. Parts for the aDCM instrument were deemed necessary and ordered from vendor. Parts were not readily available.

After parts arrived, re-calibration was scheduled but re-prioritized to approximately April, 2010. Compensatory measurements were made per the ODCM and lower tier procedures (and the redundant, non-ODCM 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.

The level instrument failed due to a problem with freeze protection caused by a failure of an associated strip heater. The heater strip was replaced, but the level instrument failed its calibration retest. A new instrument was pursued but eventually determined not to be feasible.

Instead, parts were procured, installed, and the instrument was successfully calibrated and returned to service on Jan 21, 2010 at .12:41. While out of service, compensatory measures (level estimates) were performed per the aDCM and lower tier procedures whenever water was moved into or out of the tank.

7. ODCM Reporting Requirements (continued)

Other Reporting Criteria:

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

Indian Point Energy Center (Units 1, 2, and 3) Docket No. 50-3, 50-247, & 50-286 Page 8 of 49 RADIOACTIVE EFFLUENT RELEASE REPORT B. GASEOUS EFFLUENTS 2009 TABLE lA Docket No. 50-3, 50-247, & 50-286 Page 90f49 INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) GASEOUS E.FFLUENTS

-SUMMATION OF ALL RELEASES A Rssioo &Adivation Gases Units Qtr1 Qtr2 Qtr3 Qr4 Year Est. Tolal 2000 % Error 1. Tolal Relea:;e O* 1.S0E-01 S.14E-a2 9.1SE-01 7.2SE-01 1.B4E-+OO 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 2. Averag:l relea:;e rate LCi/soc ----O.OOE-+OO

c. Partirulates

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

8 davs --2. Averag:l relea:;e rate LCi/soc 120E-OO ---2. 95E-07 3. GrcSs Alpha 0 -----D. T riti l.IT1 1. T dal relea:;e 0 215E+Q0 3.42E+00 3.69800 282E+00 1.21 E-+01 . 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 Nuclides Released 1) Fission Gases I 2) lodines 1-131 1-133 1-135 TABLE lC Docket No. 50-3, 50-247, & 50-286 Page 10 of 49 INDIAN POINT 1 and 2 CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) Units Qtr 1 Qtr2 Ci Ci Ci Qtr 3 Qtr4 Year 2009 O.OOE+OO O.OOE+OO O.OOE+OO 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 TABLE lC Docket No. 50-3, 50-247, & 50-286 Page 11 of49 INDIAN POINT 1 and 2 -BATCH GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) Nuclides Released 1) Fission Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 2) lodines Units Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Not Applicable for Batch Releases 3) Particulates Not Applicable for Batch Releases Year Qtr 1 Qtr 2 Qtr 3 Qtr 4 2009 6.38E-02 2.79E-02 3.94E-02 2.94E-02 1.60E-01 O.OOE-+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.04E-04 4.02E-05 3.59E-03 4.48E-05 4.58E-03 8.50E-04 O.OOE+OO 1.20E-03 2.79E-06 2.05E-03 1.77E-03 2.11E-05 4.31E-03 4.12E-05 6.14E-03 4.88E-04 2.50E-04 4.12E-03 6.46E-03 1.13E-02 6.30E-02 2.13E-02 7.42E-01 6.80E-01 1.51E+OO 8.98E-04 3.02E-04 1.19E-02 5.70E-03 1.88E-02 1.60E-02 1.53E-03 1.05E-01 3.88E-03 1.27E-01 2.27E-03 O.OOE+OO 2.34E-03 7.11 E-06 4.63E-03 4.99E-04 O.OOE+OO 6.06E-04 1.57E-06 1.11E-03 -Indicates

< MDA TABLE lA Docket No. 50-3, 50-247, & 50-286 Page 12 of 49 INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES A Rssim & Adivation GaSES Lhits Qr1 Qlr2 Qr3 Qr4 YfS Est. Tota 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 6.79E-a2 a01E-CG 4.27E-03 6.40E-CG 2.14E-a2 B la::Iines

1. T dal la::Iin& 131 a ----O.O<E+OO :!:25 2. Averag3 relec:se rate

0.0(£+00 C PartiOJlates

1. T dal Relec:se, wth a ----0.0(£+00 +25 half-life>

8 daIS 2. Averag3 relea;;e rate ----0.0(£+00 3. Qa;s .Alpha a ----0.0(£+00 :!:25 D. Tritiun 1. T dal relec:se a 3.5ff:+OO 6.57E+OO 4.96800 4. 1 !E+OO 1.9:£+01 +25 2. Averag3 relec:se rate 4.61E-01 a35E-01 6.24E-01 5.22E-01 6.11E-01 -Indicates

< M:)6.

TABLE lC Docket No. 50-3, 50-247, & 50-286 Page 13 of 49 INDIAN POINT 3 -CONTINUOUS GASEOUS EFFLUENTS RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) Nuclides Released 1) Fission Gases Units Qtr 1 Ar-41 Ci O.OOE+OO Xe-133 Ci 2.98E-01 Xe-135 Ci 1.76E-01 2) lodines 1-131 Ci 1-133 Ci 1-135 Ci 3) Particu lates I" Tomita r PerioH/i:i::::.>

.* ;*.*.C .* '.' .. '.> ,.*.*i,1 : ...*. \, .. ':.' ....... ' .*. t .. \i<, I': ", \""'q' .... .; *.

- - :'::'} .... , . ..... " .. ,., .* ,.... . -indicates

< M DA Qtr 2 Qtr 3 2.33E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Qtr4 O.OOE+OO O.OOE+OO O.OOE+OO Year 2009 2.33E-02 2.98E-01 1.76E-01 O.OOE+OO O.OOE+OO O.OOE+OO TABLE lC Docket No. 50-3, 50-247, & 50-286 Page 14 of 49 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:

.. ; .. ;

3.40E-'02 5.09E1.62

'

-," Ci ;;. 3.96E-02

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

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

< MDA 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 15 of 49 TABLE 2A Docket No. 50-3, 50-247, & 50-286 Page 16 of 49 INDIAN POINT 1 and 2 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES A. Rssion & Pctivation Products Units Qtr 1 1. Total Release (rot irdLd ing a 3.10E-03 Tritium, Gr Alpha, & Gases) 2 Average Di luted Crnc uCilml 6.ffiE-12 B. Tritium 1. Tolal Release Ci 1.14E+02 2 Average Di luted Crnc uCi/ml 2.42E-07 C. Dissdved & Entrained Gases 1. Tolal Release Ci O.OOE+OO 2 AverageDiluted Cone uCilml O.OOE+OO D. Gross Alp,a 11. Tolal Release Ci E. Vd ume of Waste Released 1. A"ocessoo Waste (LW & NCO) liters 1.05E+06 2 Urprocessed (SGBD, SFOS, U1 FO) liters 4.49E+07 F. Vdume of Dilution Water -Indicates

< MDA Qtr2 Qtrl 1.17E-02 1.54E-02 1.72E-11 1.79E-11 1.07E+02 2. 77E+02 1.57E-07 3. 23E-07 0.0(£+00 3. 34E-05 0.0(£+00 3:89E-14 1. 83E+06 2. 19E+06 5. 13E+07 4.49E+07 Qtr4 7.11 E-03 9.68E-12 3.87E+02 5.28E-07 1.59E-04 2.16E-13 2.40E+06 4.31E+07 Year 2000 3.73E-02 1.36E-11 8. 86E+02 3.22E-07 1.92E-04 6.99E-14 7.46E+06 1. 84E+08 Est. Tctal %Erra .:!:25 .:!:25 .:!:25 +25 +10 +10 TABLE 28 Docket No. 50-3, 50-247, & 50-286 Page 17 of 49 INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) CONTINUOUS RADIOACTIVE EFFLUENT Nuclides Released Year 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 TABLE 2B Docket No. SO-3, SO-247, & SO-286 Page 18 of 49 INDIAN POINT 1 and 2 LIQUID RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) Nuclides Released Units Ag-110m Ci Co-S8 Ci Co-60 Ci Cr-S1 Ci Cs-134 Ci Cs-137 Ci Mn-S4 Ci Ni-63 Ci Sb-124 Ci Sb-12S Ci Sr-90 Ci Te-123m Ci Te-12Sm Ci Dissolved

& Entrained Gas Kr-8S Ci Xe-133 Ci I , ,.T::o""'t'a"'I'

- f.o/'r}Pe'n'

,. i:. ',;j:"

-

'>/,,:'; -Indicates

< MDA BATCH RADIOACTIVE EFFLUENT Qtr 1 Qtr 2 Qtr l 4.21 E-OS 1.23E-05 1.18E-OS 6.S3E-OS 3.80E-05 1.40E-04 1.10E-OS 4.S2E-05 3.13E-04 2.18E-04 4.70E-04 3.17E-03 2.69E-04 2.10E-03 S.SOE-03 1.08E-03 S.14E-04 1.32E-03 Qtr 4 6.83E-06 4.94E-04 1.S1 E-03 3.30E-03 Year 2009 O.OOE+OO 6.62E-OS 2.S0E-04 O.OOE+OO l.69E-04 4.lSE-Ol O.OOE+OO 9.l7E-Ol O.OOE+OO 6.21E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-OS 1.S9E-04 1.92E-04 TABLE 2A Docket No. 50-3, 50-247, & 50-286 Page 19 of 49 INDIAN POINT 3 RADIOACTIVE EFFLUENT REPORT (Jan -Dec 2009) LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES A. Fission & .Activation Products Units Qtr 1 1. Total Release (rot inellKling Ci 3.87E-03 Tritium, Gr Alpha, & Gases) 2. Average Diluted Cone uCi/ml 8.19E-12 8. Tritium 1. Tolal Release Ci 720E+02 2. Average Diluted Cone uCi/ml 1.52E-06 C. Dissaved & Entrained Gases 1. Tolal Release Ci 7.43E-03 2. AverageDilutoo Cone uCilml 1.57E-11 D. Gross Alpha 1. Tolal Release Ci E. Volume of Waste Releasoo 1. A-ocessed Fluids (fvbn Talks) liters 1.39E+06 2. Unprocessed Fluids (sGs) liters 1.77E+06 F. Vaume of Dilution Water '-irdicates

< MDA Qtr2 Qtr3 1.86E-02 2. 35E-03 2.73E-11 2.74E-12 1.08E+02 1.33E+02 1.5SE-07 1.55E-07 6.35E-04 4.62E-04 9.32E-13 5.37E-13 S.48E+05 6.00E+05 1.35E+07 2.77E+OO Qtr4 5. 15E-04 7.01E-13 125E+01 1.71 E-OS 4.50E-06 6.13E-15 1.S0E+05 1.64E+06 Year 2009 2.53E-02 922E-12 9. 73E+02 3.54E-07 S.53E-03 3.10E-12 Est. Total % Error :!:25 :!:25 :!:25 I O.OOE+OO I + 25 3.02E+06 :!:10 1.97E+07 +10 TABLE 2B Docket No. 50-3, 50-247, & 50-286 Page 20 of49 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

,':> ;';?:' /:jicL*' **.* * ;'j:8!:Eo03 i

2.35$:0:3 " .. "-

<:2:54E:.o2

'\:i;; " ""'"'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 Indian Point Energy Centei (Units 1; 2, and 3) RADIOACTIVE EFFLUENT REPORT D. SOLID WASTE 2009 Docket No. 50-3, 50-247, & 50-286 Page 21 of49 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 U 1 West Pool 8-120 Waste Volume Curies % Error (Ci) Class fe m 3 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 m 3 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 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+OO +/-25% Waste Strea m: Other Waste 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+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) Class fe m 3 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 1 1 3 Mode of Transportation Hittman Transport R & R Trucking Inc Hittman Transport Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance H-3 0.066% Mn-54 0.474% Fe-55 15.690% Co-58 0.288% Co-60 5.686% Ni-63 21.727% Sr-90 0.082% Cs-134 9.302% Cs-137 46.684% Resins, Filters, and Evap Bottoms Waste Class B Nuclide Name Percent Abundance H-3 0.019% Mn-54 0.014% Fe-55 0.417% Co-57 0.015% Co-60 4.334% Ni-63 52.488% Sr-89 0.001% Sr-90 8.325% Sb-125 0.348% Cs-134 2.539% Cs-137 31.292% Ce-144 0.168% Pu-238 0.002% Pu-239 0.001% Pu-241 0.037% Am-241 0.002% Cm-242 0.000% Cm-243 0.001% Destination Energy Solutions

-Bear Creek Studsvik Processing

-Memphis Studsvik Processing Facility Curies 1.88E-03 1.35E-02 4.47E-01 8.20E-03 1.62E-01 6.19E-01 2.35E-03 2.65E-01 1.33E+00 Total 2.85E+OO Curies 3.18E-02 2.39E-02 7.06E-01 2.47E-02 7.34E+00 8.89E+01 1.79E-03 1.41E+01 5.89E-01 4.30E+00 5.30E+01 2.84E-01 2.61E-03 1.15E-03 6.19E-02 2.72E-03 4.71 E-05 1.20E-03 Total 1.69E+02 Resins, Filters, and Evap Bottoms Waste Class C Nuclide Name Percent Abundance H-3 0.041% Mn-54 0.020% Fe-55 0.815% Co-57 0.020% Co-60 7.746% Ni-63 61.725% Sr-89 0.000% Sr-90 0.775% Sb-125 0.682% Cs-134 4.738% Cs-137 23.299% Ce-144 0.073% Pu-238 0.003% Pu-239 0.001% Pu-241 0.061% Am-241 0.000% Cm-242 0.000% Cm-243 0.001% Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance H-3 0.021% Mn-54 0.022% Fe-55 0.680% Co-57 0.015% Co-58 0.004% Co-60 4.567% Ni-63 52.585% Sr-89 0.001% Sr-90 7.730% Sb-125 0.363% Cs-134 2.782% Cs-137 31.029% Ce-144 0.159% Pu-238 0.002% Pu-239 0.001% Pu-241 0.038% Am-241 0.002% Cm-242 0.000% Cm-243 0.001% Total Total Docket No. 50-3, 50-247, & 50-286 Page 24 of 49 Curies 4.75E-03 2.35E-03 2.27E-03 8.91 E-01 7.10E+00 5.64E-05 8.91E-02 7.85E-02 5.45E-01 2.68E+00 8.36E-03 3.00E-04 6.59E-05 7.00E-03 5.10E-05 3.27E-06 1.57E-04 1.15E+01 Curies 3.84E-02 3.98E-02 1.25E+00 2.69E-02 8.20E-03 8.39E+00 9.66E+01 1.85E-03 1.42E+01 6.67E-01 5.11E+00 5.70E+01 2.92E-01 2.91E-03 1.22E-03 6.89E-02 2.77E-03 5.04E-05 1.35E-03 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 Sum of All 4 Categories Waste Class B Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-60 Ni-63 Sr-89 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Sum of All 4 Categories Waste Class C Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-60 Ni-63 Sr-89 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.019% 0.014% 0.417% 0.015% 4.334% 52.488% 0.001% 8.325% 0.348% 2.539% 31.292% 0.168% 0.002% 0.001% 0.037% 0.002% 0.000% 0.001% Total Percent Abundance 0.041% 0.020% 0.815% 0.020% 7.746% 61.725% 0.000% 0.775% 0.682% 4.738% 23.299% 0.073% 0.003% 0.001% 0.061% 0.000% 0.000% 0.001% Total Docket No. 50-3, 50-247, & 50-286 Page 26 of 49 Curies 3.18E-02 2.39E-02 7.06E-01 2.47E-02 7.34E+00 8.89E+01 1.79E-03 1.41E+01 5.89E-01 4.30E+00 5.30E+01 2.84E-01 2.61E-03 1.15E-03 6.19E-02 2.72E-03 4.71E-05 1.20E-03 1.69E+02 Curies 4.75E-03 2.35E-03 9.37E-02 2.27E-03 8.91 E-01 7.10E+00 5.64E-05 8.91E-02 7.85E-02 5.45E-01 2.68E+00 8.36E-03 3.00E-04 6.59E-05 7.00E-03 5.10E-05 3.27E-06 1.57E-04 1.1SE+01 Sum of All 4 Categories Waste Class All Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-89 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 0.021% 0.022% 0.680% 0.015% 0.004% 4.567% 52.585% 0.001% 7.730% 0.363% 2.782% 31.029% 0.159% 0.002% 0.001% 0.038% 0.002% 0.000% 0.001% Total Docket No. 50-3, 50-247, & 50-286 Page 27 of49 Curies 3.84E-02 3.98E-02 1.25E+00 2.69E-02 8.20E-03 8.39E+00 9.66E+01 1.85E-03 1.42E+01 6.67E-01 5.11E+00 5.70E+01 2.92E-01 2.91E,03 1.22E-03 6.89E-02 2.77E-03 5.04E-05 1.35E-03 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 Class fe m 3 Shipped A 1.35E+02 3.82E+00 1.62E+00 B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO All 1.35E+02 3.82E+00 1.62E +00 Waste Strea m Dry Active Waste U3 DAW B-25 % Error (Ci) +/-25 % +/-25 % +/-25 % +/-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 m 3 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 m 3 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 Class ft3 m 3 Shipped A 1.27E+04 3.60E+02 2.4 7E +00 B O.OOE+OO O.OOE+OO O.OOE+OO C O.OOE+OO O.OOE+OO O.OOE+OO All 1.27E+04 .3.60E+02 2.4 7E +00 % Error (Ci) +/-25% +/-25% +/-25% +/-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 8 3 Mode of Transportation Hittman Transport R & R Trucking Inc Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name H-3 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Percent Abundance 15.346% 0.167% 18.254% 0.074% 0.043% 17.635% 36.074% 0.003% 2.525%

