ML20134E675
| ML20134E675 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/12/1985 |
| From: | Cochnar R CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20134E673 | List: |
| References | |
| OM12D, NUDOCS 8508200380 | |
| Download: ML20134E675 (113) | |
Text
, , ~
h OM12D: ODCM Page : i Rev. : I k., THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT OPERATIONS MMiUAL 1
l l TITLE: OFFSITE DOSE CALCULATION MANUAL l
f REVISION: 1 EFFECTIVE DATE: Later DATE PREPARER: Richard M. Cochnar q kig p__
REVIEWER: g- 6 4
/ 7' 3-PORC MEETING NO: /
85-67 , , 8-12-85 APPROVED: ( [7 7. /,2-((
ljl i
A 40 PDR ,
OM12D: ODCM
, Page : 11 Rev. : 1 Table of Contents Section Title Page,
1.0 INTRODUCTION
1 2.0 LIQUID EFFLUENTS 2 2.1 Batch Releases 2 2.1.1 Monitor Alarm Setpoint Determination 2 ,
2.1.1.1 Determination of the Minimum Acceptable 3 Dilution Factor 2.1.1.2 Determination of the Maximum Allowable Radwaste 3 ,
Tank Discharge Flow Rate '
2.1.1.3 Liquid Radwaste Discharge Radiation Monitor 4 Alarm / Trip Setpoint i 2.1.2 Compliance with 10CFR20 - Liquid Effluent 5 Concentration 2.1.2.1 Prerelease 5 2.1.2.2 Post Release 6 2.2 Continuous Releases 7 2.3 Compliance with 10CFR50 Appendix I - Liquid 9 Effluent Dose 2.3.1 Dose Calculations 9 2.3.2 Cumulation of Doses 11 2.3.3 Projection of Doses 11 2.3.4 Population Dose 12 3.0 CASEOUS EFFLUENTS 27 3.1 Monitor Alarm Setpoint Determination 29 3.1.1 Determination of the " Mix" (Noble Gas Radio- 29 nuclide Composition) of the Caseous Effluent 3.1.2 Determination of the Maximum Acceptable Total 30 i 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 31
- e Activity Release Rate of Noble Gas Radio-i nuclides in Gaseous Effluent Based on Skin
- Dose Rate Limit 3.1 (4 Determination of the Maximum Acceptable Total 32 Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent 3.1.5 Determination of the Maximum Acceptable Monitor 32 Count Rate Above Background Attributed to !
. Noble Gas Radionuclides l 3.1.5.1 Determination of the Monitor High Alarm Setpoint 33 1 3.1.5.2 Determination fo the Monitor Alert Setpoint 33 l
1
9 OM12D: ODCM Page : iii Rev. : 1 Table of Contents (Cont.)
Section Title Pjaj ge 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose 36 Rate 3.2.1 Noble Cases 36 3.2.2 Radionuclides, Particulates, and Other 36 Radionuclides 3.2.3 Dose Rate Calculations 37 3.3 Compliance with 10CFR50 Appendix I - Gaseous 65 Effluent Dose 3.3.1 Noble Cases 65 3.3.2 Radioiodines, Particulates, and Other Radio- 66 nuclides 3.3.3 Dose Calculations 66 3.3.4 Cumulation of Doses 67 3.3.5 Projection of Doses 68 3.4 Population Dose 68 4.0 TOTAL DOSE 70 4.1 Compliance with 40CFR190 - Uranium Fuel Cycle 70 Dose ,
4.2 Direct Radiation Dose From PNPP 71 I
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 73 5.1 Monitoring Program 73 .
5.2 Land Use Census Program 73 5.3 Inter Laboratory Comparison Program 74 APPENDIX A Atmospheric Dispersion and Deposition Parameters 86 APPENDIX B Lower Limit of Detection 102 REFERENCES 106
OM12D: ODCM Page : iv Eev. : 1 List of Tables Table Title Page t
2.3-1 Organs Used for Liquid Effluent Dose Calculations 13 2.3-2 Age Groups Used for Liquid Ef fluent Dose Calculations 13 2.3-3 Liquid Effluent Dose Pathways 13 l
2.3-4 Bioaccumulation Factors 14 l 2.3-5 Ingestion Dose Factors for Adult 15 l
2.3-6 Ingestion Dose Factors for Teenager 17 2.3-7 Ingestion Dose Factors for Child 19 2.3-8 Ingestion Dose Factors for Infant 21 2.3-9 External Dose Factors for Standing on Contaminated 23 Ground 2.3-10 Transit Times Required for Nuclides to Reach the 25 Point of Exposure 2.3-11 Usage Factors 25 2.3-12 Usage Factors (U, ) 26 3.1-1 Whole Body and Skin Dose Factors 35 3.2-1 Organs Used for Gaseous Effluent Dose Calculations 42 l 3.2-2 Age Groups Used for Gaseous Effluent Dose 42 Calculations 3.2-3 Gaseous Effluent Dose Pathways 43 3.2-4 Dose Factors for Exposure to a Semi-Inifinite 44 Cloud of Noble Cases 3.2-5 External Dose Factors for Standing on contaminated 45 Ground 3.2-6 Inhalation Dose Factors for Adult 47 3.2-7 Inhalation Dose Factors for Teenager 49
OM12D: ODCM Page : v Rev. : 1 List of Tables (Cont.)
Table Title Page 3.2.8 Inhalation Dose Factors for Child 51 2.2-9 Inhalation Dose Factors for Infant 53 3.2-10 Ingestion Dose Factors for Adult 55 3.2-11 Ingestion Dose Factors for Teenager 57 l 3.2-12 Ingestion Dose Factors for Child 59
! 3.2-13 Ingestion Dose Factors for Infant 61 l
3.2-14 Annual Usage Factors for the Maximum Exposed 63 j Individual t
l 3.2-15 Annual Usage Factors for the Average Individual 63 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite 69 Plume 5.1-1 PNPP Radiological Environmental Monitoring Program '/ 5 L 5.1-2 Reporting Levels for Radioactivity Concentrations 78 i
in Environmental Samples 5.1-3 Detection Capabilities for Environmental Sample 79 i Analysis and Lower Limit of Detection (LLD) l 5.1-4 Sample Locations and Media for the Radiological 81 Environmental Monitoring Program f
l A-1 Atmospheric Depletion and Deposition Factors 89 A-2 Site Boundary Atmospheric Dispersion and Deposition 91 1
Parameters for PNPP Unit 1 A-3 Atmospheric Dispersion and Deposition Parameters at 91 the Nearest Residences for PNPP Unit 1 A-4 Atmospheric Dispersion (X/Q) as a Function of 92 Distance A-5 Atmospheric Deposition (D/Q) as a Function of 97 Distance
. _.. . . . - - .- - - - . . - _ - _ = . - . - - . _ .
4 OM12D: ODCM Page : vi Rev. : 1 List of Figures Figure Title Page 2.1-1 Liquid Radioactive Waste Discharge System 8 3.0-1 Gaseous Radioactive Waste System Flow Diagram 28 3.2-1 PNPP Site Boundary and Unrestricted Area 64 5.1-1 Radiological Environmental Monitoring Program 84 j Sampling Locations Within 5 miles of PNPP l
5.1-2 Radiological Environmental Monitoring Program 85 Sampling Locations Greater Than 5 miles from PNPP s
e SCOPE OF REVISION:
Rev. 1- Incorporation of NRC review comments, both on the ODCM and RETS; and REMP changes.- ,
I
,r . . . _ . . , . . . . . _ . , .- , - . - - - - - -
, . . . , . . . - .._..,,mm- r . - - - - . . - . - _ -.~ - - - ,.- - ,.. _ , ~_
- - - . .- - _ - .-. . . - - - . _ . . - - - . _ . - . . = _ _ - - - - - - - .
OM12D: ODCM Page : 1 Rev. : 1
1.0 INTRODUCTION
This Of fsite 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 Radiological Effluent Technical Specifications. The Technical Specifications are written.to satisfy 10CFR20, 10CFR50.36 and Appendix I, and ,
40CFR190 requirements. t Sections 2 and 3 of this manual deal with liquid and gaseous radiological effluents, respectively. Each of these sections contain alarm setpoint determination, 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).
l i
i l
. . - ~ . -_ _ __ . . _ - . _ . - _ . - _ . . _ _ . . _ . . . . ~ . _ _ _- _ _ . , - _ , _ , . . _ _ . _ . - . . - _ _ . _ _ , _ - . . , _ . _ _ , . _ _ . _ .
OM12D: ODCM Page : 2 Rev. : 1 2.0 LIQUID EFFLUENTS 2.1 Batch Releases A batch release is the discharge liquid radioactive waste of a l 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. (See Figure 2.1 -1) . The maximum release l 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 Circulatin'g 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 will 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.
2.1.1 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. Concentrations for tritium and other non-gamma emitting isotopes will be those most recently determined (previou ; month / quarter). Initial source terms, until monthly / quarterly analysis results become available, for non-gamma emitting isotoptes listed in the Technical Specifications will be those generated by the GALE code, Revision 0 for PNPP (FSAR Table 11.2-13). 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.
OM12D: ODCM Page : 3 Rev. : 1 2.1.1.1 Determination of the Minimum Acceptable Dilution Factor C
DF =
) (2.1-1) i MPC Where:
DF = the minimum acceptable dilution factor determined from analysis of the liquid effluent to be released; C
i
= the concentration of radionuclide i in the batch to be released, in uCi/ml; MFC = the limiting maximum permissible concentration of l radionuclide i, from Appendix B, Table II, Column 2 of 10CFR20, in uCi/ml.
Where:
DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to release in order to ensure compliance 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.
2.1.1.2 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;
. I
OM12D: ODCM Page : 4 Rev. : 1 DF = the conservative dilution factor, as per equation 2.1-2; mdf = the minimum dilution ficw - supplied by the Service Water system, i.e., the low flow alarm setpoint of the Service Water Flow Transmitter P41-N443 =
30,000 gpm; 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 volumS* discharge throttle valves (G50-F153 or G50-F155).
2.1.1.3 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.
An MFC of 2 x 10 uCi/ml has been established for noble gases dissolved and entrained in liquid effluents.
CR = f]C E (2.1-4) f i
Where:
CR = the calculated monitor count rate above background, in cpm; C = the concentration of radioauclide i in the batch to I
be released, in uCi/ml; E = the detector efficiency of the nonitor for radio-nuclide i in cpm /(uC1/ml).
SP = 1.25 CR + BG (2.1-5)
Where:
SP = the Radwaste Discharge Radiation Monitor - ESW Dis-charge (D17K606) alarm / trip setpoint, in epm;
OM12D: ODCM Page : 5 Rev. : 1 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; 1.25 = the engineering safety factor to prevent spurious alarms. (The inverse of 0.8).
