Text

Rev 0 to Offsite Dose Calculation Manual
	ML20108B686
Person / Time
Site:	Perry
Issue date:	02/28/1985
From:	Cochnar R, Edelman M; CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Youngblood B; Office of Nuclear Reactor Regulation
References
	PROC-850228, PY-CEI-NRR-0196, PY-CEI-NRR-196, NUDOCS 8503070433
	Download: ML20108B686 (107)
	v • d • e

{{#Wiki_filter:?; 1 PERRY NUCLEAR POWER PLANT UNIT 1-0FFSITE DOSE CALCULATION MANUAL The Cleveland Electric Illuminating Company Perry, Ohio January, 1985. .g I a W B503070433 850131 PDR ADOCK 05000440 A PDR DO

OM12D: ODCI Page : i Rev. : 0 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR P0k'ER PLANT OPERATIONS MANUAL TITLE: OFFSITE DOSE CALCULATICN MANUAL (ODCM) REVISION: 0 EFFECTIVE DATE: DATE January, 1985 PREPARER: h fN - Oc shtu cc REVIEb'ER: PORC MEETING NO.: -APPROVED: 1 t v e-, y y ,+-r+ ..----,-w .-,w,

t. OM12D: ODCM Page : 11 Rev. : 0 Table of Contents Section Title Page

1.0 INTRODUCTION

1 2.0 LIQUID EFFLUENTS 2 2.1 Monitor Alarm Setpoint Determination 2 2.1.1 Determination of the Minimum Acceptable 2 Dilution Factor 2.1.2 Determination of the Maximum Allowable Radwaste 3 Tank Discharge Flow Rate 2.1.3 Liquid Radwaste Discharge Radiation Monitor 4 Alarm / Trip Setpoint 2.2 Compliance with 10CFR20 - Liquid Effluent 5 Concentration 2.2.1 Prerelease 5 2.2.2 Post Release 6 2.3 Compliance with 10CFR50 Appendix I - Liquid 7 Effluent Dose 2.3.1 Dose Calculations 7 2.3.2 Cumulation of Doses 9 2.3.3 Projection of Doses 10 2.3.4 Population Dose 10 3.0 GASEOUS EFFLUENTS 25 3.1. Monitor Alarm Setpoint Determination 25 3.1.1 Determination of the " Mix" (Noble Gas Radio-26 nuclide Composition) of the Gaseous Effluent 3.1.2 Determination of the Maximum Acceptable Total 26 Activity Release Rate of Noble Gas Radio-nuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 3.1.3 Determination of the Maximum Acceptable Total 27 Activity Release Rate of Noble Gas Radio-nuclides in Gaseous Effluent Based on Skin Dose Rate Limit 3.1.4 Determination of the Maximum Acceptable Total 28 Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent 3.1.5 Determination of the Maximum Acceptable Monitor 29 Count Rate Above Background Attributed to Noble Gas Radionuclides 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose 32 Rate 3.2.1 Noble Gases 32

OM12D: ODCM Page : iv Rev. : 0 List of Tables Table Title Page 2.3-1 Organs Used for Liquid Effluent Dose Calculations 12 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 12 2.3-3 Liquid Effluent Dose Pathways 12 2.3-4 Bioaccumulation Factors 13 2.3-5 Ingestion Dose Factors for Adult 14 2.3-6 Ingestion Dose Factors for Teenager 16 2.3-7 Ingestion Dose Factors for Child 18 2.3-8 Ingestion Dose Factors for Infant 20 2.3-9 External Dose Factors for Standing on Contaminated 22 Ground 2.3-10 Transit Times Required for Nuclides to Reach the 24 Point of Exposure 24 2.3-11 Usage Factors 3.1-1 Whole Body and Skin Dose Factors 31 3.2-1 . Organs Used for Gaseous Effluent Dose Calculations 38 3.2-2 Age Groups Used for Gaseous Effluent Dose 38 i Calculations 3.2-3 Gaseous Effluent Dose Pathways 39 3.2-4 Dose Factors for Exposure to a Semi-Inifinite 40 Cloud of Noble Gases 3.2-5 External Dose Factors for Standing on Contaminated 41 Ground 3.2-6 Inhalation Dose Factors for Adu.1.t 43 3.2-7 Inhalation Dose Factors for Teenager 45 3.2.8 Inhalation Dose Factors for Child 47 3.2-9 Inhalation Dose Factors for Infant 49

OM12D: ODCM Page : v Rev. : 0 List of Tables Table Title Page 3.2-10' Ingestion Dose Factors for Adult 51 3.2-11 Ingest (wt Dose Factors for Teenager 53 3.2-12 Ingestion Dose Factors for Child 55 3.2-13 Ingestion Dose Factors for Infant 57 3.2-14 Annual Usage Factors for the Maximum Exposed 59 Individual 3.2-15 Annual Usage Factors for the Average Individual 59 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite 64 Plume 5.1-1 PNPP Radiological Environmental Monitoring Program 69 5.1-2 Reporting Levels for Radioactivity Concentrations 71 in Environmental Samples 5.1-3 Detection Capabilities for Environmental Sample 72 Analysis and Lowcr Limit of Detection (LLD) 5.1-4 Sample Locations and Media for the Radiological 74 Environmental Monitoring Program A-1 Atmospheric Depletion and Deposition Factors 82 A-2 Site Boundary Atmospheric Dispersion and Deposition 84 Parameters for PNPP Unit 1 A-3 Atmospheric Dispersion and Deposition Parameters at 84 the Nearest Residences for PNPP Unit 1 A-4 Atmospheric Dispersion (X/Q) as a Function of 85 Distance A-5 Atmospheric Deposition (D/Q) as a Function of 90 Distance

OM12D: ODCM Page : vi Rev. : O List of Figures Figure Title Page 5.1-1 Radiological Environmental Monitoring Program 77 Sampling Locativns Within 5 miles of PNPP 5.1-2 Radiological Environmental Monitoring Program 78 Sampling Locations Greater Than 5 miles from PNPP

OM12D: ODCM Page : 1 Rev. : 0

1.0 INTRODUCTION

This Office Dose Calculation Manual (ODCM) contains information and methodologies to be used by the Perry Nuclear Power Plant (PNPP), Unit 1, to ensure compliance with PNPP Technical Specifications. The Technical Specifications are written to satisfy 10CFR20, 10CFR50.36 and Appendix I, and 40CFR190 requirements. Sections 2 and 3 of this manual deal with liquid and gaseous radiological effluents, respectively. Each of these sections contain alarm setpoint determi. ation, radiation dose and dose rate calculation methodologies, as well as limits and requirements. Section 4 covers uranium fuel cycle related radiation dose limits including direct dose. Also included in this manual, in Section 5, is information relating to the Radiological Environmental Monitoring Program (REMP). The figures and tables contained therein designate specific sample types and locations currently used to satisfy the Technical Speci-fication requirements for the REMP as well as sampling reporting' and detection capability limits. The sample types and locations are subject to change based on the results of the annual land use census. The ODCM has been prepared, as generally as possible, in order to minimize future revisions. However, any such changes will be reviewed and approved as per the Administrative Control Section of the PNPP Technical Specifications. Supplemental information needed to support calculations, both in this document and in the accompanying Radiological Effluent Techni-cal Specifications is contained in the appendices at the end of this manual. Appendix A contains atmospheric dispersion and deposition parameters, and Appendix B presents the methodology for determining the lower limit of detection (LLD).

OM12D: ODCM Page : 2 Rev. : 0 2.0- LIOUID EFFLUENTS All liquid radwaste discharges.from Perry Nuclear Power Plant will be batch releases, that is, of a discrete volume. Batch releases from the liquid radwaste system may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste distillate tank, and detergent drain tank. The maximum release rate possible, due to pump capacity, is 200 gallons per minute from all release tanks except the detergent drain tank, which has a maximum release rate of 50 gallons per minute. All of the above liquid radwaste releases go to the Emergency Service Water dis-charge which is then released through the discharge canal after mixing with Service Water effluent, and blowdown from Circulating Water system if present. The type and frequency of sampling and analysis required by the PNPP Technical Specifications is given in Table 4.11.1.1.1-1. Prior to sampling for analysis, each batch should be isolated, and thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirculated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank. This procedures ensures that the water in the tank vill be mixed and will be representative of the activity in the tank. The minimum recirculation performed is the equivalent of two volumes of the tank contents. 2.1 Monitor Alarm Setpoint Determination Monitor alarm setpoints will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release will be determined prior to release in accordance with Table 4.11.1.1.1-1 of the PNPP Technical Specifications. This method will be used to calculate the setpoint for the Radwaste Discharge. Radiation Monitor - ESW Discharge (D17K606) which provides alarm and automatic termination of liquid effluent releases from the site to unrestricted areas before concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than noble gases are exceeded. -2.1.1 Determination of the Minimum Acceptable Dilution Factor C DF, = ][, (2.1-1) i MPC f Where: DF = the minimum acceptable dilution factor determined from~ analysis of'the liquid effluent to be released;

OM12D: ODCM Page : 3 Rev. : O C = the concentration of radionuclide i in the batch to i be released, in uCi/ml; MFC = the maximum permissible concentration of radio-nuclide i, from Appendix B, Table II, Column 2 of 10CFR20, in uCi/ml. (2.1-2) DF = 10 DF, Where: DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to release in order to ensure cospliance with 10CFR20; DF = the minimum acceptable dilution factor, as per equation 2.1-1; 10 = a factor of ten less than 10CFR20 limits as specified in Appendix B, Table II, Column 2. This factor represents an order of magnitude of conservatism for liquid radwaste releases from PNPP. NOTE: If the concentration of a radionuclide is below the lower limit of detection the radionuclide shall not be included as a source term in the setpoint calcu-lation. 2.1.2 Determination of the Maximum Allowable Radwaste Tank Discharge Flow Rate 0.8 mdf f,, DF (2.1-3) = Where: f

the maximum allowable radwaste tank discharge flow rate for the batch to be released, in gpm; DF = the conservative dilution factor, as per equation 2.1-2; mdf = the minimum dilution flow - supplied by the Service Water system, i.e., the low flow alarm setpoint of the Service Water Flow Transmitter P41-N443

30,000 gpm;

OM12D: ODCM Page : -4 Rev. : 0 0.8 = an engineering factor to prevent spurious alarms. The liquid radwaste tank discharge flow should be maintained at or below this f valve by proper regulation of the high volume or low voluEe* discharge throttle valves (PCVF153 or PCVF155). 2.1.3 Liquid Radwaste Discharge Radiation Monitor Alarm / Trip Set-point Monitor alarm / trip setpoints are determined to ensure that the ' concentration of radionuclides in the liquid effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides othgr than dissolved or entrained noble gases. ~ uCi/mi has been established for noble gases An MFC of 2 x 10 dissolved and entrained in liquid effluents. CR = bC E (2.1-4) g g i i Where: CR = the calculated monitor count rate above background, in cpm; } C = the concentration of radioneclide i in the batch to i be released, in uCi/ml; E = the detector efficiency of the monitor for radio-g nuclide i in cpm /(uCi/ml). SP = 1.25 CR + BG (2.1-5) .Where: SP = the Radwaste Discharge Radiation Monitor - ESW Dis-charge (D17K606) alarm / trip setpoint, in cpm; BG = the background count rate due to internal contami-nation and radiation levels in the area of the monitor; CR = the monitor count rate, as per equation 2.1-4; J I

OM12D: ODCM Page : 5 Rev. : 0 1.25 = the engineering safety factor to prevent spurious alarms. (The inverse of 0.8). 2.2 Compliance with 10CFR20 - Liquid Effluent Concentration In order to show compliance with 10CFR20, the concentrations of radionuclides in liquid effluents will be determined and compared with maximum permissible concentrations (MPC) as defined in Appen-dix B, Table II, Column 2 of 10CFR20. Concentrations of radioac-tivity in effluents prior to dilution will be determined. Concen-tration in diluted effluent will be calculated using these results prior to each batch release, and following each batch release. PNPP has no continuous releases. 2.2.1 Prerelease The radioactivity content of each batch release will be determined prior to release. PNPP will show compliance with 10CFR20 in the following manner: The concentration of the various radionuclides in the batch release prior to dilution is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation: C f g (2.2-1) Cone f mdf Where: Conc = the concentration of radionuclide i at the i unrestricted area, in uCi/ml; C = the concentration of radionuclide i in the batch to i be released, in uCi/ml; f = the radwaste tank discharge flow rate for the batch to be released, in gpm; mdf = the minimum dilution flow, as per equation 2.1-3, in gpm.

OM12D: ODCM Page : 6 Rev. : 0 The projected radionuclide concentrations in the unrestricted area are compared to the maximum permissible concentrations in Appendix B, Table II, Column 2 of 10CFR20 in order to give a . final 10CFR compliance check, i.e., the following equation must be met: Cone (2.2-2) g i MPCf Where: Conc = the concentration of radionuclide i at the i unrestricted stea. in uCi/ml; MPC = the maximum permissible concentration of radio-g nuclide i, from Appendix B. Table II, Column 2 of 10CFR20, in uCi/ml. '2.2.2 Post Release The actual radioactivity content of each batch release will be determined following release to show final compliance with 10CFR20. The concentration of the various radionuclides in the batch -release prior to dilution is divided by the actual dilution to obtain the concentration at the unrestricted area. This calculation is shown in the following equation: C V g irt (2.2-3) Cone = f Vdil Where: Conc = the actual concentration of radionuclide i at the unrestricted area for the release, in uCi/ml; C = the concentration of radionuclide i in the batch I released, in uCi/ml; "I' " "***# "#'"3 Vdil " release (the sum of all dilution flows: Service Water, Emergency Service Water, and cooling tower blowdown), in gallons; V = the actual volume of the liquid radwaste tank dis-charged for' the batch, in gallons. i--....

OM12D: ODCM Page : 7 Rev. : 0 The concentrations in the unrestricted area are compared to the maximum permissible concentrations in Appendix B, Table II, Column 2 of 10CFR20 in order to demonstrate final compli-ance with 10CFR20, i.e., the following equation must be met: Conc i d1 (2.2-4) i MFC Where: Conc = the concentration of radionuclide i at the i unrestricted area, in uCi/ml; MPC = the maximum permissible concentration of radio-nuclide i, from Appendix B, Table II, Column 2 of 10CFR20, in uCi/ml. 2.3 Compliance With 10CFR50 Apoendix I - Liquid Effluent Dose Doses resulting from liquid effluents will be calculated monthly to show compliance with 10CFR50. A cumulative summation of total body and organ doses for each calendar quarter and calendar year will be maintained, as well as projected doses for the remainder of the quarter and year. 2.3.1 Dose Calculations. Radiation doses due to radioactive effluents from PNPP are calculated based on three main dose pathways: potable. water, aquatic foods (namely fresh water fish ingestion), and expo-sure to shoreline deposits. Irrigated food pathways, dis-cussed in Regulatory Guide 1.109, will not be of concern at PNPP as little or no water from Lake Erie is used for irriga-tion in the nearby Ohio counties of Lake, Ashtabula, Cuyahoga and Lorain. Nursery businesses and other agricultural activ-ities that require supplemental water generally rely on water drawn from small ponds and streams.

OM12D: ODCM Page : 8 Rev. : 0 Radiation dose to members of the public for liquid radwaste releases from PNPP will be calculated for the potable water, aquatic food, and shoreline deposit pathways using the follow-ing equation: 1. Potable Water: U R, p = 1100 Q D,g ) exp (-K t) (2.3 4 ap p i p 2. Aquatic Foods: U D,g ) exp (- K t) (2.3-2) 00 Q B = p f p ajp g gp y 3. Si:oreline Deposits: U W ap t ) P (2.3-3) D,g ) (exp (-K R, p = 110,000 Q T p g p 1 [1 - exp (- K t )3 g b Where: R = the dose to individuals of age group a to organ j ajp from all the radionuclides in pathway p, in mrem; B = the equilibrium biaccumulation factor for radio-ip nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/1), from Table 2.3-4, in 1/kg; D = the dose factor, specific to a given age group a, aipj radionuclide i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem /pC1, or from exposure to a given concentration of a radio-nuclide in sediment, expressed as a ratio of the dose rate, in mres/h, agd the areal radionuclide concentration, in pCi/m, from Tables 2.3-5 through 2.3-9; F = the flow rate of the liquid effluent in f /s;

OM12D: ODCM Page : 9 Rev. : 0 M = the dilution factor at the midpoint of exposure p (or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless; Q = the release of radionuclide i, in Ci; g t = the period of time for which the sediment or son is 5 b exposed to the contaminated water, 1.31 x 10 h (from RG 1.109); T = the halflife of radionuclide i, in days; t = the average transit time required for radionuclides p to reach the point of exposure, from Table 2.3-10; for internal dose, t, is the total time elapsed between release of the radionuclides and the inges-tion of food or water, in h; U = the usage factor that specifies the exposure time ap or intake rate for an individual of age group a associated with pathway p, from Table 2.3-11, in h/yr, 1/hr, or kg/hr; W = the shoreline width factor, 0.3 (from RG 1.109); y = the g dioactive decay constant of radionuclide i, in h ; 3 1100 = a factor to convert from (Ci/yr)/(f /s) to pCi/1; 110,000 = a factor to convert from (Ci/yr)/(f /s) to pCi/1 and to account for the proportionality constant used in the sediment radioactivity model. 2.3.2 Cumulation of Doses The dose contribution from liquid effluents will be calculated monthly. Calculations will be performed to determine the maximum total body as well as the maximum organ dose to an individual. These monthly dose calculations will be summed for comparison with quarterly and annual limits. The monthly results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest.

OM12D: ODCM Page : 10 Rev. : 0 To assure compliance with the dose limits of 10CFR50 Appen-dix I the following relationships should hold: for the quarter: Dose 55l 1.5 mrem total body; Dose GG; 5 mrem any organ; for the calendar year: Dose 650 3 mrem total body; Dose GG 10 mrem any organ. The quarterly limits given above represent one-half of the annual design objective. If these quarterly or annual limits are exceeded, a special report will be submitted to the NRC, in accordance with PNPP Technical Specifications, stating the reason and corrective action to be taken. This report will include results of analyses of Lake Erie water and an analysis of possible impacts through the drinking water pathway with regards to the requirements of 40CFR141. 2.3.3 Projection of Doses i Anticipated doses resulting from the release of liquid efflu-ents will be projected monthly. If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the total body or 0.2 mrem to any organ, the liquid radwaste system will be used to process waste. The values for the projected impact corre-spond to approximately one forty-eighth of the Appendix I design objective. If continued at this rate for one year, the projected impact would correspond to less than one-fourth of the Appendix I limit. The projected doses will be calculated pring Equations 2.3-1 to 2.3-3. lThe total source tera utilized for the most recent calculation should be used for the projections unless information exists ' indicating that actual releases could differ significantly in the next month. In this case, the source term should be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month. 2.3.4 Population Dose As required by Regulatory Guide 1.21, for Semiannual Radioac-tive Effluent Release Reporting, a population dose is

OM12D: ODCM Page : 11 Rev. : O calculated for doses received from all radioactive liquid effluent releases. This population dose is calculated using average individual transit times and usage factors (as compared to maximum exposed individual factors used for individual doses). The population dose is calculated by dose pathway and organ, with pathway doses being corrected for the fraction of the population assumed to be in each age group (adult, teen, child and infant: 0.71, 0.11. 0.18, 0.0 respectively).

OM12D: ODCM Page : 12 Rev. : 0 Table 2.3-1 Organs used for Liquid Effluent Dose Calculations 1. done 2. GI Tract 3. Kidney 4. Liver 5. Lung 6. Thyroid 7. Total Body 8. Skin Table 2.3-2 Age Groups used for Liquid Effluent Dose Calculations 1. Adult (17 yrs. and older) 2. Teen (11 - 17 yrs.) 3. Child (1 - 11 yrs.) 4. Infant (0 - 1 yr.) { Table 2.3-3 Liquid Effluent Dose Pathways l 1. Water ingestion 2. Shore exposure 3. Fish ingestion l } .i

OM12D: ODCM Page : 13 Rev. : 0 Table 2.3-4 Bioaccumulation Factors (B, ) (pCi/kg per pCi/ liter) Element Fish H 9.0E-01 C 4.6E 03 Na 1.0E 02 P 1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01 Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02 1 1.5E 01 Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W 1.2E 03 Np 1.0E 01

OM12D: ODCM Page : 14 Rev. : 0 Table 2.3-5 Ingestion Dose Factors for Adult (crem/pCi ingested) NUCLICE 80NE LIVER T. BOGY THYR 0!O KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1.0$ E-0 7 1.056-07 1.05E-07 1.05E-07 1 05E-07 C 14 2.84E-06 5.68E-07 5. 6 8 E -0 7 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06

1. 70 E-0 6

1. TOE-06 1.70E-06 1 70E-06 1.70E-06

====.....__._= _ - __... P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NC DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.60E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-0T NN $4 NO DATA 4.57E-06 8.72 E-0 7 NO DATA 1.36E-06 NO DATA 1.40E-05 _....==-- =_ __ MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1 46E-07 NO DATA 3.67E-06 rE 55 2.75E-06 1.90F-06 4.4 3 E-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05

3. 91 E-0 6 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.456-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-C4 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06

.___.__....==_ -- ---==..__.____. NI 65 5.28E-07 6.86E-08 3.13 E-0 8 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05

6. 96 E-0 6 NO DATA 1.03E-05 NO DATA 9.70E-06

=_ -- .==. ZN 69 1.0 3E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA

4. 02 E-0 8 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 R8 89 NO DATA 4.01E-08

2. 82 E-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA

8. 84 E-0 6 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA

1. 86 E-0 3 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-9 7 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9 30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91N 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA T.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.392-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 N8 95 6.22E-09 3.46E-09

1. 86 E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 NO 99 NO DATA 4.31E-06

8. 20E-0 7 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.985-10 8.81E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07

J 1 1 OM12D: ODCM Page : 15 Rev. : 0 Tabic 2.3-5 (Cont.) Ingestion Dose Factors for Adult (arem/pci ingested) NUCL10E BONE liver T. B O DY THYR 010 K10NEY LUNG GI-LLI .TC101 -2.54E-10 3.66E-10

3. 59 E -0 9 NO DATA 6.59E-09 1.87E-10 1 10E-21 4U103 1.85E-07 NO DATA

7. 9 7 E -0 8 NO DATA T.06E-07 NO DATA 2.16E-05 l

RU10$ 1.54E-08 NU CATA 6.03E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 ________.__--- - -..______..__..... ___....____.........__...=- RU106 2.75E-06 NO DATA

3. 4 8 E -0 7 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1.48E-07

8. 79 E -0 8 NO DATA 2.91E-07 NO DATA 6.04E-05 TE125M 2 6SE-06 9.71E-07

3. 5 9 E-0 7 8.06E-07 1.09E-05 'NO DATA 1.07E-05 TE127M 6.77E-06 2.42E-06

8. 25 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08

2. 38 E-0 8 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4.29E-06 1 82E-0 6 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3 14E-08 1.18E-08 7.63E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.46E-07 7.0 5 E-0 7 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE131 1.97E-08 8.23E-09

6. 22 E-09 1 62E-08 8.63E-08 NO DATA 2.79E-09

/ TE132 2.52E-06 1.63E-06

1. 53 E-0 6 1.80E-06 1.57E-05 NO DATA 7.71E-05

/ 1 130 7.56E-07 2.2 3E-06 8.80E-07 1 89E-04 3.48E-06 NO DATA 1.92E-06 \\ I 131 4.16E-06 5.95E-06

3. 41 E-0 6 1 95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.0 3.E-0 7 5.43E-07 1 90E-0 7 1 90E-05 8.65E-07 NO DATA 1.02E-07 1 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 1 134 1.06E-07 2.88E-07 1.03 E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4.2SE-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2 59E-06 C5136 6.51E-06 2.57E-05

1. 85 E-0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06.