2.358% 7.116% 0.325% 0.002% 0.001% 0.072% 0.002% 0.000% 0.003% Percent Abundance 15.346% 0.167% 18.254% 0.074% 0.043% 17.635% 36.074% 0.003% 2.525% 2.358% 7.116% 0.325% 0.002% Destination Energy Solutions Bear Creek Studsvik Processing Facility Total Curies 2.48E-01 2.70E-03 2.95E-01 1.19E-03 7.03E-04 2.85E-01 5.83E-01 5.30E-05 4.08E-02 3.81E-02 1.15E-01 5.26E-03 3.78E-05 9.73E-06 1.17E-03 2.57E-05 1.29E-06 S.43E-OS 1.62E+OO Curies 2.48E-01 2.70E-03 2.9SE-01 1.19E-03 7.03E-04 2.85E-01 5.83E-01 S.30E-05 4.08E-02 3.81E-02 1.1SE-01 S.26E-03 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 Sum of All 4 Categories Waste Class A Nuclide Name H-3 C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Sr-90 Nb-95 Sb-124 Sb-125 Cs-134 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 Percent Abundance 10.226% 0.011% 0.246% 21.506% 0.097% 10.631% 17.773% 30.839% 0.007% 0.005% 0.011% 1.692%

1.615% 5.072% 0.213% 0.002%

0.000% 0.047% 0.001%

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

0.246% 21.506% 0.097% 10.631% 17.773% 30.839% 0.007% 0.005% 0.011% 1.692% 1.615% 5.072% 0.213% 0.002% 0.000% 0.047%

0.001% 0.000% 0.002% Total Docket No. 50-3, 50-247, & 50-286 Page 32 of49 Curies 2.52E-01 2.59E-04 6.07E-03 5.30E-01 2.39E-03 2.62E-01 4.38E-01 7.60E-01 1.81 E-04 1.35E-04 2.83E-04 4.17E-02 3.98E-02 1.25E-01 5.26E-03 3.78E-05 9.73E-06 1.17E-03 2.57E-05 1.29E-06 5.43E-05 2.46E+OO 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 33 of 49 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.

Members of the Public: Docket No. 50-3, 50-247, & 50-286 Page 35 of 49 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 Routine Liquid Effluents Routine Airborne Effluents 1 Routine Liquid Effluents Indian Point Energy Center Total Dose, per 40 CFR 190 Units 1 and 2 Units 1 and 2 Unit 3 Unit 3 IPEC 2.28E-3 2.28E-3 9.00E-4 1.71E-3 3.36E-3 3.36E-3 2.49E-4 4.S9E-4 5.11 5.53 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 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 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;;'

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 Organ Dose Limit Percent of U mit Group Critical Organ Body IApplicable Limit Percent of U mit Gamma Air Applicable Limit Percent of U mit Beta Air Applicable Limit Percent of U mit Iodine/Part IApplicable Limit Percent of U mit ge Group Critical Organ 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,;

',', ,.,Qtr.4{*., ANNUAL* (mrem) 2.57E-04 1.67E-04 3.12E-05 1.37E-05 4.59E-04 (mrem) 5 5 5 5 10 (%) 5.14E-03 3.34E-03 6.24E-04 2.74E-04 4.59E-03 Adult Adult Adult Child Adult GI-LLI GI-LLI GI-LLI Bone GI-LLI (mrem) 1.96E-04 2.89E-05 2.12E-05 3.10E-06 2.49E-04 (mrem) 1.5 1.5 1.5 1.5 3.0 (%) 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" (mrad) 3.52E-05 1.07E-05 8.85E-06 1.34E-05 6.82E-05 (mrad) 5 5 5 5 10 (%) 7.04E-04 2.14E-04 1.77E-04 2.68E-04 6.82E-04 (mrad) 1.18E-04 2.15E-05 1.49E-05 2.24E-05 1.77E-04 (mrad) 10 10 10 10 20 (%) 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 (mrem) 5.92E-04 1.08E-03 8.20E-04 6.86E-04 3.18E-03 (mrem) 7.5 7.5 7.5 7.5 15 (%) 7.89E-03 1.44E-02 1.09E-02 9.15E-03 2.12E-02 Child Uver Indian Point Energy Center (Units 1, 2, and 3) RADIOLOGICAL EFFLUENT REPORT F. METEOROLOGICAL DATA Jan 1, 2009 -Dec 31, 2009 Docket No. 50-3, 50-247, & 50-286 Page 38 of 49 This data is stored onsite and is available in printed or electronic form.

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

Indian Point Energy Center (Units 1, 2, and 3) RADIOACTIVE EFFLUENT REPORT Docket No. 50-3, 50-247, & 50-286 Page 40 of 49 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 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 Northern Clean'Zone AdultDoses,inmrem

{littYEBa:

- TI'IYRClID"r' 1','

iIiIGlllfjj<3.4ii Hc3 1;;f,O,OOE+OO;,

'SL'A:64E::09,',:F:'4:64E-09,4,64E-09h't, ;,,,:4!64E:'()9,;, ,Sr-90 '.':O:OOE+OO):>O;OOE+OO:

' O:OOE+OO,',O,OOE-I{)O",:

i'i:':O:OOE+OO O;OOE+OO;,:

",,;.' totals:: O.OOE+OO . 4.64E c 09 4.64E;,()9 4.64E-09*

4.64E,.Q9 , 4,64E-09 Unit2 North

.lHVERfiHit if"t;"lI1LJNG,.n EGlflilHPi.:;

H"3 ;;'";*O.OOE+OO",'::"U2E:08"*

b12E"08';X:; .

T'c1:12E"08',,'

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 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::'

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 Unit 112 H-3 co:.60 ,O.OOE+OO

O.OOE+OO

'::::'O:OOE+OO

", O:OOE-I{)O O.OOE+OO::;:

,':;:'O.OOE+OO

' :YO.OOE+OO: . Ni-63 .. 1.99E i 05,i::: 9:61E-06 O.OOE-I{)O,

f: O:OOE+OO' Sr-90 ii;,O.OOE+OO OOOE-I{)O, :::<: 8:54E:05 ;,totals' . 8,34E-04 . 3:97F05 I:' .1.32E-05*;::, 1.98E-05 ' Ufiif3 North 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' Sr-90 ":?:8::15E;05;O.OOE-I{)O;

,t'Z:OOE-05'

," O.OOE-I{)O

: Z;35E-06::

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*

1:",'" ,;totals';

8!15E705," 6.10E:07:.

I', ZJ3E-05' '1. 13E-08 1:13E-081.13E'-08 1:36E-05 . Unit3 South .'$QJ9Re:2i .BONE. iWiiI1lVER?;\::J i"TTOIB.ODY,S!

HKlONEY;iAS!

ifSi;{;UN<3l;i: ;;;):;

H-3:*.LO, OOE+OO:) . ';:,

1.22E-08.,.

,: ,'1; 22E-08: ;:;. ,':0';122E c 08<' '; I" ,l22E"08'" . '(,,1 :ZZEc08 ::, Ni-63 C:0:00E+00;;e:00E+00\i";,;:;;0:00EfOO!;" ';'O.OOE+QO; O:OOE+OO>;;, ,;;,;'O.OOE+OO:;" /:.:O.OOE+OO:;;;

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':*

totals1.09E c 04**:

.. 'Z,67E-05"1.22E-08.

1.2ZE-08 :1,22E-08

' 3::15Ec06 Southern Clean Zone,' iiiJSQ;1;QRI:':S:;

1x.SONI:.

%&,\TOIElODY'" ;'THYROID:';:

ooU!JNG_ . O:OOE+OO,,:'

,: 2;98E:08<

'> 2.98E: 08,;,'2.98E-08

,,z.98Ec08

,'. ',":2,98E:08;::' " 2.98Ec08';;

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 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:

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.

totals O.OOE+OO; 2.98E:08 2.98E-08" 2. 98E:'()8 2.98E-08: " 2;98E-08, Z:98E'-08 . 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 'all isotopes 11:03E-03,'

1.37E-07 4.39E-05 1.47E-05

3,68Ec05 2009 . 4,45£t02;

0'0'0£+00

'O.ooEfO'O . '0:00£+00

'0.00£+0'0.

{4,{15E:+02; . EU,czii;fy,: . 4:63E+04' . '0;00£+00, . 'O.ooE+oo, : 0.00£+00 4*26£+00 ; !4!63E+04:

:::';i:, uCi':y%& 9.57E:l-03

'0.00£+'00

1:45£+'02 2:91E:l-'OJ 4.44E+O,1

19: 74E+Ol Pi.;uczi Ai . 4:94E..,03

r'02E+'Ot,'

0:00£+0'0

..

i 'O:ooE+oo 11196E+O:J!

a:uCi!B: :1:.04E+03 . O.ooE+ooJ*

'O.'ooE+oo:

4'14E+'O.1

'O:ooE+'O'O . !7iO,6E£O.ll

f':4*::1/QiiBr:

2:66£+'03, . 0:00£+00 '0:00£+'0'0 0:00£0+00

'0,00£:+00.

!2166E:+031

;rotaf'uC;s

6.79E+04 H3 1: 02£+01 Co 1:45E';'02, NI 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 analytical data for all onsite groundwater testing performed at Indian Point in 2009, as required per the aDeM and NEI 07-07.

B-1 IvfH-S .. , MW-I07 .MW.,.1r1 IVIW<30-69; MW...:30-B4 IVIW.;3i,;49 .I\IIW-3t

""63' MW:,31".B5 . MW-3:2'-19Q; MW':'35 MW':'36,,41 M\IV-37-22 MW-'37-32 MVV...:37...:40 . MW,,"37.;57 MW;;39-1'02:

MW.:.39-124 MVV;,39-183 MW.:.;3!3.,19?:

MW..,39-67 JVIW':39-84 MW-AO..,100: . MW-40-'12i IVIW...;4Q-162, MW-AO-27 . MW-AO-B1 MW,.41:-40 MW-42-49; MW,,4.2-7B' M\N-43-62

MW-"44-102 tylW-45,.42 Tritium Summary # Samples 1"2009 1 2 :3 1 2 6 6 7 7 7 7 7 1. 7 7 1 1 4 3 4 4 4 4 4 :2 2 2 2 2 2 4 4 4 4 4 4 3 3 5 4 3 3 4 4 4 #P()sitive Samples in 2009. .1 1, 3 1 2 6 6 -; 7 7 7 7 i 7 "1 1 1 4 3 4 4 4. 4. 4 :2 :2 1 t 2 2: 1 2 t 2 1. 4 3 3 5 4 2 1 4. 4 4 AvgPos Act 8.B1E+02 1,BOE,+()2 1.1tE'+03 1.96E+02 :3.08E+04 1,Q7E+05 6.11E+03 2.14E+04 1:99E+04 7.3tE+03 3:Q7E+02 7.4BE+02 2.11E+03 1.71E+04 B.16E+03 3.44E+04 1.46E+03 1.28E+03 1 ;05E+04 7.42E+Cl3 4,60E+03 4.66E+03 4.!51E+03 4:B1E+03 2A4E+02 2,:33E+02

9.85E+01' 1 :O:S,E+Cl4 3:90E+02 2.J.4E+02

'2:62E+02 1.28E+02 1A2E+02 1.5BE+02 1 :52E+02 1.74E+02 E+02 4:72E+02 1.5BE+04 4:27E+02 2;44E+02 1

'4;34E+02

4. 94E:+-02 2.9e;E+03 Docket No. 50-3, 50-247, & 50-286 Page 44 of 49 page 1 of 3 MinPos Act ,B,81 E+02 1.BOE+02 6:286+02:

2;26E+04 8 .. :20£;+04 4.69E+03 7:366+02 1,28E+04, 2.96E+03 4:31 Ef02 1.63E+O,3 B.85E+02' 6;54E+()3:

3.44E+04.

1A6E+03 2.37E+02 1.01E+04 S:b6E+03.

.3.85.E+03 3,76E+03 4.22E+03' 4.05E+03 :2.20E+02; 1.98E+()2 9.B56+O',1 t.oSE+Q2!