2.1.2 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 the limiting maximum permissible concentrations l (MPC) as defined in Appendix B, Table II, Column 2 of 10CFR20.
Concentrations of radioactivity in effluents prior to dilution will be determined. Concentration in diluted effluent will be calculated using these results prior to each batch release, and following each batch release. PNPP has no continuous releases.
2.1.2.1 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 Cone f
=
(2.2-1) mdf Where:
Conc = the concentration of radionuclide i at the unrestricted area, in uCi/ml; C' = the concentration of radionuclide i in the batch to be released, in uCi/ml; i f = the radwaste tank discharge flow rate for the batch to be released, in gpm; this value equalsf (Equation 2.1-3) if f,, does not exceed system 1TSItations; I
i i
k
OM12D: ODCM Page : 6 Rev. : 1 mdf = the minimum dilution flow, as per equation 2.1-3 .
in gpm.
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 g (2.2-2) i MPC g Where:
Conc I
= the concentration of radionuclide i at the unrestricted area, in uCi/ml; MPC = the limiting maximum permissible concentration of l radionuclide i, from Appendix B, Table II, Column 2 of 10CFR20, in uCi/ml.
2.1.2.2 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:
Cone g =
(2.2-3) dil Where:
Conc i
= 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 l- released, in uCi/ml; dn = the actual volume of dilution water during the V
l; release (the sum of all dilution flows: Service Water, Emergency Service Water, and cooling tower blowdown), in gallons; l l L
OM12D: ODCM Page : 7 Rev. : 1 V
1rt
= the actual volume of the liquid radwaste tank dis-charged for the batch, in gallons.
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:
b I 5 1 (2.2-4) i MPC g Where:
Conc i
= the concentration of radionuclide i at the unrestricted area, in uCi/ml; MFC = the limiting maximum permissible concentration of l radionuclide i, from Appendix B, Table II, Column 2 of 10CFR20, in uCi/ml.
2.2 Continuous Releases A continuous release is the discharge of fluid wastes of a nondiscrete volume, i.e., from a volume or system that has an input flow during the continuous release. Continuous radioactive releases are not planned for PNPP although the potential does exist for RHR heat exchanger leakage into the Emergency Service Water system.
Potentially contaminated dicharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Water system Loop A and the other for Loop B. If radiation is detected, the af fected Emergency Service Water line can be manually isolated. Whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release.
I In'the event that radioactivity is detected in the Emergency Service Water system, water discharged will be sampled and analyzed in accordance with PNPP Technical Specification Table 4.11.1.1.1-1.
To show compliance with 10CFR20, the sum of the concentrations of radionuclide "i" in unrestricted areas due to both continuous and batch releases divided by that isotope's MPC must again be less than 1.
I
LIQUID RADIOACTIVE WASTE DISCHARGE SYSTEM
- 2 5
iS4 y
2 CHEMICAL WASTE -
DISTILLATE TANKS S - - - - - -----
' = $ CLO S ES ON- ---l- ,-[ -
" > (O "
sis 3 L W SW. DISC H. FLOW D l CLOSES ON l HIGH R AD. l
/ 2 DETERGENT T =
>< = i i DR AIN TANKS g
' =
= (0 "
l i I
\
2 FLOOR DR AIN S AMPLE T ANKS S
- I CLOSES ON b !
V "" ^ O' m
- g PCV riss
/ !
- yyg 3 I z <%C
( )
l 1 e 2 WASTE
-, s
/z .
l g -mo SAMPLE TANKS l
, ,,t ,_ ,_ _ _ _ _ _ _ _ ,e___a v 5 7C LOW SW. DISCH. FLOW SW FLOW 5 A D S C H.
OM12D: ODCM Page : 9 Rev. : 1 2.3 Compliance With 10CFR50 Appendix I - Liquid Effluent Dose Doses resulting from liquid effluents will be calculated at least 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.
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 ap R = 1100 QD exp(-htp) (2.3-1)
- 2. Aquatic Foods:
U R
ajp "
F i iP aipj exP (-k i p) t (2.3-2)
- 3. Shoreline Deposits:
UW ap R = 110,000 Qg Tg D,g p [exp(-hg ep )]* (2.3-3)
[1-exp(-ktb))
L_
3' OM12D: ODCM Page : 10 Rev. : 1 Where:
R ajp = the dose to individuals of age group a to organ j 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
aipj
= the dose factor, specific to a given age group a, radionuclide 1, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem /pci, or from exposure to a given concentration of a radio-nuclide in sediment, expressed as a ratio of the doserate,inmrem/h,agdthearealradionuclide concentration, in pCi/m , from Tables 2.3-5 through 2.3-9; F = the flow rate of the liquid effluent in ft /s; Mp = the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), from Table 2.3-10, dimensionless; Qg = the release of radionuclide 1 in Ci; tg = the period of time for which the sediment or s i is 5
exposed to the contaminated water, 1.75 x 10 h (20 years); -
T g = the halflife of radionuclide i, la days; '
tp = the average transit time required for radior.uclides to reach the point of exposure, from Table 2.3-11; 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
ap
= the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, from Table 2.3-12, in h/yr, 1/hr, or kg/hr; W = the shoreline width factor. 0.3 (from Regulatory Guide 1.109);
b
OM12D: ODCM
. Page : 11 Rev. : I k=theqdioactivedecayconstantofradionuclidei, in h ;
3 1100 = a factor to convert from (Ci/yr)/(ft /s) to pCi/1; 3
110,000 = a factor to convert from (Ci/yr)/(ft 7,) t, pCi/l and to account for the proportionality constant used in the sediment radioactivity model.
2.3.2 Cumulation of Doses The dose contribution from liquid ef fluents will be calculated at least monthly. Calculations will be performed to determine l the maximum total body as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. These results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest. To assure compliance with the dose limits of 10CFR50 Appendix I the following relationships shall hold:
for the quarter:
Dose 5 1.5 mrems total body; Dose s 5 strems any organ; for the calendar year Dose s 3 mrems total body;
. Dose s 10 mrems 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.
2.3.3 Projection of Doses Anticipated doses resulting from the release of liquid efflu-ents will be projected monthly when liquid radwaste treatment systems are not being fully utilized. 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 correspond to approximately one forty-eighth of the Appendix 1 design objective. If continued at this rate for one year, the
OM12D: ODCM Page : 12 Rev. : 1 projected impact would correspond to less than one-fourth of the Appendix I limit. The prcjected doses will be calculated using Equations 2.3-1 to 2.3-3.
The doses calculated for the present me..th will be used as the projected doses unless information exists indicating that actual releases could differ significantly in tha 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 will be calculated for doses received from all radioactive liquid effluent releases. This population Jose will be calculated using average individual transit times and usage factors.
Table 2.3-12. (as compared to maximum exposed individual factors used for individual doses). The population dose will be 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 : 13 Rev. : 1 Table 2.3-1 Organs used for Liquid Effluent Dose Calculations
- 1. Bone
- 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
- 1. Water Ingestion
- 2. Shore Exposure l
- 3. Fresh Water Fish Ingestion
OM12D: ODCM Page : 14 Rev. : 1 Table 2.3-4 Bioaccumulation Factors (B, ) (pC1/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 I 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 : 15 Rev. : 1 Table 2.3-5 -
Ingestion Dose Factors for Adult (mrem /pCi ingested)
NUCLICE BONE LIVER T.RUDY THYRDID 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 1.70E-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 DATA 2.6cE-09 1 59E-09 5.86E-10 3.53E-09 6.69E-07 NN 54 NO DATA 4.575-06 8.72E-07 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 TE 55 2.75E-06 1.90F-06 4.4 3 C-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 CO 58 NO DATA 7.456-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14F-06 4.72C-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 2N 65 4.84E-06 1.54E-05 6. 96 E-0 6 NO DATA 1 03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1 97E-08 1. 3 7 E-0 9 NO DATA 1.28E-05 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 RB 86 NO DATA 2.11E-05 9. 8 3 E-0 6 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 RS 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 1.86E-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 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. 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 2.4 7E-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 2R 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1. 5 3 L*-0 5 NO DATA 3.09E-05 2R 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 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8. 2 0E-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 k
OM12D: ODCM Page : 16 Rev. : 1 Table 2.3-5 (Cont.)
Ingestion Dose Factors for Adult (mrem /pCi ingested)
NUCL10E BONE LIVER T . 800Y THYR 010 KIONEY 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 Rut 03 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NU DATA 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 2.9tE-07 NO DATA 6.04E-05 TE125M 2.6SE-06 9.7tE-07 3 59E-07 8.06E-07 1 09E-05 NO DATA 1.07E-05 TE127m 6.77E- 06 2 42E-06 8. 2 5 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.6)E-09 2.4tE-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 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09
...______..=__ -=_____.___...........___...__.- =...__.__....__.__..__._
TE132 2.52E-06 1.6 3E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.23E-06 8. 8 0 E-0 7 1.89E-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5 95E-06 3. 41 E-0 6 1.95E-03 1.02E-05 NO DATA 1.57E-06
_____ . _ _ _ _ _ . _ _ . . . . - - - - = . . . . . . . . .
I 132 2.03E-07 5.43E-07 1.90 E-0 7 1.90E-05 8.65E-07 NO D AT A 1.02E-07 1 133 1.42E-06 2.4TE-06 7. 53 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06
! 134 1.06E-07 2.88E-07 1.03E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10
===__ ..................______.......