C5137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 C5138 5.52E-08 1.09E-07

5. 40 E -0 8 NO DATA 8.01E-08 7.91E-09 4.65E-13 8A139 9.70E-08 6.91E-11

2. 8 4 E-0 9 NO DATA 6.46E-11 3 92E-11 1 72E-07 8A140 2.03E-05 2 55E 1. 3 3 E-0 6 H0 DATA ~ 8.67E-09 1.46E-08 4.18E-05 RA141

4. T I E-08 1.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2 22E-17 6A142 2.13E-08 2.19E-11

1. 34 E-0 9 NO DATA 1.85E-11 1 24E-11 3.00E-26 LA140 2.50E-09 1.262-09 3 33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 F.1RE-10 NO DATA 2 94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10

.NO DATA 5.37E-10 NO DATA .4.56E-05 CE144 4.R8E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.69E-09 4 56E-to NO DATA 2.13E-09 NO DATA 4.03E-05 PR144 3.01E-11 1.25E-11 1.5SE-12 NO DATA 7.05E-12 NO DATA 4.33E-18 N0147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3 49E-05 N 197 1.03E-07 8.61E-08 3 01E-0 8 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA '2.40E-05

1 l 1 1 1 OM12D: ODCM Page : 16 Rev. : 0 Table 2.3-6 Ingestion Dose Factors for Teenager (mren/pci ingested) NUCLIDE 80NE LIVER T.800Y THYROID K!DNEY LUNG GI-LLI _..__.= _ _-_= =_ _

==.-_______.___.....____...__....__ _==_____ H 3 NO DATA 1.06E-07 1 0eE-0 7 1.06C-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12 E-0 7 8.12F-07 8.12E-07 8.12E-07 8.12F-07 NA 24 2.30E-06 2.30E-06

2. 30 E-0 6 2.30E-06 2.30h-06 2.30E-06 2.30E-06

________________________........ _____...== _ ___.__.....__... __. __...... P 32 2.76E-04 1.71C-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR St NO DATA NO DATA 3.60E-09 2.00E-09 7.99t-10 5.14E-09 6.05E-0T PN 54 NO, DATA 5.90E-Oo 1.17E-06 NO DATA 1 76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.38C-07 2.81E-Oa NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68F-06

6. 2 S E-0 7 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.JTE-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24E-06 NU DATA NO DATA NO DATA 1.34E-05 CO 60 NO DATA 2.81E-06

6. 3 3E-0 6 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1 77E-04 1.25C-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06

== .._......______------ =..==____--.. NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 IN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 IN 69 1.47E-08 2.60E-08

1. 96E-0 9 NO DATA 1.R3E-08 NO DATA 5.16E-08 BR 83

-NO DATA NO DATA 5.74E-08 NO DATA NO DATA - NO DATA LT E-24 BR 84 NO DATA NO DATA

7. 22 E-0 8 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05 E-0 9 NO DATA NO DATA NO DATA LT E-24

~* R8 86 NO DATA 2.98E-05

1. 40 E-0 5 NO DATA NO DATA NO DATA 4.41E-06 R8 88 NO DATA 8.52E-08 4 54E-08 NO DATA NO DATA NO DATA 7.30E-15 48 89 NO DATA 5.50E-08

3. 89 E-0 8 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E.04 NO DATA

1. 26 E-0 5 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2 05E-0 3 NO DATA NO DATA NO DATA 2 33E-04 SR 91 8.07E-06 NO DATA

3. 21 E-0 7 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E.08 NO DATA

3. 6 ? E-10 NO DATA NO DATA NO DATA 1.13E-04

. _ _ _. _ _ _... _ _ _ _. _ _.. = - - = Y 91M 1 29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05 Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30C-08

8. 9,E-0 9 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E.10 NO DATA 7.11E-10 NO DATA 1.27E-04

........ _==..__.....__.........__-..-__..............____............__.._

4H 95 8.22E-09 4.50!-09

2. S I E -0 9 NO DATA 4.42E-09 NO DATA 1.95E-05 MD 99 NO DATA 6.03C-06

1. liF-0 6 NO DATA 1 38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5 14E-10 6.08E-07

1 OM12D: ODCM Page : 17 Rev. : 0 Table 2.3-6 (Cont.) Ingestion Dose Factors for Teenager (mrem /pCi ingested) NUCLIOE BONE LIVER T.000Y THYR 0f0 KtDNEY LUNG Cl-LLI TC101 3.60E-10 5.125-10 5.01E-09 NO DATA 9 26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 NU DATA

1. 09 E-0 7 NO DATA 8.99E-07 NO DATA 2.13E-05 RU105 2.18E-08 NO UAIA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05 RU106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG110M 2.05E-07 1.94E-07 1.taE-07 NO DATA 3 70E-07 NO DATA 5.45E-05 TE125M 3.83E-06 1.38E-C 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05

___________._____..___..'s TE127M 9.67E-06 3.43E-06 1.15E-06 2 30E-06 3 92L-05 NO DATA 2.41E-05 TE127 1.58E-07 5.60E-08 3.4 0 E-0 8 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE129M 1 63E-05 6.05E-06 2.58E-06 5.26E-06 6.R2E-05 NO DATA 6.12E-05 TE129 4.48E-08 1.6FE-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2 45E-07 TE13tM 2.44E-06 1.1TE-06 9.76E-07 1.T6E-06 1.22E-05 NO DATA 9 39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 ~ TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 1 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2 29E-06 I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 1 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 ! 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1 46E-07 3.87E-07

1. 39 E -0 7 6.45E-06 6.10E-07 NO DATA 5 10E-09 1 135 6.10E-07 1.57E-06

5. 82 E-0 7 1.01E-04 2.48E-06 NO DATA 1.74E-06 C5134 8.37E-05 1.97E-04 9.14 E-0 5 NO DATA 6.26E-05 2.39E-05 2.45E-06 C5136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 C5137 1.12E-04 1.49E-04 5.19E-05 NO DATA,5.07E-05 1.97E-05 2.12C-06 CS138 7.74E-08 1 49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11 84139 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22E-11 6.74E-11 1 24E-06 04140 2.8'E-05 3 48E-OS

1. 8 3E-0 6 NO DATA 1.186-06 2.34E-08 4.38E-05 RA141 6.71E-08 5.01E-11 2.24E-09 NO DATA 4.65E-11 3 43E-11 1.43E-13 DA142 2.990-08 2.99E-11 1.84E-09 NO DATA 2.53t-11 1.99E-11 9.18E-20 LA160 3.43E-09 1.71E-09 4.55E-10 NO DATA NC OATA NO DATA 9.82E-05 LAt42 1.79E-10 7.95E-It 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE141 1.33E-08 8.88E-09

1. 02 C -0 9 NO DATA 4.18E-09 NO DATA 2.54E-05 CE143 2.35E-09 1.7tE-06 1.9tE-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE144 6.96E-07 2 88E-07

3. 74 E-0 8 NO DATA 1.72E-07 NO DATA 1.75E-04 PR143 1.31E-08 5.23E-09

6. 5 2 E-10 NU DATA 3.04E-09 NO DATA 4.31E-05 PRt44 4.30E-11 1.762-11 2.18 E -12 NO DATA 1.01E-11 No DATA 4.74E-14 N014T 9.18E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05 W 187 1.46E-07 1.19E-07 4.1TE-08 NO DATA NO DATA NO DATA 3.22E-05 NP239 1.76E-09 1.66E-10 9.22F-11 NO DATA 5.2tC-10 NO DATA 2.67E-05

OM12D: ODCM P.ge : 18 Rev. : 0 Table 2.3-7 Ingestion Dose Factors for Child (mrem /pCi ingested) NUCLIUE BONE L!VER T.HOUY THYR 010 K10NEY LUNG GI-LLI H 3 NO DATA 2.03E-07 2.01E-0 7 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.*2E-06 2.42E 06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.00L-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.06E-05 3.1CE-05 10 DATA NO DATA NO DATA 2.28E-05 CR 51 40 DATA NO CATA

8. 9 0 E -0 9 4.96E-09 1.35E-09 9.02[-09 4.72E-07 MN 54 10 DATA 1.07E-05

2. 8 5 E -0 6 NO DATA 3.00E-06 NO DATA 8.98E-06 NN 56 NO DATA 3.340-0T 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.tSE-05 6.10E-06

1. 8 9 E -0 6 NO DATA NO DATA 3.456-06 1.13E-06 FE $9 1.6sE-05 2.67E-05 1.33[-05 NO DATA NO DATA 7.74E-06 2.78E-05 CO 58 NO DATA 1.80E-06

5. 51 E-0 6 NO DATA NO DATA NO DATA 1 05E-05 CO 60 NO DATA 5.29E-06 1 56 E-0 5 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E.04 2.88F-05

1. 8 3 E-0 5 NO DATA NO DATA NO DATA 1.94[-06 NI 65 2.22E-06 7.09F-07

1. 2 2 E-0 7 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NU DATA 2.45E-07 1.48E-07 NO DATA 5 92E-07 NO DATA 1.15E-05 IN 65 1.37E-05 3.05E-0) 2.2 TC-0 5 NO DATA 2.30E-05 NO DATA 6.41E-06 lN 69 4.38E-08 6.43E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA

1. 71 E-0 7 NO DATA NO DATA NO DATA LT E-24 8R 84 NO DATA NO DATA 1.986-07 NO DATA NO DATA NO DATA LT E-24 RR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 MB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.3tF-06 R8 88 NO DATA 1.90E-07

1. 3 2 E-0 7 NO DATA NO DATA NO DATA 9.32[-09 RB 89 NO DATA 1.17E-07 1.04 E-0 7 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NU OATA

3. 7 7 E-0 5 NO DATA NO DATA NO DATA 5.llE-05 SR 90 1.70E-02 NO DATA 4.31E-03 40 OATA NO DATA NO DATA 2.29E-04

$R 91 2.40E-05 NO DATA

9. 06E -0 7 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-C6 NO DATA

3. 62 E-0 7 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4 11E-06 NO DATA 1.10 E-0 9 NO DATA NO DATA NO DATA 1.17E-04 Y 91M 3.82E-10 NO DATA 1 39E-11 NO DATA NO DATA NO DATA T.48E-07 Y 91 6.02E-07 NO DATA 1.61F-08 NO DATA NO DATA NO DATA 8.02E-05 Y 92 3.60E-09 NO DATA 1.01E-10 NO DATA NO DATA NO DATA 1.04E-04 o

Y 93 1.14[-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 2R 95 1.16E-07 2.3)E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 LR 97 6.99E-09 1."1E-09 5.96E-10 NO DATA 1.45L-09 NO DATA 1.53E-04 NR 95 2.25E-08 8.* SE-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1. 3E-05

3. 2 9 E -0 6 NO DATA 2.84E-05 NO DATA 1 10E-05 TC 998 9.23E-10 1.

3.00E-08 NO DATA 2.63E-08 9.19E-10 1 03E-06 .....................'.1E-09 I 4

OM12D: ODCM Page : 19 Rev. : 0 Table 2.3-7 (Cont.) Ingestion Dose Factors for Child (mren/pCi ingested) NUCLIDE 80NE liver T. 00 DY THYR 010 KIONEY LUNG GI-L(1 IC101 1.07E-09 1 12n-09 1.42E-08 NO DATA 1.91E-08 5.92C-10 3.56E-09 Rut 03 7.31E-07 NO DATA

2. 8 t E-0 7 NO DATA 1.84E-06 NO OATA 1.89E-05 nut 05 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 Rut 06 1.17E-05 NO DATA 1.46E-06 No DATA 1.58E-05 NO DATA 1.82E-04 AG110M 5.39E-07 3.64C-07 2.91 E-0 7 No DATA 6.78E-07 NO DATA 4.33E-05 TE125M 1.14E-05 3.09E-06

1. 5 2 E-0 6 1.20E-06 NO DATA NO DATA 1.10E-05 TE12TN 2.89E-05 7.78E-06 3.4 J C-0 6 6.9tE-06 8.24E-05 NO DATA 2.34E-05 TE127 4.7tE-07 1.27F.07 1.01E-0 7 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE129 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE129 1.34E-07 3.74E-08 3.18 E-0 8 1.56E-38 3.92E-07 NO DATA 8.34E-06 TEt3tM 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.4tE-05 NO DATA 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE132 1.01E-05 4.47E-06

5. 4 0 E-0 6 6.5tE-06 4.15E-05 NO DATA 4.50E-05 t 130 2 92E-06 5.90E-06

3. 04 E -0 6 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73C-05

9. 83 E-0 6 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 132 0 00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 NO DATA 1.73E-06 I 131 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.58E-01 1.71E-05 1 19E-06 NO DAT4 5.16E-07

! 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 C5134 2.34E-04 3.84C-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 C5136 2.35E-05 6.46E-05 4.10E-0$ NO DATA 3.44E-05 5.13E-06 2.27E-06 C5137 3.27E-04 3.13C-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 C5138 2 28E-07 3.17E-07

2. 01 E-0 7 NO DATA 2.23E-07 2 40E-08 1.46E-07 BA139 4.14E-07 2.21E-10

1. 2 0E -0 8 NO DATA 1.93E-10 1.30E-10 2.39E-05 RA140 8.JtE-05 7.28E-08 4.85E-06 NO DATA 2.37t-08 4.34E-08 4.2tE-05

?.A141 2.00E-07 1.122-10 6.htE-09 N3 DATA 9.696-11 6.58E-10 1.14 E-0 T 0A142 8.74L-08 6.29E-11

4. 8 a F -0 9 NO DATA 5.01E-11 3.10E-tt 1 14E-01 L4140 1.01E-08 3.53E-09 1.19E-09 A0 DATA NC OATA NO DATA 9.84E-05 LA142 5.?4C-10 1.67F-10 5.21C-11 NO DATA NO DAT4 NO DATA 3.3tE-05 CEt41 3.97C-08 1.98C-08 2.96C-09 NO DATA 4.68E-01 NO DATA 2.47E-05 CE143 6.99C-09 3.79E-06 5.49E-Lo NO DATA 1.59E-09 NO DATA 5.55C-05 CEt44 2.08E-06 6.52E-0F 1.ttE-07 NO DATA 3.6th-07 NO DATA t.10E-04 PR141 1.93C-08 1.18C-08 L.95E-09 NO DATA 6.19E-09 NO DATA 4.24E-05 PRt44 1.29C-10 3.11E-tt 6.49E-12 NO DATA 2.Itt-tt NO DATA 8.59E-08 Not4F 2.79E-OR 2.26E-08 L.75E-09 NO DATA 1.24C-08 NO DATA 3.58E-05 W IST 4.29E-07 2.54E-07

1. t

E-0 7 NU DATA NO DATA NO DATA 3.57E-05 NP239 5.2bE-01 3.77E-lo 2.65t-to No DATA t.096-01 NO DATA 2.T9E-05

r-OM12D: ODCM Page : 20 Rev. : 0 Table 2.3-8 Mestion Dose Factors for Infant (mrem /pci ingested) NUCLiuE BONt LIVER f. 6007 THvm010 MIONEY LUNG OI-LLI H 3 NO D A T 5 3.08F-07

1. 0 0 E -0 7 3.08E-07 3.03C-07 3.08E-07 3.08E-07 C 14

2. 3 f E- ;5 5.06E-06 5. 06 E -0 6 5.06E-06 5.06t-06 5.06F-06 5.06E-06 NA 24 1.01E-05 1.01E-05 1.01E-05 1.0tE-05 1.01E-05 1.01E-05 1.0tE-05 P 32 1.70E-03 1 00E-04 6.59E-05 NU UATA NO DATA NO DATA 2.30E-05 CR St NO DATA NO DATA 1.4tE-08 1.20E-09 2 0tt-09 1.79E-08

4. t L E-0 7 MN 54 NO DATA 1.99E-05 4.5tE-06 NO DATA 4.4tE-06 NO DATA 7.3tE-06 NN 56 NO DATA 8.18E-07 1.4 t E-0 7 NU DATA 7 01E-07 NO DATA 7.43E-05 FE $5 1.39E-05 8.181-06

2. 4 C E-0 6 NO DATA NO DATA 4.19 E-0 6 1.14E-06 FE 59 3.08E-05 5.s82-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.93E-06 NO DATA NO DATA NO DATA 8.9 TE-06 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.926-05

2. 20 E -0 5 NO DATA NO DATA NO CATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.426-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-OT 2.82E-07 NO DATA 1 0 E-06 NO DATA 1.25E-05 2N 65 1.54E-05

6. 'J 1 E -0 5 2 9 t E-0 5 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.08E-0T

1. 2 S E-0 8 NO DATA 6.98E-08 NO DATA 1.37E-05 HR 83 NO DATA NO DATA

3. 63 E-0 7 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA J. 82 E-0 7 NO DATA NO DATA NO DATA LT E-24 UR 85 NO DATA NO DATA 1.94 E-0 8 NO DATA NO DATA NO DATA LT E-24 NB 86 NO DATA 1.10E-04 8 40E-05 NO DATA NO DATA NO DATA 4.35E-06 R8 88 NO DATA 4.98E-07 2.73E-01 NO DATA NO DATA NO DATA 4.85E-07 RD 89 NO DATA 2.86E-07 1.9 7 E-0 7 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA

7. 2 0E-0 5 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.05E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 NO DATA

1. 8 t E-0 6 NO DATA NO DATA NO DATA 5.92E-05

$R 92 1.92C-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA

2. 3 s E-0 9 NO DATA NO DATA NO DATA 1.20E-04 Y 9tm 8.10E-10 NO DATA 2.76E-tt NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.0tE-08 NO DATA NO DATA NO DATA 6.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 Y 93 2.43E-08 NO DATA 6.62C-10 NO DATA NO DATA NO DATA 1 12E-04 2R 95 2.06E-07 5.02E.08

3. 56 E-0 8 NO DATA 5.4tE-08 NO DATA 2.50E-05 (R 97 1.48E-08 2.54E-09 1.16E-09 NO DATA 2 56E-09 NO DATA 1.62E-04 NB 95 4.20E-08 t.71E-08

1. 03E-0 8 NO DATA 1.74k-08 NO DATA 1.46E-05 MO 91 NO DATA 1.6C2-05 6.63E-06 NO DATA 5.08E-05 No DATA t.12E-05 fC 9?*

1.92E-09 3 96E-09 5.10E-06 NO DATA 4.26k-08 2.07E-09 1.15E-06

OM12D: OI Page : 21 Rev. : 0 Table 2.3-8 (Cont.) Ingestion Dose Factors for Infant (mrem /pci ingested) NUCLICE SONE liver T.000Y THYROID K10NEY LUNG Gl.LLI IC101 2.27E.09 2 86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 NO DATA

4. oSE -0 7 NO DATA 3.08E-06 NO DATA 1.80E-05 RUIOS 1.36E-07 NO DATA

4. 5 3 E -0 8 NO DATA 1.00E-06 NO DATA 5.41E-05 RU106 2 4tE-05 NO DATA 3.01 E.0 6 NO DATA 2.85E-05 NO DATA 1.83E-04 AG110M 9;96E-07 7.27E-0T 4.81E-07 NO DATA 1 04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06

3. t > E-0 6 7.84E-06 NO DATA NO DATA 1.11E-05 TE127M 5.85E-05 1 94E-05 7.08E-06 1.69E.05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06 3 35E.07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129N 1.00E-04 3 43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E.05 TE129 2.84E.07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 'NO DATA 2.27E-05 TE131P 1.52E-05 6.12E-06 5.05E-06 1.24E.05 4.21E-05 NO DATA 1.03E.04 TE131 1 76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 1 130 6.00E-06 1.32E-05

5. 30E-0 6 1.48E-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.2 3E.05 1.86E-05 1 39E-02 4.94E-05 NO DATA 1 51E-06 I 132 1 66E-06 3 37E-06 1 20 E-0 6 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1 2SE.05 1 82E.05 5.33E-06 3.J1E-03 2.14E-35 NO DATA 3.08E-06 I 134 8 69E-07. 1 78E.06

6. 3 3 E-0 7 4.15E-05 1.99E.06 NO DATA 1.84E-06 1 135 3 64E-06 7.24E-06 2 64E.06 6.49E-04 8.07E-06 NO DATA 2.62E-06 C5134 3.77E-04 7.03E-04 7.10 E-0 5 NO DATA 1.8tE-04 7.42E-05 1.91E-06 C1136 4.59E-05 1 35E-04

5. 04 E-0 5 NO DATA 5.38E-05 1.10E-05 2.05E.06 C5137 5.22E-04 6.11E-04 4.13 E-0 5 NO DATA 1.64E-04 6.64E-05 1.91E-06 C5138 4.81E-07 7.82E-07 3.79E-0 7 NO DATA 3.90E-07 6.09E-08 1.25E.06 BA139 8.81E-07 5.84E-10

2. 5 5 E-0 8 NO DATA 3.StE-10 3 54E-10 5.58E-05 8A140 1 71E-04 1 71E-07 8.81E-06 NO DATA 4.06E-08 1 05E-07 4.20E-05 RA141 4.25E-07 2.912 10 1.346-08 NO DATA 1.75E-10 1.7FE-to 5.19E-06 BA142 1.84E-07 1 536 10 9.06E-09 NO DATA 8.81E-11 9.26E-Il 7.59E-07 LA140 2.1tE-08 8.32E-09 2.14 E -0 9 NO DATA NO DATA NO DATA 9.77E-05 LA142 1 10E.09 4.04E.10 9.6tE-L1 NO DATA NO DATA NO DATA 6.86F-05 CE141 7.8FE.08 4.80!-08

5. 65 E -0 9 NO DATA 1.48E-06 NO DATA 2.48E-05 o

CE143 1 48E-08 9.82E.06 1.17 E-0 9 NO DATA 2.96E-09 NO DATA 5.73E-05 CEt44 2 98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.7tE-04 PR143 8 13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E.05 PR144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84k.tl NO DATA 4.93E-06 N0147 5 53E-08 5.68E.08