3;3BE+02 1.85E+Q2 2:62E.f02*

1.04E+02'

'1A2E+02!

t.17E+02 t.52E+J)2 9i11 E+01 3.1'56+02 4AOE+02 1.2BE+03 2,74E+02:

1 :73E+02 1.96E+02 2.57E+02 2.06Ef02 1 .. 4:1E+03 M'axPos Ad 8.B1 E+.02 1.BOE+02 '1'.SOE+03 1.p4E+05 7.76E+03 4. 84 E:t-b,4 :3.24E+04 1.BBE+04 4.::>7E+02 1.72E+03 2.69E+03 6A3E+04 9.16E+03 3A4E+04 1.46E+03 2.92E+o3 1.13E+04 8.61E+03 5.48.E+03 4.91E+Q3 '5.94E:l-03, ,2.67E+02

,2.68E+0,2 9.85E+Q1*

4A1E+02 2.62E+02 1.52E+02 1 ;42,EH)2 1.9.8E+02 1.52E:+02 2.31E+02 6.17E+02 5.2E)E+Qg 7.22E+0;4 3;14E+02 1.96E+02 5.15E+02 7.o44E'+02 vveliName M\M45-'61 MW4f3 MW-':49-42,'

MW,;,50"o42' MW:,S1-'i04,

' 'MW+5f':19:

MW,;,52"'11 MW L 52-122i ,

MW:,52-'t8 IVIVV-:52'-'181 MW .. 52-48 MW.,53".82, M\N,:S4.'::123

'MW i 54':S8, MVV"55-24

'MW.,55':3S:

I\IIVv-':55-54 M\IV:,5i:i-83; ,MW.;57".f1 MW".57-,;ZO

'I\IIVV-:57'-4S MVV,;58,-65 MW;60'-135, MW.,60-35 r\ilW';150:.$3

' MW.,,60-,72 I\IIW:-E)2-138' MW':'6l2;,;37, Tritium Summary 4 4 4 :4 4' 4 5 4 4 4 l' 'i T 1; :1' 1 '5 4 4 4 4 4' 4 4 4 4. 4 2 2 t t 1 3 4 4 4 4 4. 4 4 4 4 4 4 # Positive i!'l;:t(:jOS 4 .4 '-1 .4 4 4 5 2 3, 1 t i 1 1 1 5 4. 4 4. 4' 4' .4 4. 4 4 4' 2 2 1, 1: J 3 '3 4 4 4 3 2 3 4 A, 4 4 ;4 1 :336+03 9.22E+02 i;3':2$6+0;3 2A96+03 1 ;S,26+03 :5;,196+02

)2;956+03 2j86+92, 2.086+02 ,1;99£::+02 5.196+02 '1.156'+02 4:926+02 , 2,29£::+02 1A76+02, 1,436+02 '5':256+03 6,516,+02 1.326+03 "1:816+03 1.756+03 1.366f03 7,40E+02 1.296+03 2.19E+()3 6At6+03 5,936+02 ;3.206+03 j;526+03 1.196+03 :4:526+02 2.486:+-02 3,416f02 4.446+02 1 :006+03 2.306+02 '3:5:16+Q2 . 1.716:+:02 J3;S,16+Q2 3:606+02 :5;536+02 3.566+02 3.286:+-02 Docket No, 50-3, 50-247, & 50-286 Page 45 of 49 page 2 of 3 Mir(Pos' ivlaxPos Act .,Act 10466+03 7,566+02 1 .. 106+()3 3; 19E+.03: '3;566+03 2.256+03 1 :66E+'03 2:,1'56+02;

,,1 ;066+0,3, 2.30E+03;

30456+03 1 :446+02 '2:916+02 1 :S56+02 2'.676+02 t,$96+02,1 5>196+02 itSE+02: 1 :156f02 .(92'6+02 4:926+02 *2.296 ... 02 .2;.296+02 1A76+021.47'E+02 10436f02; 1>436+02 5,()5E+03'5:6,5E+03 6.646f02 1.576+'031

986+03 1,436: +03,2.01

'1.t66+03 1.606fOqi

$.$8E+02 8;386+02 1,:046+03 1:596+03 8.53E+02 2.8'3E+03 5A76+03 3.156+03 3,246t03 4.226+03 ,4:226+03 1;:526+03:1.526+03

1.196+0:3, L 19E,+03 4,,136+02'

'5.196+02 3:176+02' 1 .046+03 2.006:+:02, 2.036+()2 4.99E+02 t.676+02' 1 ]36+02 5.76E+02, 2.366+02 4.646+02 4.666+02 7.366+02 2:1.76+02 A87E+()2 2.406+02 A.336':+:()2 Well Name MW-6j.;H2 NlW-63.;163 MW,,63-50:

MW'-67-10s:

MW,,67-173 M\/V'"67-219 MW-6.7,,276 MW-67-323 MW,6.7-39 ,U1..:G$S U3-40:

Note 1: Note 2: N6te,'3: Tritium Summary 4 4 4 4 4 4 4 4 4 4 5 4 4 5 4 4 4 4 4 4 4 4 1# Positiv¢ ;Samples in 2009, 4 4 4 4 4 4 '2 4 4 4 4 4 4 5 4 4 4 4 4 3, 4 4 4 All results imi in:pCiI.L Act 3 ..

o4J4E+02

'5;32E+02

5:59E+02 4.67E+02 2:89E+02 ,3.4$,E+02

'3.31E+02 2.68E+02 6.66E+02 '3.85E+03 1;96E+03 8:07E+02 1 ..

1

.3.94E+02 9.Q7p+04 3.26E+03 2.59E+03 4.55E+02 4.49 E+02, 1 Docket No. 50-3, 50-247, & 50-286 Page 46 of 49 Min Pbs Act' 2.80E+02 *t37E+02:

4.:66E+02 4:36E+02 4.22E+02' 1.97E+02' 2:98E+02 1".66E+02 4,29E+02 3;05E+03 1;77E+03 673E+02 9.t7E+02 3.6SE+()2 4);OE+02 2.69E+03 1.97E+03 3.82E+02 8.94E+02 page 3 of 3 Max Po's Act 4;78E+Q2 6,086+02 4.96E+02 ,6.23E+02 6.96E+02 4.98E+02 3.80Et02 4.2"OE+02 3.60E+02 3.40E+02 9.51E+02 4.39E+03 .. f2E+03 1.05E+03 1.10E+03 4.21 E+02 5,;37E+02 3.88E+03 3.28E+03 4,82E+02 1J2E+03 A totalof431 sa'i"nples for in 2009, with 3.85 positive' results. . . ", A sample 'is pp:sitive ifthe r¢siJlt is greater tirnes 1 sigm,a Moe is'200 pCi/L Well Name MW-42,.49

MW-44-66 MVV-63-163 Note 1: N6te2: Well Name MWA2"49'

MW .. S7 No!e 1,: Note2: Cobalt-50 Summary in 2009 5 4 4 it: P()sitlve 2009 1 1 1. All results are inpCi/L Act 5.23E+00 3'.()9E+bb Docket No. 50-3, 50-247, & 50-286 Page 47 of 49 Min Pos Act 5.23E+00 3.09E+OO 6.80E+OO Ac: t 5.23E+00 . 3. 09 EH).b $.80(:+<;>0 A t6talOf. 431 sa mph:fs Were analyzed iii 200.9.

'" A sample P9sitive inhEf;resLJlt is greater 3

1 si9 rnCl M[)(} is'1$ pCilL Nickel-53 Summary # Samples' in 2009. 5 4 5 4 #P'osJtive Samples in 2009 5 1 1 ,1 All resul,ts areinpGJ!L Avg Pos Act 6.49E+02 2,318+01 8.408+01 2.21E+01 MinPos Act 7.46 EtO.1 2.3.1E+01 8.40E+01 2:211:+:,01 MaxPos Act 1. t6E+03., . 2.91'E+Q1 8.406+01 2,ZtE+th A total of 176 fpr Ni .. i[l2009 with 8 positive.

results'.

A pO$itive if fheJ¢slIltis tharlor 3 times the 1 sigma*.uncertainty; The target MDe is,30 pCi/L Well Name ,MV\f-t1l Mw'3tc49 fI,i\N<3p';,52; MW+37';22

.. 124 ,MW-39"84

'MW,,41-4Q' I\!1W-41-63':

'MW"'42-49' MW-43-62 MW-46' ' , MW-49"26' M\I\I-49-65: , MW 7 54-1.23 MW-54..;190:

MW-54-3T ,MW-57-4S' Strontium-gO Summary t;t'Sampie.

s' ,in 2009 2 7 7: 7 :3 4 4 4 4 4 :2 2 2 2 3 3 5 4 ;4 4 4 4 4 5 5 4 4 4 4 4 4 4 4 4' 4 2 1 1 1 3 4 4 # Positive Sr;;.gp in 2009: 2 1 :3 1 3 4' 4 4 4 4 2 2 1 2 2 :3 3 '5, 3 1 1 4 4' 4 4 5 4 '1 4 4' 4 4: 4 4, 4 4' 4 2 1 1 1 1 4, 1 AVQ 1.51 E+OO' 5.58E;.01 SA3E+OO 3.50E+.OO 1.85E+01 8;35E+,OO 2:63E+01 1.82E+OO' 1.39E+OO 6.89E*01 2.8SE+,OO 1.58E+OO 4.5SE+OO 3.S4E+OO 3.09E+02 7.80E:'01 1.,3SE+01 f.83E+01 1..3,5E+01 4.10E+OO 2.78E+01 2.77E+01 2.30E+OO 4.54E+o6:

1 :4SE+01 8:85E+OQ 5;90E+OO :r.i83E+OO 2.0SE+01 3.0SE.+01 2.64E+01 2,75E+OO 4.72E+01 2.71E+OQ 2.25E+OO 6,33E-01' 2.10E+OO 1;o9E+06 Docket No. 50-3, 50-247, & 50-286 Page 48 of 49 page 1 of 2 Minpgs A,e,t 5;S9E':01 4'.03E+OQ 2AOE+OO ,8.8tE+OO 1.11E+Ot 1.11E+OO 1.99E+01' 1.24E+OO S:89E.:m 2.37E+OO 1 J1E+OO 4.00E+OO :2.67E+00 7',80E-:01 8:60E':01 1.23E+o1 1.74E+Q1 1.J4E:+Ot 1.9E3E+OO 2A2E;+Ol :2.37E+Ot 2,jOE+QO 3.77E+OO 1.43E+01 7.42E+OO 1.90E+O'1 1.41 E+OO 1.71 E+01 2AtE+of 2.71 E+OO 4.72E+Ot 2:.7'7E+OO

,l2':25E+OO 6(33 E.;O 1 1 :31E+OO 1.09E+QQ ,Ad 1.tOE+.OQ 8.00E*01 7.12E+OO t,2.4E+01 2.38E+O:1 1.69E+01 3;17E+01 2.40E+o6 t87E+Oq 5:38E+OO 4.08E+o6 f3.:.7'7 E:+02 124E+Og

.. 01, 1 :50E-i:01 2:07E+01 6;73E+Oq 3.00E+O,1 3:tQE-+:O.1 2:30E+OO 5:91 E+bb' 1:51 E+O:1 1:02E+O,1 1.98E+01 2;'OOE;:bq.

3;07E+O,1 4;*t4E+01 3,27E+01 2:78E+OQ' 4.72E+01 2.77E+QO 2.83E+OO 1.09E+'OO Well.*Name MW63-121 . MW,g;3.,93 MW,.66..:36 . MVV.,67 -105 U1"CSS U 3'-T 1. U3;;T2 Note 1-; N6te2*: Note 3: Wen Name ,MW30".84

'Mw-41'.:40, MW':'42-49 . MW,.55-24' MW.:.57..:11 MW.,SO-1.54 Nole.1: Note 2: Note: 3: Strontium-gO Summary # Samples, hi 2009' 4 4 4 4 4 3 4 4 # Positive in 2009, 1 1 4 2 4 .3 1 '1 AILresutts arelh pOi/t. Avg Pos Act 7.30E-Ot 9:31E+00 1;13E+01 2.24E+01 1,04E+.QO 1.76E+00 Docket No. 50-3, 50-247, & 50-286 Page 49 of 49 Min Pos Act 7.30E..:01 S.44E':01

.6.82E+00 6.37E+00 1.41 E+01 1 ;Q4E+QO 1.76E+00 page 2 of 2 Max Pas Act 7.30E-01 5,44E-()1 1..22E+01 SA9E-01 '1A2E+01 3.56E+01 LQ4.E+OQ 1.76E+00, AtotalofA3.1 sample's*Vi/ere*ahalyzed in 2009 With 14S>pqsitive resqfts, .. r_ A sampfeispositive ifthed'esuft is greater than or equarto:3 tlr:nesthe 1

ThE! target MDCi.s'1pCi/L Cesium-137 Summary # Positive #Samples' Samples in AvgPos Min Pos Max Pos in 2009 2009 Act Act Act S 1. 8.97E+00 8:97E+00 8.97E+00 :3 1 4.2SE+ob 4.26E+.ob 4.2SE+DO S S 6.73E+04 S.42E+03 f.40E+OS 1 f,18E+()i 1.181::+01 1;18E+01 4 1 7.7SE+.00 T7SE+00 7.76E+00 4 1 1.03E+01 1.03E+01 1'.03E+01 1 1 3.89E+00 3:89E+00 3.89E+00 4 1 1.34'E+Q1 1.34E+01 1.34E+01 5 '1 B.99E+Ob 8.99E+00*

5 1 ;:3 4E+0 1 1:34E+01 1.34E+Ol AIlr'Efsults are .. iri pCi/L Atotal of 431, samples were.analyzed in 2009 with 14 positive res.ults. . ,', ... . . A sample is )fthe, result is' greater, than:orequal to 3 1 sigma uncertail'lty:

target IV! DC is' 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 1.1 1.2 1.3 2.0 2.1 2.2 2.3 2.4 2.5 2.6 3.0 3.1 3.2 3.3 3.4 3.5 3.6 4.0 4.1 4.2 4.3 4.4 5.0 RADIATION MONITORS AND SETPOINTS Effluent Monitoring System Description Setpoints for Airborne Effluent Monitors Setpoints for Liquid Effluent Monitors LIQUID EFFLUENT METHODOLOGY Liquid Effluent Releases -General Information Liquid Effluent Concentrations Liquid Effluent Dose Calculation Requirements Dose Methodology (Computer Calculation)

Backup Simplified Dose Methodology Site-Specific Bio-Accumulation and Dose Factors GASEOUS EFFLUENT METHODOLOGY 1 1 2 6 9 12 13 16 16 Gaseous Effluent Releases -General Information 25 Gaseous Effluent Dose Calculation Requirements 30 Dose Methodology (Computer Calculation) 31 Backup Simplified Dose Methodology 43 Calculation of Meteorological Dispersion Factors 46 Justification and Use of Finite Cloud Assumptions for Assessing SB Dose 51 TOTAL DOSE DETERMINATIONS 10CFR190 Dose Evaluation Doses from Liquid Releases Doses from Atmospheric Releases Doses to MEMBERS OF THE PUBLIC Visiting the Site LOWER LIMIT OF DETECTION 100 100 100 101 102 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 3.2.1-1 Radioactive Gaseous Waste Sampling and Analysis D 3.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.5.1-1 Radiological Environmental Monitoring Program D 3.5.1-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples D 3.5.1-3 Detection Capabilities for Environmental Sample Analysis . Figures: 4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 4.1-2 MAP DEFINING RELEASE POINTS IPEC ODCM . vi D 3.1.1-2 D 3.2.1-2 D 3.3.1-6 D 3.3.2-5 D 3.5.1-6 D 3.5.1-9 D3.5.1-10 D 4.1-2 D 4.1-3 Revision 2 LIST OF TABLES AND FIGURES PART 11-CALCULATIONAL METHODOLOGIES 1-1 1-2 2-1 2-2 2-3 2-4 3-1a 3-1b 3-1c 3-1d 3-2 3-3a 3-3b 3-3c 3-3d 3-4 3-5 3-6 3-7 3-8 3-9 3-10a 3-10b 3-10c 3-10d 3-11a 3-11b 3-11c 3-12a 3-12b 3-12c 3-12d 3-13 Unit 2 Effluent Radiation Monitor System Data Unit 3 Effluent Radiation Monitor System Data Site Related Adult Ingestion Dose Commitment Factors Site Related Teen Ingestion Dose Commitment Factors Site Related Child Ingestion Dose Commitment Factors Bio-Accumulation Factors for Liquid Effluent Isotopes Adult Inhalation Dose Factors Teen Inhalation Dose Factors Child Inhalation Dose Factors Infant Inhalation Dose Factors TBISkin GP Dose Factors, wI Half Life & Stable Element Transfer Data Adult Ingestion Dose Factors Teen Ingestion Dose Factors Child Ingestion Dose Factors Infant Ingestion Dose Factors Total Body Dose Factors, Ki, from Noble Gas (Gamma) Skin Dose Factors, Li, from Noble Gas (Beta) Air Dose Factors, Mi, from Noble Gas (Gamma) Air Dose Factors, Ni, from Noble Gas (Beta) NG Dose Factors for Instantaneous and Time Average Mixtures at the SB Locations of Site Boundary and Nearest Residence Adult Inhalation Ri(l) Teen Inhalation Ri(l) Child Inhalation Ri(l) Infant Inhalation Ri(l) Adult Ingestion (Leafy Vegetable)

Ri(V) Teen Ingestion (Leafy Vegetable)

Ri(V) Child Ingestion (Leafy Vegetable)

Ri(V) Adult Grass-Cow-Milk Pathway Ri(C) Teen Grass-Cow-Milk Pathway Ri(C) Child Grass-Cow-Milk Pathway Ri(C) Infant Grass-Cow-Milk Pathway Ri(C) Total Body and Skin Ground Plane Dose Factors Ri(G) and Ri(S) 4 5 18 20 22 24 52 54 56 58 60 62 64 66 68 70 71 72 73 74 75 76 78 80 82 84 86 88 90 92 94 96 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 1 OCFR50 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. GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S)

OF THE PUBLIC MAXIMUM PERMISSIBLE CONCENTRATION WATER (MPCW) OFFSITE DOSE CALCULATION MANUAL PRIMARY TO SECONDARY LEAK PROCESS CONTROL PROGRAM IPEC ODCM Definition A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S)

OF THE PUBLIC includes all persons who are not 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.