I 135 4.43E-07 1.16E-06 4. 2 8E-0 7 7.65E-05 1.86E-06 NO DATA 1.31E-06 C5134 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 1.85E-05 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 7.9tE-09 4.65E-13 BA139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1 72E-07 BA140 2.03E-05 2.55E-08 1. 3 3 E -0 6 40 DATA 8.67E-09 1.46E-08 4.18E-05 BA141 4. 71 E-0 8 1.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2 19E-11 1 34E-0 9 NO DATA 1.85E-11 1.24E-11 1.00E-26 LAt40 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. 4 5E -1 1 NO DATA NO DATA NO DATA 4.25E-07
. CE141 9.36E-09 6. 3 3E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.2?F-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 i'
CE144 4.88E-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 PRl44 3.01E-11 1.25E-11 1.5sE-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND14 7 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 3.01 E-0 8 NO DATA NO DATA NO DATA 2.82E-05 l NP239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 l
I s
?
l
- - . - , _ _ _ -, - ,~ , n--
OM12D: ODCM Page : 17 Rev. : 1 Table 2.3-6 Ingestion Dose Factors for Teenager (mren/pCi ingested)
NUCLIDE BONE LIVER T.BOOY 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 L 14 4.06E-06 8.12E-07 8.12 E-0 7 8.12F-07 8.12E-07 R.12E-07 8.12F-07 NA 24 2.30E-06 2.30E-06 2. 30 E-0 6 2.30E-06 2.30t-06 2.30E-06 2.30E-06 P 32 2.760-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NU DATA NO DATA 3.60E-09 2.00E-09 7.99E-10 5.14[-09 6.05E-07 PN 54 NO DATA 5.90E-00 1 17E-06 NO DATA 1.76E-06 NO DATA 1.2tE-05 MN 56 40 DATA 1.58E-07 2. 8 t E-0 8 NO DATA 2.00E-07 NO DATA 1.04E-05 FE $5 3.78E-06 2.68F-06 6. 2 5E-0 7 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.JfE-05 5. 2 9 E -0 6 NO DATA NO DATA 4.32E-06 3.24E-05
___...__..______.___.___ =____._______ ... ______________..____.___ ....__
CD 58 NO DATA 9.72E-OT 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 CU 60 NO DATA 2.61E-06 6. 3 3 E-0 6 NO DATA NO DATA NO DATA 3.66E-05 41 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06
___._____...____..==_ __=...--- ===________.......__.. ___..................
NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 IN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E 05 40 DATA 8.47E 06
.__....===-- =____ ________....___....___
IN 69 1.47E-08 2.60E-08 1. 96E-0 9 NO DATA 1.R3E-08 NO DATA 5 16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA- NO DATA LT E-24 BR 84 NO DATA ND DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-19 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15
= __=.______.________...-__.___.__
R8 89 NO DATA 5.50E-08 3. 8 9 E-0 8 NO DATA NO DATA NO DATA 8.43E'17 SR 89 4.40E-04 NO DATA 1. 26 E-0 5 NO DATA NO DATA NO DATA 5 24E-05 SR 90 8.30E-03 NO DATA 2.0$E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 11 8.07E-06 NO DATA 3.21E-07 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 3.69E-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 ZH 95 4.12E-08 1.30E-08 8. 94 E-0 9 NO DATA 1.91E-08 NO DATA 3.00E-05 1R 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 1H 95 8.22E-09 4.50I-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 MO 99 NO DATA 6.03E-06 1.15F-06 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 O
OM12D: ODCM Page : 18 Rev. : 1 Table 2.3-6 (Cont.)
Ingestion Dose Factors for Teenager (mrem /pCi ingested)
NUCLIDE BONE LtvER I.60DY THYR 0!D KtDNEY LUNG GI-LLI
= __ ___
fC101 3.60E-10 5 125-10 5. 0 3 E-0 9 NO DATA 9.26E-09 3.12E-10 8.75E-17 9U103 2.55E-07 NU DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU105 2 18E-08 NO UATA 8. 4 6 E -0 9 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-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 3.92E-05 NO DATA 2.41E-05 IE127 1.58E-07 5.6GE-08 3.40 E-0 8 1 09E-07 6.40E-07 NO DATA 1.22E-05 TE129M 1.63E-05 6.05F-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05
==....._______... ==. ___
TE129 4.48E-05 1.6TE-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE131M 2.4 4E-06 _1.1 TE-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 2.290-09 TE132 3 49E-06 2.21E-06 2.06E-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 8.19E-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. 04 E-0 6 4.76E-04 5.98E-06 NO DATA 2.58E-06 1 134 1.46E-07 3 07E-07 1. 39E-0 7 6.45E-06 6.10E-07 NO DATA 5 10E-09 I 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 2.12E-06 C5138 7.76E-08 1.49E-07 7. 4 5 E-0 8 NO DATA 1.10E-07 1 28E-08 6.76E-11 84139 1.39E-07 9.78E-11 4. 0 5 E-0 9 NO DATA 9.22E-11 6.74E-11 1.24E-06 DA140 2 84E-05 3.48E-OS 1. 8 3 E-0 6 NO DATA 1.186-08 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 OA142 2.99E-08 2 99E-11 1 84E-09 NO DATA 2.53t-11 1.99E-11 9.18E-20 LA140 3.48E-09 1 710-09 4. 5 5 E-10 No DATA NC DATA NO DATA 9.82E-05 L A14 2 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06
. CE141 1.33E-08 8.88E-09 1.02E-09 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 5.230-09 6. 5 2 E -10 NU DATA 3.n4E-09 NO DATA 4.31E-05 PR144 4.30E-11 1 76E-11 2.18 E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 ND147 9.38E-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 4.1 TE-0 8 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 1
i i
OM12D: ODCM Page : 19 Rev. : 1 Table 2.3-7 Ingestion Dose Factors for Child (mrem /pci ingested)
NtlCL I UE BONE LIVER T.HOUY THYROID KIDNEY 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 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.00E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.06E-05 3.10E-05 10 DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO CATA 0. 9 0E -0 9 4.94E-09 1.35E-09 9.02E-09 4.72E-07 FN 54 NO DATA 1 07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-0F 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.456-06 1.13E-06 FE 59 1.65E-05 2.6FE-05 1.33E-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 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 N1 65 2.22E-06 2.09F-07 1. 22 E-0 7 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1 37E-05 3.oSE-05 2. 2 TC-0 5 NO DATA 2.30E-05 NO DATA 6.41E-06 IN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1. 71E-0 7 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1. 9 8 E-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 MB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31F-06 RB 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. 04E-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 UATA 4. 31 E-0 3 40 DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9. 06E-0 7 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9 03E-06 NO DATA 3.62 E-0 7 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.11E-08 NO DATA 1.10 E-0 9 NO DATA NO DATA NO DATA 1 17E-04 Y 91M 3.82E-10 NO DATA 1. 3 9 E-1 1 h0 DATA NO DATA NO DATA 7.48E-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 1.0 3 E-10 NO DATA NO DATA NO DATA 1.04E-04 Y 93 1 14C-08 NO DATA 3.13 E-10 NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.16E-07 2.25E-08 2.2 7E-0 8 NO DATA 3.65E-08 NO DATA 2.66E-05 LR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NR 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA t.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99= 9.23E-10 1.8tE-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06 f
I i
OM12D: ODCM Page : 20 Rev. : 1 Table 2.3-7 (Cont.)
Ingestion Dose Factors for Child (mrem /pci ingested)
NUCLIUE 80NE liver T.000Y THYRutD KIDhEY LUNG GI-LLI 1C101 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-07 NO DATA 1.84E-06 NO DATA 1.89E-05 flut05 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. 52 E-0 6 3.20E-06 NO DATA NO DATA 1.10E-05 TE12TM 2.89E-05 7.78E-06 3.43C-06 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 DATA 1 84E-05 TE129 4.87E-05 1.56E-05 7.56E-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 TE131M 7.20E-06 2.49E-06 2. 6 5 E-0 6 5.12E-06 2.41E-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 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 t 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73C-05 9.83E-06 5.72E-03 2.8'E-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 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1 22E-05 NO DATA 2.95E-06 1 134 '4.19E-07 7.78E-07 3.58E-07 '1.79E-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 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 C5136 2.35E-05 6.46E-05 4.10E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS137 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 2.01E-07 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 4.8SE-06 NO DATA 2.37t-08 4.34E-08 4.2tE-05
?, A 141 2.00E-07 1.122-10 6.51E-09 NO DATA 9.69E-11 6.58E-10 1.14E-07 OA142 8.74E-08 6.29E-11 4.88F-09 NO DATA 5.09E-11 1.70E-11 1.14E-09 LA140 1 01E-08 1.53E-09 1.19E-09 40 DATA NO OATA NO DATA 9.84E-05 LA142 5.?4E-10 1.67E-10 5.23E-11 NO DATA NO DAT4 NO DATA 3.31E-05 CE141 ).97E-08 1.98E-08 2.94E-09 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. 5 2E-0 7 1. l l E-0 7 NO CATA 3.61E-07 NO DATA t.70E-04 PRt43 1.93E-08 1.18t-08 1. 9 5 E -0 9 NO DATA 6.19E-09 NO DATA 4.24E-05 PRt44 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 NDt47 2.79E-OR 2.26E-08 1.75E-09 NO DATA 1.24E-06 NO DATA 3.58E-05 W 187 4.29E-07 2.54r-07 1 14E-0 7 NU DATA NO DATA NO DATA 3.57E-05
- HP239 5.25E-09 3.77E-10 2.65t-10 NO DATA 1.09E-09 NO DATA 2.79E-05 l
I k
1
OM12D: ODCM Page : 21, Rev. : 1 Table 2.3-8 Ingestion Dose Factors for Infant (mrem /pCi ingested)
NUCLIDE BONE liver T.600Y THYROID K10NEY LUNG O!-LLI H 3 NO DATA 3.08E-07 3. 08 E-0 7 3. ORE-07 3.08E-07 3.08E-07 3.08E-07 C 14 2.3FE-05 5.06E-06 5. 0 6E-0 6 5.06E-06 5.06E-06 5.06F-06 5.06E-06 NA 24 1.01E-05 1.01C-05 1. 01 E-0 5 1.01E-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 51 NO DATA NO DATA 1.41E-08 1.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 NO DATA 1.99E-05 4.5tE-06 NO DATA 4.4tE-06 NO DATA 7.31E-06 MN 56 NO DATA 8.18E-07 1.41 E-0 7 NU DATA 7.03E-07 NO DATA 7.43E-05' TE 55 1.39E-05 8.18E-06 2.4CE-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.385-03 2.12E-05 NO CATA 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 7E-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 2.20E-05 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-0T 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 2N 65 1.34E-05 6. 's t E-05 2. 91 E-0 5 NO DATA 3.06E-05 NO DATA 5.33E-05
---.................................--.............--......:= - -----
IN 69 9.33E-08 1.08E-0T 1.2SE-08 NO DATA 6.98E-08 NO DATA 1.37E-05 BR 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 1.94E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1. TOE-04 8. 4 0 E -0 5 NO DATA NO DATA NO DATA 4.35E-06 d6 88 NO DATA 4.98E-07 2.73E-0T NO DATA NO DATA NO DATA 4.85E-07 RD 89 NO DATA 2.86E-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. 71E-0 3 NO DATA NO DATA NO DATA 2.3tE-04 SR 91 5.00E-05 NO DATA 1.8tE-06 NO D ATA' NO DATA NO DATA 5.92E-05 SR 92 1.92C-05 NO DATA 7.13 E-0 7 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.3JE-09 NO DATA NO DATA NO DATA 1.20E-04 Y 91m 8.10E-10 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 DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50F-05 2R 97 1.48E-08 2 54E-09 1 16E-09 NO DATA 2 56E-09 NO DATA 1.62E-04 N8 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.?4t-08 NO DATA 1.46E-05 MO 99 NO DATA 3.40E-05 6. 6 3 E-0 6 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26t-08 2.07E-09 1.15E-06
OM12D: ODCM Page : 22 Rev. : 1 Table 2.3-8 (Cont.)