3. 4 8 E -0 9 NO DATA 2.196-08 NO DATA 3.60E 05 w 187 9.03E.07 6.28E-07 2.17 E -01 NO DATA NO DATA NO DATA 3.69E-05 NP239 1 11E-08 9.93E-10 5.616 10 No UATA 1.98E-09 NO DATA 2.87E-05 l

c-OM12D: ODCM Page : 22 Rev. : 0 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground (mrem /h per pCi/m ) Element Total Body SkM H-3 0.0 0.0 C-14 0.0 0.0 NA 24 2.50E-08 2.90E-08 p.32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn 54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 7.00E-09 8.20E-09 Co-58 Co-60 1.70E 08 2.00E-08 0.0 0.0 Ni-63 3.70E-09 4.30E-09 Nr 65 1.50E-09 1.70E-09 N~f5 4.00E-09 4.60E-09 4 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E 08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 $r-89 5.60E-13 6.50E-13 $r-91 7.10E-09 8.30E-09 $r-92 9.00E-09 1.00E 08 y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 .Y.91 2.40E-11 2.70E-11 y-92 1.60E 09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E 09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te 127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te 129M 7.70E-10 9.00E-10 Te 129 7.10E-10 8.40E 10 Te-131M 8.40E 09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te 132 1.70E 09 2.00E-09 i i i t

c OM12D: ODCM Page : 23 Rev. : 0 Table 2.3-9 (Cont.) External Dose Factors for Standing on Contaminated Ground 2 -(mrem /h per pCi/m ) Element Total Body Skin 1-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E 08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E 08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E 08 2.40E-08 Sa-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 84-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E La-140 1.50E-08 1.70E 08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E 09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.0CE-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 i i t l l t

OM12D: ODCM Page : 24 Rev. : 0 Table 2.3-10 Transit Times Required for Nuclides to Reach the Point of Exposure (t ) Maximum Exposed Average Exposed Individual Individual

Eventual transit time for water ingestion 12 h 24 h Eventual transit time for fish ingestion 24 h 168 h Eventual ~ transit time for shore exposure 0h 0h
for population dose calculations Table 2.3-11 Usage Factors (U, )

Maximum Exposed Average Exposed Individual Individual

Water ingestion (1/yr) Adult 730 370 Water ingestion (1/yr) Teen 510 269 Water ingestion (1/yr) Child 510 260 Water ingestion (1/yr) Infant 330 Fresh water fish ingestion (kg/yr) Adult 21 6.9 Fresh water fish ingestion (kg/yr) Teen 16 5.2

' Fresh water fish ingestion (kg/yr) Child 6.9 2.2 Fresh water fish ingestion (kg/yr) Infant Shore exposure (h/yr) Adult 12 8.3 Shore exposure (h/yr) Teen 67 47 Shore exposure (h/yr) Child 14 9.5 Shore exposure (h/yr) Infant

for population dose calculations

r OM12D: ODCM 1-Page : 25 Rev. : 0 l - 3.'0 CASEOUS EFFLUENTS There are four environmental release points for gaseous effluents used for Unit 1 operation of Perry Nuclear Power Plant: Heater Bay / Turbine Building Vent, Offgas Vent Pipe, Unit I and Unit 2 = Vents. Radiological releases from each vent will be monitored by a noble gas radiation monitor. All gaseous effluent releases from PNPP will be continuous i releases. Containment /drywell purges and vents will be considered periods of increased radiological release as they are vented through the Unit 1 concurrent with normal, continuous releases. .All releases are considered to be long-term, i.e., greater than 500 hours per year, and ground level. Containment /drywell purge and vent will be limited to 3000 hours per year during operational conditions 1, 2, and 3 (power operation, startup, and hot shutdown). 3.1 Monitor' Alarm Setpoint Determinatio'n the following calculation methods provide a means of determining the high alarm setpoint-(HSP) and the alert setpoint (ASP) to ensure' compliance with 10CFR20 dose rate limits to areas at or 1 beyond the site boundary for the noble gas channels of the 'following monitors: 1. Heater Bay / Turbine Building Vent Radiaton Monitor (ID17KS56) i 2. Offgas' Vent Pipe Radiation Monitor (ID17K836) 3. UI Vent' Radiation Monitor (1D17K786) 4. U2 Vent Radiation Monitor.(2D17K786). 4 The Unit 2 Vent Radiation' Monitor is included in the operation of Unit 1 methodology.because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intermediate Building ventilations are exhausted through the Unit 2 Vent. The High Alarm Setpoint (HSP) for each release point radiation monitor will be set at 70 percent of the 10CFR20 dose rate limits and the alert-setpoint -(ASP) will be set at 10 percent of these Itaits. NOTE: The values of 70 percent-for the HSP and 10 percent for .the ASP are set as' fractions of the total activity that may be released via the monitored pathways to ensure that the site boundary done rate limits are not exceeded. Any single ASP can be exceeded without the 10CFR20 limits being exceeded.- If any two monitors exceed the ASP or t e. 6 -r -+r -m. ,,,-.-m.-~,m.. m -m.----. c.,,v-, re.-,.re., ,. -ve wir,v, ,,--www-r+=ce-t-w w e e4 w w w

OM12D: ODCM Page : 26 Rev. : 0 any one exceeds the HSP it is possible that the limits have been exceeded. This procedure determines the monitor alarm setpoints that indicate if the dose rate beyond the site boundary due to noble gas radionuclides in gaseous effluent released from the site exceeds 500 mrem / year to the whole body or 3000 mrem / year to the skin. 3.1.1 Determination of the " Mix" (Noble Gas Radionuclide Cocposition) of the Caseous Ef fluent Determine the gaseous source terms that are a. representative of the " mix" of the gaseous effluent. Gaseous source terms are the concentrations of the noble gas radionuclides in the effluent as determined by routine analysis of the various sources of gaseous effluents. During the early period of operation, before a sufficient operational effluent source term data base has been obtained, source terms will be those generated by the GALE code, Revision 0 for PNPP. b. Determine the fraction of the total radioactivity in the gaseous effluent for each noble gas radionuclide in the gaseous effluent. AI (3.1-1) S = g l[, Af i Where: S' = the fraction of the total for radionuclide i in the effluent; A = the activity of radionuclide i in the gaseous effluent. NOTE: If the activity of a noble gas radionuclide is below the lower limit of detection the noble gas radionuclide shall not be included as a source term in this setpoint calculation. 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 500 (3.1-2) Qb " IAIN) ){ K S i i

OM12D: ODCM Page : 27 Rev. : 0 Where. Q = the maximum acceptable total activity release rate b of all noble gas radionuclides in the effluent (for whole body exposure), in uCi/s; K = the total body dose factor for a semi-infinite g cloud of radionuclide 1 (includes the attenuation 2 of Sg/cm of tisgue) from Table 3.1-1, in (mrem /yr)/(uCi/m ); S = the fraction of the total for radionuclide i, as g per Section 3.1.1; X/Q=thehighestannualaveragerelativedispersgonfgetor for areas at the site boundary = 6.53 x 10- s/m (from Appendix A NE direction at the site boundary); NOTE: The dispersion parameters used in these calculations are the highest calculated site boundary values for any of the land-based sectors. AT PNPP the site boundary locations in the following sectors are over water only: N, NNE, NNW, NW, W. WNW. 500 = the whole body dose rate limit, in mrem /yr. 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Caseous Effluent Based on Skin Dose Rate Limit 3000 (3.1-3) Q, = (x/Q) 7(L1 + 1.1 M ) s1 1 i Where: Q = the maximum acceptable total activity release rate s of all noble gas radionuclides in the effluent (for skin exposure), in uC1/s; L = the beta skin dose factor for a semi-infinite cloud I of radionuclide 1 (includes attenuation by3)he outer t " dead" layer of skin), in (mrem /yr)/(uCi/m ; M = the gemma air dose factor for a uniform semi infinite 5 g cloud of radionuclide i, in (mrad /yr)/(uCi/m ); ( l

OM12D: ODCM Page : 28 Rev. : O S = the fraction of the total for radionuclide 1, as per g Section 3.1.1; X/Q = the highest annual average relative disgersion factor, -D as per equation 3.1-2 = 6.53 x 10 s/m ; 1.1 = the air dose to tissue dose equivalent conversion factor, in mrem / mrad; 3000 = the skin dose rate limit, in mrem /yr. (L + 1.1 M ) values are shown in Table 3.1-1. g 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent -3 2.12 x 10 Q (3.W C = g f Where: 1 C = the maximum acceptable total radioactivity concen-g tration of all noble gas radionuclides in the effluent, in uCi/ce; f = the actual flow at the point of relegse from the respective flow rate recorders, in f / min; NOTE: When actual flow rates are not available, the following design flow assumptions will be used: Vent Flow Rate ft / min - Heater Bay / Turbine Building 360,000 (summer) 198,000 (winter) - Offgas 16,700 - Unit i 124,500 - Unit 2 (Control Complex and Intermediate Building Ventilations) 42,400 and Q, calculated in equations Q* = the smaller of Q3.1-2 and 3.1-3,brespecEively, in uC1/s; -3 2.12 x 10 = the conversi n factor to convert (uCi/s)/(f t / min.) to uCi/cc.

OM12D: ODCM Page : 29 Rev. : 0 3.1.5 Determination of the Maximus Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides (3.1-5) CR = 0.8 (C ) (E,) g Where: the calculated monitor count rate above background CR = attributed to noble gas radionuclides,-in net epm; the maximum acceptable radioactivity concentration, C = t as per equation 3.1-4, in uCi/ce; the detector efficiency of the monitor for the " mix" E = of noble gas radionuclides in the effluent, in cpm /(uCi/cc) the total uCi/cc concentration divided into the net = monitor count rate taken at the time the sample was taken; during the early period of operation, before a sufficient operational effluent source term data base has been obtained, the value will be calculated using monitor calibration data; 0.8 = an engineering safety factor. 3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP = 0.70 CR -+ BG (3.1-6) Where: HSP = the high alarm setpoint (including background), in cpm; BG = the background count rate due to internal contamina-tion and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in epm; the calculated monitor net count rate, as per CR = C equation 3.1-5, in epm; 0.70 = the fraction of the maxinum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.

OM12D: ODCM Page : 30 Rev. : 0 3.1.5.2 Determination of the Monitor Alert Serpoint ASP = 0.10 CR + BG (3.1-7) Where: ASP = the alert setpoint (including background), in cpm; BG = the background count rate due to internal con-tamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air; CR = the calculated monitor net count rate, as per equation 3.1-5, in cpm; 0.10 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways. +

OM: 2D: ODCM Page : 31 Rev. : 0 Table 3.1-1 Whole Body and Skin Dose Factors Total Whole Body Total Skin Dose Factor (mremf+r/ ph)i/m ) (L 1.lM Dose Factor y Radionuclide (K } (mrem /yr/p Ci/m ) g Kr-83m 7.56E-02 2.12E+01 Kc-85m 1.17E+03 2.81E+03 Kr-85 1.61E+01 1.36E+03 Kr-87 5.92E+03 1.65E+04 Kr-88 1.47E+04 1.91E+04 Kr-89 1.66E+04 2.91E+04 Xe-131m 9.15E+01 6.48E+02 Xe-133m 2.51E+02 1.35E+03 Xe-133 2.94E+02 6.94E+02 Xe-135m 3.12E+03 4.41E+03 Xe-135 1.81E+03 3.97E+03 Xe-137 1.42E+03 1.39E+04 Xe-138' 8.83E+03 1.43E+04 Ar-41 8.84E+03 1.29E+04 r ,-w.- - - -. c

OM12D: ODCM Page : 32 Rev. : 0 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are conservatively applied on an instantaneous basis at the controlling location. 3.2.1 Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem /yr to the total body and 3000 mrem /yr to the skin. Only the external dose pathway will be considered for noble gases. Because all gaseous effluent releases from PNPP are considered ground level, the controlling location for these dose rate limits is the site boundary location with the highest relative dispersion factor (X/Q) for the period of release. (See Appendix A for elaboration.) The alarm setpoint determinations discussed in the previous i section should ensure compliance with these dose rate limits. l However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents will be calculated. The calculations will be based on the results of analyses obtained pursuant to the PNPP Technical Specifications. 3.2.2 Radionuclides, Particulates, and Other Radionuclides The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days is limited to 1500 mrem /yr to any organ by PNPP Technical Specifications. The calculation of dose rate from these radionuclides will be performed weekly based on results of analyses obtained persuant to those Technical Specificatons. The controlling location for this limit is a function of the noble gas controlling location, i.e., the location of the highest relative deposition (D/Q) for the period of release (See Appendix A), as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of residences in each sector, and garden and farm animal locations.

OM12D: ODCM Page : 33 Rev. : 0 3.2.3 Dose Rate Calculations The following is the equation used to calculate the dose rate resultant frem the release of radioactive materials in gasecus effluents to areas at or beyond the site boundary for the purpose of showigg compliance with 10CFR20. D, p = 3.15 x 10 *(X/QorD/Q)*1DF

Q (3.2-1)

Where: D = the organ j dose rate as a function of age group ajp a and pathway p, in mrem /yr; DF = the dose factor for organ type j, age group a, agjp pathway p for isotope i (see Tables 3.2-1 through 3.2-3); units and equations used (equations 3.2-2 through 3.2-6) are provided later in this sec-tion; X/Q or D/Q = the normal or depletgd relative dispersion factor (X/Q), in g/m, or relative deposi- ~ tion (D/Q), in m, at the receptor distance (see Appendix' A); I 3.15 x 10 = the conversion factor to convert (arem

uCi)/(Ci
s) to mrem /yr; Q = the release rate of isotope 1, in uCi/s g

= 472 C f g Where: C = the concentration of radionuclide i in the gaseous g effluent, in uCi/cc; f=tgegaseouseffluentflowrateduringtherelease,in f / min; 3 472 = the conversion factor (cc/f )/(s/ min). The following relationships are used to derive the dose factors (DF for noble gases, tritium, radioiodines and particulate $dE)edinequation3.2-1. I

01112D: ODC11 Page : 34 Rev. : 0 Total Body Dose Factors from Exposure to a Semi-Inifinite a. Plume T DF =S X DFB (3.2-2) p f

4here:

T DF = the total body factor due to immersion in a g semi-infig)ite cloud of radionuclide i, in (mrem

m /(Ci
s);

DFB = the total body gamma dose factor for a semi-infinitecloudofradionuclideiyhich includestheattenuationof5gfem of tissue from Table 3.2-4, in (mrem

m )/(pCi
yr);

S = the attenuation factor that accounts for the F dose reduction due to the shielding provided by residential structures, dimensionless: maximum exposed individual = 0.7, population dose 0.5 (RG 1.109); = the annual avergge concentration of radionuclide Xf i in air (pCi/m ), for a ungt release rage (Ci/yr) and a unit X/Q (s/m ), in (pCi/m )/ 3 (Ci/yr)(s/m ).

l OM12D: ODCM Page : 35 Rev. : 0 b. Skin Dose Factors for Exposure to a Semi-Infinite Plume S DF =X (1.1 S DF{ + DFS ) (3.2-3) f p Where: S = the skin dose factor due to immersion in g) semi-DFf infinite cloud of radionuclide i, (mrem

m /

(Ci

s);

DF = the gamma air dose factor for a uniform semi-infinite cloud of rgdionuclide i, from Table 3.2-4, in (mrad

m )/(pci
yr);

DFS' = the beta skin dose factor for a semi-infinite cloud of radionuclide i (includes attenuation by the outer " dead" layer of skin), from Table 3.2-4 in (arem

m )/(pci
yr);

S = the attenuation factor that accounts for the dose F reduction due to the shielding provided by resi-dential structures, dimensionless: maximum exposed individual = 0.7, population dose = 0.5 (RG 1.109); =theannualaverggeconcentrationofradionuclide Xg i in air (pCi/m ), for a ungt release raje (C1/gr) and a unit X/Q (s/n ), in (pCi/m )/(Ci/yr) (s/m ); 1.1 = the air dose to tissue dose equivalent conver-sion factor, in mrem / mrad. Dose Factors from External Irradiation from Radionuclides c. Deposited onto the Ground Surface G G DF = 8760 C DFG S (3.2-4) f F Where: G DF = the dose factor for radionuclide i to organ Id -j~resulting from exposure to radionuclides i. deposited ne the ground surface, in 2 (mrem

m )/Ci; i

G C = the ground plane concentration (pCi/m ) of f f l l

OM12D: ODCM Page : 36 Rev. : 0 radionuclideiforaunitreleaserate(Ci/yg), andaunig)D/Q,relatiyegounddeposition(m in (pCi/m /(Ci/yr)(m~ ); DFG = the open field ground plane dose conversion factor for organ j from rgdionuclide i, from Table 3.2-5, in (mrem

m )/(pci
hr);

S = the attenuation factor that accounts for the F dose reduction due to the shielding provided by residential structures, dimensionless: maximum exposed individual = 0.7, population dose = 0.5 (RG 1.109); 8760 = the number of hours in a year. d. Dose Factors from Inhalation of Radionuclides in Air A (3.2-5) DF,g3 = DFA,f) R, Xf Where: A DF = the dose factor for radionuclide i to organ aij j of an individual in age g3oup a due to inhalation, in (mrem

m )/(Ci
s);

DFA = the inhalation dose factor for radionuclide aij i, organ j, and age group a (the value for skin is assumed to be 0), from Tables 3.2-6 through 3.2-9, in mrem /pci; R =theannualairintakeforindivijualsinage group a, from Table 3.2-14, in m /yr; = the annual averg)ge concentration of radionuclide Xf i in air (pCi/m,foraungtreleaserage (Ci/yr) and a unit X/Q (s/n ), in (pCi/m )/ 3 (Ci/yr)(s/m ).

OM12D: ODCM Page : 37 Rev. : O e. Dose Factors from the Ingestion of Atmospherically Released Radionuclides in Food D F F L L M M V V C ] (3.2-6) DF, = DFI [U, Cg + U,f C + U, C + U, fy Where: D DF = the dose factor for radionuclide i to organ

Id j of an individual in age group a from the ingestion of meat, Icafy vegetables, milk, and produce (non-leafy vggetables, fruits, and grains) in (mrem
m )/Ci, or jn the cases of H-3 and C-14 in (mrem
m )/(Ci
s);

F L M V C,C,C,C = the concentrations of radionuclide i in meat, leafy vegetables, milk, and produce, respectively (pCi/kg or pCi/1) for a unit release rate (Ci/yr)andaunitD/g), relative ground deposition (m- , or in cases of H-3 and C-14, a unit X/Q, relajiveground-levelconcentyation (s/m ), in -(pCi/kg)(Ci/gr)(m~ ) ) or (pCifl)/ or (pCi/kg})/(Ci/yr)(S/mor (pCi/1)(Ci/yr)(s/m ) (Ci/yr) (m _ DFI = the ingestion dose factor for radionuclide

3 1, organ j, and age group a, from Tables 3.2-10 through 3.2-13, in mrem /pci; f,f = the respective fractions of the ingestion y

rates of leafy vegetables and produce that are produced in the garden of interest, 1.0 and 0.76 respectively (RG 1.109); F L M V U,U,U,U = the annual intake (usage) of meat, 8 leafy vegetables, milk, and produce respectively, for individuals in age group a, from Table 3.2-15, in kg/yr or 1/yr. >. ~. -

OM12D: ODCM Page : 38 Rev. : 0 Table 3.2-1 Organ used for Gaseous Effluent Dose Calculations 1. Bone 2. GI Tract 3. Kidney 4. Liver 5. Lung 6. Thyroid 7. Total Body 8. Skin Table 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 1. Adult (17 yr and older) 2. Teen (11-17 yr) 3. Child (1-11 yr) 4. Infant (0-1 yr)

l i i ~ OM12D: ODCM [ Page : 39 L-Rev. : 0 l [ Table 3.2-3 Gaseous Effluent Dose Pathways [.- 1. Plume 2. Ground Shine l_ l-3. Vegetables 4. Meat i ? I 5. Cows j 6. Goats 7. Inhalation t.' s i' I i i i i t t

OM12D: ODCM Page : 40 Rev. : 0 Table 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases DFB

Nuclide DFS
DF,f y

g 1.93E-05 7.56E-08 Kr-83m Kr-85m 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.34E-03 1.72E-05 1.61E-05 Kr-87 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.29E-03 1.63E-02 1.56E-02 Xe-131m 4.76E-04 1.56E-04 9.15E-05 Xe-133m 9.94E-04 3.27E-04 2.51E-04 Xe-133 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.11E-04 3.36E-03 3.12E-03 Xe-135 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.13E-03 9.21E-03 8.83E-03 Ar-41 2.69E-03 9.30E-03 8.84E-03 mrem

m pC1
yr 3

mrad

m pC1
yr

.s OM12D: ODCM Page : 41 Rev. : 0 Table 3.2-5 External Dose Factors for Standing on Contaminated Ground (crem/hr per pCi/m ). Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-8D 1.70E-08 2.00E-08 Ni-63 0.0 0.0 3.70E-09 4.30E-09 Nr-65 1.50E-09 1.70E-09 Cu-64 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10' 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 4 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110N 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E 11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09

r OM12D: ODCM Page : 42 Rev. : 0 Table 3.2-5 (Cont.) External Dose Factors for Standing on Contaminated Ground (mrem /hr per pCi/m ) Element Total Body Skin I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133-3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 B4-135 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 '1,00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Mp-239 9.50E-1C 1.10E-09 b e h' J

OM12D: ODCM Page : 43 Rev. : 0 Table 3.2-6 Inhalation Dose Factors for Adult (mrem /pCi inhaled) NUCLIOE BONE liver T.R00Y THYROIO K10NEY LUNG GI-LL1

== __________.____________= H 3 NO DATA 1.58E-07

1. 5 8 F-0 7 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07

4. 2 6E-0 7 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06

1. 2 8 E -0 6 1.28E-06 1.28E-06 1.28E-06 1.28E-06

==_____ _ _.. = = = _ _ P 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NC OATA NO DATA 1.08E-05 CR 51 NO DATA NO DATA 1.25 E-0 8 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 T.8FE-0T NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 FE 55 3.0TE-06 2.12E-06 4.91E-0 7 NO OATA-NO DATA 9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1 32E-06 NO DATA NO DATA 1 27E-04 2.35E-05 CD 58 NO DATA 1.98E-07

2. 59 E -0 7 NO DATA NC OATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.44E-06 1 85E-06 NO DATA NO DATA 7.46E-04 1.56E-05 N163 5.40E-05 3.93E-06

1. 81 E -0 6 NO DATA NO DATA 2.23E-05 1.67E-06

= ____. - __=_ -. _ _ _ _ _ = NI 65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.00E-07 1.54E-06 CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 _ _ = _. - -= _.==__.___= ZN 69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5 27E-12 1.15E-07 2.04E-09 6R 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 BR 84 NO DATA NG DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 8R 85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA

LT E R8 86 NO DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 RD 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 R8 89 NO DATA 3.20E-08 2.12 E-0 8 NO DATA NO DATA NO DATA 1.16E-21 SR 89 3.80E-05 NO DATA

1. 09 E-0 6 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05

=_

= SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO CATA 5.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA

7. 01 E-0 9 NO DATA NO DATA 2.12E-05 6.32E-05

__________.=_ = Y 91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.78E-05 NO DATA

1. 5 5 E-0 6 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3 77E-11 No DATA NO DATA 1.96E-06 9.19E-06

_._____==__ =.__==_. =__ _= =____.________.______=_ Y 93 1.18E-08 NO DATA 3.2 6E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.88E-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1.516-08

2. 8 7E-0 9 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07

OM12D: ODCM Page : 44 Rev. : 0 Table 3.2-6 (Cont.) Inhalation Dose Factors for Adult (mrem /pCi inhaled) ? NUCL10E BONE liver T.00DY THYROID K10NEY LUNG GI-LL1 ..--.------...........-..== TC101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 f.36E-21 .RU103 1.91E-07 NO DATA