MPCW is that concentration of a radionuclide equal to ten times the EFFLUENT CONCENTRATIONS specified in 10CFR20, Appendix B, Table 2, Column 2. The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite 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. A PRIMARY TO SECONDARY LEAK is defined by a quantifiable leak rate equal to or greater than 0.5 gpd, AND a) The presence of fission or activation products in the secondary fluid, verified as Steam Generator U-tube leaks (and not from other known contamination, such as IVSWS leaks), OR b) Tritium activity in the secondary fluid indicating an increase above historical baseline (normal diffusion) of 5.00E-6 uCi/ml or greater. The PROCESS CONTROL PROGRAM is a manual containing and/or referencing selected operational information concerning the solidification of radioactive wastes from liquid systems. D1.1-1 Revision 2 o 1.1 Definitions PURGE -PURGING SITE BOUNDARY SOLIDIFICATION SOURCE CHECK UNRESTRICTED AREA VENTILATION EXHAUST TREATMENT SYSTEM VENTING IPEC ODCM Definitions 01.1 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.

The SITE BOUNDARY is that line beyond which the land is neither owned, leased, nor otherwise controlled by the licensee(s).

SOLI 01 FICA TION is the conversion of wet wastes into a form that meets shipping and burial ground requirements.

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

An UNRESTRICTED AREA is any area at or beyond the SITE 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) A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal 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 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.

01.1-2 Revision 2 1.0 USE AND APPLICATION 1.2 Logical Connectors Logical Connectors D 1.2 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. 'IPEC ODCM 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. 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 RELEASE TYPE 1. Batch Waste Release Tanks (b) eg, Waste Tanks, SG Draindowns, etc 2. Continuous Releases (e) eg, SG Blowdown, U1 NCO, U1 SFDS, etc 3. Service Water (in Radiologically Controlled Areas) 4. Turbine Hall Drains, SG Feedwater (i) IPECODCM Liquid Effluents Concentration D 3.1.1 TableD 3.1.1-1 (Page 1 of2) Radioactive Liquid Waste Sampling and Analysis MINIMUM LOWER LIMIT OF DETECTION SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS (LLD) in uCi/ml, TYPE FREQUENCY FREQUENCY (a),(g),(c)

Principal Gamma Emitters 5E-7 Grab Sample Each Batch (h) Each Batch (h) Mo-99, Ce-144 5E-6 1-131 1E-6 One batch per Dissolved and Grab Sample 31 days Entrained Gases 1E-5 31 days (h) (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 Composite (d) Composite 7 days Principal Gamma Emitters (c) 5E-7 Mo-99, Ce-144 5E-6 1-131 1E-6 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 Grab Sample 31 days 31 days Gamma and Beta Per liquid batch emitters OJ releases, above. Gamma and Beta Per liquid batch Composite (d) Composite 7 days emitters OJ releases, above. 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 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 A. Calculated dose to a A.1 MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents to UNRESTRICTED AREAS exceeds limits. IPEC ODCM REQUIRED ACTION COMPLETION TIME Prepare and submit to the 30 days NRC, pursuant to D 5.3, a Special Report that (1) Identifies the cause(s) 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 3.1.2. D 3.1.2 -1 Revision 2 ACTIONS (continued)

CONDITION B. Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents exceeds 2 times the limits. C. Required Action B.2 and Associated Completion time not met. IPECODCM REQUIRED ACTION B.1 Calculate the annual dose to a MEMBER OF THE PUBLIC which includes contributions from direct . radiation from the units (including outside storage tanks, etc.). AND B.2 Verify that the limits of DLCO 3.4 have not been exceeded.

C.1 Prepare and submit to the NRC, pursuant to 0 5.3, a 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.

03.1.2 -2 Liquid Effluents Dose 03.1.2 COMPLETION TIME Immediately Immediately 30 days Revision 2 SURVEILLANCE REQUIREMENTS DSR 3.1.2.1 IPEe ODCM SURVEILLANCE.

Determine cumulative dose contributions from liquid effluents for the current calendar quarter and the . current calendar year. D 3.1.2 -3 Liquid Effluents Dose D 3.1.2 FREQUENCY 31 days 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 treatment.

Projected doses due to the liquid effluent, from the unit, to UNRESTRICTED AREAS would exceed limits. SURVEILLANCE REQUIREMENTS NRC, pursuant to D 5.3, a Special Report that includes:

(1) An explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the 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 FREQUENCY DSR 3.1.3.1 IPEC ODCM Project the doses due to liquid effluents from each unit 31 days to UNRESTRICTED AREAS. D 3.1.3 -1 Revision 2 D 3.1 LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks Liquid Holdup Tanks D 3.1.4 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 Outdoor Temporary Tanks Radioactive Effluent Release Report. SURVEILLANCE REQUIREMENTS DSR 3.1.4.1 IPECODCM SURVEILLANCE Determine that the quantity of radioactivity in outdoor liquid unprotected tanks (listed above) does not exceed the limit. D 3.1.4 -1 next Radioactive Effluent Release Report FREQUENCY 31 days, during periods where radioactive liquid is being added to the tanks, in accordance with the methodology and parameters of the ODCM Revision 2 Gaseous Effluents Dose Rate D 3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS Gaseous Effluents Dose Rate D 3.2.1 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 A. The dose rate(s) at or beyond the SITE BOUNDARY due to radioactive gaseous effluents exceeds limits. A.1 Restore the release rate to within the limit. SURVEILLANCE REQUIREMENTS DSR 3.2.1.1 DSR 3.2.1.2 IPEC ODCM SURVEILLANCE The dose rate from noble gases in gaseous effluents shall be determined to be within the limits of DLCO 3.2.1.a. The dose rate from 1-131, H-3 and all 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. D 3.2.1 -1 COMPLETION TIME Immediately FREQUENCY In accordance with Table D 3.2.1-1 In accordance with Table D 3.2.1-1 Revision 2 GASEOUS RELEASE TYPE 1. Waste Gas Storage Tank Purge 2. Vapor Containment Press Relief 3. Condenser Air Ejector 4. Continuous Ventilation:

a. Main Plant Vent (unit 2) b. Stack Vent (unit 1) c. Main Plant Vent (unit 3) d. Radioactive Machine Shop Vent (unit 3) e. Admin Bldg Vent (unit 3) IPEC aDCM 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 SAMPLE SAMPLE ANALYSIS SAMPLE LIMIT OF TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD) (a) Principal Grab Noble 1E-4 Sample Each Tank (h) Each Tank (h) Gas (NG) Il Cilcc Gamma Emitters (b) Grab Principal NG Sample Each Purge (h) Each Purge (h) Gamma 1E-4 Emitters (b) Il Cilcc Grab Principal NG . 1E-4 Sample 31 days (i) 31 days (i) Gamma Il Cilcc Emitters (b) Grab Principal NG 1E-4 Sample 31 days 31 days Gamma Il Ci/cc Emitters (b) Grab Principal NG 1E-4 Sample 31 days (c) 31 days (c) Gamma Il Cilcc Emitters (b) H-3 Continuous 31 days (e) H-3 1E-6 Specific Il Cilcc Charcoal 1E-12 Sample Continuous (f) 7 days (c), (g) 1-131 Il Cilcc Principal Particulate Gamma 1 E-11 Sample Continuous (f) 7 days (c), (9) Emitters (b) Il C ilcc (1-131, Others) Composite 1E-11 Particulate Continuous (f) 31 days Gross Alpha Il Cilcc Sample Composite 1 E-11 Particulate Continuous (f) 92 days Sr-89 / Sr-90 Il C ilcc Sample Noble Gas Noble Gases 1E-6 Monitor Continuous (f) Continuous (f) Gross Beta IlCilcc (d) or Gamma 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 A.' The calculated air dose at A.1 or beyond the SITE. BOUNDARY due to noble gases released in gaseous effluents exceeds limits. IPEC ODCM REQUIRED ACTION COMPLETION TIME Prepare and submit to the 30 days NRC, pursuant to D 5.3, a Special Report that (1) Identifies'the cause(s) 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. D 3.2.2-1 Revision 2 ACTIONS (continued)

CONDITION B. Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in airborne effluents exceeds 2 times the limits. C. Required Action B.2 and Associated Completion time not met. IPEC ODCM B.1 AND B.2 C.1 Gaseous Effluent Dose -Noble Gas D 3.2.2 REQUIRED ACTION COMPLETION TIME Calculate the annual dose to Immediately a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the units (including outside storage tanks, etc.). Immediately Verify that the limits of DLCO 3.4 have not been exceeded.

Prepare and submit to the NRC, pursuant to D 5.3, a 30 days 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.

D 3.2.2 -2 Revision 2 Gaseous Effluent Dose -Noble Gas D 3.2.2 SURVEILLANCE REQUIREMENTS DSR 3.2.2.1 IPEC ODCM SURVEILLANCE Determine cumulative dose contributions for the current calendar quarter and current calendar year. D 3.2.2 ':' 3 FREQUENCY 31 days 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 A. The dose from 1-131, A.1 tritium, and radioactive material in particulate form with half-lives>

8 days released in gaseous effluents at or beyond the SITE BOUNDARY exceeds limits. IPEC ODCM REQUIRED ACTION COMPLETION TIME Prepare and submit to the 30 days NRC, pursuant to 0 5.3, a Special Report that (1) Identifies the cause(s) 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 3.2.3. 03.2.3 -1 Revision 2 ACTIONS (continued)

CONDITION B. Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents exceeds 2 times the limits. C. Required Action B.2 and Associated Completion time not met. IPECODCM B.1 AND B.2 C.1 Gaseous Effluent Dose -Iodine and Particulate D 3.2.3 REQUIRED ACTION COMPLETION TIME Calculate the annual dose to Immediately a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the units (including outside storage tanks, etc.). Verify that the limits of DLCO Immediately 3.4 have not been exceeded.

Prepare and submit to the NRC, pursuant to D 5.3, a 30 days 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.

D 3.2.3 -2 Revision 2 Gaseous Effluent Dose -Iodine and Particulate D 3.2.3 SURVEILLANCE REQUIREMENTS DSR 3.2.3.1 IPEC aDCM SURVEILLANCE Determine cumulative dose contributions for the current calendar quarter and current calendar year for 1-131, tritium, and radioactive material in particulate form with half-lives>

8 days. D 3.2.3 -3 FREQUENCY 31 days 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 waste is being discharged without treatment.

A.1 Prepare and submit to the 30 days AND Projected doses due to the gaseous effluent, from the unit, at and beyond the SITE BOUNDARY would exceed limits. SURVEILLANCE REQUIREMENTS NRC, pursuant to D 5.3, a Special Report that includes the following:

(1) Identification of any inoperable equipment or subsystems and the reason for the inoperability, (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 DSR 3.2.4.1 IPEC ODCM Project the doses due to gaseous effluents from each unit at and beyond the SITE BOUNDARY.

D 3.2.4 -1 FREQUENCY 31 days 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 waste is being discharged without treatment.

Prepare and submit to the 30 days Projected doses due to gaseous effluent, from each unit, to areas at or beyond the SITE BOUNDARY would exceed limits. SURVEILLANCE REQUIREMENTS NRC, pursuant to D 5.3, a Special Report that includes the following:

(1) Identification of any inoperable equipment or subsystems and the reason for the inoperability, (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 DSR 3.2.5.1 IPEC ODCM Project the doses from gaseous releases from each unit to areas at and beyond the SITE BOUNDARY when the GASEOUS RADWASTE TREATMENT SYSTEMS are not being fully utilized.

D 3.2.5-1 FREQUENCY 31 days Revision 2 o 3.2 GASEOUS EFFLUENTS o 3.2.6 Gas Storage Tanks Gas Storage Tanks o 3.2.6 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 A. Level of radioactivity exceeds the limits. A.1 Suspend addition of radioactive material.

A.2 Reduce content to within the limits. SURVEILLANCE REQUIREMENTS DSR 3.2.6.1 IPEC ODCM SURVEILLANCE The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limits above, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank in accordance with the methodology and parameters in the ODCM. 03.2.6 -1 COMPLETION TIME Immediately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months FREQUENCY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during addition of radioactive material to the tank 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 ACTIONS (continued)

CONDITION B. One or more required channels inoperable.

C. As required by Required Action B.1 and referenced in Table D 3.3.1-1. D. As required by Required Action B.1 and referenced in Table D 3.3.1-1. IPEC ODCM B.1 AND B.2 C.1 AND C.2 D.1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 REQUIRED ACTION COMPLETION TIME Enter the Condition Immediately referenced in Table D 3.3.1-1 for the channel. Restore inoperable 30 days channel(s) to OPERABLE status. Analyze at least 2 Prior to initiating a independent samples in release accordance with Table D 3.1.1-1. -----------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. Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months samples for radioactivity at a limit of detection of at least AND 5 x 10-7 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter D 3.3.1 -2 Revision 2 ACTIONS (continued)

CONDITION E. As required by Required E.1 Action B.1 and referenced in Table D 3.3.1-1. OR E.2 F. As required by Required F.1 Action B.1 and referenced in Table D 3.3.1-1. G. As required by Required G.1 Action B.1 and referenced in Table D 3.3.1-1. H. Required Action B.2 and H.1 associated Completion Time not met. IPEC ODCM Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 REQUIRED ACTION COMPLETION TIME Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months samples for radioactivity at a limit of detection of at AND least 5 x 10.7 when specific activity is Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months > 0.01 DOSE thereafter EQUIVALENT 1-131. 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 1 0.7 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 DOSE thereafter EQUIVALENT 1-131. ---------------

NOTE ------------

Pump performance curves 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generated in place may be 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.

Estimate tank liquid level. Immediately AND During liquid additions to the tank Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report inoperability was not corrected in a timely manner. 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.

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

DSR 3.3.1.6 DSR 3.3.1.7 DSR 3.3.1.8 DSR 3.3.1.9 IPEC ODCM SURVEILLANCE Perform CHANNEL OPERATIONAL TEST. The 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 Perform CHANNEL OPERATIONAL TEST. The 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. Perform CHANNEL OPERATIONAL TEST Perform CHANNEL CALIBRATION D 3.3.1 -5 FREQUENCY 92 days 92 days 24 months 24 months 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 APPLICABILITY REQUIRED CONDITIONS REFERENCED INSTRUMENT OR OTHER CHANNELS FROM SURVEILLANCE SPECIFIED PER REQUIRED REQUIREMENTS 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 Blowdown Effluent Line (R-51) DSR 3.3.1.7 (e) DSR 3.3.1.9 (d) c. Unit 1 Sphere Foundation DSR 3.3.1.1 Drain Sump Effluent Line (R-62) (a) D DSR 3.3.1.4 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 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 INSTRUMENT

3. Flow Rate Measurement Devices a. Unit 2 Liquid Radwaste Effluent Line (CT971-FRE, CT971-FIE)

b. Unit 2 Steam Generator Blowdown Effluent Line (FI-1241 to FI-1244, and FT-1241 to FT-1244) c. Unit 1 North Curtain Drain Effluent Line (f) (LW-FE-12)

d. Unit 1 Sphere Foundation Drain Sump (f) (FR-7874)

e. Unit 3 Liquid Radwaste Effluent Line (FE-1064, FI-1064) f. Unit 3 Cond Polisher (CPF) Effluent Line (3LG-FIT-41, (3LG-FM-41,3LG-FR-41)

g. Unit 3 Steam Generator Blowdown Effluent Line (FT-545 to 548, FIR-543,544)

4. Tank Level Indicating Devices (c) a. Unit 1 Waste Distillate Storage Tank #13 (CT967-L1E-1, L1E-2) b. Unit 1 Waste Distillate Storage Tank #14 (CT974-L1E-1, L1E-2) c. Unit 2 Primary Water Storage Tank (LT-1131, L1-1131) d. Unit 2 Refueling Water Storage Tank (L1-920, L T-920, L T-5751) e. Unit 3 Refueling Water Storage Tank (L1-920A, L1-920B) IPEC aDCM APPLICABILITY OR OTHER SPECIFIED CONDITIONS (a) (a) (i) (a) (a) (a) (a) (a) (i) (a) (a) (a) (a) (a) D 3.3.1 -7 REQUIRED CHANNELS PER INSTRUMENT CONDITIONS REFERENCED FROM REQUIRED ACTION B.1 F F F F F F F G G G G G SURVEILLANCE REQUIREMENTS DSR 3.3.1.2 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.2 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.2 DSR 3.3.1.9 DSR 3.3.1.2 DSR 3.3.1.9 DSR 3.3.1.2 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.2 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.2 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.1 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.1 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.1 DSR 3.3.1.5 DSR 3.3.1.9 DSR 3.3.1.1 G) DSR 3.3.1.1 G) (b) (b) (b) (b) (b) Revision 2 6/09 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 INSTRUMENT OR OTHER CHANNELS REFERENCED SURVEILLANCE 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 Unit 3 CPF High Total DSR 3.3.1.1 (b) (a) G DSR 3.3.1.8 Dissolved Solids Tank DSR 3.3.1.9 (h) (3-LG-Ll-12)

j. Unit 3 CPF Low Total DSR 3.3.1.1 (b) (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 ACTIONS (continued)

CONDITION C. As required by Required Action B.1 and referenced in Table D 3.3.2-1. D. As required by Required Action B.1 and referenced in Table D 3.3.2-1. E. As required by Required Action B.1 and referenced in Table D 3.3.2-1. F. As required by Required Action B.1 and referenced in Table D 3.3.2-1. ,IPEC ODCM Radioactive Gaseous Effluent Monitoring Instrumentation .D 3.3.2 REQUIRED ACTION COMPLETION TIME C.1 Take grab samples. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.1 Estimate the' flow rate for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the inoperable channel(s).

AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter E.1 Continuously collect 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples using auxiliary sampling equipment as required in Table D 3.2.1-1. F.1 Determine the radioactive 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months content of the receiving 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 D 3.3.2 -2 Revision 2 ACTIONS (continued)

CONDITION G. As required by Required Action B.1 and referenced in Table D 3.3.2-1, for gas decay tank releases.

H. Required Action B.2 and associated Completion Time not met. I. Required Action and associated Completion Time for Condition C, D, E or F not met. J .. Required Action and associated Completion . Time for Condition G not met. K. As required by Required Action B.1 and referenced in Table D 3.3.2-1 (in MODES 1-4 only). IPEG ODCM Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 REQUIRED ACTION COMPLETION TIME G.1 Analyze at least 2 Prior to initiating a . independent.

samples in gas decay tank accordance with release 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.1 Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report inoperability was not frequency corrected in a timely manner. 1.1 Suspend gaseous effluent Immediately releases monitored by the inoperable channel(s). , J.1 Suspe.nd gaseous effluent Immediately releases from Waste Gas Holdup System . K.1 Take Noble Gas grab Prior to venting samples and analyze for Vapor Containment . gross activity. (VC) K.2 Immediately suspend PURGING the VC. 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 b occurs if the instrument indicates measured levels a ove the alarm/trip setpoint.

This test does NOT include of 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), 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 of 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 INSTRUMENT APPLICABILITY REQUIRED CONDITIONS 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 Monitor, providing (b) 1 F DSR 3.3.2.4 DSR 3.3.2.6 Alarm, (R-20) DSR 3.3.2.7 (c) 2. Condenser Air Evacuation System a. Unit 2 Noble Gas DSR 3.3.2.1 Activity, (R-4S) (a) 1 C DSR 3.3.2.4 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 and OR OTHER CHANNELS REFERENCED SURVEILLANCE APPLICABLE UNIT SPECIFIED PER FROM REQUIREMENTS (1,2, or 3) CONDITIONS INSTRUMENT REQUIRED 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)

Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 e. 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 INSTRUMENT APPLICABILITY REQUIRED CONDITIONS and OR OTHER CHANNELS REFERENCED SURVEILLANCE APPLICABLE UNIT SPECIFIED PER FROM REQUIREMENTS (1,2, or 3) CONDITIONS INSTRUMENT REQUIRED 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

8. 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 INSTRUMENT APpLICABILITY REQUIRED CONDITIONS REFERENCED SURVEILLANCE and OR OTHER* CHANNELS FROM .. REQUIREMENTS APPLICABLE UNIT SPECIFIED PER (1,2, or 3) CONDITIONS INSTRUMENT REQUIRED ACTION B.1 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 Radioactive Effluents Total Dose 03.4.1 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 DSR 3.4.1.1 IPEC ODCM SURVEILLANCE Perform a cumulative dose calculation due to radioactive material in gaseous and liquid effluents to determine compliance with DLCO 3.4.1. . D 3.4.1 -2 FREQUENCY 12 months 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 ACTIONS (continued)

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

NOTE S-------------

1.0nly applicable if the radioactivity/radionuclides are not the result of plant effluents.

2. For radionuclides other than those in Table 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. Report and describe the condition in the Annual Radiological Environmental Operating Report. D 3.5.1 -2 In accordance with the Annual Radiological Environmental Operating Report frequency Revision 2 ACTIONS (continued)

CONDITION C. Milk or fresh vegetation samp es unavailable from one or more of the sample locations required by Table D 3.5.1-1. D. Environmental samples required in Table D 3.5.1-1 are unobtainable due to samplin U equipment malfunc Ions. IPEC ODCM C.1 AND C.2 -AND C.3 D.1 AND D.2 Radiological Environmental Monitoring Program D 3.5.1 REQUIRED ACTION COMPLETION TIME Identify specific locations 30 days for obtaining replacement ana add them to the adiological Environmental Monitoring Program. Delete the specific locations from which 30 days samples were unavailable from the Environmental onitoring . Program. 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 the new location s) with supporting information identifyinib the cause of the unavaila ility of samples and {ustifyin g the selection of he new location(s) for obtaining samples. Ensure all efforts are made Prior to the end of to complete corrective action(s).

the next sampling period Report all deviations from In accordance with the schedule in the the Annual Annual adlological Radiological Environmental perating Environmental Report. Operating Report D 3.5.1 -3 Revision 2 ACTIONS (continued)

CONDITION E. Samples required by Table D 3.5.1-1 not obtained in the media of choice, at the most desired location, or at the most desired time. IPEC ODCM Radiological Environmental Monitoring Program D 3.5.1 REQUIRED ACTION E.1 Choose suitable alternative media and locations for the pathway in q'uestion.

E.2 Make appropriate substitutions in the Radiological Environmental Monitoring Program. AND E.3 Submit in the next Radioactive Effluent Release Report documentation for a 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. D 3.5.1 COMPLETION TIME 30 days 30 days In accordance with the Radioactive Effluent Release Report Revision 2 Radiological Environmental Monitoring*

Program D 3.5.1 SURVEILLANCE REQUIREMENTS DSR 3.5.1.1 IPEC aDCM SURVEILLANCE Collect and analyze radiological environmental monitoring samples pursuant to the requirements of Table D 3.5.1-1 and the detection capabilities required by Table D 3.5.1-3. D 3.5.1 -5 FREQUENCY In accordance with Table D 3.5.1-1 Revision 2 EXPOSURE PATHWAY AND/OR SAMPLE 1. Direct Radiation

2. Airborne Radioiodine and Particulates

3. Waterborne

a. Surface (f) b. Drinking IPEC aDCM Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 1 of 3) Radiological Environmental Monitoring Program NUMBER SAMPLING AND OF COLLECTION SAMPLES SAMPLE FREQUENCY STATIONS LOCATIONS (a) 41 routine (1 ) An inner ring of stations Quarterly 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 5 locations (1 ) 3 samples (A1-A3) from Continuous sampler (A1-A5) locations close to the site' operation with sample boundary in different collection weekly or sectors, of the highest more frequently if calculated annual average required by dust ground level D/Q loading (2) 1 sample (A4) from the vicinity of an established year-round community having the highest calculated annual average ground level D/Q (3) 1 sample (A5) from a control location, approximately 15-30 km distant, and in the least prevalent wind direction (c) 1 sample Upstream (Wa1) Composite sample (used as a Control Station) over a one month period (g) 1 sample* Downstream (Wa2) 1 sample Nearest water supply (Wb1) Grab sample: Monthly D 3.5.1 -6 TYPE AND FREQUENCY OF ANALYSIS Gamma dose quarterly Radioiodine canister:

Analyze weekly for 1-131 Particulate sampler: (1 ) Analyze for gross beta radioactivity

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change (d). (2) Perform gamma isotopic analysis on each sample (e) in which gross beta activity is > 10 times the previous yearly mean of control samples. (3) Gamma isotopic analysis of composite sample (e) (by location) once per 3 months. (1 ) Gamma isotopic analysis of each sample (e) once per month. (2) Composite and analyze for H-3 quarterly.

(1 ) Gross beta and gamma isotopic analyses(e) of each sample monthly. (2) Composite and analyze for H-3*quarterly.

Revision'2 EXPOSURE PATHWAY ANDIOR SAMPLE 3. Waterborne (continued)

c. Soil from Shoreline

d. Ground Water 4. Ingestion

a. Milk (i) b. Fish and Invertebrates IPEC ODCM Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 2 of 3) Radiological Environmental Monitoring Program SAMPLING AND NUMBER OF SAMPLE COLLECTION TYPE AND FREQUENCY OF SAMPLES LOCATIONS (a) FREQUENCY ANALYSIS 2 samples Downstream area (Wc1) Twice per year at least 90 Gamma isotopic (e) with existing or potential days apart and Sr-90 analyses recreational value of each sample, semi-annually.

Upstream area (Wc2) control sample 1 sample Monitoring Well, SWof Semi-Annually Gamma isotopic (e), Site Boundary (Lafarge)

H-3, Ni-63, and Sr-90 analyses of each sample, semi-annually.

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 > 1 mrem 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 (1) 1 sample each In the vicinity of a plant 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) D 3.5.1 -7 Revision 2 6/09 EXPOSURE PATHWAY AND/OR SAMPLE 4. Ingestion (continued)

c. Food Products Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-1 (page 3 of 3) Radiological Environmental Monitoring Program SAMPLING AND NUMBER OF SAMPLE COLLECTION SAMPLES LOCATIONS (a) FREQUENCY Grown nearest to each TYPE AND FREQUENCY OF ANALYSIS (1) Samples of 3 of 2 different offsite different kinds locations of highest of broad leaf predicted annual 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 RADIONUCLIDE ANALYSIS H-3 Mn-54 Fe-59 Co-58 Co-60 Ni-63 *** Zn-65 Sr-90 *** Zr-95 Nb-95 1-131 Cs-134 Cs-137 8a-140 La-140 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 ** WATER AIRBORNE FISH MILK FOOD PARTIUCLATE OR PRODUCTS (pCi/L) GASES (pCi/m3) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) 20,000

1,000 30,000 400 10,000 1,000 30,000 300 10,000 300 1,000 300 20,000 8* 40 400 400 .2* 0.9 3 100 30 10 1,000 60 1,000 50 20 2,000 70 2,000 200 300 200 300 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 RADIONUCLIDE ANALYSIS Gross Beta H-3 Mn-54 Fe-59 Co-58 Co-60 Ni-63 (f) Zn-65 Sr-90 (f) Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 IPEC ODCM 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) AIRBORNE FISH FOOD SOIL or WATER PARTIUCLATE 9,R (pCi/kg, MILK PRODUCTS SEDIMENT (pCi/L) GASES (pCi/m ) wet) (pCi/L) (pCi/kg, wet) (pCilkg, dry) 4 0.01 2,000 (d) 15 130 30 260 15 130 15 130 30 100 30 260 1 5 5000 15 15 1 (d) 0.07 1 60 . 15 0.05 130 15 60 150 18 0.06 150 18 80 180 15 15 15 15 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 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.

Land Use Census D.3.5.2 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 m 2 (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 A. Land use census identifies A.1 locaticm(s) that yields a calculated dose, dose commitment, or D/Q value greater than the values currently being calculated in DSR 3.2.3.1. IPEC ODCM REQUIRED ACTION Identify the new location(s) in the next Radioactive Effluent Release Report. D3.5.2 -1 COMPLETION TIME In accordance with the Radioactive Effluent Release Report Revision 2 ACTIONS (continued)

B. CONDITION Land use census identifies location(s) that yields a calculated dose, or dose commitment (via the same exposure pathway) a factor greater than 2 than at a location from which samples are currently being obtained in accordance with Table D 3.5.1-1. REQUIRED ACTION B.1 Add the new location(s) to . the Radiological Environmental Monitoring Program. B.2 Delete the sampling location(s), excluding the control station location, having the lowest 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 Radioactive Effluent Release Report documentation for a change 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 Land Use Census D 3.5.2 COMPLETION TIME 30 days After October 31 of the year in which the land use census was conducted In accordance with the Radioactive Effluent Release Report Revision 2 SURVEILLANCE REQUIREMENTS DSR 3.5.2.1 DSR3.5.2.2 IPEC ODCM SURVEILLANCE Conduct the land use census during the growing 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.

Report the results of the land use census in the Annual Radiological Environmental Operating Report. D 3.5.2 -3 Land Use Census D 3.5.2 FREQUENCY 366 days In accordance with the Annual Radiological Environmental Operating Report 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 A. Analyses not performed as A.1 required.

SURVEILLANCE REQUIREMENTS REQUIRED ACTION Report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report: SURVEILLANCE DSR 3.5.3.1 IPEC ODCM Report a summary of the results obtained as part of the Interlaboratory Comparison Program in the Annual Radiological Environmental Operating Report.' 03.5.3 -1 COMPLETION TIME In accordance with the Annual Radiological Environmental Operating Report FREQUENCY In accordance with the Annual Radiological Environmental Operating Report 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 A. Radioactive solid waste does not comply with Process Control Program requirements.

IPEC ODCM A.1 REQUIRED ACTION Suspend shipments of solid radioactive waste. D 3.6.1 -1 COMPLETION TIME Immediately Revision 2 Solid Radwaste Treatment System D 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE DSR 3.6.1.1 Verify solidification of specimens in accordance with the Processing Control Program. DSR 3.6.1.2 Record the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the Radioactive Effluent Release Report period: IPEC ODCM 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).

D 3.6.1 -2 FREQUENCY Prior to each shipment Prior to each shipment Revision 2 UNRESTRICTED AREA 04.1 04.0 DESIGN FEATURES o 4.1 UNRESTRICTED AREA 04.1.1 04.1.2 IPEC ODCM 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. For the purpose of satisfying 10 CFR Part 20, the "Restricted Area" is the same as the "Exclusion Area" defined in the FSARs. 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 .'.

EXCLUSION.

J 3;

UNIT 3:

CANAl. z ;:)0:: :J: GA$. PIPElIl'I.E PROPERTY LINE" ., . EASEUENT/

IPEC aDCM EXCLlJSION ,AREA BOUNDARY .' D 4.1 -2

.. "", .. ,., ... " .. , .. ,., .. ,., .*.... ' ",' " '... ; " . . ' '. .

tLECTRItAi..

'345 KV TRANSMISSION LINE Revision 2 6/09 UNRESTRICTED AREA Figure D 4.1-2 MAP DEFINING RELEASE POINTS 0: GASEOUS EFF,LlJEN:r RE,LEA.SE POINT I i o U-2 TURBINE BLDG_ '-;.."," <':,:, DISCHARGE CANAL !U-1TURBINE BLDG. U'1 INTAKE STRUCTURE BLO,WDOWN'FLASH TANKNENT : ' :, ....

IPEC ODCM D 4.1 -3 A ..... 'RWStO U-3 TURBINE BLDG. Revision 2 D 4.1 , N 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 15 th 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. IPEC ODCM 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. 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 07-07 -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 D 5.0 ADMINISTRATIVE CONTROLS D 5.3 Special Reports Special Reports D 5.3 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 D 5.0 ADMINISTRATIVE CONTROLS Major Changes to Radioactive Waste Systems . D 5.4 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",

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: IPEC ODCM

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.