Ingestion Dose Factors for Infant (mrem /pci ingested)
NUCLICE BONE liver T.00DY THYROID KIDNEY 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. 9 5 E-0 7 NO DATA 3.08E-06 NO DATA 1.80E-05 RUl05 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.4tE-05 rut 06 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. 81 E-0 7 NO DATA 1.04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE127M 5.85E-05 1.94E-05 7. C 6E-0 6 a 69E-05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.145-07 2.44E-06 NO DATA 2.10E-05 TE129M 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 6.6 3E-0 8 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE131M 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. 61 E -0 6 1.52F-05 6.44E-05 NO DATA 3.8tE-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 4.23E-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 1.25E-05 1 82E-05 5.33E-06 3.31E-03 2.14E-05 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 1.44E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-C6 C5134 3.77E-04 7.03E-04 7.10 E -0 5 NO DATA 1.81E-04 7.42E-05 1.91E-06 C5136 4.59E-05 1.35E-04 5 04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 C5137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 C5138 4.8tE-07 7.82E-07 3.79E-0 7 NO DATA 3.90E-07 6.09E-08 1.25E-06 8A139 8.81E-07 5.84E-10 2. 5 5 E -0 8 NO DATA 3.51E-10 3.54E-10 5.58E-05 8At40 1.7tE-04 1.7tE-07 8.8tE-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 RAl41 4.2SE-07 2.912-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-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 L A 14 2 1.10E-09 4.04E-10 9.6/E-11 NO DATA NC DATA NO DATA 6.86E-05 0 CE141 7.87E-08 4.80?-08 5. 6 5 E -0 9 NO DATA 1.48E-08 NO DATA 2.48E-05 CE143 1.48E-08 9.82C-06 1 17E-09 NO DATA 2.966-09 NO DATA 5.73E-05 CE144 2.982-06 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-06 NO DA'A 4.29E-05 PR144 2.74L-10 1.06E-10 1. 3 8 E-11 NO DATA 3.84t-11 NO DATA 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03C-07 6.28E-07 2.17 E-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
OM12D: ODCM Page : 23 R :nt. : 1 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground (mrem /h per pCi/m2 )
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-SL, 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 1.70E-08 2.00E-08 Co-60 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 4.4vE-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-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 l
OM12D: ODCM Page : 24 .
Rev. : 1 Table 2.3-9 (Cont.)
External Dose Factors for Standing on Contaminated Ground (mrem /h per pCi/m2 )
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 Ba-139 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 3.10r 09 3.60E-09 Np-239 9.50E-10 1.10E-09 4
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OM12D: ODCM
. Page : 25 Rev. : 1 Table 2.3-10 1
Liquid Radwaste Dilution Factors (M_)
e Maximum Individual Dilution Factors M
Pathway Location _j',
Potable Water Ingestion 3.9 mile WSW of site 31.5 Fresh Water Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 0.7 mile ENE of Site 14.5 Population Dose Dilution Factors M
Pathway P, Location _,
Potable Water Ingestion Population Weighted Average 316 Fresh Water Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 7.7 mile WSW of site 162 Table 2.3-11 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 1
1 l
OM12D: ODCM Page : 26 Rev. : 1 Table 2.3-12 Usage Factors (U, )
Maximum Exposed Average Exposed Individual Individual
- Water ingestion (1/yr) Adult 730 370 Water ingestion (1/yr) Teen 510 260 Water ingestion (1/yr) Child 510 260 Water ingestion (1/yr) Infant 330 --
Fresh water fish ingestion (kg/yr) Adult 21 6.9 l
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 I
l l
OM12D: ODCM f Page : 27
! Rev. : 1 L 3.0 GASEOUS EFFLUENTS There are four environmental release points for gaseous effluents used for Unit 1 operation of Perry Nuclear Power Piant: Heater Bay / Turbine Building Vent, Offgas Vent Pipe, and Unit 1 and Unit 2 Vents. (See Figure 3.0-1). The plant vents for Units 1 and 2 are l located on top of the Intermediate Building, Elevation 753'9". The l
Heater Bay / Turbine Building vent is located on top of the Heater Bay Builidng, Elevation 722'0". The Offgas Vent Pipe is I
located on top of the Offgas Building, Elevation 723'0". Site ground level elevation is 620'. '
Radiological releases from each vent will be monitored by a nobic gas radiation monitor.
All gaseous effluent releases from PNPP will be continuous releases. Containment /drywell purges and vents will be considered periods of increased radiological release as they are vented through the Unit 1 Vent concurrent with normal, continuous releases. All releases are considered to be long-term, i.e.,
l greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year, and ground level.
Containment /drywell purge and vent will be limited to 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> per year during operational conditions 1, 2, and 3 (power operation, startup, and hot shutdown).
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- 4 OM12D: ODCM Page : 29 Rev. : 1 3.1 Monitor Alarm Setpoint Determination 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 beyond the site boundary for the nobic gas channels of the following monitors:
- 1. Heater Bay / Turbine Building Vent Radiaton Monitor (ID17K856)
- 2. Of f-Gas Vent Pipe Radiation Monitor (ID17K836)
- 3. UI Vent Radiation Monitor (ID17K786)
- 4. U2 Vent Radiation Monitor (2D17K786).
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 serpoint (ASP) will be set at 10 percent of these limits.
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 dose 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 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 Composition) of the Gaseous Effluent
- a. Determine the gaseous source terms that are 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
OM12D: ODCM Page : 30 Rev. : 1 l 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 (FSAR Tables 11.3-9 and 11.3-10).
- b. Determine the fraction of the total radioactivity in the gaseous effluent for each noble gas radionuclide in the gaseous effluent.
A S =
(3.1-1)
}Ai i
Where:
SI = the fraction of the total for radionuclide i in the effluent; A g = the activity of radionuclide i in the gaseous
, effluent.
1 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)
S Qb =(x/Q)K g g l 1 Where: Qb = the maximum acceptable total activity release rate of all noble gas radionuclides in the effitent (for whole body exposure), in uCi/s; l K g = the total body dose factor for a semi-infinite cloud of2radionuclide 1 (includes the attenuation of Sg/cm of tisgue) from Table 3.1-1, in (mrem /yr)/(uCi/m ); r S = the fraction of the total for radionuclide i, as i
- per Section 3.1.1; i
l l I l~
OM12D: ODCM Page : 31 Rev. : 1 X/Q=thehighestannualaveragerelativedispersgonfgetor for areas at the site boundary = 5.8 x 10 s/m (from Appendix A, NE direction at the site boundary); NOTE: The dispersion parameters used in these calcu-lations are the highest calculated site boun-dary 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 Gaseous Effluent Based on Skin Dose Rate Limit 3000 (3.1-3) Q, = (X/Q) {(L1 + 1.1 M 1) S1 i Where: Qs = the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for skin exposure), in uCi/s; LI = the beta skin dose factor for a semi-infinite cloud of radionuclide 1 (includes attenuation by 3the outer
" dead" layer of skin), in (mrem /yr)/(uCi/m );
Mg = the gamma air dose factor for a uniform semiginfinite cloud of radionuclide 1, in (mrad /yr)/(uCi/m ); Sg = the fraction of the total for radionuclide 1, as per Section 3.1.1; u X/Q = the highest annual average relativg disgersion factor, as per Equation 3.1-2 = 5.8 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. (Lg + 1.1 Mg ) values are shown in Table 3.1-1.
OM12D: ODCM Page : 32 Rev. : 1
. 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous '
Effluent 2.12 x 10 ~3 Qt C = (3.1-4) f Where: CE = the maxit.um acceptable total radioactivity concen-tration tf all noble gas radionuclides in the effluent, in uCi/ce; f = the octual flow at the point of releage'from the respective flow rate recorders, in ft / min; iiOTE: 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 1 124,500
- Unit 2 (Control Complex and Intermediate Building Ventilations) 42,400 Q g = the smaller of Q and Q , calculated in Equations 3.1-2 and 3.1-3,brespecEively, in uC1/s;
~
2.12 x 10 = the conversign factor to convert (uCi/s) (ft / min) to uCi/cc. 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate i Above Background Attributed to Noble Gas Radionuclides CR = 0.8 (C ) (E,) (3.1-5) Where: CR c
= the calculated monitor count rate above background
( attributed to noble gas radionuclides, in net epm; l-t I A
OM12D: ODCM Page : 33 Rev. : 1 CE = the maximum acceptable radioactivity concentration, as per Equation 3.1-4, in uCi/ce; E = the detector efficiency of the monitor for the " mix" 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 i HSP = 0.70 CR + BC (3.1-6) c Where: HSP = the high alarm setpoint (including background), in cpm; l BG = the background count rate due to internal contamina-l tion and radiation levels in the area in which the
- monitor is installed when the monitor chamber is ,
j filled with uncontaminated air, in epm; CR = the calculated monitor net count rate, as per equation 3.1-5, in cpm; 1 ! 0.70 = 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 , l pathways, E 3.1.5.2 Determination of the Monitor Alert Setpoint t ASP = 0.10 CR + BG (3.1-7)
- C Where
- '
ASP = the alert setpoint (including background), 4 in epm; 1 f , i 4
i OM12D: ODCM Page : 34 Rev. : 1 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; CRe
= the calculated monitor net count rate, as per equation 3.1-5, in epm; 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.