8. 2 3 E -0 8 NO DATA 7.29E-07 6.31E-05 1.38E-05 RU105

,9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1 37E-06 6.02E-06 2 ~~ ~ ~ ~~ ~ ~~ ~ ~~ 8 64E 05 5b bIi5~~~550lE-05 50 0ATA i 6 5205 555i[-b3 5$5452b4 -kU106 AG110M 1.35E-06 1.25E-06 7.43C-07 NO DATA 2.46E-06 5.79E-04 3.785-05 TE125N 4.27E-07 1 98E-07 5.84E-09 1.31E-07 1.55E-06 3.92E-05 8.83E-06 ...........=_ __=-= =.---- = - - = = - - -__==. TE127M 1.58E-06 7.21E-07

1. 96 E -0 7 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.035-11

3. 8 7E-11 1 32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M 1.22E-06 5.84E-07 1.98 E-0 7 4.30E-07 4.57E-06 1.45E-04 4.79E-05

= TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07, 1.96E-08 TE131N 8.74E-09 5.45E-09 3.63F-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132 3.2SE 08 2.69E-08

2. 02 E-0 8 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 1 68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 1 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07

=...--.--. 1 132 1 4SE-07 4.07E-07

1. 4 5 E-0 7 1.43E-05 6.48E-07 NO DATA 5.08E-08 1 133 1.08E-06 1 85E-06 5.65E-07 2.69E-04 3.23E-06 NO OATA 1.11E-06 1 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10

=-_ ! 135 3.35E-07 8.73E-07 3.21E-07 5.6CE-05 1.39E-06 NO DATA 6.56E-07 C5134 4.66E-05 1.06E-04. 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 C5136 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 =

===_ 05137 5.98E-05 7.76E-05

5. 3 5 E-0 5 NO DATA 2.78E-05 9.40E-06 1.05E-06 C5138 4.14E-08 7.76E-08 4.05 E-0 8 NO DATA 6.00E-08 6.07E-09 2.33E-13 8A139 1.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 BA140 4.88E-06 6.13E-09 5.21 E-0 7 NO DATA 2.09E-09 1.59E-04 2.73E-05

( nA141 1.25E-11 9.41E-15 4.20E NO DATA 8.75E-15 2.42E-07 1 45E-17 8A142 3.29E-12 3.38E-15 2.07E-Il NO DATA 2.86E-15 1.49E-07 1.96E-26 I' LA140 4.30E-08 2.17E-08 5.73E-09 NU OATA NO DATA -1.70E-05 5.73E-05 L A142 8.54E-11 3.88E-11 9.64E-12 NO DATA NO DATA 7.91E-07 2.64E-07 i-CE141 2.49E-06 1.692-06

1. 91 E-0 7 NO DATA 7.83E-07 4.52E-05 1.50E-05

..--.=_-

==--

CE143-2.33E-08 1.72E-08 1.91E-09 NO DAT4 7.60E-09 9.97E-06 2.83E-05 -CE144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1 02E-04 PR143 1.17E-06

4. 69E-07 ' 5. 80E-0 8 NO DATA 2.70E-07 3.51E-05 2.50E-05

- _ _ - -.... -... - - -. - - -.. - - - - - - -....... - - - = = - - = =. - - - ---..=__ .=__ t ~ PR144 3.76E-12 1.56E-12

1. 91 E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 N0147 6.59E-07 7.62E-07

4. 56 E -0 8 NO DATA

'4.45E-07 2.76E-05 2.16E-05 W 187-1.06E-09 8.856-10 3.10 E-10 NO DATA NO DATA 3 63E-06 1.94E-05 l NP239 2.37E-08 2.82E-09

1. 5 5 E-0 9 NO DATA 8.75E-09 4.70E-06 1.49E-05

\\ l-i 1-l r i l L

OM12D: ODCH Page : 45 Rev. : 0 Table 3.2-7 -Inhalation' Dose Factors for Teenager (mren/pci inhaled) NUC L I CE ' 80NE LIVER T. BODY THYROID K1DNEY LUNC G1-tL1 H 3 NO DATA-1.59E-0F 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3 25E-06 6.C9E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1 72E-06 1.72E 1. 72 E-0 6 1.72E-06 1.72E-06 1.72E-06 1 72E-06 P 32 2.36E-04

1. 3 7C-0)

8. 9 5 E -0 6 NO DATA NC DATA NO DATA 1.16F-05

.40 OATA NO DATA 1.69F-08 9.37E-09 3.642-09 2.62E-06 3.75E-07 CR 51 FN 54 No DATA 6.396-06 1.0)E-06 NO DATA 1.59E-06 2 48E-04 8.35E-06 ... =--__ -------------................. --.--.........--.----.......------. MN 56 NO DATA 2.124-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1 99E-06 4.622-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 CD SS NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1 68E-04 1.19E-05 CO 60 NO DATA 1.8?E-06 2 48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63. 7 25E-05 '5.43E-06 2.47E-06 NO DATA NO DATA 3 84E-05 1.77E-06 -== N1 6$ 2.73E-10 3.o6E-11 1.59E-11 NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.546-10 1.06E-10 NO DATA 8.01E-10 1 39E-06 7.68E-06 IN 65 -4.82E-06 1.67E-05

7. 80 E-0 6 NO DATA 1.08E-05 1.55E-04 5.83E-06

== (N 69 6.04E-12 1.15F-11

8. 0 7E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 AR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA N0' DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24

--...-...............__= 18R 85 NO DATA NO DATA 2.29E.09 NO DATA NO' DATA NO DATA LT E-24 R8 86-NO DATA 2.38E-05 1.0$E-05 NO DATA NO DATA NO DATA 2.21E-06 RS 88 NO DATA 6.82E-08 3 40E-0 8 NO DATA NO DATA NO DATA 3.65E-15 R8 89 NO DATA 4.40E-08

2. 91E-0 8 NO DATA NO DATA NO DATA 4.22E-17

-SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 -NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO CATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1 19E-09 NO CATA 5.08E-11 NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1 00 E -0 8 NO DATA NO DATA 3 66E-05 6.99E-05 _=__==.....--..........--.-~.---.-...-.....--...------------- Y 91M 4.63E-11 NO DATA 1.77E-12 NO DATA .NO DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06

2. 0.6 E-0 5 Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05

'2R 95 1.82E-05 5.73E-06

3. 94 E-0 6 NO DATA 8.42E-06 3.36E-04 1.86E-05 2R 17 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1 62E-05 7.88E-05

_= _:----. --..-- --.............--..---...--......--...... NB 95 2.32E-06 1.29E-06

7. 08 E-0 7 NO DATA 1.25E-06 9.39E-05 1.21E-05 MO 99 t40 D AT A 2.11E-08 4.03E-09 40 DATA 5.14E-08 1 92E-05 3.36E-05 TC 99e 1.73E-13 4.83E-11 6.24E-12 NO DATA 7.20E-12 1 44E-0T 7.66E-07

_ =. - - - -. - - - -......... - -.... - -...... - -... - -..... - -.. e

OM12D: ODCM Page : 46 Rev. : 0 Table 3.2-7 (Cont.) Inhalation Dose Factors for Teenager (mrem /pCi inhaled) e' NUCLICE BONE Liv 6R T.800Y THYROIO KIONEY LUNG CI-LLI

=

TC101 7.40E-15 1.0bE-14 1.03E-13 NO DATA 1 90E-13 8.34E-08 1.09E-16 HU103 2.63E-07 NO DATA 1.12 E-0 7 NO DATA 9.29E-07 9.79E-05 1.36E-05 3U105 1.40E-10 NU OATA 5.42 E -11 NO DATA 1.76E-10 2.27E-06 1.13E-05 .._____.....= RU106 1.23E-05 NO DATA

1. 5 5 E-0 6 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG110M 1.73E-06 1.640-06 9.99 E-0 7 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE125M 6.10E-07 2.80E-01 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE127M 2.25E-06 1.020-06

2. 7 3 E-0 7 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14F-10 5.52C-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05

.TE129M 1.74E-06 8.230-0T 2 81E-0 7 5.72E-07 6.49E-06 2.47E-04 5.06E-05 __..=- = TE129 8.87E-12 4.22E-12 2.20E-12 6.4RE-12 3.32E-11 4.12E-07 2.02E-07 TE131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.04E-12 6.30E-1? 1.55E-12 7.72E-12 2.92E-07 1.89E-09 =_- .TE132 4.50E-08 3.o3E-08

2. 74 E-0 8 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96 E-0 7 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06

3. 30 E-0 6 1.83E-03 1.05E-05 NO DATA 8.11F-07 1 132 1.99E-07 5.47E-07

1. 9 7E-0 7 1.89E-05 8.65E-07 NO DATA 1.59E-07 1 133 1.52E-06 2.36E-06

7. 78 E-0 7 3.65E-04 4.49E-06 NO DATA 1.29E-06

! 134 1.11E-07 2.90E-07

1. 05 E-0 7 4.94E-06 4.58E-07 h0 DATA 2.55E-09

....___...__.......=== _===== I 135 4.62E-07 1.1SE-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 C5134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 C5136 6.44E-06 2 42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 C5137 8.38E-05 1.06E-04

3. 89 E-0 5 NO DATA 3.80E-05 1.51E-05 1.06E-06 C5138 5.82E 1.07E-07

5. 5 8 E -0 8 NO DATA 8.28E-08 9.84E-09 3.38E-11 8A139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 8.06E-07

__....__.__.=___===___.......................__..._____..__.____....____ -__ SA140 6.84E-06 8.38E-09

4. 40E-0 7 NO DATA 2.85E-09 2.54E-04 2.86E-05

- B A 141 1.T8E-11 1.s2E-14 5.91E-13 NO DATA t.23E-14 4.1tE 9.33E-14 154142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LAt40 5.99E-08 2.95C-08 7.82C-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA142 1 20C-10 5.31E-11 1.32E-l1 NO DATA NO DATA 1.27E-06 1.50C-06 CEt41 3.55E-06 2.37C-06

2. 71 E-0 7 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.42E-08

2. 70 E -0 9 NO DATA 1.086-08 1.63E-05 3.19E-05 CE144 6 11E-04 2.53E-04

3. 2 8 E-0 5 NO DATA 1.516-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E 2.19E-07 2.94E-14 N0147 9.83E-07 1.07E-06

6. 41 E-0 8 NO DATA 6.29E-07 4.65E-05 2.28F-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 pP239 4.23E-08 3.99E-09

2. 21 E-0 9 NO OATA 1.25E-08 A.11E-06 1.65E-03

r OM12D: ODCM Page : 47 Rev. : 0 Table 3.2-8 Inhalation Dose Factors for Child (mrem /pCi inhaled) NUCLIDE SONE LIVER T. RO DY THYR 010 KIDNEY LUNG GI-LLI H 3 NO DATA 3.04E-07 3.04E-0 7 3.04d-07 3.04E-07 3.04E-07 1.04E-07 C 14 9.70E-06 1.62E-06

1. 92 E -0 6 L.22E-06 1.82E-06 1.8?E-06 1 82E-06 NA 24 4.35E-06 4.35*-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.6TE-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.3tr-Ga 6.576-09 4.59E-06 2 93C-07 MN 54 NO DATA 1.16E-05 2.57E-Oo NO DATA 2.7tE-06 4.26E-04 6.19E-06 MN 56 NU DATA 4.48E-to 8.43E-It NO DAIA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.00E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.c4E-06 4.510-06 No DATA NO DATA 3.43C-04 1.91E-05 CO 58 NO DATA

4. 7 9E-0 7

8. 5 5 E-0 7 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05

7. 56 E-0 6 NO DATA NO DATA 7.43E-05 1.7tE-06

..___.._--===== _________.........._--_-_._____.________________..___..__ NI 65 8.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.2tE-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 2.N 6 5 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 .. ______..==__ ---__..__________.....__.___.________________.___.______... IN 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 NR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA KO DATA LT E-24 UR 84 NO DATA NU DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 Ek 5 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 RG 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 RD 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA N'O DATA 4.66E-09 5.11h-10 RB 89' NO DATA

9. 3 3E-08

7. 8 3 E-0 8 NO DATA NO DATA NO DATA SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 1.1tE-06 NO DATA 2.94E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 91F 1.37E-10 NO DATA 4.9aE-12 NO DATA NO DATA 7.60F-07 4.64E-07 Y 91 2.47E-04 NO DATA

6. 5 9 E-0 6 NO DhTA NO DATA 3.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-C6 6.46E-05

_______......._______._____..___________..t..______.____..______..____...... Y 93 5.04E-08 No DATA 1.lUE-09 NO DAf4 NO DATA 2 01E-05 1.05E-04 ZR 95 5.13E-05 1.13E-05

1. 00 E-0 5 NO DA T A 1.616-05 6.03E-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO D A ' A 1.0$E-08 3 06E-05 9.49E-05

=--..__._____............ NB 95 6.35E-06 2.48E-06

1. 77 E -0 6 NO 04? A 2.33E-06 1.66E-04 1.00E-05 MO 99 NO DATA 4.66E-08 1.15 E _0 8 NO DAlt 1.06E-07 3.66E-05 3.42E-05 TC 997 4.81E-13 9.4tC-13 1.56E-It NO DA;A 1 37E-It 2.57E-07 1.30E-06

4 OM12D: ODCM Page : 48 Rev. : 0 Table 3.2-8 (Cont.) Inhalation Dose Factors for Child (arem/pCi inhaled) WUCLt0E 80NE LIVER T.dODY THYRul0 KIONEY LUNG GI-LLI TC101 2 19C-14 2.300-t* 2 91E-13 No UATA 3.9?E-13 1.5aE-07 4.41E-09 RU103 7.SSE-07 NO DATA 2 90E-0 7 NO DATA 1.90E-06 1.79E-04 1.21E-C5 AU105 4.136-10 NU OATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU106 3 682-05 NU OAIA 4.57E-06 NO DATA 4.9FE-05 3.87E-03 1 16E-04 AG110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74L-06 1.48E-03 2.71E-05 TE125M 1.82E-06 6.295-07 2.47E-07 5.20E-07 NG DATA 1.29E-04 9.13E-06 TE127M 6.72E-06 2.31E-Oo

8. toe-07 1.64E-06 1.72E-05 4.00E-04 1 93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.9tE-09 2.71E-06 1.52E-05 4.91E-05 TEt2?P 5.19E-C6 1 85E-06 8.22E-07 1.7tE-06 1.16E-05 4{76E-04 TE129 2.64E-11 '9.45E-12 6.44C-12 1.93E-11 6.94E-11 7.91E-07 6.89E-06

. TE13tr-3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 5.87C-12 2.28E-12 -1.78C-12 4.59E-12. 1.59C-11 5.55E-07' 3 60E-07 .._-___.===_--__ --..._______...______. ___._= TE132_ l.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 2.2aE-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 1 131 1.30E-05 1.30E-05

7. 3 7 E -0 6 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07. 1.10E-06 5.01E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07

- 1 133-4.48C-06 5.49E-06

2. 0 8 E -0 6 1.04E-03 9.13E-06 NO DATA 1.48E-06

! 134 3.17E-07 5.84E-07 2 6?E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.16E-06 1.12 E -0 6 2.14C-04 3 62E-06 NO DA7A 1 20E-06 C5134 1.76E-04 2.74C-04

6. 0 7 E -0 5 NO DATA-8 93E-05 3.27E-05' 1.04E-06 L.

- C5136,1.76E-05 4.62E-05 3.14E-05 NO DATA 2 58E-05 3.93E-06 1 13E-06 C5137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.8tE-05 9.78E-07 3 C5138 1.71E-07 2.27E-07 1.50E-07 NO DATA - 1 68E-07 1.84E-08 7.29E-08 RA139 4.98E-10 2.66F-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1 56E-05 i L '0A140 2.00E-05 1.75E-08

1. t FE-0 6 NO DATA 5.71E-09 4.71E-04 2.75E 8A141 5.29E-11 2.95E-14 1 72E-12 NO DATA 2.56E-14 7.89E-07.7 44E-08 BA142 1.35E-11 9.73C-15 7.54E-13 NO DATA 7.57E-15 4.44E-07 7 41E-10

)' f LA140 't.74E-07. 6.08E-08 2 04 E-0 8 NO DATA NO DATA 4.94E-05 6.10E-05 { l LA142. 3.50E-10. 1.11E-10 -3.49E-!! NO DATA NO DATA 2.35E-06 2 05E-05 l CE141 1.06E-05 5.28E-06 7.8 3E-01 ' NO D ATA 2.3tE-06 1.47E-04 1.53E-05 m. I~ CE143 9.89E-08 5.37E-08 7.7FE-09 NO DATA 2.26E-08 3.12E-05 3 44E-05 ~ CE144 1.836-03 5.72C-04 9.77E-05 NO.0ATA 3.17E-04 3.23E-03 1 05E-04 PR143 4.99E-06 1.50E-06 2 4 7 E-0 7 NO DATA 8.11t-07 1.17E-04 2.63E-05 PR144-1.61E-11 4.996-12.8.10E-13 ' No DATA 2.64E-12 4.23E-07 5.32E, - N0147 2.92E-06 2.36E-06

1. 84 E-0 7 NO DATA 1.30E-06 ~ 8.87E-05 2 22E-05 l

- W 187 4.41E-09 2 61E-09 1.1TE-09 NO DATA NO DATA 1.11E-05 2 46E-05 NP239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1 73E-05 I' o o. l I I-t-

OM12D: ODCM Page : 49 Rev. : 0 Table 3.2-9 Inhalation Dese Factors for Infant (mrem /pCi inhaled) NUCLIDE BONE LtvER T.80DY THYR 010 KIDNEY LUNG Gt-LLI H 3 NO DATA 4.62E-07 4.62E-07 4.62F-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.S4E-06 7.54E-06

7. 5 4 E-0 6 7.54E-06 7.54E-06 7.54E-06 7.54E-06

--- _=- -

P 32 1.45E-03 8.0 3E-05 S.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA

6. 3 7E -0 8 4.11E-08 9.45E-09 9 17E-06 2.55E-07 MN 54 NO DATA 1.8tE-05 3. 56 C-0 6 NO DATA 3.56E-06 7 14E-04 5.04E-06 MN $6 NO DATA 1.10E-09

1. 5 3 E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.4tE-05 8.39E-06 2 38E-06 NO DATA NO DATA 6.2tE-05 7.82E-07

~ FE 59 9.69E-06 1.685-05 6.776-06 NO DATA NO DATA 7.2SE-04 1.77E-05

.--- -_ -=

CD $8 NO DATA

8. 7 t E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 CO 60 NO DATA 5.73E-06 ~ 8. 29 E -0 6 NO DATA NO DATA 1 49E-04 1.73E-06 NI 63 2.42E-04 1.46E-05

= =_ = NI 65 1.71E-09 2.03C-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22 E-0 5 NO DATA 2.32E-05 4.62E-04 3.67E-05 2.87Ek1 1.05E-06 9.44E-06 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA BR 83 NO DATA' NO DATA

2. 72 E-0 7 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO D'ATA

2. 86E-0 7 NO DATA NO DATA

.NO DATA LT E-24 8R 85 NO DATA NO DATA

1. 46E-0 8 NO DATA NO DATA NO DATA LT.E-24 R8 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 AD 88 NO DATA 3 98E-07 2.0$E-0 7 NO DATA NO DATA NO DATA 2.42E-07

_= _=----------____

== R8 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 No DATA 8.15C-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO D&TA 2 47E-09 NO DATA NO OATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 Y 90 2.35E-06 NO DATA

6. 30 E -0 8 NO DATA NO DATA 1.92E-04 7.43E-05 Y 91M 2.91E-10 NO DATA 9.90E-12 NO DATA No DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12 E-0 5 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 e

=-- -=. Y 93 1 07 E-07 NO DATA 2.9tE-09 NO DATA NO DATA 5 46E-05 1.19E-04 LR 95 8.24E-0$ 1.99E-05

1. 4 5 E-0 5 NO DATA 2.22E-05 1.25E-03 1.55E-05 2R 9F 1.07E-07 1.83E-08

8. 36 E-0 9 NO DATA 1.85E-08 7.88E-05 1.00E-04

.--___==

NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.87E-06 3.42E-04 9.05E-06 MO 99 HO DATA 1.186-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06

OM12D: ODCM Page : 50 Rev. : 0 Table 3.2-9 (Cont.) Inhalation Dose Factors for Infant (mrem /pCi inhaled) NUCLICE BONE LIVER T.80DY THYROID K10NEY LUNG GI-LLI TC101 4.65E-14 5.98E-14 5.80E-13 NO DATA 6.99E-13 4 17E-07 6.03E-07 Rul03 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RU105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG1104 7,13E-06 5.16E-06

3. 5 7 E-0 6 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE125M 3.40E-06 1.42C-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06

=..______ _......___ TE127M 1.19E-05 4.93E-06 1.482-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10

3. 4 9E -10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129r 1 01E-05 4.35C-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05

_ = _ _ _ _ - _ _ _= TE129 5 63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131N 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1 42E-04 8.51E-05 TE131 1 24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 1.15E-05 1 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 1 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 't.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 ! 135 2.76E-06 5.43E-06 1.99E-06 4 97E-04 6.05E-06 NO DATA 1.31E-06 C5134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37F-04

3. 2 5 E-0 5 NO DATA 1.23E-04 5.09E-05 9.53E-07 C5138 3.61E-07 5.S8E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26F-07 BA139 1.06E-09 7.03E-13 3 07E-11~NO DATA 4.73E-13 4.25E-06 3 64E-05 BA140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 e4141 1.12E-10 7.70C-14 3.55E-12 NO DATA 4.64E-14.2.12E-06 3.39E-06 HA142 2.84E-11 2.365-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 -4.95E-07 1A140 3.61E-07 1 43t-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 l

CE141 1.98E-05 1 19E-05

1. 42 E-0 6 NO DATA 3.75E-06 3.69E-04 1.54E-05 t

l CE143 2.09E-07 1 18E-07

1. 58 E-0 8 NO DATA 4.03E-08 8.30E-05 3.55E-05 OE144 2.28E-03 8.oSE-04 1.26E-04 NO DATA 3.84E-04 7.03E-03' 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05

_________..=- =-. PR144 3 422-11 1.32E-11 1.72E-12 NO DATA

4. ROE-12 1.15E-06 3.06E-06 N014 T 5.67E-06 5.811-06

3. 57 E-0 7 NO DATA 2.25E-06 2.30E-04 2.23E-05 w 187 9.26E-09 6.44C-09 2.2 3 E-0 9 NO DATA NO DATA 2.83E-05 2.54E-05 NP239 2.65E-07

2. 3 7E-0 8 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05 e

1

OM12D: ODCM Page : 51 Rev. : 0 Table 3.2-10 Ingestion Dose Factor for Adult (mrem /pci ingested) NUCLICE SONE LIVER T.80CY THYR 0!D KIDNEY LUNG GI-LLI -====.....-- H 3 NO DATA 1.05E-07 1.05 E-0 7 1.056-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07

5. 6 8 E-0 7 5.68E-07 5.68E-07 5.68E-07 5.68E-07 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. 4 6 E -0 6 NO DATA NC DATA NO DATA 2.17E-05 CR 51 NO DATA NO CATA

2. 6c E -0 9 1.59E-09 5.86E-10 3.53E-09 6.69E-07 NN 54 NO DATA 4.57E-06

8. 72 E-0 7 NO DATA 1.36E-06 NO DATA 1 40E-05

=_-. -..--- - -=. NN 56 NO DATA 1.15E-07

2. 04 E-0 8 NO DATA 1 46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06

4. 4 3 E-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 b0 58 DkTA 7.456-07

1. 6 7 E-0 6 NO DATA NO O TA NO DATA 1 SLE 05 N

CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06

=

=- NI 65 5.28E-07 6.86E-08 3.13 E-0 8 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.542-05

6. 9 6 E-0 6 NO DATA 1.03E-05 NO DATA 9.70E-06

- =_ - _ _ -==____- --==-_ __ ZN 69 1.03E-08 1.97E-08

1. 37 E-0 9 NO DATA 1.28E-08 NO DATA 2.96E-09 8R 83 NO DATA NO DATA

4. 02 E-0 8 NO DATA NO DATA NO DATA 5.79E-08 8R 84 NO DATA NO DATA

5. 21E-0 8 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 RB 86

'NO DATA 2.11E-05

9. 83 E-0 6 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08

3. 21E-0 8 NO DATA NO DATA NO DATA 8.36E-19

=.