D 5.5-1 Revision 2 6/09 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),

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 6/09 Indian Point Energy Center Offsite Dose Calculation Manual Part I (REeS) BASES 3.0 APPLICABILITY BASES Applicability B 0 3.0 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 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.2 Liquid Effluents Dose BASES Liquid Effluents Dose D 3.1.2 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 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System BASES Liquid Radwaste Treatment System D 3.1.3 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 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks BASES Liquid Holdup Tanks D 3.1.4 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 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate BASES Gaseous Effluents Dose Rate D 3.2.1 This Control provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10 CFR Part 50. This Control is provided to ensure that gaseous effluents from all units on the* site will be appropriately controlled.

It provides operational flexibility for releasing gaseous effluents to satisfy the Section 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 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.2 Gaseous Effluents Dose -Noble Gas BASES Gaseous Effluents Dose -Noble Gas o 3.2.2 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 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 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System BASES Gaseous Radwaste Treatment System D 3.2.4 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 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.5 Ventilation Exhaust Treatment System BASES Ventilation Exhaust Treatment System o 3.2.5 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 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.6 Gas Storage Tanks BASES Gas Storage Tanks D 3.2.6 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 D 3.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 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 D 3.3 INSTRUMENTATION Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 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 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose BASES Radioactive Effluents Total Dose D 3.4.1 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 D 3.S RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.S.2 Land Use Census BASES Land Use Census D 3.S.2 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'm 2 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 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.3 Interlaboratory Comparison Program BASES Interlaboratory Comparison Program D 3.5.3 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 D 3.6 SOLID RADWASTE TREATMENT SYSTEM D 3.6.1 Solid Radwaste Treatment System BASES Solid Radwaste Treatment System D 3.6.1 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) of Limit Basis lodine/Particulate*

Noble Gases 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: IPEC ODCM 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)

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 1 OCFR20 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: IPEC ODCM AS where: = AS C M (C) * (M) = = = Alert or Warn setpoint in /lCi/ml Average monitor reading at time of sample 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. 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 R-42 Containment Gas Monitor 72' Fan Bldg 1E-7 to 1 E-2 Containment Ventilation Isolation J..lCi/cc R-44 Plant Vent Radiogas Monitor 88' Fan Bldg 1E-7 to 1 E-2 Shuts RCV-014 (isolating gas tanks), stops VC J..lCi/cc release fans and shuts VC vent/purge valves. R-45 Condenser Air Ejector Monitor In-line detector on the air ejector 1 E-6 to 1 E-1 Alarm diverts air ejector exhaust to VC and exhaust header J..lCi/cc secures steam to priming air ejector re-heaters.

R-50 Waste Gas Disposal System 98' PAB 0.1 to 1E5 Ci None. RECS 03.2.6 is assured by setpoint Monitor basis per ODCM Part II, Sec 3.1.12. R-27 Plant Vent Wide-Range Drawn from inside Plant Vent, 1 E-7 t01 E+5 None. PV Concentration and release rate Monitor to 85' BAB J..lCi/cc information only, for accident applications.

R-60 Unit 1 Stack Vent Unit 1 Nuclear Services Bldg 1 E-7 to 1E-2 None Radiogas Monitor 100' Elevation J..lCi/cc Fan Cooler Unit Service Adjacent to service water return 1 E-7 to 1E-2 R-46 / 53 Water Return line from V.C. fan cooler units and J..lCi/cc None motor coolers R-47 Component Cooling System Adjacent to line monitors on each 1 E-6 to 1E-2 None. Setpoints are not based on effluent.

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 J..lCi/cc None Monitors R-54 Waste Disposal Liquid Effluent In-line monitor on 70' CSB 1E-7 to 1E-2 Terminates Distillate Tank releases on alarm Monitor J..lCi/cc R-49 SG Blowdown Monitor 15' Transformer Yard Housing 1E-6 to 1E+2 Closes blowdown isolation valves J..lCi/cc R-51 Sec Boiler Blowdown 43' Superheater Bldg 1 E-7 to 1E-2 None Purification J..lCilcc R-52 Sec Boiler Blowdown 33' Superheater Bldg 1 E-7 to 1E-2 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 R-12 Containment Gas Monitor Samples drawn from 32 and 35 1 E-7 to 1 E-1 /-lCi/cc Containment Ventilation Isolation Containment Fan Coolers Plant Vent Radiogas Monitor In Plant Vent at approximately Secures waste gas tank release and R-14 105' elevation 1 E-6 to 1 E-1 /-lCi/cc Containment Ventilation Isolation In-line detector on the air ejector On alarm, diverts air ejector exhaust to R-15 Condenser Air Ejector Monitor 1 E-6 to 1 E+O /-lCi/cc VC and secures steam to priming air 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 1 E-2 to 1 E+3 /-lCi/cc 50,000 Ci per tank, per RECS D3.2.6. Plant Vent Wide-Range Drawn from inside Plant Vent Secure waste gas tank release and R-27 Monitor 1 E-7 to 1 E+5 /-lCi/cc Containment Ventilation Isolation Administration Building Vent 4th Floor Administration Building 1E+1 to 1E+6 cpm R-46 Monitor Exhaust Plenum for (typically 5.0E-8 to None Radiogas Monitor Controlled Areas 5.0E-2 IlCi/cc) R-59 RAMS Building Vent Radiogas 55' RAMS Building Monitor 1 E-6 to 1 E+2 /-lCi/cc None Monitor Exhaust Plenum Fan Cooler and Motor Cooler Adjacent to service water return Service Water Return line from V.C. fan cooler units and 1 E-7 to 1 E-1 /-lCi/cc None R-16 AlB motor coolers Component Cooling System Adjacent to line monitors on each 1 E-6 to 1 E-1 /-lCi/ml None. These setpoints are not based on R-17 AlB pump outlet pump outlet effluent and are for information only. Component Cooling Heat Adjacent to line, mounted on SW R-23 Exchanger Service Water return from Component Cooling 1 E-7 to 1 E-1 /-lCi/cc None Monitor Heat Exchanger Waste Disposal Liquid Effluent In-line monitor on monitor tank 1 E-7 to 1 E-1 /-lCi/cc Terminates monitor tank release on alarm R-18 Monitor recirc pump discharge PAB blowdown room monitors Closes blowdown isolation valves and SG R-19 SG Blowdown Monitor steam generator blown 1 E-6 to 1 E+2 /-lCi/cc sample valves Recirc line of HTDS/L TDS tanks Terminates HTDS or LTDS tank release. CPF Regen Waste Release in CPF (used when primary to 1 E-7 to 1 E-1 /-lCi/cc Applicable only in a primary to secondary 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 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: IPEC ODCM RWST: PWST: 10 curies x 10 6 j.1Ci / curie = 7.3 x 10-3 j.1Ci / ml 358,500gal x 3785ml / gal 10 curies x 10 6 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 10 6 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 10 6 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. 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 Drain = Specific

Makeup -Effluent Activity Activity Rate SG BlowdownJ Rate to the 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:

IPECODCM 11750 gals

2 Tank Volumes 39 u 4 u -----=---------. nours nours 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.

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 IPEC aDCM 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 Totalactivity

where: ADC= MPCWt:

CG CG+CB or ADC = Allowed diluted concentration in uCi/ml Page 10 of 136 Revision 2 IPEC ODCM 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 ADC where; 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 Page 11 of 136 Revision 2 aDCM Part II -Calculational Methodologies

g. The permissible discharge rate is calculated as follows: ADC*B D CG Where: 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: IPEC aDCM [Dose ] Current Month Dose + Previous months' Dose [ mlajo. r d 1 = +/- 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.

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: IPEC ODCM m n D(T) = I [Air

I (dtk)(Cik)(F k)] i=! k=l 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. dt k = 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.

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 IPEC ODCM 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. Page 14 of 136 Revision 2 IPEC aDCM 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 3.8 Teen 1.7 Child 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.

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. IPEC ODCM 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.

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 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.

IPEC ODCM 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.

Page 26 of 136 Revision 2 aDCM Part II -Calculational Methodologies 3.1.12 Gas Storage Tank Activity Limits Unit 2: 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:

(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 7 6 mrem -m 3 / j.1Ci -yr )(1. 81E -3 sec/ m ) IPEC aDCM 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. 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 Where: < 14.7 (0) (14.7 + P)V or [A1eq < 14.7 (0133) (14.7 + P)V [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: IPEC aDCM . (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-m 3 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 C'I -----;---------;:--'------

=. + /l 1 cc 525fe * (164.7 P sia]

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. 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 O 2 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 2 form. 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 IPEC ODCM . 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. 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: IPEC ODCM 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. 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: [major J [Dose 1 Current Month Dose + Previous months' Dose I d = +/- 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 IPEC ODCM 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).

Page 31 of 136 Revision 2 IPEC aDCM 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. Q i = 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 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: Q t = The release rate of all noble gases summed together in )lei/sec, Le., the sum of all Q L 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. IPEC aDCM Page 33 of 136 Revision 2 aDCM Part II -Calculational Methodologies Q i = 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, 10 6 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 IPEC aDCM 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 Gamma Air Beta Air Smrad 10 mrad Page 34 of 136 Any Calendar Year 10 mrad 20 mrad 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. q i 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 IPEC aDCM 3.3.4.1 The equations in this section are used to meet the calculational requirements of RECS D3.2.3. 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

}t;.: .. , '.

Receptor" ....*... ., "," f; i. .: . :'.: . 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 IPEC aDCM 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 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 Releases shall be cumulative over the calendar quarter or year, as appropriate.

W = 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. 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 m 2 *mrem/yr per or mrem/yr per These dose factors are determined as described in Sections 3.3.4.5a-d.

Page 36 of 136 Revision 2 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)

[Wn(in)Oi

+ wn(in)qi]+ (Ri(G)+ Ri(V))*[Wn(dep)Oi

+wn(dep)qi]]

i DS=(3.17E-8) [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 IPEC aDCM 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, 10 6 pCi/uCi (BR) a = Breathing rate of the receptor of age group (a) in m 3/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 i th 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)) RI( G)(D / Q) = Ki Where: K' = A constant of conversion, 10 6 pCi/I-lCi.

K" = A constant of conversion, 8760 hr/yr. m 2 *mrem/ yr uCi/sec ki = Decay constant for the i th radionuclide sec*1* t = The exposure time, 4.73 x 10 8 sec (15 years). DFGi = The ground plane dose conversion factor for i th 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. Page 38 of 136 Revision 2 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, 10 6 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 = fg = kw= tL = th = The fraction of the annual intake of leafy vegetation grown locally. The fraction of the annual intake of non-leafy vegetation grown locally. 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).

The average time between harvest of leafy vegetation and its consumption, in seconds. 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 IPEC aDCM 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, 10 6 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, 10 3 m/kg; 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 IPEC ODCM 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. 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 1 E-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 IPEC aDCM 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 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. 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 =

(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 Ct = = Concentration of isotope i (IlCi/cc) in analysis, t (for either PV or MT pathway) 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 IPEC ODCM 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. 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.

IPEC ODCM 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.

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: NOTE: 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. 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.

IPEC ODCM Page 47 of 136 Revision 2 IPEC ODCM 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.

Where: This factor is defined as: F = [NTOTALl8760]m 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. m 8760 ANMX F15MX = 10g(ANMX / F15MX) 10g(8760)

= The total number of hours in a year. = The calculated historical average dispersion (sec/m3) or deposition (m-2) factor for the compass sector and distance of interest.

= 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 term dispersion and deposition parameters (F15MX) is the Gaussian 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 1 O-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, 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. 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: IPEC aDCM a) Site Boundary Noble Gas: F15MX ANMX = = Unit 2 7.724E-5 sec/m 3 2.219E-6 sec/m 3 m= log(ANMX / F15MX) = -0.391 log(8760)

F= [NTOT AU8760]..o*391 b) Nearest Residence Inhalation:

F15MX ANMX = = m= log(ANMX / F15MX) log(8760)

F= Unit 2 4.992E-5 sec/m 3 1.030E-6 sec/m 3 -0.428 [NTOTAU8760rO.

428 c) Nearest Residence Deposition:

Page 49 of 136 Unit 3 1.590E-4 sec/m 3 4.470E-6 sec/m 3 -0.393 [NTOTAU8760rO.

393 Unit 3 4.888E-5 sec/m 3 .1.016E-6 sec/m 3 -0.427 [NTOT AU8760rO.427 Revision 2 IPEC aDCM F15MX ANMX = = aDCM Part II -Calculational Methodologies 3.995E-7 m*2 4.019E-7 m o2 7.517E-9 m o2 7.451 E-9 m o2 m= log(ANM¥ / F15M¥) = _ 0.438 log(8760)

-0.439 F= [NTOTALl8760rO.

438 [NTOT ALl8760rO.

439 Page 50 of 136 Revision 2 IPEC aDCM d) 5-mile Inhalation:

F15MX ANMX = = m= log(ANMX / F15MX) log(8760)

F = e) 5-mile Deposition:

F15MX ANMX = = m= log(ANMX / F15MX) log(8760)

= F = aDCM Part II -Calculational Methodologies Same for both Units 2 and 3 6.192E-6 sec/m 3 7.223E-7 sec/m 3 -0.237 [NTOTALl8760rO.

237 Same for both Units 2 and 3 9.501 E-9 m-2 1.350E-9 m-2 -0.215 [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 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 2.86E-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 1.15E-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) Isotope H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 IPEC ODCM Halflife unit Fm 12.350 53.300 15.000 14.290 27.704 312.500 2.578 2.700 44.529 70.800 5.27l 96.000 2.520 12.701 243.900 0.950 2.390 0.530 0.050 18.660 0.297 0.253 50.500 29.120 9.500 2.710 2.667 0.829 58.510 3.54.0 10.100 63.980 16.900 35.150 2.750 6.020 0.237 39.280 4.440 368.200 249.900 2.700 60.200 2.770 Y D H D D D H Y D D Y Y H H D H H H H D H H D Y H H D H D H H D H D D H H D H D D D D Y 1. 00E-02 1.00E-04 4.00E-02 2.50E-02 2.20E-03 2.50E-04 2.50E-04 1. 20E-03 1. 20E-03 1.00E-03 1. 00E-03 6.70E-03 6.70E-03 1. 40E-02 3.90E-02 3.90E-02 5.00E-02 5.00E-02 5.00E-02 3.00E-02 3.00E-02 3.00E-02 8.00E-04 8.00E-04 8.00E-04 8.00E-04 1.00E-05 1.00E-05 1.00E-05 1. 00E-05 1. 00E-05 5.00E-06 5.00E-06 2.50E-03 7.50E-03 2.50E-02 2.50E-02 1.00E-06 1. 00E-06 1.00E-06 5.00E-02 1.50E-03 1. 50E-03 1. 50E-03 Page 61 of 136 Ground Plane Dose Factors TotBody(DFg)