1 I OM12D: ODCM Page : 35 Fev. : 1 Table 3.1-1 Whole Body and Skin Dose Factors Total Whole Body Total Skin Dose Factor l Dose Factor (L Radionuclide (Kg ) (mrem /yr/p Ci/m ) (mremfy+1.lM)r/ phi /m ) l Kr-83m 7.56E-02 2.12E+01 Kr-85m 1.17E+03 2.81E+03 l Kr-85 1.61E+01 1.36E+03 Kr-87 5.92E+03 1.65E+04 I Kr-88 1.47E+04 1.91E+04 Kr-89 1.66E+04 2.91E+04 Xe-131m 9.15E+01 6.48E+02 l Xe-133m 2.51E+02 1.35E+03 Xe-133 2.94E+02 6.94E+02 i Xe-135m 3.12E+03 4.41E+03 Xe-135 1.81E+03 3.97E+03 Xe-137 1.42E+03 1.39E+04 l i Xe-138' 8.83E+03 1.43E+04 ,
'Ar-41 8.84E+03 1.29E+04 s
l
OM12D: ODCM Page : 36 Rev. : 1 3.2 Compliance With 10CFR20 - Caseous 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 (see Figure 3.2-1) with the highest relative l dispersion factor (X/Q) for the period of release. (See Appendix A for elaboration on atmospheric dispersion). The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits. 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 for elaboration on atmospheric deposition), 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 : 37 l Rev. : 1 1 3.2.3 Dose Rate Calculations The following is the equation used to calculate the dose rate resultant from the release of radioactive materials in gaseous effluents to areas at or beyond the site boundary for the purpose of showi g compliance with CFR20. D p
= 3.15 x 10 9 * (X/Q or D/Q)
- DF *Q g (3.2-1)
Where: D aj p = the organ j dose rate as a function of age group a and pathway p, in mrem /yr; agjP = the dose factor for organ type j, age group a, DF pathway p for isotope 1 (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); 1 3.15 x 10 = the conversion factor to convert (mrem
- uCi)/(Ci
- s) to mrem /yr; Q g = the release rate of isotope i, in uCi/s
= 472 Cg f Where:
C = the concentration of radionuclide i in the i gaseous effluent, in uCi/ce; f = the gaseous effluent y flow rate during the release, in ft / min; 472 = the conversion factor (cc/f t 3 )f(,f,gn), The following relationships are used to derive the dose factors (DF I for noble gases, tritium, radioiodines and particulate $ die)dinequation3.2-1.
OM12D: ODCM Page : 38 Rev. I 1
- a. Total Body Dose Factors from Exposure to a Semi-Inifinite Plume T
DF =S p Xg DFB g (3.2-2) f Where: T DF g = the total body factor due to immersion in a semi-infig)ite (mrem
- m /(Cicloud
- s); of radionuclide i, in DFB f
= the total body gamma dose factor for a semi-infinite cloud of radionuclide i yhich includestheattenuationofSgfem 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, dimension 1 cast maximum exposed individual = 0.7 population dose 0.5 (Regulatory Guide 1.109) Xg = the annual avergge concentration of radionuclide iinair(pCi/m),foraung)treleasera5'U (Ci/yr) and a unit X/Q (s/m , in (pCi/m (Ci/yr)(s/m 3).
OM12D ODCM Page : 39 Rev. : 1
- b. Skin Dose Factors for Exposure to a Semi-Infinito Plume S
DFg =Xg (1.1 SF F7+DFS) g g (3.2-3) Where S DF g = the skin dose factor due to immersion in g semi-infinite cloud of radionuclido 1, (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 i
= the beta skin dose factor for a semi-infinite cloud of radionuclide 1 (includes attenuation '
layer of skin), from Table by the outer " 3.2-4 in (mrem
- m dead'j)/(pCi
- yr);
SF = the attenuation factor that accounts for the dose reduction due to the shtolding provided by resi-dential structures, dimensionless maximum exposed individual = 0.7, population dose = 0.5 (Regulatory Guide 1.109): Xg = the annual avergge concentration of radionuclide iinair(pC1/m),foraungtreleasera5*)/(C1/yr) (C1/gr) and a unit X/Q (s/m ), in (pC1/m (s/m ) 1.1 = the air done to tissue dose equivalent conver-sion factor, in mrom/ mrad.
- c. Dose Factors from External Irradiation from Radionuclides Deposited onto the Ground Surface C G DFg ) = 8760 Cg DFG g
)
S 7 (3.2-4) i Where: 1 G DF = the dose factor for radionuclide i to organ ij j resulting from exposure to radionuclides i , deposited3 onto the ground surface, in (mrom
- m')/Cil l G l
Cg a the ground plane concentration (pCi/m ) of
OM12D: ODCH Page : 40 Rev. I 1 radionuclide i for a unit release rate (C1/yr and a unil)D/4 in (pCi/m r*2ati ' 8 "ad d" Position (
/(Ci/yr)(m"l);
DFG g = the open field ground plane doso conversion factor for organ j from rgdlonuclide i, from Table 3.2-5, in (mrem
- m )/(pCi
- hr);
SF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, dimensionless: maximum exposed individual = 0.7, population dose = 0.5 (Regulatory Cuide 1.109): 8760 = the number of hours in a year.
- d. Dose Factors from Inhalation of Radionuclides in Air A
DF,g) = DFA,g) R, Xg (3.2-5) Wherut A the dose factor for radionuclide i to organ DF"Id=jofanindividualinageg5"P*d"* toinhalation,in(mrem *m)/(Ci*s}/s)] [ -- equivalent to (mrem /yr)(yr/C1)(m DFA aij
= the inhalation dose factor for radionuclide 1, organ j, and ago group a (the value for
. s'<in is assumed to be 0), from Tables 3.2-6 etrough 3.2-9, in mrem /pci; R* =theatnualairintakeforindivigualsinage group a, from Table 3.2-14, in m /yri l
Xg =theaniualavergr,econcentrationofradionuclide l 1ina;r(pci/m),foraung)treleaserage (Ci/yr) and3a unit X/Q (a/m , in (pCi/m )/ l (C1/yr)(s/m ). l 4 l t
l l OM12D: ODCM Page : 41 Rev. 1 l
- e. Dose Factors from the Ingestion of Atmospherically Released Radionuclides in Food D F F L L MM V V DF
= DFI,g) W , Cg + U,f CL g + U, C1 + U, fy Cg] (3.2-6)
Where D DF" '$ = the dose factor for radionuclide i to organ j of an individual in age group a from the ingestion of meat, leafy vegetables, milk, and produce (non-leafy vggetables, fruits, andgrains)in(mrem *m)/Ci,orjnthe cases of 11-3 and C-14 in (mrem
- m )/(Ci
- s);
F L M V C,C,C,C g g g g a 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), ground deposition (m
~
,relative or in cases of H-3 and C-14, a unit X/Q.
c ace"* rela 518'"ad-2*va(s/m ), )in (pCi/kg)(Ci/g or (pC1/ky})/(Ci/yr)(S/m (Ci/yr)(m /) or (pCif1)/ or (pCi/1)(C1/yr)(s/m /); DF1 = the ingestion dose factor for radionuclide "U i, organ j , and age group a. from Tables 3.2-10 through 3.2-13, in mrem /pci; f,fy t = the respective fractions of the ingestion rates of leafy vegetables and produce that are produced in the garden of interest, 1.0 and 0.76 respectively (Regulatory Guide 1.109); F L M V U,U,U,U = the annual intake (usage) of meat, leafy vegetables, milk, and produce respectively, for individuals in age group a, from Table 3.2-14, in l kg/yr or 1/yr.
OM12D: ODCM Page : 42 Rev. : 1 Table 3.2-1 Organ used for Caseous Effluent Dose Calculations
- 1. Bone
- 2. CI Tract
- 3. Kidney
- 4. Liver
- 5. Lung
- 6. Thyroid
- 7. Total Body
- 8. Skin Table 3.2-2 Age Groups Used for Caseous Effluent Dose Calculations
- 1. Adult (17 yr and older)
- 2. Teen (11-17 yr)
- 3. Child (1-11 yr)
- 4. Infant (0-1 yr)
I l
OM12D: ODCM Page : 43 Rev. : 1 Table 3.2-3 Gaseous Effluent Dose Pathways
- 1. Plume
- 2. Ground Shine
- 3. Vegetables
- 4. Meat
- 5. Cows
- 6. Goats
- 7. Inhalation 1
't
OM12D: ODCM Page : 44 Rev. : 1 , Table 3.2-4 i P Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Cases Nuclide DFS
- DFg ** DFB;*
Kr-83m --- 1.93E-05 7.56E-08 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 ' 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 3
- mrem
- m pC1
- yr i ** mrad
- m pC1
- yr l
l l l \ i
- i l f
1 i l 1 l
r 6 OM12D: ODCM Page : 45 Rev. : 1 l l Table 3.2-5 . External Dose Factors for Standing on Contaminated Ground (mrem /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-60 1.70E-08 2.00E-08 Ni 63 0.0 0.0 Nr 65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 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 3 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13
$r-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 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E 19 5.10E-09 Ru-106 1.50E-09 1.80E-09 1
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 s
OM12D: ODCM Page : 46 Rev. : 1 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 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 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.(0E 09 Np 239 9.50E-10 1.10E 09 8 4
OM12D: ODCM Page : 47 Rev. : 1 Table 3.2-6 Inhalation Dose Factors for Adult (mrem /pCi inhaled) NUCLIDE BONE LtvER T.ROCY THYROIO K10NEY LUNG GI-LLI 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 4.26E-0T 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E.06 1.28E-06 P 32 1.652-04 9.64E-06 6. 2 6 E.0 6 NO DATA NC DATA NO DATA 1.08E-05 CR 51 No DATA NO DATA 1. 2 5 E -0 8 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 f.8FE-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 MN $6 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1 18E.06 2.53E-06 FE $5 3.0FE-06 2.12E-06 4.91E-07 NU DATA NO DATA 9.01E-06 7.54E-07 FE 59 1.47E.06 1.47E-Oo 1 32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 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 8)E-0 6 NO DATA NO DATA 7.46E.04 1.56E-05 N1 63 5.40E-05 3.93E-06 1 81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 NI 65 1.92E-10 2.02E-11 1 14F-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 BR 83 NO DATA NO DATA 3.01E 0 8 NO DATA NO DATA NO DATA 2.90E-08 BR 84 NO DATA NO DATA 3. 91 E-0 8 NO DATA NO DATA NO DATA 2.05E-13 8 P. 85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA- LT E RB 86 NO OATA 1.69E-05 7.37E-06 NO DATA NO DATA h0 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 3.206-08 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21