== ---... =_ =-......... RB 89 NO DATA 4.01E-0S 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 da DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 __ _= - -_ = ._.-----.= - = -. = - SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA

2. S a E-10 NO DATA NO DATA NO DATA 1.02E-04

--- -------==_ =--= Y 91N 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91

1. 41 E-0.7 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05

.......==

==__

=_ =_=.----- = Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.392-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04

==_ - - - - - -.... - - - - - - - - - - - - -.... - - - - = - = _ _ - - - - N8 95 6.22E-09 3.46E-09

1. 86 E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 NO 99 NO DATA 4.31E-06

8. 2 0 E-0 7 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 o~<,-e

OM12D: ODCM Page : 52 Rev. : 0 Table 3.2-10 (Cont.) Ingestion Dose Factor for Adult (mrem /pCi ingested) NUCL10E BONE LIVER T.800Y THYROID K10NEY LUNG GI-LLI - =.__ _ __ __ - - - - - - - - - - - -... - - - - -. = _ TC101 2.S4E-10 3.66E-10

3. 59 E -0 9 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NU OATA 6.0SE-09 NO DATA 1.99E-07 NO DATA 9.42E-06

- - - -........ - - - - - - - - - - - - - - - -....... - -..... _ -== _ _...... ---... ..===_ RU106 2.75E-06 NO DATA

3. 4 8 E-0 7 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1 48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE125M 2.69E-06 9.71E-07 3 59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05

__

= - -

==-- TE127M 6.77E-06 2.42C-06 8 25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08

2. 38 E-0 8 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129N 1.15E-05 4.29E-06

1. 82 E-0 6 3.95E-06 4 80E-05 NO DATA 5.79E-05

_=

=__ --. _=.__

-==.......... TE129 3 14E-08 1.18E-08 7.63E-09 2 41E-08 1.32E-07 NO DATA 2.37E-08 TC131M 1.73E-06 8.46E-07 7 05 E-0 7 1.34E-06 8.57E-06 N0*0ATA 8.40E-05 TE131 1 97E-08 8.23E-09

6. 22 E-0 9 1 62E-08 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.63E-06

1. 53 E-0 6 1 80E-06 1.57E-05 NO DATA' 7.71E-05 1 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3.41E-06 1 95E-03 1.02E-05 NO DATA 1.57E-06

...---.=_ I 132 2 03E-07 5.43E-07 1.90E-07 1 90E-05 8.65E-07 NO DAT A 1.02E-07 1 133 1.42E-06 2.47E-06 7.53E-07 3 63E-04 4 31E-06 NO DATA 2.22E-06 1 134 1.06E-07 2.88E-07 1.03E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 1 135 4.43E-07 1.16E-06 4 2 8 E-0 7 7.65E-05 1.86E-06 NO DATA 1 31E-06 CS134 6.22E-05 1 48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2 59E-06 CS136 6.51E-06 2.57E-05

1. 8 5 E-0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1 09E 7.14E-0 5 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS138 5 52E-08 1 09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 SA139 9.70E-08 6.91E-11

2. 84 E-0 9 NO DATA 6.46E-11 3.92E-11 1.72E-07 8A140 2.03C-05 2 55E-08 1 3 3 E-06 NO DATA 8.67E-09 1 46E-08 4.18E-05 84141

4. TIE-0 8 1.56E-11 1.59E-09 'NO DATA 3.31E-11 2 02E-11 2.22E-17 6A142 2 13E-08 2 19E-11 1 34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26

.....--....... -......--....--.-.---= LA140 2.500-09 1.262-09 J.33E-10 NU OATA NO DATA NO DATA 9.25E-05 L A142 1.28E-10 5 825-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 OE141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 __==... .... - -........ - -. - -.................. - -... - - -... -..... - - - - - - - = OE143 1.65E-09 1.22F-06 -1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.48E-07 2 045-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3 69E-09 4.56E-10 No DATA 2 13E-09 NO DATA 4.03E-05

==__==.---..............-- PRI44 3.01E-11 1 25E 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 N0147 6.29E-09 7.27E-09

4. 35 E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 197 1.03E-07 8.61E-08 3.01E-0 8 NO DATA NO DATA NO DATA 2.82E-05

_ = NP239 1.19E-09 1.17E-10 6.45E-11' NO DATA 3.65E-10 NO DATA 2.40E-05 o o l L L

9- 'i 1 OM12D: ODCM Page : 53 Rev. : 0 ' Table 3.2-11 Ingestion Dose Factors for Teenager (arem/pCi ingested) NUCLICE BONE LIVER T.800V THYROIO. KIDNEY LUNG GI-LLI , H 3 NO DATA 1.06E-07 1.00E-0 7 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C - - 14 -4.06E 8.12E-07 8 12 E-0 7 8.12F-07 8.12E-07 8.12E-07 8 12F-07 NA 24 2.30E-06 2.30E-06

2. 30 E-0 6 2.30E-06 2.30h-06. 2.30E-06~ 2.30E-06 P 32 2.76E-04 1.71C-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05~

CR 51 NO DATA NO DATA

3. 60 E-0 9 2.00E 7.89E-10 5 14E-09 6.05E-0T PN $4 NO DATA 5.90E-Oo 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05

=====-----...........___ - MN-56 NO DATA 1.38E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68F-06

6. 2 5 E -0 7 NO DATA NO DATA 1.70E-06 1 16E-06 FE 59 5.87E-06 1.JFE-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05

---.....--..=---_-= - CO 58 NO DATA 9.72E-0T. 2. 24 E-0 6 NO DATA NO DATA _ NO DATA 1.34E-05 CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA -NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 I.25C-05

0. 00E-0 6 NO DATA NO DATA NO DATA 1.99E-06

.... ____=

__ =-= NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5 19E-06 CU 64 NO DATA 1.15E-07

5. 41 E-0 8 NO DATA 2.91E-07 NO DATA 8.92E-06 2N 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06

== IN 69 1 47E-08 2.60E-08 1.96E-09 NO DATA 1.R3E-08 NO DATA 5.16E-08 BR 83 NO DATA NO DATA

5. 74 E-0 8 NO DATA NO DATA

NO DATA LT E-24 BR 84

-NO DATA NO DATA

7. 22 E-0 8 NO DATA NO DATA NO DATA LT E-24 SR 85 N0' DATA NO DATA 3.05E iO9 NO DATA NO DATA NO DATA LT E-24 R S 8 6 -. NO DATA 2.9BE 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 R8 88-NO DATA

'8.52E-08 4.54E-08 NO DATA-NO DATA NO DATA 7.30E-15 -.R8 89 NO DATA' 5.50E-08 .89E-08 NO DATA NO DATA NO DATA- ~.43E 8 - SR 87 - 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA S.24E-05 . SR 90 8.30E-03 NO DATA 2.05 E-0 3 NO DATA NO DATA NO DATA 2.33E-04' SR 91 8.07E-06 NO DATA 3 21 E-0 7 NO DATA NO DATA - NO DATA 3.66E-05 SR 92 3.05E-06 'NO DATA 1 30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA

3. 69 E-10 NO DATA NO DATA NO DATA 1.13E-04 Y.

91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA' NO DATA 6.09E-09 3 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 4.24E-05' Y 92' 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3 32E-05 j.- Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30C-08 8.9*E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1 27E-04

..--...--.....--.-------...--.--. ------ -........=--

46.95 8.22E-09 4.565-09

2. 51 E -0 9 NO DATA 4.42E-09 N0' DATA 1.95E-05 MD 99 NO DATA 6.03E 1.13 F-0 6 NO DATA 1.38E-05 NO DATA 1.08E-05 a

TC 99H 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 e.08E-07 -. -........ - -.. - -. - -.. = = _ = - J 6 f t -.-.-,---,w.e, --.w

OM12D: ODCM Page : 54 Rev. : 0 Table 3.2-11 (Cont.) Ingestion Dose Factor for Teenager (mrem /pCi ingested) NUCLIOE BONE L1VER T.80DY THYR 01D K1DNEY LUNG GI-LL1 rC101 3.60E-10 5.12E-10 5 0 3E-09 NO DATA 9 26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 NU DATA 1 09E-0 7 NO DATA 8.99E-07 NO DATA 2.13E-05 RU105 2 18E-08 NO DATA 8 46E-0 9 NO DATA 2.75E-07 NO DATA 1 76E-05 =- -=....................... RU106 3.92E-06 NO DATA 4.14E-07 NO DATA 7.56E-06 NO DATA 1 88E-04 AG110M 2.05E-07 1.94E-07

1. laE-0 7 NO DATA 3 70E-07 NO DATA 5 45E-05 TE125M 3.83E-06 1.386-06 5 12E-07 1.07E-06 NO DATA NO DATA 1.13E-05

= TE127M 9.67E-06 3.43E-06 1 15E-06 2.30E-06 3.92t-05 NO DATA 2 41E-05 IE127 1 58E-07 5.60E-08 3 40E-08 1.09E-07 6.40E-07 NO DATA 1 22E-05 TE129M 1 63E-05 6.05E-06

2. 5 8 E-0 6 5.26E-06 6.82E-05 NO DATA 6.12E-05

- _ _ -_ _ _=--....=. - TE129 4.48E-OS 1.67E-08 1.01E-08 3 20E-08 1.88E-07 NO DATA 2 45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.T6E-06 1.22E-05 NO DATA 9 39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2 29E-09 TE132 3 49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7 00E-05 I 130 1 03E-06 2.98E-06 1 19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.85E-06 8.11E-06

4. 4 0 E-0 6 2 39E-03 1 41E-05 NO DATA 1 62E-06 1 132 2.79E-07 7 30E-07 2 62E-07 2.46E-05 1.15E-06 NObATA 3 18E-07 1 133 2 01E-06 3.41E-06

1. 04 E-0 6 4.76E-04 5.98E-06 NO DATA 2.58E-06 1 134 1.46E-07 3.87E-07

1. 39E-0 7 6.45E-06 6.10E-07 NO DATA 5.10E-09

=_ 1 135 6.10E-07 1 57E-06

5. 82 E-0 7 1.01E-04 2.48E-06 NO DATA 1 74E-06 CS134 8 37E-05 1.97E-04 9.14 E-0 5 NO DATA 6.26E-05 2.39E-05 2 45E-06

~ C5136 8.59E-06 3.38E-05

2. 2 7 E-0 5 NO DATA 1.84E-05 2.90E-96 2 72E-06 C5137 1.12E-04 1.49E-04 5 19E-05 NO DATA 5.07E-05 1.97E-05 2 12E-06

. - __ _ _= CS138 7.76E-08 1.49E-07 7.4SE-08 NO DATA 1.10E-07 1.28E-08 6 76E-11 84139 1.39E-07 9.78E-11 4.9SE-09 NO DATA 9.22E-11 6.74E-11 1.24E-06 _-_ --==....==_ = = = = _ -= BA140 2 84E-05 3.48E-OS 1 8 3E-0 6 NO DATA 1.18E-08 2.34E-08 4.38E-05 BA141 6.71E-08 5.01E-11 2 24E-09 NO DATA 4.65E-11 3.43E-11 1.43E-13 DA142 2.99E-08 2.99E-11 1 84E-09 NO DATA 2.53t-11 1 99E-11 9.18E-20

==_ --........... ......- - - - - = LA140 3.485-09 1.71C-09

4. 5 5 E -10 NO DATA NC DATA NO DATA 9.32E-05 LA142 1.79C-10 7.95E-11 1 98E-11 NO DATA NO DATA NO DATA 2 42E-06 Ch141 1.33E-08 8.88E-09

1. 02 E-0 9 NO DATA 4.18E-09 NO DATA 2 54E-05

-............=-- - CE143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5 14E-05 CE144 6.96E-07 2.88E-07 3 74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR143 1.31E-08 5.23C-09

6. 52 E-10 NO DATA 3.04E-09 NO DATA 4.31E-05

==.............................................. ....a................== PR144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 ND14T 9.18E-09 1.02C-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3 68E 'W~187 1.46E-07 1.19C-07, 4 1TE-08 NO DATA NO DATA NO DATA 3.22E-05 =................... NP239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05

1 l OM12D: ODCM Page : 55 Rev. : 0 Table 3.2-12 Ingestion Dose Factors for Child (mrem /pci ingested) l NUCLIUE BONE LIVER T.HOUY THYROID K10NEY LUNG GI-LLI H 3 NO DATA 2.03E-07 2.01E-0 7 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.*2E-06

2. 4 2 E-0 6 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 S.SOE-06 5.80E-06 5.80E-06 5.80E-06 5.00E-06 5.80E-06 5.80E-06

- _-- =___..................................................---............ P-32 8.25E-04 3.86E-05 3.1 C E -0 5 40 DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO CATA

8. 90E -0 9 4.94E-09 1.35E-09 9.020-09 4.72E-07 MN 54 NO DATA 1.07E-05

2. 8 5E-0 6 NO DATA 3.00C-06 NO DATA 8.98E-06 NN $6 NO DATA 3.34E-0T 7.54E-00 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89c-06 NO DATA NC DATA 3.45E-06 1.13E-06 FE 59 1.6SE-05 2.6TE-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05

---_==..... .........----......-------........-...............----....._= CD 58 NO DATA 1.80E-06

5. 51 E-0 6 NO DATA NO DATA NO DATA 1.05E-05 CD 60 NO DATA 5.29E-06

1. 56 E -0 5 NO DATA NO DATA NO DATA 2.93E-05 N163 5.38E-C4 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1 94E-06

........................--..--............................=-- ____..... - NI 65 2.22E-06 2.09F-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07

1. 48E-0 7 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1 37E-05 3.oSE-0) 2.2 7E-0 5 NO DATA 2.30E-05 NO DATA 6.41E-06

.....---.= -- -...... = =. .=_. ZN 69 4.38E-08 6.33E-08

5. 85 E-0 9 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.9 8E-0 7 NO DATA NO DATA NO DATA LT E-24

_= - __-==-- RR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12 E-0 5 NO DATA NO DATA NO DATA 4.31E-06 R8 88 'NO DATA 1.90E-07

1. 3 2 E-0 7 NO DATA NO DATA NO DATA 9.32E-09

--.. =__ =_ .. - _.. = - - _

=

RB 89 NO DATA 1.17E-07 1.04 E-0 7 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA NO. DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA

9. 0 6 E -0 7 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.11E-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04

.--..= _==.........__---_= = Y 91M 3.82E-10 NO DATA 1.37E-11 NO DATA NO DATA NO DATA T.48E-07 Y 91 6.02E-07 NO DATA 1 61 F-0 8 NO DATA NO DATA NO DATA 8.02E-05 Y 92 3.60E-01 NO DATA 1.03E-10 NO DATA NO DATA NO DATA 1.04E-04 Y 93 1.14E-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.16E-07 2.2SE-08 2.2 7 E-0 8 NO DATA 3.65E-08 NO DATA 2.66E-05 ) ZR 97 6.99E-09 1.01E-09 S.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 N8 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05

3. 2 9 E-0 6 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09

3. 00 E-0 8 NO DATA 2.63E-08 9.19E-10 1.03E-06

OM12D: ODCM Page 1 56 Rev. : 0 Table 3.2-12 (Cont.) Ingestion Dose Factors for Child (mrem /pC1 ingested) NUCLICE-BONE LIVER T.000Y THYROID KIONEY LUNG G1.LLI .- =- - _ - - -.......... - -...... - - - - - - - - - - -. - - - - - - -... = TC101 -1.07E-09 1.126-09 1.42E-08 NO DATA 1.91E-08 5.92C-10 3.56E-09 RU103 7.31E-07 NO DATA

2. 81E-0 7 NO DATA 1.84E-06 Nn DATA 1.89E-05 RU105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 'NO DATA 4.21E-05

.==_==........---..........=- = RU106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AG110M 5.39E-07 3 64E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 -_-------- ----=== -- - =. = = _ - =__. _. -_=-....= -===-..........-- TE12TM 2.89E-05 7.78E-06

3. 4 J E-0 6 6.91E-06 e.24E-05 NO DATA 2.34E-05 TE127 4.71E-07 1 27F-07 1.01E-0 7 3.26E-07 1.34E-06 NO CATA 1.84E-05 TE129M 4.87E-05 1.36E-05 7.SoE-06 1.57E-05 1.43E-04 NO DATA 5.94E-05

....... --___...........=- =- TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE131H 7.20E-06 2 49E-06 2 65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE131 8.30E-08 2.53E-08

2. 4 7 E-0 8 6.35E-08 2.51E-07 NO DATA 4.36E-07

= =. _=___.

==...__ - .. = . - - -.. = - - = --- TE132 1.01E-05 4.47E-06

5. 4 0 E-0 6 6.51E-06 4 15E-05 NO DATA 4.50E-05 1 130 2.92E-06 5.90E-06 3.04E-0 6 6.50E-04 8.82E-06 NO DATA 2.76E-06 1 131 1.72E-05 1.73E-05

9. 83E-0 6 5.72E-03 2.84E-05 NO DATA 1 54E-06

.=--=. --_ --_= I 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.2SE-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06

2. 7 7 E-0 6 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07

- =.- _. =... - - - - - - - = = - - - I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 CS134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-04 2.27E-06 C513'7 3.27E-04 3.13E-04 4.62E-05 NO DA A .02E-04 3.67E-05 1.96E-06 C5138 2.28E-07 3.17E-07

2. 01 E-0 7 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA139 4.14E-07 2 21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05

--- _ =.... =_ -- -==----==_ RA140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37t-08 4.34E-08 4.21E-05 SA141 2.00E-07 1.120-10

6. 51 E -0 9 NO DATA 9.69E-11 6.58E-10 1.14E-07 GA142 8.f4E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09

........_=--_=..........----......-......-......--........................ L4140 1.01E-08 3.53E-09 1 19E-09 A0 DATA NO DATA NO DATA 9.84E-05 LA142 5.?4E-10 1.67E-10 5.2 3E-11 NO DATA NO Daft NO DATA 3 31E-05 CE141 3.97C-08 1 98C-08 2.94 C-0 9 NO DATA 8.68E-09 NO DATA 2 47E-05 =........................... ........................-----............._==_ CE143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE144 2.08E-06 6.52E-07 1.11 E-0 7 NO DATA 3.61E-07 NO DATA 1 70E-04 PR143 3.93E-08 1.18C-08

1. 9 5 E -0 9 NO DATA 6.39E-09 NO DATA 4.24E-05 PR144 1.29E-10 1.91E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 N0147 2.79E-0R 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 1.14E-0 7 NO DATA NO DATA NO DATA 3.57E-05 4.29E-07.2.54E-07 w 187

- -__

_-__.........-.............= ..........= NP239 5.2SE-09 3.77E-10 2.6St-10 NO DATA 1.096-09 NO DATA 2.79E-05

OM12D: ODCH Page : 57 Rev. : 0 Table 3.2-13 Ingestion Dose Factors for Infant (mrem /pCi ingested) NUCLIDE BONE LIVER T.60GY THYROID KIDNEY LUNG G1.LLI H 3 NO DATA 3.08E-07 3.00E-0 7 3.08E-07 3.08E-07 3.00E-07 3.08E-07 C 14 2.37E-05 5.06E-06

5. 0 6 C-0 6 5.06E-06 5.06E-06 5.06F-06 5.06C-06 NA 24 1.01E-05 1.01C-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P.