O.OOE+OO O.OOE+OO 2.50E-08 O.OOE+OO 2.20E-10 5.80E-09 1.10E-08 O.OOE+OO 8.00E-09 7.00E-09 1.70E-08 O.OOE+OO 3.70E-09 1. 50E-09 4.00E-09 O.OOE+OO 6.40E-11 1.20E-08 O.OOE+OO 6.30E-10 3.50E-09 1. 50E-08 5.60E-13 O.OOE+OO 7.10E-09 9.00E-09 2.20E-12 3.80E-09 2.40E-11 1.60E-09 5.70E-10 5.00E-09 5.50E-09 5.10E-09 1.90E-09 9.60E-10 2.70E-09 3.60E-09 4.50E-09 1.50E-09 1.80E-08 O.OOE+OO 1.30E-08 3.10E-09 Skin (DFs) O.OOE+OO O.OOE+OO 2.90E-08 O.OOE+OO 2.60E-10 6.80E-09 1.30E-08 O.OOE+OO 9.40E-09 8.20E-09 2.00E-08 O.OOE+OO 4.30E-09 1.70E-09 4.60E-09 O.OOE+OO 9.30E-11 1.40E-08 O.OOE+OO 7.20E-10 4.00E-09 1.80E-08 6.50E-13 O.OOE+OO 8.30E-09 1. 00E-08 2.60E-12 4.40E-09 2.70E-11 1.90E-09 7.80E-10 5.80E-09 6.40E-09 6.00E-09 2.20E-09 1.10E-09 3.00E-09 4.20E-09 5.10E-09 1.80E-09 2.10E-08 O.OOE+OO 1. 50E-08 3.50E-09 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) Isotope Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 K-40 Co-57 Sr-85 Y-88 Nb-94 Nb-97 Cd-109 Sn-113 Ba-133 Te-134 Ce-139 Hg-203 IPECODCM Halflife unit 58.000 D 109.000 D 9.350 H 33.600 D 1.160 H 30.000 H 0.417 H 3.258 D 12.360 H 8.040 D 2.300 H 20.800 H 0.877 H 6.610 H 2.062 Y 13.100 D 30.000 Y 0.537 H 1. 378 H 12.740 D 0.304 H 0.177 H 1.678 D 1. 542 H 32.501 D 33.000 H 284.300 D 13.560 D 0.288 H 10.980 D 23.900 H 2.360 D 1.28E+09 Y 270.900 D 64.840 D 106.640 D 2.03E+04 Y 1.202 H 1.271 Y 115.100 D 10.740 Y 0.697 H 137.660 D 46.600 D Fm 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1. 00E-03 1. 00E-03 6.00E-03 6.00E-03 6.00E-03 6.00E-03 6.00E-03 6.00E-03 1.20E-02 1. 20E-02 1.20E-02 1. 20E-02 4.00E-04 4.00E-04 4.00E-04 4.00E-04 5.00E-06 5.00E-06 1. 00E-04 1.00E-04 1.00E-04 5.00E-06 5.00E-06 5.00E-06 5.00E-04 5.00E-06 1.00E-02 1.00E-03 8.00E-04 1.00E-05 2.50E-03 2.50E-03 1. 20E-04 2.50E-03 4.00E-04 1.00E-03 1.00E-04 3.80E-02 Page 62 of 136 Ground Plane Dose Factors TotBody(DFg) 3.50E-11 1.10E-12 1.00E-11 7.70E-10 7.10E-10 8.40E-09 2.20E-09 1.70E-09 1.40E-08 2.80E-09 1.70E-08 3.70E-09 1.60E-08 1. 20E-08 1. 20E-08 1.50E-08 4.20E-09 2.10E-08 2.40E-09 2.10E-09 4.30E-09 7.90E-09 1. 50E-08 1. 50E-08 5.50E-10 2.20E-09 3.20E-10 O.OOE+OO 2.00E-10 1.00E-09 3.10E-09 9.50E-10 O.OOE+OO 9.10E-10 O.OOE+OO O.OOE+OO O.OOE+OO 4.60E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.00E-09 O.OOE+OO O.OOE+OO Skin(DFs) 4.80E-11 1.30E-12 1.10E-11*

9.00E-10 8.40E-10 9.90E-09 2.60E-06 2.00E-09 1.70E-08 3.40E-09 2.00E-08 4.50E-09 1.90E-08 1.40E-08 1.40E-08 1.70E-08 4.90E-09 2.40E-08 2.7QE-09 2.40E-09 4.90E-09 9.00E-09 1.70E-08 1.80E-08 6.20E-10 2.50E-09 3.70E-10 O.OOE+OO 2.30E-10 1. 20E-09 3.60E-09 1.10E-09 O.OOE+OO 1.00E-09 O.OOE+OO O.OOE+OO O.OOE+OO 5.40E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1. 20E-09 O.OOE+OO O.OOE+OO 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 Kr-83m 7.56E-08 1E+6 8.86E-01 5.78E-01 Kr-85m 1.17E-03 1E+6 7.49E-01 4.46E-01 Kr-85 1.61 E-05 1E+6 6.73E-01 3.85E-01 Kr-87 5.92E-03 1E+6 5.68E-01 3.09E-01 Kr-88 1.47E-02 1E+6 5.40E-01 2.88E-01 Kr-89 1.66E-02 1E+6 5.60E-01 3.03E-01 Kr-90 1.56E-02 1E+6 5.97E-01 3.29E-01 Xe-131m 9.15E-05 1E+6 8.67E-01 5.62E-01 Xe-133m 2.51E-04 1E+6 8.17E-01 5.12E-01 Xe-133 2.94E-04 1E+6 8.86E-01 5.78E-01 Xe-135m 3.12E-03 1E+6 6.75E-01 3.87E-01 Xe-135 1.81E-03 1E+6 7.60E-01 4.55E-01 Xe-137 1.42E-03 1E+6 6.46E-01 3:65E-01 Xe-138 8.83E-03 1E+6 5.75E-01 3.14E-01 Ar-41 8.84E-03 1E+6 5.89E-01 3.21 E-01 * ** *** 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 = U2 Ki *** U3 Ki *** 6.70E-02 4.37E-02 8.76E+02 5.22E+02 1.08E+01 6.19E+OO 3.36E+03 1.83E+03 7.93E+03 4.23E+03 9.30E+03 5.03E+03 9.31E+03 5.13E+03 7.94E+01 5.14E+01 2.05E+02 1.29E+02 2.60E+02 1.70E+02 2.11E+03 1.21E+03 1.38E+03 8.24E+02 9.18E+02 5.18E+02 5.07E+03 2.77E+03 5.21E+03 2.84E+03 Revision 2

** IPEC aDCM aDCM Part II -Calculational Methodologies Table 3-5 Skin Dose Factors Li From Noble Gases (beta) Nucline Beta Skin* (pCi/uCi)

= U** Dose Factor x 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) 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 Kr-83m 1.93E-05 1E+6 8.86E-01 5.78E-01 Kr-85m 1.23E:.03 1E+6 7.49E-01 4.46E-01 Kr-85 1.72E-05 1E+6 6.73E-01 3.85E-01 Kr-87 6.17E-03 1E+6 5.68E-01 3.09E-01 Kr-88 1.52E-02 1E+6 5.40E-01 2.88E-01 Kr-89 1.73E-02 1E+6 5.60E-01 3.03E-01 Kr-90 1.63E-02 1E+6 5.97E-01 3.29E-01 Xe-131m 1.56E-04 1E+6 8.67E-01 5.62E-01 Xe-133m 3.27E-04 1E+6 8.17E-01 5.12E-01 Xe-133 3.53E-04 1E+6 8.86E-01 5.78E-01 Xe-135m 3.36E-03 1E+6 6.75E-01 3.87E-01 Xe-135 1.92E-03 1E+6 7.60E-01 4.55E-01 Xe-137 1.51E-03 1E+6 6.46E-01 3.65E-01 Xe-138 9.21E-03 1E+6 5.75E-01 3.14E-01 Ar-41 9.30E-03 1E+6 5.89E-01 3.21 E-01 * ** *** From Reg Guide 1.109, Table B-1 (mrad/yr per pCi/m3) The finite cloud correction factor is described in Section 3.6 Mi (mrad/yr per uCi/m 3) IPEC ODCM Page 73 of 136 U2 Mi *** U3 Mi *** 1.71E+01 1.12E+01 9.21 E+02 5.49E+02 1.16E+01 6.62E+OO 3.50E+03 1.91E+03 8.20E+03 4.37E+03 9.69E+03 5.24E+03 9.73E+03 5.36E+03 1.35E+02 8.77E+01 2.67E+02 1.68E+02 3.13E+02 2.04E+02 2.27E+03 1.30E+03 1.46E+03 8.74E+02 9.76E+02 5.51E+02 5.29E+03 2.89E+03 5.48E+03 2.99E+03 Revision 2

** IPEC ODCM 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) 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/m 3 K = 237 K = 153 L = 1310 -L = 1310 mremlyr per uCi/m 3 L =540 L = 540 -1601 = 905 rnrad/yr per uCi/m 3 = 281 AT = 181 M= M M N = 1977 /i= 1977 rnrad/yr per uCi/m 3 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 Sector Distance Distance Distance to Site to Site to nearest by Boundary Boundary residence, 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-04-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 Isotope H-3 Be-7 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-:90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-llOm Sb-122 Sb-124 Sb-125 IPEC aDCM aDCM Part II -Calculational Methodologies Table 3-10c CHILD INHALATION Ri(I) 3 (mrem/yr per uCi/m ) BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI O.OOE+OO 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 2.60E+06 1.14E+05 9.88E+04 O.OOE+OO O.OOE+OO O.OOE+OO 4.22E+04 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 O.OOE+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1.58E+06 2.29E+04 O.OOE+OO 1.66E+00 3.12E-01 O.OOE+OO 1.67E+00 1.31E+04 1.23E+05 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO 1:11E+05 2.87E+03 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 O.OOE+OO 1.31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 2.99E+00 2.96E-01 1.64E-01 O.OOE+OO O.OOE+OO 8.18E+03 8.40E+04 O.OOE+OO 1.99E+00 1.07E+00 O.OOE+OO 6.03E+00 9.58E+03 3.67E+04 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 6.70E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 1.42E+03 1.02E+04 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.48E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 O.OOE+OO 5.62E+02 3.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E+01 O.OOE+OO 3.45E+02 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.89E+00 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05 1.01E+08 O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 1.21E+02 O.OOE+OO 4.59E+00 O.OOE+OO O.OOE+OO 5.33E+04 1.74E+05 1.31E+01 O.OOE+OO 5.25E-01 O.OOE+OO O.OOE+OO 2.40E+04 2.42E+05 4.11E+03 O.OOE+OO 1.11E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 5.07E-01 O.OOE+OO 1.84E-02 O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 2.04E+01 O.OOE+OO 5.81E-01 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 1.86E+02 O.OOE+OO 5.11E+00 O.OOE+OO O.OOE+OO 7.44E+04 3.89E+05 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11E+04 1.88E+02 2.72E+01 1.60E+01 O.OOE+OO 3.88E+01 1.13E+05 3.51E+05 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 O.OOE+OO 1.72E+02 4.25E+01 O.OOE+OO 3.92E+02 1.35E+05 1.27E+05 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51E+02 4.81E+03 8.10E-05 8.51E-05 1.08E-03 O.OOE+OO 1.45E-03 5.85E+02 1.63E+01 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 1.53E+00 O.OOE+OO 5.55E-01 O.OOE+OO 1.34E+00 1.59E+04 9.95E+04 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.00E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+05 9.84E+04 7.59E+02 2.07E+04 9.10E+01 O.OOE+OO 2.32E+06 4.03E+04 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 (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 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 IRWSF SGM ISFSI = = = = The Vapor Containment structures The Interim Radioactive Waste Storage Facility The Steam Generator Mausoleums (both units) 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 1 OCFR20 ... " 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):

where: LLD = E= V= k= y= 'A= t= Note: IPEC aDCM 2.71 + 3.29 Sb * +(Tb ) LLD Ts Ts E

V

k

Y

e*),J 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 The counting efficiency (as counts per transformation)

The sample size (in units of mass or volume) A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per The fractional radiochemical yield (when applicable)

The radioactive decay constant for the particular radionuclide The elapsed time between midpoint of sample collection and time of counting 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. 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 tiT s)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. IPEC ODCM Page 105 of 136 Revision 2 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 I P3-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".

IPEC aDCM Page 106 of 136 Revision 2 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. 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 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 Dose Rate Cumulative Dose Dose Projection aDCM Part II -Calculational Methodologies APPENDIX A

SUMMARY

of RADIOLOGICAL EFFLUENT CONTROLS (RECS) LIQUID: AIRBORNE:

The diluted concentration of 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. Dose commitment to any member Air Dose at the SITE BOUNDARY is limited to: 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. 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: 0.06 mrem total body, or 0.2 mrad gamma air dose, 0.4 mrad beta air dose, or 0.2 mrem critical organ, 0.3 mrem to any organ at the nearest residence, clean-up 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 Sec Boiler Blowdown Pllrifir.::ltinn HX North Curtain Drain Sphere Foundation Drain Sumo 13 WDST SG water 80-10, Roof & Floor Drains, SeD, etc U1 Foundation Drain Discharge Canal }---. R-49 Service Water R-52 -51 R-62 wI totalizer R-54 SW 14 WDST R-47

'-------, 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. These and other systems are monitored per the IPEC 80-10 compliance program. Any identified effluent is evaluated for inclusion in integrated totals. I 6/09 IPEC aDCM Page 109 of 136 Revision 2 6/09 aDCM Part II -Calculational Methodologies APPENDIX B (Page 2 or 2) UNIT 3 LIqUID EFFLUENT SIMPLIFIED FLOW DIAGRAM Steam Generator' slowdown (4), Waste, HOldup Tanks Fan Cooler 't.:Jnff' , 1..... ____ ..... Service Waste Processing Ip ,#'1 Waste Flash Tank Venl see Fiqure 3-1 Processing

-[ "" "J )-----' Polisher Turbine,Hall Drains ____ .Monitor TankVent I '

3-1 Monitor Tanks b: " S ¢ H A R G E ____ VVarer FCU Motor Component Cooling Water ,I R Component Cooling HeatEXchan\Jer Service, Water IPEC aDCM L--.:,component

'Cooling Water Storm Drains; Grbund Water, and 80-10 Page 110 of 136 R ii, To Hudson River' Revision 2 aDCM Part II -Calculational Methodologies APPENDIXC (Page 1 of 2) UNITS 1 and 2 GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM Containment Pressure Relief Containment Purge Fuel Storage Building MOB Exhaust R-49 containment Unit 2 SG Slowdown Flash Tank .. -I *1 Unit 2 Vent --......