$d 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E 04 4.37E-05 SR 90 1.24E.02 NO DATA 7. 62 E-0 4 NO DATA NO DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3.13 E -10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E.10 NO CATA 1.64E-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 4.8tE 05 I
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 6 E.10 NO DATA NO DATA 6.06E-06 5.27E-05 ' 6.77E-06 2.21E-04 1.88E-05 i IR 95 1.34E-05 4.3CE-06 2.9tE-06 NO DATA ZR 97 1.21E-08 2 45C-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 ! N8 95 t.76E-06 9.77E 07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E 05 MO 99 NO DATA 1 51E-08 2. 8 7E.0 9 NO DATA 3 64E-08 1.14E-05 1.10E-05 1.64E-13 4.63E-12 NO DATA 5.52E.12 9.55E-08 5.20E-07 l TC 99M 1.29E-13 i i
OM12D: ODCM Page : 48 Rev. : 1 Table 3.2-6 (Cont.) Inhalation Dose Factors for Adult (mrem /pci inhaled) NUCLICE BONE LIVER T.000Y THYR 0!D KIONEY LUNG GI-LLI IC101 5 22E-15 7.52E-15 7.38E-14 NO DATA 1 35E-13 4.99E-08 T.36E-21
. Rut 03 1 9tE-07 NO DATA 8. 2 3 E -0 8 NO DATA 7.29E-07 6.3tE-05 1.38E-05 RU105 9.88E-11 NG DATA 3.89E-11 NO DATA 1.77E-10 1.37E-06 6.02E-06 RUl06 8.64E-06 NO DATA 1.0iE-06 NO DATA t.67E-05 1.17E-03 1.14E-04 AGt10F t.35E-06 1.252-06 7. 4 3 E-0 7 NO DATA 2 46E-06 5.79E-04 3.78E-05 TE125M 4 27E-07 1.98E-07 5.84E-08 1 3tE-07 1.55E-06 3.92E-05 8.83E-06
. TEt27M 1.58E-06 7.2tE-07 1. 96 E-0 7' 4.1tE-07 5.72E-06 1.20E-04 1.87E-05 TEt27 t.75E-10 8.035-11 3.8 FE-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129* 1.22E-06 5.64E-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 1.53E-12 4. 8 7E-12 2.34E-11 2.42E-07 1.96E-08 TE131M 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 3.25E-08 2.69E-08 2.02E-08 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 1.45E-07 4.07E-07 1. 4 5 E-0 7 1.43E-05 6.40E-07 NO DATA 5.08E-08 8 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 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 1 135 3.35E-07 8.73E-07 3.2tE-07 5.60E-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 CS137 5.98E-05 7.76E-05 5.35E-05 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 BA139 1.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 HA140 4.88E-06 6.13F-09 l.2 t E-0 7 NO DATA 2 09E-09 1.59E-04 2.73F-05 mat 41 1.25E-11 9.4tE-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1 45E-17 RA142 3.29E-12 3.38E-15 2.07E-ti NO DATA 2.86E-15 1.49E-07 1.96E-26 LA140 4.10E-08 2 17E-08 5.73E-01 NU OATA NO DATA 1.70E-05 5.73E-05 LA142 8.54E-Il 3.88E-11 9.64E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CC141 2.49E-06 1.696-06 1.9 t E-0 7 NO DATA 7.83E-07 4.52E-05 1.50E-05 CFt43 2 33E-04 1.72E-06 1.9th-09 NO DAT4 7.60E-09 9.97E-06 2.83E-05 CEl44 4.29E-04 1.79E-04 2.30E-05 NO DATA t.06E-04 9.72E-04 1.02E-04 PR143 1.1FE-06 4.69E-07 5. 80E-0 8 NO DATA 2.70E-07 3. Sit-05 2.50E-05 PR144 3.76E-12 1.56E-12 1. 91 E -13 NO DATA 8.RIE-13 1. 2 7 F.-0 7 2.69E-18 N0147 6.59*-07 7.62E-0T 4. 5 6 E -0 8 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3 63E-06 1.94E-05 NP239 2.37E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 l.49E-05 t e
i 4 4 OM12D: ODCM Page : 49 i Rev. : 1 j Table 3.2-7 Inhalation Dose Factors for Teenager (mrem /pCi inhaled) BONE LIVER T . B O DY THYROID KIDNEY LUNG GI-LLI NUCL I C E g H 3 NO DATA 1.59E-0F 1.59E-07 1.59E-07 1.59F-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 I 4A 24 1.72E-06 1.72C-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1 72E-06 l ............................................................................ 4 2 36E-04 1.17 -0) 8.95E-06 NO DATA NC DATA NO DATA 1.16F-05
! P 32 1.942-09 2 62E-06 3.75E-07 CR 51 ND DATA NO DATA t.69F-08 9.37E-09 WN 54 NO DATA 6.39F-06 1.0)E-06 NO DATA 1.59E-06 2 48E-04 8.35E-06 NU DATA 2.246-10 1.90E-06 7.18E-06
*N 56 NO DATA 2.12d-10 3.15E-tl 7.99E-07 4.18E-06 2 98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 FE 55 NO DATA 1.9tf-04 2 23E-05 FE $1 1 19E 06 4.62d-04 1.79E-06 NO DATA NO DATA 1.68E-04 1.19F-05 CD SC NO DATA 2.59F-07 3.47E-07 NO DATA t
NO DATA 1.81E-06 2.48E-06 NO DATA NO DATA 1 09E-03 3.24E-05 CO 60 NO DATA 3.84E-05 1.77E-04 NI 63 7.25E-05 5.43E-06 2 47E-06 NO DATA NI 6b 2.73E-10 3.u6F-tt 1.59E-11 NO DATA NO DATA 1 17E-06 4.59E-06 CU 64 NO DATA 2.54E-10 1 06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 IN 65 4.c2E-06 1.67E-05 7 80E-0 6 NO DATA 1.08E-05 1.55E-04 5.83E-06 8.07E.13 NO DATA 7.53E-12 1.98E-07 3 56E-08 2N 69 6.04E-12 1.15F-tt NO DATA LT E-24 NO DATA NO DATA 4.30E-08 NO DATA NO DATA RR 83 NO DATA NO DATA LT E-24 DR 84 NO DATA NU OATA 5.4tE-08 NO DATA NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA L1 E-24 BR 85 NO DATA NO DATA 2.2tE-06 RD 86 NO DATA 2.38E-05 1.0$E-05 NO DATA 6.82E-06 3 40E-08 NO DATA NO DATA NO DATA 3 65E-15 R9 88 NO DATA 4.40E-08 2.9 tE-0 8 NO DATA NO DATA NO DATA 4.22E-17 RB 89 NO DATA NO DATA 3 02E-04 4.64E-05 SR 89 5.43E-05 No DATA 1.56E.06 NO DATA 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9 56E-05 SR 90 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05
$R 91 1 10E-08 NO DATA 3.43E-06 1.49E-05 SR 92 1 19E-09 NO DATA 5.08E-it NO DATA NO DATA 3.F3E-07 NO DATA 1. 00 E -0 8 NO DATA NO DATA 3.66E-05 6.99E-05 Y 90 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 Y 9le 4.63E-11 NO DATA NO DATA 3.67E-04 5.ttE-05 Y 91 8 26E.05 NO DATA 2.21E-06 NO DATA Y 92 1 84E-01 NO DATA 5.36E.11 NO DATA NO DATA 3.35E-06 2.06E-05 Y 93 1 69E-08 NO DATA 4. 6 5 E -10 NO DATA NO DATA 1.04E-05 7.24E-05 2R 95 1.82E-05 5.73E-06 3.94E-06 NO DATA c.42E-06 3.36E-04 1.86E-05 2R 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 ND 95 2.32E-06 1.29E-06 7.08E-0 7 NU OATA 1.25E-06 9.39E-05 1.2tE-05 MO 99 40 DATA 2.11E-08 4.01E-09 40 DATA 5.14E-08 1.92E-05 3.36E-05 IC 99M 1.13E-13 4.A3E-ll 6 24E-12 NO DATA F.20E-12 1 44E-0F 7.66E-07 f
OM12D: ODCM Page : 50 Rev. : 1 Table 3.2-7 (Cont.) Inhalation Dose Factors for Teenager (mrem /pci inhaled) NUELICE BONE LIVFR T.800Y THYR 010 KIDNEY LUNG G1-LLI TClot 7.40E-15 1.05E.14 1 03 E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 nul03 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 1Ut05 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 . rut 06 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 1.64[-06 9. 99E-0 7 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE124M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9 38E-06 TEl27M 2.25E-06 1.02C-06 2. 7 3E-0 7 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TEl27 2.5tE-10 1.14F-10 5.52[-lt 1.77E-10 9.10E-10 1 40E-06 1.01E-05 TE129M 1.74E-06 8.23C-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 TE13te 1.23E-08 7.51[-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.040-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4.50E-08 3.63E-08 2. 74 E-0 8 3.07E-08 2.44E-07 5.61E-05 5.79E-05 1 130 7.80E-07 2.24E-06 8.96E-0 7 1.86E-04 3.44E-06 NO DATA 1.14E-06 1 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11F-07 I 132 1.99E-07 5.47E-07 1. 9 7 E-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 1 134 1.11E-07 2.90E-07 1. 05 E-0 7 4 94E-06 4.58E-07 NO DATA 2.55E-09 1 135 4.62E-07 1.18C-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 1.7 t E-0 5 NO DATA 1.38E-05 2.22E-06 1.36E-06 C5137 8.38E-05 1.06E-04 3.89E-0S NO DATA 3.80E-05 1.51E-05 1.06E-06 C5138 5.82E-08 1.07E-07 5. 5 8 E-0 8 NO DATA 8.28E-08 9.84E-09 3.38E-Il 8A139 1.67E-10 1.18E-13 4 8TE-12 NO DATA 1.115-13 8.08E-07 8.06E-07 04140 6.84E-06 8.38F-09 4. 4 0E-0 7 NO SATA 2.85E-09 2.54E-04 2.86E-05 04141 1.78E-It 1.32E-t4 S . 91E-13 NO DATA l.235-t4 4.1tE-07 9.33E-14 HA142 4.62E-12 4.63E-15 2.84E-13 NO 04TA 3 92E-15 2.39E-07 5.99E-20 LAl40 S.99E-08 2.95[-08 7.82E-09 NO CATA NO DATA 2.68E-05 6.09E-05 LA142 1.20E-10 5.JLE-t! 1.32E-Il NO DATA NO DATA 1.27E-06 1.50E-06 CEl41 3.55E-06 2.37[-06 2. 7 t E-0 7 NO DATA 1.llE-06 7.67E-05 1.58E-05 CE143 1.32E-08 2.42E-06 2. 70E-0 9 NO DATA l.08E-08 1.63E-05 3.19E-05 CE144 6 11E-04 2 53E-04 3. 2 8 E -0 5 NO DATA 1.51E-04 1.67E-03 1.08E-04 PRl43 1 67E-06 6.64E-07 8 28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PRt44 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 N0147 9.83E-07 1.07E-06 6. 4 t E-0 8 NO DATA 6.26E-07 4.65E-05 2.28F-05 W 187 1.50E-09 1.229-09 4. 2 9 E-10 NO DATA NO DATA 5.92E-06 2.2tE-05 PP239 4.21E-08 3.99E-09 2.2tE-09 NU DATA 1.25E-08 A.llE-06 1.65E-05