32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.10E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 =._-- ___.__.____ __...______..___ _.......__..________...__._. __.....===_ MN $6 NO DATA 8.18E-07 1.41E-0 7 NU DATA 7.03E-07 NO DATA 7.43E-05 TE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.93E-06 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 3 NI 65 4.70E-06 5.32E-07 2.426-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07

2. 82 E-0 7 NO DATA 1.03E-06 NO DATA 1 25E-05 ZN 65 1.34E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5 33E-05

-= .=... ZN 69 9.33E-08 1.08E-01

1. 2 5 E-0 8 NO DATA 6.98E_08 No DATA 1.376-05 l

HR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 - = =... =..- BR 85 NO DATA NO DATA 1 94 E-0 8 NO DATA NO DATA NO DATA LT E-24 RS 86 NO DATA 1.70E-04 8.4 0 E-0 5 NO DATA NO DATA h0"D'ATA-4'.~35E-06 ' M8 88 .NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 RD 89 NO DATA 2.06E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89-2.51E-03 NO DATA 7.2 0 E-0 5 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.0$E-02 NO DATA

4. 71 E-0 3 NO DATA NO DATA NO DATA 2.31E-04

==....... __.. __--...__.... SR 91 5 00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.3sE-09 NO DATA NO DATA NO DATA 1.20E-04 . - - _ - _. _..... - _ _...... _...... _ _ _ _ _ _ _ _..... _ _ _.. - =- = Y 91M 8.10E-1C NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA No DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 =.___.........____. _.-... __...-_-_--.._...... ___..._...._____...___.=_ Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DA T/. NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.5 6 E-0 8 NO DATA 5.41E-08 NO DATA 2.50F-05 ZR 97 1.48E-08 2.54C-09 1.16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 N8 95 4.20E-08 1.73E-08

1. 00 E -0 8 NO DATA 1.74h-08 NO DATA 1.46E-05 MO 99 NO DATA 3.402-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 998 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26h-08 2.07E-09 1.15E-06

OM12D: ODCM Page : 58 Rev. : 0 Table 3.2-13 (Cont.) Ingestion Dose Factors for Infant NUCLICE BONE LIVER T.000Y THYR 0!D.KIONEY LUNG GI-LLI .= - - - - - - - - = = _ - - TC101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1 56E-09 4.86E-07 RU103 1.48E-06 NO DATA

4. 95 E-0 7 NO DATA 3.08E-06 NO DATA 1.80E-05 Rut 05 1.36E-07 NO DATA 4.58E-08 40 DATA 1.00E-06 NO DATA 5.41E-05

...- _ - - = - - - - - - - - - - -.. - - - - - -... - - - - - - - -...... - - - RU106 2.41E-05 NO DATA 3.01 E-0 6 NO DATA 2.85E-05 NO DATA 1.83E-04 AG110M 9.96E-07 7.27E-07 4.81E-0 7 NO DATA 1.04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15 E-0 6 7.84E-06 NO DATA NO DATA 1.11E-05 = _ =_-- ._==_ - - - - - - - - - - - - - - - -.... - - - = _ - - -- TE127N 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06

3. 35 E-0 7 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129H 1.00E-04 3.43E-05

1. 54 E-0 5 3.84E-05 2.50E-04. NO DATA 5.97E-05

- =. = ....----===-_ -- =_ TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE131F 1.52E-05 6.12E-06 5.0$E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE131 1.76E-07 6.50E-08

4. 94 E-0 8 1 57E-07 4.50E-07 NO DATA 7.11E-06

==.....-- =--__ --==_ TE132 2.08E-05 1.03F-05

9. 61 E -0 6 1.52E-05 6.44E-05 NO DATA 3.81E-05

! 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06 1 131 3.59E-05 4 23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 _=..-- - _-- _.-==-- 1 132 1.66E-06 3.37E-06 1 2 0 E-0 6 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2 14E-35 NO DATA 3.08E-06 i 134 8.69E-07 1.78E-06 6.33E 0 7 4.15E-05 1.99E-06 NO DATA 1.84E-06 ! 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 CS134 3.77E-04 7.03E-04 7.10 E-0 5 NO DATA 1.SIE-04 7 42E-05 1.91E CS136 4.59E-05 1.35E-04 5 04E-0 5 NO DATA 5 38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04

4. 3 3 E-0 5 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3 79E-0 7 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07 5.84E-10

2. 5 5 E-0 8 NO DATA 3.51E-10 3 54E-10 5.58E-05

.-------............ -=____ .....-.--=. 8A140 1.71E-04 1.71E-07

8. 81E-0 6 NO DATA 4.06E-08 1 0$E-07 4.20E-05 PA141 4.25E-07 2.912-10

1. 3

E-0 8 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.536-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07

__ _ - _ =, __=___ LA140 2.11E-08 8 32E-09 2.14 E -0 9 NO DATA NO DATA NO DATA 9.77E-05 LA142 1.10E-09 4.04E-10 9.6 /E -11 NO D AT A NC DATA NO DATA 6.86E-05 CE141 7.87E-08 4.80E-08

5. 6S E -0 9 NO DATA 1.48E-08 NO DATA 2.48E-05

- - - - - - - - - - - _ - - - = = - - =....... - - - - -... - - - - - -.................. - -....... - -. - - -. CE143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR143 8.13E-08 3.c4E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 N0147 5.53E-08 5.68E-08

3. 4 0 E -0 9 NO DATA 2.19E-08 NO DATA 3 60E-05 W 187 9.03E-07 6.28E-07 2.17E-0 7 NO DATA NO DATA NO DATA 3.69E-05

=- --- -------- .------.-------.--..- -- --------.-----.----- --.------==--- NP239 1.11E-08 9.93E-10

5. 61 E-10 NO DATA 1.98E-09 NO DATA 2 87E-05

m I OM12D: ODCM Page : 59 Rev. : 0 Table 3.2-14 Annual Usage Factors for the Maximum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables & grain (kg/yr)* 520 630 520 Leafy vegetables 26 42 64 (kg/yr) Milk (1 /yr) 330 330 400 310 Meat & poultry (kg/yr) 41 65 110 3 l Inhalation _(m /yr) 1400 3700 8000 8000

Consists of the following (on a mass basis): 22% fruit, 54% vegtables (including leafy vegetables), and 24% grain.

l-Table 3.2-15 i Annual Usage Factors for the Average Individual Calculations Pathway Child Teen Adult Fruits, vegetables, & l grain (kg/yr)* 200 240 190 \\ j Milk ( 1/yr) 170 200 110 l l [ Meat & poultry (kg/yr) 37 59 95 Inhalation (m fyr) 3700 8000 8000

Consists of the following (on a mass basis):

22" f ruit, 54% vegetables (including leafy vegetables), and 24% grain.

OM12D: ODCM Page : 60 Rev. : 0 3.3 Compliance With 10CFR50 Appendix I - Caseous Effluent Dose Doses resulting from the release of noble gases, radioiodines, tritium and radionuclides in particulate form must be calcualted to show compliance with Appendix I of 10CFR50. The calculations will be performed monthly for all gaseous effluents. 3.3.1 Noble Gases Section II.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor to unrestricted areas such that the estimated annual gamma air dose is limited to 10 millirads and the beta air dose is limited to 20 millirads. The external dose pathway only will be considered for noble gases. The controlling location for the above stated dose limits is the site boundary location with the highest relative dispersion factor (X/Q) for the period of release. PNPP Technical Specifications limit the dose resulting from the release of noble gas radionuclides in gaseous effluents to the following: For gamma radiation, during any calendar quarter: a. D 5 mrad, ir b. For beta radiation, during any calendar quarter: D, d 10 mrad, For gamma radiation, during any calendar year: c. D d 10 mrad, d. For beta radiation, during any calendar year: D, d 20 mrad.

OM12D: ODCM Page : 61 Rev. : 0 3.3.2 Radiciodines, Particulates, and Other Radionuclides Section II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive materials in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. The controlling location for this organ dose limit is a function of the noble gas controlling location, i.e., the location of the highest relative deposition (D/Q) for the period of release, as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of residences in each sector, and garden and farm animal locations. PNPP Technical Specifications limit the dose resultant from the release of iodine -131, iodine -133, tritium, and all radionuclides in particulate form with half-lives greater than eight days to the following: a. During any calendar quarter: dose to any organEG;7.5 mrem

and, b.

During any calendar year: dose to any organsGCIS mrem. 3.3.3 Dose Calculations The following calculations are used to calculate gamma and beta air doses resultant from noble gas releases to areas at or beyond the site boundary for purpose of showing compliance - with 10CFR50 Appendix I. The equations used to calculate organ doses resultant from the release of iodine -131, iodine -133, tritium and radionuclides in particulate form with half-lives greater than eight days are the found in Section 3.2.3. The dose rate obtained is integrated over the appropriate surveillance or sampling time period.

OM12D: ODOI Page : 62 Rev. : O a. Gamma Air Dose from Noble Gas Releases = 3.15 x 10

X/Q
Q DF (3.3-1) ir g

Where: 7 D = the annual gamma air dose due to noble gas

I*

radionuclides, in mrad /yr; DF = the gamma air dose factor for a uniform semi-infinite cloud of rgdionuclide i, from Table 3.3-1, in (mrad

m )/(Ci
s);

Q = the release rate of radionuclide i, in uCi/s; g X/Q = the normal relative dispersion factor, in s/m ; 3.15 x 10 = the conversion factor to convert (mrad

uC1)/(Ci
s) to mrad /yr.

b. Beta Air dose from Noble Gas Releases 0 = 3.15 x 101

X/Q
1 Q DF D

g f air i Where: D = the annual beta air dose due to noble gas

I*

radionuclides, in mrad /yr; DF@ = the beta air dose factor for a uniform semi-I infinitecloudofrgdionuclidei,fromTable 3.3-1, in (mrad

m )/(Ci
s);

Q = the release rate of radionuclide i, in uCi/s; g X/Q = the normal relative dispersion factor, in s/m ; 3.15 x 10 = the conversion factor to convert (mrad

uC1)/(C1
s) to mrad /yr.

3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated monthly. Calculations will be performed to determine the maximum air dose as well as the maximum organ dose to an individual. These monthly dose calculations will be summed for comparison with quarterly and annual limits. The monthly results should be added to the doses cumulated

OM12D: ODCM Page : 63 Rev. : 0 from other months in the quarter of interest and in the year of interest. To assure compliance with 10CFR50 Appendix I the dose limits for air dose and organ dose are those found in Sections 3.3.1 and 3.3.2 respectively. The quarterly limits specified in those sections represent one half of the annual design objectives. If these limits are exceeded, a special report will be submitted to the NRC in accordance with PNPP Technical Specifications. 3.3.5 Projection of Doses Doser resulting from the release of gaseous effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month. In this case the source term should be adjusted to reflect this information and the justifcation for the adjustment noted. If the sum of the projected doses for the 31-day period exceeds 0.3 mrem to any organ, appropriate portions of the ventilation exhaust treatment system will be operated to reduce releases. The values for the projected impact correspond to about one forty-eighth of the Appendix I limits. If continued for a year, these values would correspond to less than one-fourth of the Appendix I limits. 3.4 Population Dose As required by Regulatory Guide 1.21, for Semiannual Radioactive Effluent Release Reporting, a population dose is calculated for the doses received resultant of all gaseous effluent releases. The population dose is computed, taking into account geographically population distribution and pathway using the equations in Section 3.2. However, the dose factors, DF differ. The populationdosefactorsarecalculatedinagjEn,ersimilartothat a used for individuals except that Regulatory Guide 1.109 Revision 1 assumptions for average individuals are used rather than for maximum exposed individuals and they are averaged over all age . groups after weighting by the fraction of population in each age group.

OM12D: ODCM Page : 64 Rev. : 0 Figure 3.3-1 Camma and Beta Air Dose Yactors for Semi-Infinite Plune mrad

m

( Ci

s f Nuclide Dg g

Ar-41 2.95+2 1.04+2 Kr-83m 6.12-1 9.13 Kr-85m 3.90+1 6.24+1 Kr-85 5.45-1 6.18+1 Kr-87 1.96+2 3.27+2 Kr-88 4.82+2 9.29+1 Kr-89 5.48+2 3.36+2 Kr-90 5.14+2 2.48+2 Xe-131m 4.95 3.52+1 Xe-133m 1.04+1 4.69+1 Xe-133 1.12+1 3.33+1 Xe-135m 1.07+2 2.34+1 Xe-135 6.09+1 7.80+1 Xe-137 4.79+1 4.03+2 Xe-138 2.92+2 1.51+2

OM12D: ODCM Page : 65 Rev. : 0 4.0 TOTAL DOSE 4.1 Compliance With 40CFR190 - Uranium Fuel Cycle Dose Annual dose contributions from liquid and gaseous effluent releases, as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CFR190 annual limit of 25 mrem total body or any organ (except the thyroid which is 75 mrem). Additionally, the Technical Specifications require that when the calculated doses associated with the effluent releases exceed twice the limit of Specifications 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b, calculations shall be mada including the direct radiation component to determine whether the limits of Specification 3.11.4 have been exceeded, i.e., that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 arem) over 12 consecu-tive months. If such is the case, the licensee shall prepare and submit a special report to the Commission within 30 days and limit subsequent release to prevent reoccurrence of exceeding the above limits. This special report is to include an analysis which dem,onstrates that radiation exposure to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the standards in 40CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations. If analysis indicates that releases resulting in doses that exceed the 40CFR190 standard could have occurred, then a variance from the Commission to permit such releases will be requested or if possible, action will be taken to reduce subsequent releases. This report shall contain: 1. A determination of which fuel cycle facilities or operations, in addition to the nuclear power reactor unit (s) at the site, contribute to the annual dose to the maximum exposed individu-al. Nuclear fuel facilities over five miles from PNPP need not be considered in this determination. 2. A determination of the maximum exposed individual. 3. A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described in this ODCM. Where additional information on pathways and nuclides is needed, the best available information will be used and documented.

OM12D: ODCM Page : 66 Rev. : 0 4. A determination of the dose resulting from direct radiation from the plant and storage facilities. The total body and organ doses resulting from liquid effluents from the PNPP will be summed with the doses resulting from gaseous releases of noble gases, radioiodines, and particulates. These doses will be based upon releases from the PUPP during the past 3 quarters and from the quarter in which twice the specification was exceeded. The doses from the PNPP will be summed with the doses to the maximum exposed individual contributed from other operations of the uranium fuel cycle. 4.2 Direct Radiation Dose From PNPP Potential direct radiation dose to individuals outside PNPP will arise from (a) skyshine and direct dose from the turbines, (b) direct dose from the external surfaces of buildings, and (c) direct dose from stored radwaste. Coolant activation by high energy neutrons, the 0 6 (n.p)N reaction,isofinterestinBWRsjecauseitcanresultinturbine skyshine and direct dose. The N present in the steam of a direct cycle BWR is carried with the steam into the turbine moisture and associated equipment of the secondary cycle. separatorsf6 Although N has a 7.13 second half-life, its gamma emission can present a radiation dose problem to the site boundary as a result of the high energy gamma scatter from structures and the atmosphere. All external walls of buildings at PNPP have been designed to attenuate radiation sources from within the plant to maximum of 0.5 mrem /h outside, with an expected radiation dose of 0.25 mrem /h.- All radwaste will be stored in the radwaste storage area which is part of the total building complex. All radwaste storage areas have outside walls that are 4 feet thick and they too are designed for an outside radiation zone of 0.5 mrem /h. Direct radiation dose analyses for normal operations, were performed based on 80% load factor and 100% occupancy at the closest site boundary location NSW sector. Direct dose from turbine skyshine was calculated to be 1.3 mrem /yr and direct dose frog the surf ace of buildings was calculated to be 2.2 x 10 mrem /yr. Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the l l site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with analyses performed quarterly i and annually. L.

OM12D: ODCM Page : 67 Rev. : 0 t 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i 5.1 ' Monitoring Program Environmental samples shall be collected and analyzed according to Table 5.1-1 at locations shown in Figures 5.1-1 and 5.1-2. Table 5.1-4 describes sample locations, associated media, and approximate distances and directions from the site. Analytical techniques used shall ensure that the detection capabilities in Table 5.1-3 are achieved. The results of.the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring 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 modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of. radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation The exposures of individuals resulting from the station operation. initial radiological environmental monitoring program should be conducted for the first three years of commercial operation; following this period.. program changes may be proposed based on operational experience. 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 reasonable 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 report. 5.2 Land Use Census Program A land use census will be conducted annually to identify the location of'the nearest residence, the nearest vegetable garden greater than 500 square feet, and the nearest milk-producing snimal m in each of the 22b' meteorological sectors within a distance of five miles. If a land use census identifies a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at the location from which samples are currently l_ being obtained the new location (s) will be added to the lI radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the i

OM12D: ODCM Page : 68 Rev. : O same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Any location f rom which milk can no longer be obtained may be dropped from the surveillance program af ter notifying the NRC in writing that they are no longer obtainable at that location. The land use census shall be conducted during the growing season at least once per calendar year using that information that will provide the best results, such as by a door-to-door survey, aerial survey, general observations, or by consulting local agriculture authorities. The results of the land census shall be included in the Annual Radiological Environmental Operating Report. 5.3 Inter Laboratory Comparison Program The laboratories of the licensee and/or licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent This participation shall include all of the program. determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring The results of analysis of these crosscheck samples shall program. be included in.the Annual Radiological Environmental Operating Report. If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report.

Table 5.1-1 PNPP Radiological Environmental Monitoring Program Analysis Sample Media Locations

Sampling Frequency Type Frequency l

Airborne radiciodine (* 1.-3, 4, 5, 6, 35 Continuous sampler operation Radioiodine Weekly following and with collection weekly or as 1-131 canister change g particulates required by dust loading, Particulates(d) Weekly following loading, whichever is more Gross Beta filter change frequent Camma Isotopic

Composite, by location quarterly Direct Radiation *}

At each airborne Continuous sampling, one TLD Camma Dose Quarterly (3 TLDs/ location) monitoring location exchanged quarterly 1 through 24. 35 Continuous sampling, one TLD Camma Dose Annually 41, 42, 43 exchanged annually Continuous sampling, one TLD Camma Dose Quarterly or exchanged quarterly or under emergency under emergency situations situations If) Waterborng) 28, 34, 36, 37 Composite H-3 Composite, by surface location, quarterly g Cross Beta Monthly woo drinking S $ U. Casuna Isotopic Monthly I Sediment fron ") 25, 26, 27, 32 Semiannually - Spring and Canuna Isotopic Semiannuallyo os o shoreline Fall as weather permits See footnotes at end of table. s

i 4 Table 5.1-1 (Cont.) PNPP Radiological Environmental Monitoring Program i Analysis i Sample Media - 1.oca tions* Sampling Frequency Type Frequency 9 Ingestg 29, 30, 31, 33 Monthly when animals are not I-131 *), Monthly I Milk on pasture. Camma g Isotopic i I 29, 30, 31, 33 Semimonthly when animals are I-131 "). Semimonthly on pasture Gamma Isotopic Fish *} 25, 32 Semiannually - Spring and Camma Semiannually I Fall as weather permits Isotopic (edible portion) Food Products (*} 38, 39, 40 Annually, at the time of I-131(*}. Annually harvest, broad leaf vegetation, Camma g and fruits Isotopic Silage (*} 29, 30, 31, 33 Annually, location determined by Camma Isotopic Annually annual milk - animal and l garden census

o m o E $$ $

(a) Sampling begins at least six months prior to PNPP operation, including one pasture season.

E$

(b) Sampling begins at least one year prior to PNPP operation. (c) Sampling begins at least two years prior to PNPP operation. (d) Particulate sample filters will be analyzed for gross beta 24 hours or more af ter sampling to allow for radan u o8 .and thoron daughter decay. (e) Camma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be ~ attributable.to the effluents-from the facility. If gross beta activity in air or water is greater than ten times the mean of control samples for any. medium, gasuna isotopic analysis will be performed on the individual samples. (f) Composite samples will be collected with equipment that is capable of collecting an aliquot at time intervals j 'that are very short (e.g., hourly) relative to the compositing period (e.g., monthly). i

Table 5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples WATER AIRBORNEPARTICigTE FISH MILK FOOD PRODl! CTS ANALYSIS (pCi/L) OR CASES (pCi/m ) (pCi/kg, wet) (pCi/L) (pCi/kg, vet) H-3(O 2 x 10 4 Itn-54 1 x 10 3 x 10 2 0 Fe-59 4 x 10 1 x 10 3 4 co-58 1 x 10 3 x 10 Co-60 3 x 10 1 x 10 2 0 Zn-65 3 x 10 2 x 10 2 Zr-Nb-95 4 x 10 3 2 I-131 2 0.9 1 x 10 3 1 x 10 3 Cs-134 30 1D 2 x 10 60 1 x 10 3 Cs-137 50 20 70 2 x 10 mmo 2 3 x 10 g Ba-La-140 2 x 10 .... ? (1) For drinking water samples. The value given is the 40CFR part 141 value. oyo 9

1 Table 5.1-3 Detection Capabilities for Environmental Sample Analysis and Lower Limit of Detection (LLD)'"' WATER AIRBORNEPARTICUlfTE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSTS (pCi/L) OR CASES (pCi/m ) (pCi/kg. wet) (pCi/L) (pCi/kg, wet) (pCi/kg, dry). -2 Cross Beta 4 1 x 10 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 Zr-95 15 I-131 1 7 x 10 1 60 150 ~ -2 Cs-134 15 5 x 10 130 15 60 180 -2 Cs-137 18 6 x 10 150 18 80 mmo aas l, [ [$ Ba-140 60 60 La-140 15 15 oyo 9

a r i Table 5.1-3 (Cont.) Table Notations

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 Radio-logical Environmental Operating Report pursuant to Specification 6.9.1.10. For these radionuclides in Table 4.12-1 which are not detected, the typical LLDs for the measurement system will be separately reported in the annual report. bRequired detection capabilities-for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recom-sendations of Regulatory Guide 4.13, except for specification regarding energy-dependence. Correction factors shall be provided for energy rang 9s not meeting the energy dependence specification. The methodology for determining the LLD is contained in Appendix B. EEO 4 % t; t!8 9 1

a s e i k 1 Table 5.1-4 Sample Locations and Media for the Radiological Environmental Monitoring Program Perry Nuclear Power Plant ocotion Description Distance Direction Media (1) No. (Miles) I Redbird (Naines Road, North of West Chapel Road) 3.4 ENE APT. AI.TLD.PR, on pole 3303609; first pole south of first drivevay on left SO 2 Site boundary; Tree Line 0.7 E TLD.S0 Ash tree 1000 feet mRI of second trarsmission tower from road 3 Meteorological tower 1.0 SE APT.AI.TLD On fence surrounding the equipment shelter 4 Site Boundary 0.7 3 APT.AI.TLD,SO On pole fu?9/ SPc5-30; inside auxiliary road gate of Parmly Road 5 Site Boundary, Quincy Substation 0.6 SV APT.AI.TLD On pole #L1283/9300, east side of substation 6 Concord Service Center (Control) 11.0 SSW APT.AI.TT.D.PR, Auburn Road south of Rt. 90; on inside rear fence next to gate SO 7 Site Boundary; Lockwood Road Bus turnarrand 0.6 NE TLD On tree on right, 100 feet post the turnaround 0.8 ENE TLD 8 Site Bo,undary; Tree Line 1000 feet N of location #2 on tree near rusted manure spreader 0.7 ESE TLD 9 Site Boyndary; Transmission Line Tover Third tower from Antioch Road toward the plant 10 Site Boundary; Southsoutheast Corner Security Fence 0.8 SSE TLD Og pole at turn in the fence 0.6 SSW

TLD 11 Site Boundary; Transmission Line Tower On' tower at Su corner of Center and Parmly Roads

[828@ 0.6 USW TLD.PR,SO fgg 12 Site Bo)ndary; Transmission Line Tower Access road f on N side of Parmly just U of location f5 .... E .4.7 ENE T1.D 13 Madison-on-the-Lake At end of Whitevood Drive N of Chapel Road. oyo O I:u side of turnaround on pole #835803 ~ 14 Hubbard Rnad (South of North Ridge Road) 4.9 E TLD.S0 On pole #28974 on W side of road, S side of McMackin Creek 15 Madison Substation (Eagle Street) 5.1 ESE TLD Pirst pole next to substation near railroad tracks 9 9 e

a e Table 5.1-4 (Cont.) Samp1e Locations and Media for the Radiological Environmental Honitoring Program ~ Perry Nuclear Power Plant Lecation Description Distance Direction Media (1) (Hiles) No. 16 Dayton Road (North of Interstate 90) 5.0 SE TLD On pole #572203 on left after dirt drivevay which is just af ter the sharp lef t on Dayton af ter crossing I-90 17 Chadwick Road (Cul de Sac South of Interstate 90) 5.2 SSE TLD on pole #276222/1182011; last pole on left 18 Blair Road 5.0 S TLD.S0 on pole on left just after road makes 90 degree left cu rve from south to east heading toward Crand River Bridge 19 Lane Road and South Ridge Road 5.3 SSU TLD On pole #PC5648, 100 feet north of intersection 20 Nursery Road at Route 2 Overpass 5.3 SU TI.D.S0 On pole #828976 across from entrance to Route 2 21 !!ardy Road at Painesville Township Park 5.1 USU TLD on pole 1378345, east of park entrance 22 Painesville 6.9 SU TLD On S side of Hain Street across from Evergreen Cemetery entrance, on tree 60 feet west of pole #DBPG296 23 Fairport liarbor (Iligh Street and New Street) 7.9 USU TLD On pole on street aide of substation 24 St. Clair Avenue Substation (Control) 15.1 SU TLD In centor; on rear fence corner near railroad tracks 25 PNPP Discharge 0.6 NNU SFD.FS11 26 offshore at Redbird, vicinity of Ohio Unter Service Company Intake 4.2 ENE SED Wmo 27 of fshore, vicinity of Fairport liarbor Water Supply System Intake 7.9 USU SED E$$ 28 Ashtabula (Control), CEI Cenerating Station Intake 22.0 ENE UTR

S!