- atmosphere

22 Aux Feed Pump Vent, SG Atmospherics, or Safeties 1--. atmosphere Steam Generators R-45 R-5976 atmosphere BID Flash Tank h atmosp ere Vent (Unit 2) Unit 1 SG Slowdown Flash Tank 1----+ BID Flash Tank atmosphere Vent (Unit l,forSBBPS)

CSB Exhaust NS B Exhaust Unit I Annulus House Service Boilers IPEC aDCM Unit I Stack atmosphere Page 111 of 136 Revision 2 I 6/09 aDCM Part II -Calculational Methodologies APPENDIXC (Page 2 of 2) UNIT 3 GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM (on high alarm) Waste Gas Tanks Fuel Storage Building Trubine Administration Building Cont. Release Point Liquid Waste Batch Release Monitor Tanks Vents Cont. Release Point Recirc See '-----__<11--'---+

River Figure 2-1 r--I I I I I ,--------------------------------

___ L __ I I I RCV-014 Radioactive Machine Shop Fill Cont. Release Points Cont. Release Point PV Cont. Release Point #32 Aux Feed Pump Excess Steam Vent Main Steam IPEC aDCM #32 Aux Feed Pump STEAM GEN Atmospherics and Safeties to BDR Page 112 of 136 Generator Blow-down FlashTank SIG BID to River 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 Total activity or ADC= MPCWt

CG CGtCB or 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: Where; ICi MPCWt = _-:--,-i __ -:-I (CYMPCWi)

I 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: where; E = Dr*CG ADC Dr = Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm The permissible discharge rate is then calculated as follows: D ADC*B. 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 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 SAMPLE DESIGNATION

/ STATION DR1/57 DR2/59 DR3/90 DR4/28 DR5/35 DR6/88 DR7/14 DR8/03 DR9/34 DR10/05 DR11/53 DR12/74 DR13/76 DR14/78 DR15/80 DR16/82 DR17/58 . DR18/60 DR19/62 DR20/64 DR21/66 DR22/67 DR23/69 DR24/92 DR25/71 DR26/72 DR27/73 DR28/81 DR29/77 DR30/79 DR31/75 DR32/83 DR33/33 DR34/38 DR35/89 DR36/61 DR37/56 DR38/20 DR39/29 DR40/23 DR41/27

Control Station IPEC ODCM ODCM Part II -Calculational Methodologies APPENDIXG (Page 1 of 7) ENVIRONMENTAL SAMPLING POINTS LOCATION Roa Hook Old Pemart Avenue Charles Point Lents Cove Broadway and Bleakley Avenue Reuter-Stokes Pole #6 Water Meter House Service Center Building South East Corner of Site NYU Tower White Beach West Shore Drive -South West Shore Drive -North Rt. 9W, across from RlS #14 Rt. 9W -South of Ayers Road Ayers Road Ht. 9D -Garrison Gallows Hill Road and Sprout Brook Road West Brook Drive (near the Community Center) Lincoln Road -Cortlandt (School Parking Lot) Croton Ave. -Cortlandt Colabaugh Pond Rd. -Cortlandt Mt. Airy & Windsor Road Warren Rd. -Cortlandt Warren Ave. -Haverstraw Railroad Ave. & 9W Haverstraw Willow Grove Rd. & Captain Faldermeyer Drive Palisades Parkway, Lake Welch Exit Palisades Parkway Anthony Wayne Park Palisades Parkway Rt. 9W Fort Montgomery Hamilton Street (Substation)

Furnace Dock (Substation)

Highland Ave. & Sprout Brook Rd. (near Rock Cut) Lower South Street and Franklin Street Verplanck

-Broadway & 6 th St. Cortlandt Yacht Club (aka Montrose Marina) Grassy Point *Roseton Croton Point Page 116 of 136 DISTANCE 2.0 mi -N 1.8 mi -NNE 0.88 mi -NE 0.45 mi -ENE 0.37 mi -E 0.32 mi -ESE 0.3 mi-SE 0.35 mi -SSE 0.52 mi-S 0.88 mi-SSW 0.92 mi-SW 1.59 mi-WSW 1.21 mi-W 1.2 mi-WNW 1.02 mi-NW 1.01 mi -NNW 5.41 mi -N 5.02 mi -NNE 5.03 mi -NE 4.6 mi -ENE 4.87 mi -E 4.5 mi-ESE 4.97 mi -SE 3.84 mi -SSE 4.83 mi-S 4.53 mi-SSW 4.97 mi-SW 4.96 mi-WSW 4.15 mi-W 4.57mi:....WNW 4.65mi-NW 4.82 mi-NNW 2.88 mi -NE 3.43 mi -SE 2.89 mi :--NNE 1.3 mi -NE 1.25 mi-SSW 1.5 mi -S 3.37 mi-SSW 20.7mi-N 6.36 mi -SSE Revision 2 SAMPLE DESIGNATION/

STATION A1/4 A2/94 A3/95 A4/5 A5/23 Wa1/9 Wa2/10 Wb1/7 Wc1/53 Wc2/50 ODCM Part II -Calculational Methodologies.

APPENDIXG (Page 2 of 7) ENVIRONMENTAL SAMPLING POINTS LOCATION Airborne Algonquin Gas Line IPEC Training Center Meteorological Tower NYU Tower *Roseton DISTANCE 0.28 mi -SW 0.39 mi-S 0.46 mi -SSW 0.88 mi-SSW 20.7 mi -N Waterborne -Surface (Hudson River Water) *Plant Inlet (Hudson River Intake)0.16 mi -W Discharge Canal (Mixing Zone)0.3 mi -WSW Waterborne

-Drinking Camp Field Reservoir Soil From Shoreline White Beach *Manitou Inlet 3.4 mi -NE 0.92 mi-SW 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 Bluegill Sunfish White Perch Pumpkin Seed White Catfish Blueback Herring American Eel Crabs Exposure Pathway/Sample:

Ingestion-Food Products (Broad Leaf Vegetation)

Ic1/95 Ic2/94 Ic3/23 *Control Station IPEC ODeM Meteorological Tower IPEC Training Center *Roseton Page 117 of 136 0.46 mi -SSW 0.39 mi -S 20.7 mi -N Revision 2 SAMPLE DESIGNATION/

STATION DR8/3 A1/4 A4, DR10/5 Wb1/7 **/8 Wa1/9 Wa2/10 DR7/14 **/17 DR38/20 Ib2,A5,DR40,lc3/23

Ib1/25 DR41/27 DR4/28 DR39/29 DR33/33 DR9/34 DR5/35 DR34/38 **/44 Wc2/50 Wc1, DR11/53 DR37/56 DR1/57 DR17/58 DR2/59 DR18/60 DR36/61 DR19/62 DR20/64 DR21/66 DR22/67 DR23/69

Control Station IPEC ODCM ODCM Part II -Calculational Methodologies APPENDIXG (Page 3 of 7) ENVIRONMENTAL SAMPLING POINTS LOCATION Service Center Building Algonquin Gas Line NYU Tower Camp Field Reservoir Croton Reservoir

Plant Inlet (Hudson River Intake) Discharge Canal (Mixing Zone) Water Meter House Off Verplanck Cortlandt Yacht Club (AKA Montrose Marina) *Roseton where available, downstream Croton Point Lents Cove Grassy Point Hamilton Street (Substation)

South East Corner of Site Broadway & Bleakley Avenue Furnace Dock (Substation)

Peekskill Gas Holder Building *Manitou Inlet White Beach Verplanck

-Broadway & 6 th Street Roa Hook Rt. 9D Garrison Old Pemart Ave. Gallows Hill Road and Sprout Brook Road Lower South Street and Franklin*

Street West Brook Drive (near the Community Center) Lincoln Road -Cortlandt (School Parking Lot) Croton Ave. -Cortlandt Colabaugh Pond Rd. -Cortlandt Mt. Airy & Windsor Road DISTANCE 0.35 mi -SSE 0.28 mi -SW 0.88 mi-SSW 3.4 mi -NE 6.3 mi -SE 0.16 mi -W 0.3 mi -WSW 0.3 mi -SE 1.5 mi -SSW 1.5 mi-S 20.7mi-N N/A 6.36 mi -SSE 0.45 mi -ENE 3.37 mi-SSW 2.88 mi -NE 0.52 mi-S 0.37 mi -E 3.43 mi -SE 1.84 mi -NE 4.48 mi-NNW 0.92 mi-SW 1.25 mi -SSW 2.0 mi-N 5.41 mi-N 1.8 mi -NNE 5.02 mi -NNE 1.3 mi -NE 5.03 mi -NE 4.6 mi -ENE 4.87 mi-E 4.5 mi-ESE 4.97 mi -SE SAMPLE TYPES 3 1,2 1,2,3 6 6 7 7,8 3 8,9,10 3 1,2,3,4,5,11,12 12 1,2,3 3,8,9,10 1,2,3 3 3 3 3 1,2,11 10 3,10 3 3 3 3 3 3 3 3 3 3 3 ** Items are in excess of RECS requirements 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

Control Station ** Items are in excess of RECS requirements Sample types are: 1. 2. 3. 4. 5. 6. 7. Air particulates Radioiodine' Direct gamma Broadleaf vegetation Soil Drinking water Hudson River (H.R.) water IPEC ODCM 8. 9. 10. 11. 12. 13. H.R. bottom sediment H.R. aquatic vegetation H.R. shoreline soil Fallout Fish and invertebrates Groundwater well Page 119 of 136 . Revision 2 6/09 ODCM Part 11-Calculational Methodologies APPENDIXG (Page 5 of 7) ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS Within Two Miles of Indian Point , ...........*..........

".' lonai Island _. R., ocklari9QOur;jty , .. ... . .. ,

N -VVatetpprne:

"$u rface(t-l R)Wa#: o L()cafion PR# DI-AirtlC:>Tne., P9diculate;anCf Radioioqin¢.'A#

IPEC ODCM Page 120 of 136 1 mile: Icff-*Btoatlleaf

<:>-HRShprelihe:sbii yve¥!; Ib1.,. Fish* andl hvertebrates' (Vilh¢re . ava) 19 bl,edownstFearn)'

Revision 2 ODCM Part II -Calculational Methodologies APPENDIXG (Page 6 of 7) ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS Greater Than Two Miles from Indian Point N}: III@ ic3 Upstream:

Ib2 County Bear Mountain Bridge .@. Rdtklc3nd County N' Key: 0 .,[jirectRadiationSampleLocationDR#

o .-Airborne Sampling

<>"> Huds'on River ShorelineSoiLWC#

IPEC ODCM Page 121 of 136 Putnam County @ ): "qJ)

C:QunW smlle.s, Ic3.-BrCladleaf

vegetation

Q -

FiSh: and Invertebrates, (wbereavailable upstream)

Revision 2 ODCM Part II -Calculational Methodologies APPENDIXG (Page 7 of 7) ENVIRONMENTAL SAMPLING POINTS ADDITIONAL SAMPLING LOCATIONS N Rdiiefon (20.7 mi. N):'23."'p

Putnclm :GOUJ1ty Bear MoLintain 10:+ 17:' T,

.. 29: III .----4;:

S4 : ... <> .. Roqkland :County Key: 11-Air :ParticLllateac.RRdioiodine

.. -HR Bottom Sedirnent p -Precipitation dw;.*D rinkingWater HudSon. River <> -HR .Shorelihe,Sbii

+-:Soil °8;*dw 5 miles GVV-MonitoririgWelljSW of Site Boundary IPEC ODCM Page 122 of 136 Revision 2 6/09 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. Unit 1 or 2 Site Nearest 5-miles Release Points Receptor Boundary Resident Down Valley, Haverstraw Concentration 2.219E-06 1.030E-06 7.22E-07 Primary Vent X/Q (sec/m3) [SSW, 755 m] [SSW, 1574 m] 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] Unit 3 Site Nearest 5-miles Release Point Receptor Boundary Resident Down Valley, 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 D/Q (m*2) [SSW, 480 m] [S, 1133 m] 1.35E-09 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 b) IP3 worst sector X/Q = 4.47E-6 sec/m3 c) IP3 K-bar for instantaneous mixture = 849 mrem* m 3 flO .yr d) IP2 worst sector X/Q . = 2.22E-6 sec/m3

3 e) IP2 K-bar for instantaneous mixture = 1507 mrem m flO. yr f) Q = !-lCi/sec Solve for Q: Q [ (X/Q 3) (K bar3) + (X/Q 2) (K bar2)] = 500 mrem/yr Q [(4.47E-6)

(849) + (2.22E-6)

(1507)] = 500 mrem/yr Note: Units 2 and 3 effective dose factors (KLMN) are equivalent, except for site-specific finite cloud correction, as defined in Table 3-8. Therefore, without performing any specific calculations for an actual release, the default 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 e) IP2 (Li + 1.1 Mi) = 3071 mrem e m 3 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): Unit 2: mremem 3 (1.75E+5 uCi/sec) (2.22E-6 sec/m3) (3071 . ) = 1194 mrem/yr j.lO e yr Unit 3: mremem 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 Gamma air dose 5 mrad limit Beta air dose 10 mrad limit For a Calendar Year 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 Q = 5mrad / qtr = 3.21 E+4 /lCi/sec (1/ 4yr)(M)(X

/ Q) gamma dose rate beta dose rate Q = lOmrad / qtr = 1.44E+4 /lCi/sec (1I4yr)(N)(X

/ Q) unit 3 2.47E+4/lCi/sec 7.14E+3 /lCi/sec 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 > 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 JiCil m 3 Assumed Pathway: Child Inhalation at Unrestricted Area Boundary Solve the following equation for Q: . [(Q)PI(c)(Wv(in))

Unit 3] + [(Q)PI(c)(Wv(in))

Unit 2] = 1500 mrem/yr . . mrem 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) IP3 Dose Contribution:

1.38E+1 JiCi*1.62£7 mrem m 3 *4.47£_6 sec sec yr JiCi m 3 = 1003 mrem/yr IP2 Dose Contribution:

1.38E+1 JiCi

1.62£7 mrem m 3

2.22£ _ 6 sec sec yr JiCi m 3 = 497 mrem/yr 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: X/Q (in sec/m3 at the nearest resident)

D/Q (in m-2 at the nearest resident)

Unit 2 1.03E-6 7.52E-9 RI(c) ::: 1.62E+7 mreml , child thyroid inhalation dose factor for 1-131 flCilm RG = 1.72E+7 m 2 mreml yr -----"--, ground plane dose factor for 1-131 flCi / sec Unit 3 1.02E-6 7.45E-9 (for both units) (for both units) RV(c) = 4.75E+10 m 2 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 Q (Rlc)(X/Q) in mrem/yr per uCi/sec = Q (RG) (D/Q) in mrem/yr per uCi/sec = Q (RVc)(D/Q) in mrem/yr per uCi/sec = Unit 2 16.7

Q 0.129*Q 357

Q The sum for each unit (X

Q ) in mrem/yr per uCi/sec. 374

Q Unit 3 16.5

Q 0.128

Q 354

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) (IP2) . mrem/ yr Q

374 . = 30 mrem/yr; flO/sec 8.02E-2 IlCi/sec 4.01 E-2 IlCi/sec (IP3) . mrem/yr Q

371 . = 30 mrem/yr; flCi/sec 8.10E-2 IlCi/sec 4.05E-2 IlCi/sec (Annual limits are 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: X/Q (in sec/m3 at 5-miles down valley) D/Q (in m-2 at 5-miles down valley) Units 2 or 3 7.22E-7 1.35E-9 RI(i) = 1.48E+ 7 mrem I y; , infant thyroid inhalation dose factor for 1-131 j.1Ci I m RG = 2.10E+7 m 2 mreml yr . ----'--, g round plane dose factor for 1-131 j.1Ci I sec (for both units) (for both units) 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 Q (Rli)(X/Q) in mrem/yr per uCi/sec = Q (RG) (D/Q) in mrem/yr per uCi/sec = Q (RCi)(D/Q) in mrem/yr per uCi/sec = The sum for each unit ( X Q ) in mrem/yr per uCi/sec. Units 2 or 3 10.7

Q 0.028

Q 1412

Q 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 . mremlyr Q

1428 = 30 mrem/yr; j.1Ci I sec (Quarterly Limit) 2.10E-2 !lCi/sec (Annual Limit) 1.05E-2 !lCi/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: Streamtube Manholes Monitoring Wells, Monitoring Wells, upper zone lower zone Northern NA Background Background Clean Zone Unit 2 None MW-S2-11 MW-S2-18 MW-S2-64 MW-S2-122 North MW-S2-48 MW-S2-162 MW-S2-181 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 1/2 MH-4A MW-SO-66 MW-S4-37 MW-S3-120 MW-S4-S8 MW-S7-11 MW-S7-20 MW-S4-123 MW-S4-144 MW-S7-4S MW-S4-173 MW-S4-190 Unit 3 MW-S8-26 MW-S4-S8 MW-S4-123 North CB-14, CB-34 MW-S8-6S MW-S4-144 MW-S4-173 MW-S4-190 Unit 3 B8 U3-T2 MW-44-102 MW-41-63 South U3-Tt U3-4D 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-51-104 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: Streamtube Manholes Monitoring Wells, Monitoring Wells, upper zone lower zone Northern NA Background Background Clean Zone Unit 2 MH-1 MW-60-35 MW-37-22 MW-60-53 MW-60-72 North MH-12 MW-37-32 MW-49-26 MW-60-135 MW-60-154 MW-49-42 MW-60-176 MW-37-22 MW-37-32 MW-67-105 MW-67-173 Units MH-14 MW-49-26 MW-49-42 MW-67-219.

MW-67-276 1and 2 MW-49-65 MW-66-21 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 CB-15 MW-62-53 MW-62-71 MW-62-182 MW-63-112 North MW-63-18 MW-63-34 MW-63-121 MW-63-163 MW-63-50 MW-63-93 MW-63-174 Unit 3 U3-T1 U3-T2 MW-41-63 MW-44-102 South none U3-4D MW-40-81 MW-40-100 Southern C2 MW-40-27 MW-40-46 MW-40-127 MW-40-162 Clean Zone MW-51-40 MW-51-79 MW-51-104 MW-51-135 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: Streamtube Percent of Stormwater Flow 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 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

Text

SUBJECT:

Dear Sir or Madam:

Enclosures:

4.5 tanks

SUMMARY

Navigation menu

Search