OM12D: ODCM Page : 51 Rev. : 1 Table 3.2-8 Inhalation Dose Factors for Child (mrem /pci inhaled) NUCLICE BONE LIVER T.RODY THYROID KIONEY LUNG GI-LLI H J NO DATA 3.04C-07 3.04E.0 T 3.046-07 3.04E-07 3.04E-07 1.04E-07 C 14 9.70E-06 1.62E-06 1.82E-06 t.22E-06 1.82E-06 1.8?E-06 1.82E-06 NA 24 4.35E-06 4.35~-06 4.3SE-06 4. 3SE-06 4.35E-06 4.35E-06 4.35E-06 P 32 T.04E-04 1.095-05 2.6TE-05 NO DATA NO DATA Nn DATA 1.14E-05 CR 51 NO DATA NO DATA 4 17E-08 2.3tr-08 6.576-09 4.59E-06 2.93C-07 MN 54 NO DATA 1 16E-05 2. 5 7 E -0 6 NO DATA 2.7tE-06 4.26E-04 6.19F-06 MN 56 NU DATA 4.48E-to 8.43E-11 NO DA1A 4.52E-10 3.55C-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 FL 59 5.59C-06 9.c4E-06 4.51L-06 NO DATA NU OATA 3.43C-04 1.91E-05 CO $8 NO DATA 4.T96-07 8.55E-07 NO DAT1 NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E.06 6.12E-06 NO DATA NO DATA t.9tE-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06 til 65 8.08E-10 7.99E-11 4.44C-11 Nn DATA NU OATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90C-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 2.N 65 1.15E-05 3.06E-05 1.90C-05 No DATA 1.93E-05 2.69E-04 4.41E-06 2N 69 1.8tE-11 2.61E-11 2.410-12 NO DATA 1 58E-11 3.84E-07 2.75E-06 HR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 UR 84 NO DATA NU OATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 ER 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 R0 86 NO DATA 5.36C-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 RD 88 NO DATA 1.52E-0T 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.13!-08 7.8sE-08 NO DATA NO DATA NO DATA 5.ttE-10 l 59 89 1.62C-04 NO DATA 4.66E-06 NO DATA NO DATA 5.81C-04 4.52E-05 SR 90 2.73E-02 NO DATA 1. 74 E -0 3 NO DATA NO DATA 3.99E-03 9 28E-05 SP 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 6.49C-06 6.55E-05 l Y 90 1.!!E-06 NO DATA 2.94E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 9tr 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60F-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59 E -0 6 No DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-C6 6.46E-05 1 Y 93 5.04E-08 NO DATA 1.)UE-09 NO DATA NO DATA 2.01E-05 1.05E-04 2R 95 5.13E-05 1.13E-05 1.006 05 No DATA 1.6td-05 6.03E-04 1.65E-05 2R 97 5.07C-08 7.34E-09 4 32E-09 NO DATA 1 05E-08 3.06E-05 9.49E-05 N8 95 6.35E-06 2.48E-06 1. 7 7 E -0 6 NO DATA 2.33E.06 1.66E-04 1.00E-05 MO 99 NO DATA 4.66E-06 1.tSE-08 NO DAf t L.06E-07 3.66E-05 3.42E.05 IC 99P 4.8tE-13 9.410-13 1.56E-11 NO DATA L.37E-It 2.57E-07 1.30E-06
OM12D: ODCM Page : 52 Rev..: 1 Table 3.2-8 (Cont.) Inhalation Dose Factors for Child (mree/pCi inhaled) NUCL10E SUNE LIVER T.duDY THYRut0 KIONEY LUNG GI-LLI fttot 2.19C-14 2.30r-14 2.91E-13 NO UATA 3.92E-13 1.58E-07 4.416-09 RU103 7.55k-07 NO DATA 2.90F-0 7 NO DATA l.90E-06 1.79E-04 1.216-C5 RU105 4.136-10 NU OATA t.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU106 3.68E-05 NU OATA 4.5ff-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AGtt0* 4.56E-06 3 08E-06 2.47E-06 N0 UATA 5.74L-06 1.48E-03 2.71E-05 TE125N 1.82E-06 6.295-07 2.4 7E-0 7 5.202-07 NG DATA 1.29E-04 9 13E-06 TE1278 6.72E-06 2.3tE-00 8. t oE-0 7 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 IEt21e 5.19E-C6 1.85E-06 8.22E-07 1.7tE-06 1.36E-05 4.76E-04 4.9tE-05
- TE129 2.64E-11 9.45E-12 6.44C-12 1.93E-It 6.94L-It 7.91E-07 6.89E-06 TE13tr 3.63E-08 1.60E-08 1. 3 7 E-0 8 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 5.87C-12 2.28E-12 1.78C-12 4.69E-12 1.59C-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3 72E-05 1 130 2.21E-06 4.435-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 1 131 1.30E-05 1.30E-05 7.37E-06 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 DA7A 8.65E-07 t 133 4.48C-06 5.49C-06 2 08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.845-07 2 69E-0 7 1.37E-05 8 92E-07 NO DATA 2.58E-07 I 135 1.13E-06 2.16E-06 1.12 E -0 6 2.14C-04 3.62E-06 NO DATA 1.20E-06 C5134 1.76E-04 2.74C-04 6.0 7E-0 5 NO DATA 8.93E-05 3.27E-05 1.04E-06 C5136 1.76E-05 4.62C-05 3.14 E-0 5 NO DATA 2.58E-05 3.93E-06 1.13E-06 C5137 2.45E-04 2.23C-04 3.4 7E-0 5 NO DATA 7.63C-05 2.8tE-05 9.78E-07 C5138 1.7tE-07 2.2TE-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 84139 4.98E-10 2.66F-13 1.4SE-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 DAt40 2 00E-Ch 1.75E-08 1 1 TE-0 6 NO DA7A 5.7tE-09 4.7tE-04 2.75E-05 BAl41 5 29C-ll 2.95C-14 1.72F-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 Ba142 1 35E-Il 9.73C-15 F.54E-t 3 NO DATA 7.37E-15 4.44E-07 7.41E-10 LAl40 1.74E-OF 6.08E-08 2 04E-06 NO DATA NO DATA 4.94E-05 6.10E-05 LA142 3 50E-10 1.110-10 3.49E-Lt NO DATA NO DATA 2.35E-06 2.05E-05 CEt41 1.06E-05 5.28E-06 T. 8 3 E-01 NO DATA 2 3tE-06 1.47E-04 1.53E-05 o ............................................................................
CE143 9.89E-08 5.372-08 7.71E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CEt44 1.836-03 5.72C-04 9.77E-05 NO DATA 3.17d-04 3.23C-03 1.05C-04 PRt43 4.99E-06 1.SOE-06 2. 4 7 E -0 7 NO DATA 8.11k-07 1.17E-04 2.63E-05 PRt44 1.blE-11 4.99d-12 8.10 E.13 NO DATA 2.64E-12 4.23E-07 5.32E-08 NU147 2.920-06 2.36E-06 1.84E-07 NO DATA 1 30E-06 8.876-05 2.22F-05 W 187 4.416-09 2.6tC-09 1.!TF-09 NO DATA NO DATA 1.1tE-05 2.46E-05 , NP239 1.26E-07 9.04f-09 6.35E-09 NO DATA 2 63E-08 1 57E-05 1 73E-05 4
OM12D: ODCM Page : 53 Rev. : 1 Table 3.2-9 Inhalation Dose Factors for Infant (mrem /pCi inhaled) l NUCL!nE BUNE liver T.800Y THYROID 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.T9C-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 T.54E-06 7.54C-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 6.03E-05 S.5JE-0S NO DATA NO DATA NO DATA 1.tSE-05 CR St NO DATA NO DATA 6.3?E-08 4.1tE-08 9.45E-09 9.17E-06 2.55E-07 NN 54 NO DATA 1.8tE-05 3.56C-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 NN 56 NO DATA 1.100-09 1.50E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.4tt-05 8.39L-06 2.38E-06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.7FE-06 NO DATA NO DATA 7.25E-04 1.77E-05 CO 58 NU OATA 8. 7 t E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1.46E-05 8. 2 9 E -0 6 NO DATA NO DATA 1.49E-04 1 73E-06 NI 65 1.7tE.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 2N 65 1 38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 [ IN 69 3.85E-11 6.91C-11 5.13E-12 NO DATA 2 87E-tt 1.05E-06 9.44E-06 RR 83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 2. 86E-0 7 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT.E-24 RO 86 NO DATA 1.36E.04 6. 30E.0 5 NO DATA NO DATA NO DATA 2.17E-06 RD 88 NO DATA 3.98E-07 2.03E-0 7 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84C-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NU OATA 1. 8 5 E -0 3 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO 0&TA 2.4 7 E -0 9 NO DATA NO DATA 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 2.35C-06 NO DATA 6 30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 I Y 9tr 2.9tE-10 NO DATA 9.90E-12 NO DATA NO DATA 1.9?E-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 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 Y 91 1.07E-07 NO DATA 2.9tE-09 NO DATA NO DATA 5.46E-OS 1.19E-04 2R 95 d.24[-0S t.19E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 24 9T 1.07C-07 1.81E-08 8.36E-09 NU OATA 1.85E-08 7.88E-05 1 00E-04 NR OS 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.tTE-06 3.42E-04 9.05E-06 NO 19 N0 04TA 1.186-07 2. 3 t E-0 8 NO DATA 1.P9E-07 9.63E-05 3 48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-tt NO DATA 2.22E-It 5.79E-07 1.45E-06
OM12D: ODCM Page : 54 , Rev. : 1 Table 3.2-9 (Cont.) Inhalation Dose Factors for Infant (mrem /pCi inhaled) l NUCLICE BONE L!vER T . 80DY THYROID KIONEY LUNG GI-LLI TC101 4.65E-14 5.98E-14 5. 80 E-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 RUl06 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 l AG1104 7,13F-06 5.16E-06 3. 5 7 E -0 6 NO DATA 7.60E-06 2.62E-03 2.36E-05 1 TE125M 3.40E-06 1.42E-06 .70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 j
. . . . . . . . - = = = - - ...-........'..........---.....
. _=____=...=-_=-- = _.
TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1 32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M 1.01E-05 4.35E-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 TE131M 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 3.15E-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 i i 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 1 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07
..............................-... ....=== _- .---==- -- = _ .
I 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 __====-= - ...-. .. ... .................--............-==- _= ___. C5137 3.92E-04 4.37F-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 CS138 3.61E-07 5.SdE-07 2. 84 E-0 7 NO DATA 2.93E-07 4.67E-08 6.26F-07 BA139 1.06E-09 7.03E-13 3.C7E-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 UA141 1.12E-10 7.700-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06
- NA142 2.84E-11 2.365-14 1. 40 E -12 NO DATA 1.36E-14 1.11E-06 4.9$E-07
....--........................... ......====----- _=.......................
LA140 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 CE141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.TSE-06 3.69E-04 1.54E-05
====___.........