29 Hilk Farm 1.4 ESE HLK 30 Milk Farn 2.3 SSU MI.K oyoy 31 1111k Farn 1.4 ESE HLK 32 Hentor-on-the-Lake (Control) 15.8 USU S ED.FS11 33 Brockglen Farm (Control) 10.2 S HLK 34 PHPP Intake 0.7 NU UTR 35 Site Boundary, Center of Sector, follow Tree Line around 0.6 E APT.AI.TLD

~. Table 5.1-4 (Cont.) Sample Locations and Media for the Radiological Environmental Monitoring Program Perry Nuclear Power Plant location Description Distance Direction Media No. (Miles) 'TR 36 Painesville Water Supply Intake 3.9' WSW W 37 Ohio Water Service Company. Lake Erie East. Hadison; at end 4.1 EllE WTR of Green Road in Redbird 38 Fa rm a t site boundary, of f Antioch Road 1.1 E FP 39 Coldings. 3515 North Ridge Road 1.8 SSW FP 40 Antioch Road 1.1 F. FP 41 Clark Road 1.1 SW TLD ~ One-half mile from Center Road.. Located ten feet from road on tree. 42 Parmly Road 0.8 SSW TLD Approximately one-half mile from Center Road located on utility pole 582923 near southwest corner of plant fence. 43 Parmly Road 0.8 SSE TLD I Approxmiately 0.6 miles from Center Road. Approach stream ,' crossing under Parmly Road. Approximately 50 ft. from road ' located on tree. (1) APT = Air particulate AI - Air iodine TLD - Ambient gamma dose rate SED = Sediment VTR = Water FSH - Fish E7@ MLK = Milk 4%C FP = Food Products .... E' - -SO - Soil PR = Precipitation OM@ 9

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OM12D: ODCM Page : 79 Rev. : 0 Appendix A Atmospheric Dispersion and Deposition Parameters

OM12D: ODQt Page : 80 Rev. : 0 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses will be calculated using the following equations. Dose calculations will be performed hourly based on hourly meteorological and effluent data. All atmospheric releases at PNPP are considered to be ground-level releases. Constant Mean Wind Direction Relative Dispersion Factor a. f (A-1) X/Q = (G) (x) (a) Where: X/Q = the relative dispersion factor at ground level, in s/m ; T = the terrain correction factor, dimensionless; g u = the wind speed, in m/s; x = the distance of calculation, in m; 2.032 = (2/ n)b divided by the width in radians of a 22.5* sector 2 [, +"i a,* 3 a= the lesser of or 2R j i Where: H = the building height, in m; = the vertical dispersion coefficient, in m. e f I

OH12D: ODCM Page : 81 Rev. : 0 b. Depleted Relative Dispersion Factor X/Q = (X/Q)(DPL ) (A-2) d Where: X/Q = the depleted relative dispersion fget 'r (for airborne d halogens and particulates), in s/m ; DPL = the ground depletion factor for the jth distance, /nter-d polated from Table A-1, dimensionless; X/Q = the relative dispersion factor, as per equation A-1. c. Ground Deposition D/Q = (A-3) 0.3927 x Where: D/Q=therelativedepositjonperunitarea(forhalogensand particulates), in m ; h DEP = the ground deposition factor for tge j distance,. interpolated from Table A-1, in m ; T = terrain correction factor, dimensionless; g x = the j* distance, in m; 0.3927 - radians per 225* sector f f

Table A-1 Atmospheric Depletion and Deposition Factors Pasquill Distance (meters) Stability class 200 500 1,000 2,000 3,000 6,000 10,000 30,000 50,000 80,000 Deplet'on Factorn (DPL)) All 0.970 0.936 0.900 0.860 0.832 0.770 0.714 0.590 0.517 0.440 ~ Deposition Factors (DEP )(m ) All 1.25E-4 8.0E-5 5.4E-5 3.2E-5 2.6E-5 1.5E-5 9.9E-6 4.5E-6 3.0E-6 2.0E-6 3 ?50

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.... ? $8 9

f OM12D: ODCM Page : 83 Rev. : 0 The following tables contain annual average atmospheric dispersion and deposition parameters for long-term releases at PNPP. Long-term releases are those that occur greater than 500 hours per year. The highest annual average relative concentration (X/Q) value at the sight boundary for sectors overland shall be used for radioactive gaseous effluent monitor setpoint calculations. The dispersion model used was XOQD0Q, with PNPP FSAR site-specific terrain adjustment factors included. Dispersion values are based on the three FSAR years of meteorological data, ground-level releases, sector spread for purge ' calculations, and twelve wind speed classes. 4 94

9 OM12D: ODCM Page : 84 Rev. : 0 Table A-2 Site Boundary Atmospheric Dispersion and Deposition Parameters for PNPP Unit 1 SECTOR DISTANCE X/G D/G (MILES) (SEC. /. CUD. METER) (PER SG. METER) N O.18 5.863E-05 1.636E-07 NNE O.25 1.808E-05 7.555E-08 6.530E-06 3.291E-08 NE O.42 2.023E-06 1.633E-08 ENE O. 67 2.177E-06 1.626E-08 E O.69 ESE O.70 1.425E-06 1.028E-08 SE O.84 1.277E-06 8.144E-09 SSE O.90 1.958E-06 1.205E-08 S O.88 2.325E-06 1.370E-08 i 1.112E-06 5.215E-09 SSW O.90 SW O.65 2.598E-06 1.291E-08 WSW O.56 4.622E-06 1.447E-08 W O.27 3.273E-05 5.301E-08 WNW O.18 6.859E-05 8.426E.-08 NW O.17 7.902E-05 1.283E-07 NNW O.17 6.151E-05 1.220E-07 I Table A-3 Atmospheric Dispersion and Deposition Parameters at the Nearest Residences for PNPP Unit 1 SECTOR DISTANCE X/G D/G (MILES) (SEC./ CUD. METER) (PER SG. METER) S O.79 2.754E-06 1.649E-08 SSW O. 61 2.042E-06 9.976E-09 SW. 1.22 9.859E-07 4.415E-09 WSW 1.04 1.031E-06 2.943E-09 .NE O. 63 3.537E-06 1.735E-08 ENE O.79 1.560E-06 1.236E-08 E 1.10 7.163E-07 4.987E-09 ESE 1.15 4.544E-07 3.062E-09 SE

1. 19 4.042E-07 2.438E-09 SSE O.85 2.130E-06 1.321E-08 h

t OM12D: ODCM Page : 85 Rev. : 0 Table A 4 Atmospheric Dispersion (X/Q) as a Function of Distance (s/m ) O. 4 O. 5 O. 6 SECTOR O. 2 O. 3 , (MILES) (MILES) (MILES) (MILES) (MILES) 5.OOSE-05 2.518E-05 1.574E-05 1.097E-05 8.265E-06 N NNE 2.635E-05 1.355E-05 8.634E-06 6.091E-06 4.628E-06 NE 2.091E-05 1.099E-05 7.073E-06 5.OO7E-06 3.793E-06 1.293E-05 6.949E-06 4.504E-06 3.192E-06 2.410E-06 ENE 1.459E-05 7.824E-06 5.044E-06 3.564E-06 2.690E-06 E 9.899E-06 5.327E-06 3.443E-06 2.433E-06 1.830E-06 ESE 1.157E-05 6.226E-06 4.033E-06 2.856E-06 2.153E-06 SE SSE 1.964E-05 1.054E-05 6.844E-06 4.860E-06 3.676E-06 2.342E-05 1.246E-05 8.011E-06 5.654E-06 4.262E-06 S 1.145E-05 6.111E-06 3.955E-06 2.800E-06 2.110E-06 SSN 1.612E-05 8.585E-06 5.543E-06 3.921E-06 2.956E-06 SW 2.404E-05 1.244E-05 7.857E-06 5.498E-06 4.144E-06 WSW 5.411E-05 2.692E-05 1.657E-05 1.142E-05 8.537E-06 W 5.461E-05 2.689E-05 1.639E-05 1.119E-05 8.266E-06 WNW 5.907E-05 2.920E-05 1.790E-05 1.228E-05 9.112E-06 NW 4.811E-05 2.383E-05 1.464E-05 1.OO6E-05 7.482E-06 NNW SECTOR O. 7 O. 8 O. 9

1. O

1. 1 (MILES)

(MILES) (MILES) (MILES) (MILES) 6.444E-06 5.23%E-06 4.420E-06 3.816E-06 2.042E-06 N 3.641E-06 2.965E-06 2.494E-06 2.141E-06 1.283E-06 NNE 2.982E-06 2.424E-06 2.032E-06 1.738E-06 1.038E-06 NE ENE 1.892E-06 1.534E-06 1.279E-06 1.~O88E-06 6.461E-07 E 2.111E-06 1.711E-06 1.426E-06 1.213E-06 7.206E-07 ESE 1.433E-06 1.160E-06 9.651E-07 8.199E-07 4.864E-07 SE 1.689E-06 1.36BE-06 1.138E-06 9.670E-07 4.590E-07 2.892E-06 2.346E-06 1.952E-06 1.658E-06 5.722E-07 SSE 3.341E-06 2.707E-06 2.256E-06 1.921E-06 7.380E-07 S SSN 1.653E-06 1.339E-06 1.116E-06 9.505E-07 5.231E-07 2.316E-06 1.877E-06 1.568E-06 1.337E-06 6.371E-07 SW-3.238E-06 2.628E-06 2.209E-06 1.897E-06 9.570E-07 WSW 6.602E-06 5.342E-06 4.527E-06 3.923E-06 2.106E-06 W 6.316E-06 5.080E-06 4.316E-06 3.755E-06 2.142E-06 WNW 6.995E-06 5.639E-06 4.785E-06 4.156E-06 2.367E-06 NW 5.756E-06 4.644E-06 3.938E-06 3.417E-06 1.945E-06 NNW

l OM12D: ODCM Page : 86 l 1 Rev. : 0 Table A-4 (Cont.) Atmospheric Dispersion (X/Q) as a Function of Distance (s/m ) SECTOR

1. 2

1. 3

1. 4

1. 5

1. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 1.809E-06 1.618E-06 1.460E-06 1.327E-06 1.214E-06 NNE 1.131E-06 1.008E-06 9.058E-07 8.203E-07 7.482E-07 9.123E-07 8.107E-07 7.268E-07 6.567E-07 5.977E-07 NE 5.656E-07 5.005E-07 4.470E-07 4.024E-07 3.650E-07 ENE 6.307E-07 5.581E-07 4.984E-07 4.487E-07 4.070E-07 E 4.253E-07 3.760E-07 3.355E-07 3.018E-07 2.735E-07 ESE 4.013E-07 3.547E-07 3.165E-07 2.846E-07 2.580E-07 SE 5.OO3E-07 4.422E-07 3.945E-07 3.549E-07 3.216E-07 SSE 6.463E-07 5.722E-07 5.113E-07 4.605E-07 4.179E-07 5 4.582E-07 4.058E-07 3.627E-07 3.267E-07 2.966E-07 SSW 5.588E-07 4.955E-07 4.433E-07 3.998E-07 3.632E-07 SW 8.441E-07 7.521E-07 6.761E-07 6.123E-07 5.585E-07 WSW W 1.871E-06 1.678E-06 1.518E-06 1.382E-06 1.267E-06 1.909E-06 1.718E-06 1.558E-06 1.422E-06 1.307E-06 WNW 2.107E-06 1.893E-06 1.715E-06 1.564E-06 1.436E-06 NW NNW 1.730E-06 1.553E-06 1.406E-06 1.282E-06 1.176E-06 SECTOR g,7 g, g g,9

2. 0

2. 1 (MILES)

(MILES) (MILES) (MILES) (MILES) N 1.116E-06 1.031E-06 9.573E-07 8.920E-07 8.341E-07 NNE 6.860E-07 6.321E-07 5.852E-07 5.439E-07 5.074E-07 NE 5.469E-07 5.030E-07 4.648E-07 4.313E-07 3.652E-07 ENE 3.329E-07 3.053E-07 2.813E-07 2.603E-07 2.419E-07 E 3.712E-07 3.403E-07 3.136E-07 2.902E-07 2.451E-07 ESE 2.493E-07 2.285E-07 2.104E-07 1.946E-07 1.807E-07 SE 2.351E-07 2.154E-07 1.984E-07 1.835E-07 1.703E-07 SSE 2.931E-07 2.686E-07 2.473E-07 2.287E-07 1.460E-07 S 3.813E-07 3.498E-07 3.225E-07 2.985E-07 1.387E-07 2.707E-07 2.484E-07 2.290E-07 2.120E-07 1.408E-07 SSW 3.318E-07 3.047E-07 2.811E-07 2.605E-07 2.423E-07 SW 5.120E-07 4.718E-07 4.368E-07 4.060E-07 5.854E-07 WSW W 1.168E-06 1.081E-06 1.005E-06 9.377E-07 1.357E-06 WNW 1.206E-06 1.119E-06 1.042E-06 9.740E-07 1.329E-06 NW 1.324E-06 1.227E-06 1.142E-06 1.067E-06 1.OOOE-06 NNW 1.084E-06 1.OOSE-06 9.345E-07 8.727E-07 8.177E-07 A -u.

OM12D: ODCM Page : 87 Rev. : 0 Table A-4 (Cont.) Atmospheric Dispersion (X/Q) as a Function of Distance (s/m ) SECTOR

2. 2

2. 3

2. 4

2. 5

2. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 7.825E-07 7.362E-07 6.945E-07 6.568E-07 6.228E-07 NNE 4.750E-07 4.459E-07 4.199E-07 3.963E-07 3.751E-07 NE 3.413E-07 3.2OOE-07 3.OO8E-07 2.836E-07 2.680E-07 ENE 2.255E-07 2.109E-07 1.979E-07 1.861E-07 1.756E-07 2.2SSE-07 2.137E-07 2.OOSE-07 1.886E-07 1.779E-07 E ESE 1.683E-07 1.574E-07 1.476E-07 1.387E-07 1.308E-07 SE 1.587E-07 1.484E-07 1.391E-07 1.308E-07 1.233E-07 SSE-1.360E-07 1.272E-07 1.192E-07 1.121E-07 1.057E-07 S 1.294E-07 1.211E-07 1.136E-07 1.069E-07 1.OO9E-07 SSW 1.313E-07 1.229E-07 1.153E-07 1.085E-07 1.024E-07 2.262E-07 2.118E-07 1.989E-07 1.873E-07 1.768E-07 SW-5.479E-07 5.144E-07 4.843E-07 4.572E-07 4.327E-07 WSW W 1.275E-06'1.201E-06 1.134E-06 1.074E-06 1.019E-06 1.250E-06 1.179E-06 1.116E-06 1.058E-06 1.005E-06 WNW 9.402E-07 8.865E-07 8.380E-07 7.941E-07 7.543E-07 NW 7.686E-07 7.245E-07 6.847E-07 6.486E-07 6.159E-07 NNW SECTOR

2. 7

2. 8

2. 9

3. 0 3.1 (MILES)

(MILES) (MILES) (MILES) (MILES) 5.915E-07 5.629E-07 5.367E-07 5.125E-07 4.902E-07 N 3.556E-07 3.378E-07 3.216E-07 3.066E-07 2.928E-07 'NNE 2.538E-07 2.409E-07 2.290E-07 2.181E-07 2.080E-07 NE ENE 1.'659E-07 1.571E-07 1.491E-07 1.418E-07 1.350E-07 E 1.681E-07 1.592E-07 1.511E-07 1.436E-07 1.368E-07 ESE 1.236E-07 1.170E-07 1.110E-07 1.055E-07 9.127E-08 SE 1.165E-07 1.103E-07 1.046E-07 9.939E-08 9.461E-08 9.984E-08 9.452E-08 8.965E-08 8.520E-08 8.111E-08 SSE 9.536E-08 9.034E-08 8.575E-08 8.155E-08 7.769E-08 S 9.685E-08 9.176E-08 8.712E-08 8.'286E-08 7.894E-08 SSW SW 1.673E-07 1.586E-07 1.506E-07 1.433E-07 1.366E-07 4.102E-07 3.897E-07 3.709E-07 3.537E-07 2.781E-07 WSW 9.693E-07 9.234E-07 8.812E-07 8.423E-07 7.589E-07 W 9.568E-07 9.12SE-07 8.717E-07 8.341E-07 8.991E-07 WNW .7.177E-07 6.841E-07 6.533E-07 6.248E-07 6.529E-07 NW 5.859E-07 5.584E-07 5.331E-07 5.097E-07 4.802E-07 NNW t

c-OM12D: ODCM Page : 88 Rev. : 0 Table A 4 (Cont.) Atmospheric Dispersion (X/Q) as a Function of Distance (s/m ) SECTOR

3. 2

3. 3

3. 4

3. 5

3. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 4.695E-07 4.503E-07 4.325E-07 4.158E-07 4.OO4E-07 NNE 2.800E-07 2.682E-07 2.572E-07 2.470E-07 2.376E-07 NE 1.988E-07 1.902E-07 1.822E-07 1.748E-07 1.680E-07 ENE 1.288E-07 1.230E-07 1.177E-07 1.127E-07 1.082E-07 E 1.305E-07 1.246E-07 1.192E-07 1.142E-07 1.096E-07 ESE 8.702E-08 8.310E-08 7.947E-08 7.608E-08 7.299E-08 9.021E-08 8.615E-08 8.238E-08 7.886E-08 7.565E-08 SE SSE 7.733E-08 7.385E-08 7.062E-08 6.761E-08 6.485E-08 7.412E-08 7.083E-08 6.778E-08 6.492E-08 6.232E-08 S 7.532E-08 7.198E-08 6.889E-08 6.599E-08 6.335E-08 SSW SW 1.304E-07 1.247E-07 1.194E-07 1.144E-07 1.099E-07 WSW 2.660E-07 2.548E-07 2.444E-07 2.346E-07 2.256E-07 W 7.275E-07 6.984E-07 6.713E-07 6.458E-07 6.22SE-07 WNW 8.628E-07 8.290E-07 7.975E-07 7.679E-07 7.408E-07 NW 6.263E-07 6.015E-07 5.785E-07 5.568E-07 5.369E-07 NNW _4.682E-07 4.496E _07 4.323E-07 4.160E-07 4.011E-07 SECTOR

3. 7

3. 8

3. 9

4. 0

4. 1 (MILES)

(MILES) (MILES) (MILES) (MILES) N 3.859E-07 3.723E-07 3.594E-07 3.474E-07 3.055E-07 NNE 2.286E-07 2.203E-07 2.125E-07 2.051E-07 1.802E-07 NE 1.615E-07 1.555E-07 1.498E-07 1.445E-07 1.395E-07 ENE 1.039E-07 9.984E-08 9.608E-08 9.255E-08 8.924E-08 E 1.052E-07 1.011E-07 9.731E-08 9.374E-08 9.038E-08 ESE 7.OO7E-08 6.733E-08 6.478E-08 6.238E-08 6.013E-08 SE 7.262E-08 6.978E-08 6.713E-08 6.465E-OB 5.665E-08 SSE '6.226E-08 5.983E-08 5.756E-08 5.543E-08 5.343E-08 5 5.985E-08 5.755E-08 5.540E-08 5.338E-08 5.148E-08 SSW 6.085E-08 5.852E-08 5.633E-08 5.428E-08 5.235E-08 SW 1.056E-07 1.015E-07 9.779E-08 9.426E-08 9.094E-08 WSW 2.172E-07 2.092E-07 2.018E-07 1.948E-07 1.614E-07 W 6.OO3E-07 5.795E-07 5.600E-07 5.416E-07 3.932E-07 WNW 7.150E-07 6.907E-07 6.679E-07 6.464E-07 4.870E-07 NW 5.181E-07 5.OO3E-07 4.837E-07 4.680E-07 4.532E-07 m -3.869E-07 3.736E-07 3.611E-07_3,A9_4E_07 3.,07.5E-07 -, - NNW - -~-

OM12D: ODCM Page : 89 Rev. : 0 Table A-4 (Cont.) Atmospheric Dispersion (X/Q) as a Function of Distance (s/m ) SECTOR

4. 2

4. 3

4. 4

4. 5

4. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) 2.958E-07 2.866E-07 2.779E-07 2.696E-07 2.618E-07 N NNE 1.742E-07 1.686E-07 1.633E-07 1.583E-07 1.536E-07 NE 1.348E-07 1.304E-07 1.262E-07 1.222E-07 1.185E-07 8.612E-08 8.319E-08 8.042E-08 7.779E-08 7.534E-08 ENE 8.723E-08 8.425E-08 8.144E-08 7.878E-08 7.630E-08 E 5.802E-08 5.603E-08 5.415E-08 5.236E-08 5.071E-08 ESE 5.465E-08 5.278E-08 5.100E-08 4.932E-08 4.776E-08 SE 5.154E-08 4.977E-08 4.810E-08 4.652E-08 4.504E-08 SSE 4.969E-08 4.801E-08 4.642E-08 4.491E-08 4.351E-08 S 5.054E-08 4.883E-08 4.722E-08 4.568E-08 4.426E-08 SSW 8.782E-08 8.488E-08 8.211E-08 7.947E-08 7.701E-08 SW WSW 1.560E-07 1.510E-07 1.463E-07 1.418E-07 1.376E-07 3.809E-07 3.692E-07 3.582E-07 3.'477E-07 3.380E-07 W 4.721E-07 4.580E-07 4.447E-07 4.319E-07 4.2OOE-07 WNW 4.392E-07 4.260E-07 4.134E-07 4.015E-07 3.903E-07 NW 2.980E-07 2.890E-07 2.804E-07 2.723E-07 2.647E-07 NNW SECTOR 4, 7

4. 8

4. 9

5. 0 (MILES)

(MILES) (MILES) (MILES) 2.544E-07 2.473E-07 2.406E-07 2.342E-07 N NNE 1.491E-07 1.448E-07 1.408E-07 1.369E-07 NE 1.150E-07 1.116E-07 1.084E-07 1.053E-07 7.3OOE-08 7.078E-08 6.868E-08 6.668E-08 ENE 7.393E-08 7.168E-08 6.955E-08 6.753E-08 E i 4.912E-08 4.762E-08 4.619E-08 4.484E-08 ESE ( 4.626E-08 4.484E-08 4.350E-08 4.222E-08 SE 4.363E-08 4.230E-08 4.103E-08 3.983E-08 SSE 4.216E-08 4.089E-08 3.968E-08 3.854E-08 S SSW 4.290E-08 4.161E-08 4.038E-08 3.921E-08 i SW 7.466E-08 7.243E-08 7.031E-08 6.830E-08 WSW 1.335E-07 1.297E-07 1.261E-07 1.226E-07 W 3.285E-07 3.196E-07 3.111E-07 3.029E-07 4.086E-07 3.977E-07 3.873E-07 3.774E-07 WNW 3.796E-07 3.694E-07 3.597E-07 3.504E-07 NW l 2.574E-07 2.504E-07 2.438E-07 2.375E-07 NNW ~ ~~

Otll2D: ODCM Page : 90 Rev. : 0 Table A-5 Atmospheric Deposition (D/Q) as a Function of Distance (m- ) SECTOR O. 2

0. 3 O. 4

0. 5

0. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 1.432E-07 7.772E-08 4.960E-08 3.470E-08 2.580E-08 NNE 1.052E-07 5.711E-08 3.645E-08 2.550E-08 1.896E-08 1.031E-07 5.596E-08 3.572E-08 2.498E-08 1.858E-08 NE 1.OS6E-07 5.894E-08 3.762E-08 2.631E-08 1.957E-08 ENE 1.124E-07 6.100E-08 3.893E-08 2.723E-08 2.025E-08 .E 7.390E-08 4.012E-08 2.560E-08 1.791E-08 1.332E-08 ESE 7.853E-08 4.263E-08 2.721E-08 1.903E-08 1.416E-08 SE 1.312E-07 7.124E-08 4.546E-08 3.180E-08 2.365E-08 SSE 1.449E-07 7.865E-08 5.019E-08 3.511E-08 2.611E-08 S SSW 5.725E-08 3.-108E-08 1.984E-08 1.388E-08 1.032E-08 8.160E-08 4.430E-08 2.827E-08 1.978E-08 1.471E-08 SW 7.160E-08 3.887E-08 2.481E-08 1.735E-08 1.291E-08 WSW 8.173E-08 4.437E-08 2.832E-08 1.981E-08 1.473E-08 W WNW 6.974E-08 3.786E-08 2.416E-08 1.690E-08 1.257E-08 1.008E-07 5.471E-08 3.491E-08 2.442E-08 1.816E-08 NW 9.945E-08 5.399E-08 3.446E-08 2.410E-08 1.793E-08 NNW SECTOR O. 7

0. 8

0. 9

1. 0

1. 1 (MILES)

(MILES) (MILES) (MILES) (MILES) N 2.004E-08 1.600E-08 1.310E-08 1.095E-08 5.686E-09 NNE 1.473E-08 1.176E-08 9.627E-09 8.047E-09 4.701E-09 NE 1.443E-08 1.152E-08 9.434E-09 7.885E-09 4.607E-09: ENE-1.520E-08 1.213E-08 9.936E-09 8.305E-09 4.852E-09 E 1.573E-08 1.~255E-08 1.028E-08 8.594E-09 5.021E-09 -ESE-1.034E-08 8.258E-09 6.763E-09 5.653E-09 3.302E-09 -SE 1.099E-08 8.775E-09 7.187E-09 6.007E-09 2.807E-09 SSE-1.837E-08 1.466E-08 1.201E-08 1.004E-08 3.412E-09 S 2.028E-08 1.619E-08 1.326E-08 1.108E-08 4.185E-09 SSW 8.014E-09 6.397E-09 5.239E-09.4.379E-09 2.368E-09 SW 1.142E-08.9.119E-09 7.468E-09 6.242E-09 2.917E-09 WSW 1.OO2E-08 8.OO1E-09 6.552E-09 5.'477E-09 2.694E-09 W 1.144E-08 9.133E-09 7.480E-09 6.252E-09 3.247E-09 WNW 9.763E-09 7.793E-09 6.383E-09 5.335E-09 2.933E-09 NW-1.411E-08 1.126E-08 9.222E-09 7.708E-09 4.238E-09 NNW-1.392E-08 1.111E-08 9.102E-09 7.607E-09 4.183E-09 i

OM12D: ODCM Page : 91 Rev. : 0 Table A-5 (Cont.) Atmospheric Deposition (D/Q) as a Function of Distance (m- ) SECTOR

1. 2

1. 3

1. 4

1. 5

1. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) 4.899E-09 4.269E-09 3.757E-09 3.335E-09 2.984E-09 N 4.050E-09 3.529E-09 3.106E-09 2.757E-09 2.467E-09 NNE 3.968E-09 3.458E-09 3.044E-09 2.702E-09 2.418E-09 NE 4.180E-09 3.642E-09 3.206E-09 2.845E-09 2.546E-09 ENE 4.325E-09 3.769E-09 3.317E-09 2.945E-09 2.635E-09 E ESE 2.845E-09 2.479E-09 2.182E-09 1.937E-09 1.733E-09 2.418E-09 2.108E-09 1.855E-09 1.646E-09 1.473E-09 SE 2.939E-09 2.561E-09 2.254E-09 2.OO1E-09 1.790E-09 SSE 3.605E-09 3.142E-09 2.765E-09 2.454E-09 2.196E-09 S 2.040E-09 1.778E-09 1.565E-09 1.389E-09 1.243E-09 SSW SW 2.513E-09 2.190E-09 1.928E-09 1.711E-09 1.531E-09 2.321E-09 2.023E-09 1.780E-09 1.580E-09 1.414E-09 WSW W 2.797E-09 2.437E-09 2.145E-09 1.904E-09 1.704E-09 WNW 2.527E-09 2.202E-09 1.938E-09 1.720E-09 1.539E-09 3.651E-09 3.182E-09 2.800E-09 2.486E-09 2.224E-09 NW 3.603E-09 3.140E-09 2.764E-09 2.453E-09 2.195E-09 NNW SECTOR

1. 7

1. 8

1. 9

2. O

2. 1 (MILES)

(MILES) (MILES) (MILES) (MILES) N 2.686E-09 2.432E-09 2.213E-09 2.023E-09 1.858E-09 NNE 2.221E-09 2.010E-09 1.830E-09 1.673E-09 1.536E-09 NE 2.176E-09 1.970E-09 1.793E-09 1.639E-09 1.368E-09 2.292E-09 2.075E-09 1.888E-09 1.726E-09 1.585E-09 ENE 2.372E-09 2.147E-09 1.954E-09 1.786E-09 1.491E-09 E ESE 1.560E-09 1.412E-09 1.285E-09 1.175E-09 1.079E-09 SE 1.326E-09 1.201E-09 1.093E-09 9.989E-10 9.172E-10 SSE 1.612E-09 1.459E-09 1.328E-09 1.214E-09 7.663E-10 S 1.977E-09 1.790E-09 1.629E-09 1.489E-09 6.836E-10 SSW 1.119E-09 1.013E-09 9.216E-10 8.426E-10 5.526E-10 SW 1.378E-09 1.248E-09 1.135E-09 1.038E-09 9.531E-10 WSW 1.273E-09 1.152E-09 1.049E-09 9.587E-10 1.360E-09 W 1.534E-09 1.388E-09 1.264E-09 1.155E-09 1.639E-09 WNW 1.386E-09 1.254E-09 1.142E-09 1.044E-09 1.394E-09 NW 2.OO2E-09 1.812E-09 1.649E-09 1.508E-09 1.385E-09 NNW --~ -- -1w976E-09 1.709E-09 1.628E-09 1.488E-09_1.367E-09,_,

OM12D: ODCM 92 Page : Rev. : 0 Table A-5 (Cont.) Atmospheric Deposition (D/Q) as a Function of DLstance (m- ) SECTOR

2. 2

2. 3

2. 4

2. 5

2. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 1.712E-09 1.584E-09 1.470E-09 1.368E-09 1.277E-09 NNE 1.416E-09 1.309E-09 1.215E-09 1.131E-09 1.056E-09 NE 1.261E-09 1.166E-09 1.082E-09 1.OO7E-09 9.404E-10 ENE 1.461E-09 1.351E-09 1.254E-09 1.167E-09 1.089E-09 E 1.374E-09 1.271E-09 1.180E-09 1.098E-09 1.02SE-09 9.944E-10 9.198E-10 8.535E-10 7.943E-10 7.416E-10 ESE 3.454E-10 7.819E-10 7.256E-10 6.752E-iO 6.304E-10 SE 7.063E-10 6.533E-10 6.062E-10 5.641E-10 5.267E-10 SSE 6.301E-10 5.828E-10 5.408E-10 5.033E-10 4.699E-10 S 5.093E-10 4.711E-10 4.371E-10 4.06SE-10 3.798E-10 HSSW 8.785E-10 8.126E-10 7.540E-10 7.017E-10 6.551E-10 SW 1.254E-09 1.160E-09 1.076E-09 1.OO2E-09 9.350E-10 WSW W !.511E-09 1.398E-09 1.297E-09 1.207E-09 1.127E-09 WNW 1.285E-09 1.188E-09 1.103E-09 1.026E-09 9.581E-10 NW 1.276E-09 1.180E-09 1.095E-09 1.019E-09 9.517E-10 1.260E-09 1.165E-09 1.081E-09 1.OO6E-09 9.393E-10 NNW SE(HOR

2. 7

2. 8

2. 9

3. 0 3.1 (MILES)

(MILES) (MILES) (MILES) (MILES) N 1.195E-09 1.120E-09 1.053E-09 9.913E-10 9.353E-10 NNE 9.876E-10 9.261E-10 8.703E-10 8.195E-10 7.732E-10 NE 8.797E-10 8.250E-10 7.753E-10 7.301E-10 6.888E-10 ENE 1.019E-09 9.557E-10 8.982E-10 8.458E-10 7.980E-10 E 9.588E-10 8.991E-10 8.450E-10 7.957E-10 7.507E-10 ESE 6.937E-10 6.505E-10 6.114E-10 5.757E-10 4.938E-10 RSE - 5.898E-10 5.530E-10 5.197E-10 4.894E-10 4.618E-10 SSE 4.927E-10 4.620E-10 4.342E-10 4.089E-10 3.858E-10 S 4.396E-10 4.122E-10 3.874E-10 3.648E-10 3.442E-10 SSW 3.553E-10 3.332E-10 3.131E-10 2.949E-10 2.782E-10 L SW 6.129E-10 5.747E-10 5.401E-10 5.086E-10 4.798E-10 WSW 8.748E-10 8.203E-10 7.709E-10 7.259E-10 5.640E-10 [. W 1.054E-09 9.884E-10 9.289E-10 8.747E-10 7.767E-10 l WNW 8.963E-10 8.405E-10 7.899E-10 7.438E-10 7.895E-10 8.903E-10 8.349E-10 7.846E-10 7.3G8E-10 7.604E-10 L,, _,,, NW. NNW. 8.787E-10 8.240E-10'7.744E;10'7.292E-10 6.880E ~ f i

OM12D: ODCM Page : 93 Rev. : 0 i Table A-5 (Cont.) Atmospheric Deposition (D/Q) as a Function of Distance (m~ ) i SECTOR

3. 2

3. 3

3. 4

3. 5

3. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 8.840E-10 8.369E-10 7.936E-10 7.534E-10 7.170E-10 NNE 7.308E-10 6.919E-10 6.561E-10 6.229E-10 5.927E-10 j-NE 6.510E-10 6.164E-10 5.845E-10 5.549E-10 5.280E-10 ENE 7.542E-10 7.141E-10 6.771E-10 6.428E-10 6.117E-10 E 7.096E-10 6.718E-10 6.370E-10 6.048E-10 5.755E-10 ESE 4.667E-10 4.419E-10 4.190E-10 3.978E-10 3.785E-10 SE 4.364E-10 4.132E-10 3.918E-10 3.720E-10 3.540E-10 SSE 3.646E-10 3.452E-10 3.273E-10 3.100E-10 2.957E-10 S 3.253E-10 3.080E-10 2.920E-10 2.772E-10 2.638E-10 SSW 2.629E-10 2.489E-10 2.361E-10 2.241E-10 2.133E-10 SW '4.535E-10 4.294E-10 4.072E-10 3.865E-10 3.678E-10 WSW 5.331E-10 5.047E-10 4.786E-10 4.544E-10 4.324E-10 W 7.341E-10 6.950E-10 6.591E-10 6.257E-10 5.954E WNW 7.462E-10 7.065E-10 6.699E-10 6.360E-10 6.052E-10 NW 7.187E-10 6.805E-10 6.453E-10 6.126E-10 5.829E-10. NNW 6.503E-10 6.156E-10 5.838E-10 5.542E-10 5.274E-10 SECTOR

3. 7

3. 8

3. 9.

4. O 4.' 1 (MILES)

(MILES) (MILES) (MILES) (MILES) N 6.827E-10 6.509E-10 6.214E-10 5.939E-10 5.165E-10 NNE 5.644E-10 5.382E-10 5.137E-10 4.910E-10 4.270E-10 NE 5.028E-10 4.794E-10 4.576E-10 4.373E-10 4.184E-10 ENE 5.825E-10 5.554E-10 5.302E-10 5.067E-10 4.847E-10 E 5.480E-10 5.225E-10 4.988E-10 4.767E-10 4.560E-10 ESE 3.604E-10 3.437E-10 3.281E-10 3.135E-10 3.OOOE-10 SE 3.371E-10 3.214E-10 3.068E-10 2.932E-10 2.550E-10 SSE 2.816E-10 2.685E-10 2.563E-10 2.449E-10 2.343E-10 S 2.512E-10 2.395E-10 2.287E-10 2.185E-10 2.091E-10 SSW 2.031E-10 1.936E-10 1.848E-10 1.766E-10 1.690E-10 SW 3.503E-10 3.340E-10 3.186E-10 3.047E-10 2.915E-10 WSW 4.117E-10 3.926E-10 3.747E-10 3.581E-10-2.937E-10 W 5.670E-10 5.406E-10 5.160E-10 4.932E-10 3.539E-10 WNW 5.763E-10 5.495E-10 5.245E-10 5.013E-10 3.730E-10 5.551E-10 5.293E-10 5.052E-10 4.828E-10 4.619E-10 NW. NNW 5.022E-10 4.788E-10 4.571E-10 4.368E-10 3.799E-10

OM12D: ODCM Page : 94 Rev. : 0 Table A-5 (Cont.) Atmospheric Deposition (D/Q) as a Function of Distance (m' ) SECTOR

4. 2

4. 3

4. 4

4. 5

4. 6 (MILES)

(MILES) (MILES) (MILES) (MILES) N 4.947E-10 4.742E-10 4.550E-10 4.369E-10 4.202E-10 NNE 4.089E-10 3.920E-10 3.762E-10 3.612E-10 3.474E-10 NE 4.OO7E-10 3.841E-10 3.686E-10 3.539E-10 3.404E-10 ENE 4.642E-10 4.450E-10 4.270E-10 4.100E-10 3.943E-10 E 4.367E-10 4.187E-10 4.017E-10 3.857E-10 3.710E-10 ESE 2.873E-10 2.754E-10 2.642E-10 2.537E-10 2.440E-10 SE 2.442E-10 2.341E-10 2.24'6E-10 2.157E-10 2.074E-10 SSE 2.244E-10 2.151E-10 2.064E-10 1.982E-10 1.906E-10 S 2.OO2E-10 1.919E-10 1.842E-10 1.768E-10 1.701E-10 SSW 1.618E-10 1.552E-10 1.489E-10 1.429E-10 1.375E-10 SW 2.792E-10 2.676E-10 2.568E-10 2.466E-10 2.371E-10 WSW 2.813E-10 2.696E-10 2.587E-10 2.484E-10 2.389E-10 W 3.389E-10 3.249E-10 3.117E-10 2.993E-10 2.879E-10 WNW 3.572E-10 3.425E-10 3.286E-10 3.155E-10 3.034E-10 NW 4.424E-10 4.241E-10 4.069E-10 3.907E-10 3.75SE-10 NNW 3.639E-10 3.488E-10 3.347E-10 3.214E-10 3.091E-10 4 SECTOR

4. 7

4. 8

4. 9

5. 0 (MILES)

(MILES) (MILES) (MILES) C N 4.042E-10 3.892E-10 3.749E-10 3.615E-10 NNE 3.342E-10 3.217E-10 3.100E-10 2.989E-10 NE 3.274E-10 3.153E-10 3.037E-10 2.929E-10 ENE 3.793E-10 3.652E-10 3.519E-10 3.393E-10 E 3.569E-10 3.436E-10 3.311E-10 3.192E-10 ESE 2.347E-10 2.260E-10 2.178E-10 2.100E-10 SE 1.996E-10 1.921E-10 1.851E-10 1.785E-10 SSE 1.834E-10 1.766E-10 1.701E-10 1.640E-iO 5 1.636E-10 1.575E-10 1.518E-10 1.463E-10 SSW 1.323E-10 1.273E-10 1.227E-10 1.183E-10 SW 2.281E-10 2.196E-10 2.116E-10 2.040E-10 WSW 2.298E-10 2.213E-10 2.132E-10 2.056E-10 W 2.769E-10 2.666E-10 2.569E-10 2.477E-10 WNW 2.919E-10 2.810E-10 2.708E-10 2.611E-10 .NW 3.615E-10 3.48DE-1D_3.353E-10.3.233E-10 NNW 2.9735-10 2.863E-10 2.758E-10 2.659E-10 b

OM12D: ODCM Page : 95 Rev. : 0 t APPENDIX B Lower Limit of Detection l l I f 1 ? l. I

I i OM12D: ODCM Page : 96 Rev. : 0 The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with a 95 percent probability with a 5 percent probability of falsely concluding that a blank observation represents a "real" signal. For a measurement system (which may include radiochemical separation) based on gross beta, gross alpha, liquid scintillatirn, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from che gross sample count to obtain a net count due to sample activity: )h 3.3;f

b
b (B-1)

+ ( s b / LLD = (C)(E)(V)(Y ) exp (- K h.t) Where: LLD = the "apriori" lower limit of detection..as defined above; C = the conversion factor of transformations per unit time-per uCi or pCi; E = the detector efficiency; r = the background c:unt rate in units of transformations b per unit time; t = the counting tire of background; b t, = the counting time of the sample; V = the sample size, in units of mass or volume; Y = the fractional radiochemical sample collection or concen-tration yield (when applicable); ht = for plant effluents, the elapsed time between the midpoint of semple collection and time of counting; for environ-l mental samples, the elapsed time between sample collection (or _end of the sample collection period) and time of counting; K = the.r dicactive der.ay ronstant. f or_the radionuclide in 1 -- L question. E ks

OM12D: ODCM Page : 97 Rev. : 0 The LLD is defined as an "apriori" (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. For gamma ray spectroscopy analyses (Canberra Spectran - F Version 2): L exP (0.693 ht/t ) D q (C)(E)(t)(V)(Y )(Y7) Where: LLD = the lower limit of detection, in uCi or pCi per unit mass or volume; C = the conversion factor of transformations per unit time per uCi or pCi; E = the detector efficiency for the energy in question; t = the data collection (counting) time of sample; g = the half-life of the radionuclide in question; t V = the sample size, in units of mass or volume; Y = the fractional radiochemical, sample collection, or con-centration yield (when applicable); Y.y = the yield of the gamma ray in question; ht = for plant effluents the elapsed time between midpoint of sample collection and time of counting; for environ-mental samples, the elapsed time between sample collec-tion (or end of the sample collection period) and the time of counting; L.-.---...-.

OM12D: ODCM Page : 98 Rev. : 0 L = the detection limit D f = k' + 2k _N (1 + N_) (B

B)*I*

8 1 (B-2a) 1 2 I (2n 2n / Where: B = the number of counts in n background channels below the y peak due to Cocpton scattering, etc., determined at the same time a photopeak is measured; B = the number of counts in the n background channels above 2 the peak; k = an abscissa of the normal' distribution corresponding to confidence level, = 1.645 at a confidence level of 95%; I = the measured value of interference in the photopeak of interest due to environmental background, detector contamination, etc., determined by a separate measurement with no sample; N = the number of channels in the photopeak of interest; n = the number of background channels on each side of the photopeak of interest; a = the standard deviation of I. 7 Typical values of E, V, Y, and 6 e shall be used in the calculation. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the backgrcund shall include tre typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11-1, 4.11-2 and 4.12-1 of the Radiological Effluent Technical Specifications for the Perry Nuclear Power Plant will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably .small sample sizes, tha presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in --4her4nnua1-Radiological Environmental Operating Report or-the. Semiannual,- _,- Radioactive Effluent Release Report.

OM12D: ODCM Page : 99 Rev. : 0 REFERENCES '1. Title 10. " Energy," Chapter 1, Code of Federal Regulations; Part 20, U.S. Government Printing Office, Washington, D.C. 20402, January 1, 1984.

- 2.

Title 10, " Energy," Chapter 1,. Code of Federal Regulations; Part 50; U.S. Government Printing Office, Washington, D.C. 20402, January 1, 1984.

3.

Title 40, " Protection of Environment," Chapter 1, Code of Federal Regulations. Part 190, Federal Register, Vol. 42 Washington, D.C. 20402, January 13, 1977. .4. U.S. Nuclear Regulatory Commission,." Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133,' Washington, D.C. 20555, October,1981. 5. U.S. Nuclear Regulatory Commission, " Draft Radiological Effluent Technical Specifications for PWR's," USNRC NUREG-0473, Revision 2,. Washington, D.C. 20555, February, 1980. 6. Regulatory Guide 1.21 " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1. U.S. Nuclear Regulatory Commission. Washington, D.C. 20555, June 1974.

7.

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-0, U.S. Nuclear Regulatory Commission, Washington, D.C. 20S55, March, 1976. ~8. 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. U.S. Nuclear Regulatory Commission, Washington.D.C. 20555, October 1977. '9. Regulatory Guide 1.111, " Methods for Estimating Atmospheric l? Transpor.t and Diepersion of Geseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1,'U.S. Nuclear ~ Regulatory Commission, Washington, D.C. 20555, July 1977. 10. Regulatory Guide 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental.and Routine Reactor Releases for the Purpose of M _.~. Implementing Appendix I," Revision 1, U.S. Nuclear Regulatory ~ Commission, Washington, D.C. 20S55, April 1977.

OM12D: ODCM Pagn : 100 - LAST Rev. : 0 REFERENCES (Cont.)

11. Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment," U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, February,1979. 12. U.S. Nuclear Regulatory Commission, " Branch Technical Position," Revision 1, Washington, D.C. 20555, November, 1979.

13. Perry Nuclear Power Plant, Unit 1 and 2, " Final Safety Analysis Report," Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August, 1984, 14.

Perry Nuclear Power Plant, Units 1 and 2, " Environmental Report, Operating License Stage," Supplement 3, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, November, 1981. 15. Perry Nuclear Power Plant, Units 1 and 2, " Radiological Environmental Monitoring Program Manual," The Cleveland Electric Illuminating Company, Perry, Ohio 44081, February,1985.

16. " Midas User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant," Pickard, Lowe and Garrick, Washington, D.C. 20036, July, 1983.

DW/0DCM1/A-H/gn

7 7, u, n; - tr e <.L e 3 r: u. m P.O. BOX 5000 - CLEVELAND, OHIO 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLDG. - 55 PUBLICSOUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCUAR February 28, 1985 PY-CEI/NRR-0196 L Mr. B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Offsite Dose Calculation Manual

Dear Mr. Youngblood:

In accordance with your request, Cleveland Electric Illuminating Company is submitting the attached copy of the Perry Nuclear Power Plant Offsite Dose Calculation Manual, Rev. 1. We look forward to working with the NRC Staff during the review of the Offsite Dose Calculation Manual. Please call if you have any questions. Very trul yours, 3 b Murra-R. Edelman Vice President Nuclear Group MRE:nje Attachment ec: Jay Silberg, Esq. John Stefano (2) J. Grobe S. Brown ' ('}}

PY-CEI-NRR-0196, Rev 0 to Offsite Dose Calculation Manual

Contents

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1.0 INTRODUCTION

1.0 INTRODUCTION

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PY-CEI-NRR-0196, Rev 0 to Offsite Dose Calculation Manual

Text

1.0 INTRODUCTION

1.0 INTRODUCTION

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Dear Mr. Youngblood:

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