CE143 2.09E-07 1.18E-07 1.5RE-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.oSE-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 l PR143 1.00E-05 1.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 I PR144 3.42E-11 1.32E-11 1. 72 E-12 NO DATA 4. ROE-12 1.15E-06 3.06E-06 ND14T 5.67E-06 5.81F-06 3.57E-07 NO DATA 2.2SE-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 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
I OM12D: ODCM Page : 55 l Rev. : 1 Table 3.2-10 Ingestion Dose Factor for Adult (mrem /pCi ingested) l ! NUCLICE 80NE liver T.80CY THYRO 10 K1DNEY LUNG G1-LLI I - - . . - - - . _ - - - - . . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - - - - . . . . . . . - - - - . - - - - - . . j H 3 NO DATA 1.05E-07 1. 0$ E-0 7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.T0E-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 2.6cE-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 NN 54 NO DATA 4.575-06 8. 72 E-0 7 NO DATA 1.36E-06 NO DATA 1 40E-05
. - - - - - - - - - - . - - - - . . - - . . . . . . . . . . . . - - . . . . . . - - - - - - - - - - - - - - ==_ -----.
MN 56 NO DATA 1.15C-07 2.04 E-0 8 NO DATA 1.46E-07 NO DATA 3.67E-06 TE 55 2.75E-06 1.90F-06 4.4 3 C-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 CO 58 NO DATA 7.456-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14F-06 4.72C-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 3.13E-08 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 6.96E-06 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 2.14E 09 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA 2.11E-05 9. 8 3 E -0 6 NO DATA NO DATA NO DATA 4.16E-06 R8 88 NO DATA 6.05E-08 1.21E-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. 8 4 E-0 6 NO 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 2.20E-07 NO DATA NbbATA NO DATA 2 70E-05 I SR 92 2.15E-06 NO DATA 9 30E-0 8 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2. 5 8 E-10 NO DATA NO DATA NO DATA '1.02E-04
----- - _--- _=----
_== = - Y 91N 9.09E-11 NO DATA 3.52E-12 NO DAf4 NO DATA NO DATA 2.67E-10 f Y 91 1. 41 E-0.7 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 l . Y 92 8.45E-10 NO DATA 2.47E-11 NO DA1A 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
==-- ------..------.-.---
NB 95 6.22E-09 3.46E-09 1. 86 E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 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 6.985-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 G
OM12D: ODCM Page : 56 Rev. : 1 Table 3.2-10 (Cont.) Ingestion Dose Factor for Adult (mrem /pCi ingested) NUCL10E BONE LIVER T. BODY THYRO 10 KIDNEY 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 RU103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NU DATA 6. 0 S E -0 9 NO DATA 1.99E-07 NO DATA 9.42E-06
. . . . . - - . . . . . . - - - - - - - - - - . . . . . - . . . . - - - . . . - - - - - - . . . . . . . . . . . . . . . - = - - ____==_
RU106 2.75E-06 NO DATA 3.48E-07 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 3.59C-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127M 6.77E-06 2.42E-06 8.2 5 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 TE129N 1.15E-05 4.29E-06 1.82E-06 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-0 9 1.62E-08 8.63E-08 NO DATA 2.79E-09
- _ =. _=_.__= =_ _-- _- _= - . _ = - - - __ _. .
TE132 2.52E-06 1.63E-06 1.53E-06 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 2.0 3.E-0 7 5.43E-07 1. 90E-0 7 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1 03E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10
...........--= - ==_
I 135 4.43E-07 1.16E-06 4.28E-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 CS136 6.51E-06 2.57E-05 1. 85 E -0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06
=_ ... .- == __ ==... _____= -=
CS137 7.97E-05 1.09E-04 7.14 E-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 BA139 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-08 1. 3 3 E-0 6 NO DATA 8.67E-09 1.46E-08 4.18E-05 OA141 4.71E-08 1.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 64142 2.13E-08 2.19E-11 1 34E-09 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 5.825-11 1.45E-11 NO DATA NC DATA NO DATA 4.25E-07
. CE141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05
...--..----. ----.....--........................... ..-------..=- =.-
CE143 1.65E-09 1.2?E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.ABE-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 PR144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND147 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-08 NO DATA NO DATA NO DATA 2.82E-05
... .....-........................--- a.....................................
NP239 1.19E-09 1.17E-10 6. 4 5 E-1 1 NO DATA 3.65E-10 NO DATA 2.40E-05 l l l
OM12D: ODCM Page : 57 Rev. : 1 Table 3.2-11 Ingestion Dose Factors for Teenager (mren/pCi ingested) NUCLIDE BONE LIVER T.800Y THYR 0!D K!DNEY 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-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 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NU DATA NO DATA 3. 60 E-0 9 2.00E-09 7.99E-10 5.14E-09 6.05E-07 PN 54 NO DATA 5.90E-Oc 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05
....._..___........_ ....___..............___...............____.......=
MN 56 40 DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE $5 3.78E-06 2.68F-06 6. 2 5 E -0 7 NO DATA NU DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.JiE-05 5.29E-06 No DATA NO DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 CU 60 NO DATA 2.61E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-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. 41 E-0 8 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-09 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 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1 4 0E-0 5 NO DATA NO GATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO VATA NO DATA 7.30E-15 _....__ ..=_= __..........__ - - - _ _ . . . . . . . _ . . _ . . . = ._._................ R8 89 NO DATA 5.50E-08 3. 8 9 E-0 8 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1 26E-05 NO DATA NO DATA NO DATA 5.24E-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 21E-07 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 3.69E-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 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ER 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04
....._.. ________. _.........._ _....._-__==-- -.........--__- .. -_-___..
NH 95 8.22E-09 4.50!-09 2. S I E -0 9 NO DATA 4.42E-09 NO DATA 1.95E-05 MO 99 NO DATA 6.03E-06 1.12F-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.12E-10 9.265-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07 d a n ,, - . ~ . , c--, , . - , . . - __ , s , . . _
I OM12D: ODCM Page : 58 Rev. : 1 Table 3.2-11 (Cont.) Ingestion Dose Factor for Teenager (mrem /pCi ingested) BONE liver T.80DY THYROID K10NEY LUNG GI-LLI NUCLIDE TC101 3.60E-10 5.12E-10 5.01E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 NU OATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU105 2.18E-08 NO UATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05
----------------------------------------------------~~----------------------
3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 RU106 AG110M 2.05E-07 1.94E-07 1.laE-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE125M 3.83E-06 1.386-06 5.12E-07 1 0 7E-06 NO DATA NO DATA 1.13E-05 1 15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TF127M 9.67E-06 3.43E-06 1 58E-07 5.60E-08 3 40E-0 8 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE127 TEi29M 1 63E-05 6.05E-06 2.58E-06 5.26E 6.R2E-05 NO DATA 6.12E-05
------------ -------------------------- -===- - -------------------------
TE129 4.48E-09 1 67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-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 2.06E-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 1 131 5.85E-06 8.19E-06 c.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 I 133 2 01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 1 134 1.46E-07 3.07E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5 10E-09
! 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 C5134 8.37E-05 1 97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06
---------------------.----------------- ------------------------------------ 1.97E-05 2.12E-06 CS137 1.12E-04 1.49E-04 5 19E-05 NO DATA 5.07E-05 CS138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11 8A139 1.39E-07 9.78E-11 4.0$E-09 NO DATA 9.22E-11 6.74E-11 1.24E-06 DA140 2.84E-05 3.48E-09 1 83E-06 NO DATA 1.186-08 2.34E-08 4.38E-05 6.71E-08 5.01E-11 2.24E-09 NO DATA 4.65E-11 3.43E-11 1.43E-13 BA141 nA142 2 990-08 2 99E-11 1.84E-09 10 DATA 2.53t-11 1.99E-11 9.18E-20 1.71E-09 4.55E-10 No DATA NC DATA NO DATA 9.82E-05 LA140 3.48E-09 7.95E-11 1 98E-11 NO DATA NO DATA NO DATA 2.42E-06 LA142 1.79E-10 CE141 1 33E-08 8.88E-09 1.02E-09 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
- 6. 52 E -10 NO DATA 3.n4E-09 NO DATA 4.31E-05 PR143 1 31E-08 5.23E-09 1.01E-11 NO DATA 4.74E-14 PR144 4.30E-11 1.76E-11 2.18 E-12 NO DATA 3.68E-05 ND147 9.38E-09 1 02E-08 6.11E-10 NO DATA 5 99E-09 NO DATA 1 46E-07 1.19E-07 4.1TE-08 NO DATA NO DATA NO DATA 3.22E-05 W 187 -- ----
--------------------------------------------------------------------2.67E-05 NP239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA l
l l l
OM12D: ODCM Page : 59 Rev. : 1 Table 3.2-12 Ingestion Dose Factors for Child (mrem /pCi ingested) NUCLIUE BONE LIVER T.HOUY THYROID KIDNEY 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 no 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.1CE-05 40 DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO CATA 0.90E-09 4.94E-c9 1.35E-09 9.02E-09 4.72E-07 MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00C-06 NO DATA 8.98E-06 NN 56 NO DATA 3.34E-07 7.540-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1 15E-05 6.10E-06 1.89"-06 NU DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.6TE-05 1.3st-05 NO DATA NO DATA 7.74E-06 2.78E-05
..__._...... =._.._.. ..___.___ .......___.......__.__._...._......_... ..
CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-C4 2.88F-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-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1.37E-05 3.05E-05 2.2TE-05 NO DATA 2.30E-05 NO DATA 6.41E-06
.......... _....... _____....... _....... __... ___.=- _- =_ _ _ _ _ . = = -
ZN 69 4.38E-08 6.J3E-08 5.85E-09 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 1.98E-07 NO DATA' NO DATA NO DATA LT E-24
======_
RR 85 NO OATA 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 RB 88 END DATA 1.90E-07 1. 32 E-0 7 NO DATA NO DATA NO DATA 9.32C-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 ND 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 9.06E-07 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 ha DATA No DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1.61F-08 NO DATA NO DATA NO DATA 8.02E-05 . Y 92 3.60E-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 2R 95 1.16E-07 2.35E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 1. ZR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.25E-08 8.76E-00 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06
OM12D1 ODCM Page : 60 Rev. : 1 Table 3.2-12 (Cont.) , Ingestion Dose Factors for Child (mrem /pCi ingested) NUCLIOE BONE LIVER T.000Y THYROID KIDNEY LUNG GI-LLI _..__..___________.....__.... ..__..._-_---................__-- ---- =_ .. TC101 1.07E-09 1.12n-09 1.42E-08 NO DATA 1.91E-08 5.92C-10 3.56E-09 RU103 7.31E-07 NO DATA 2. 81 E -0 7 NO DATA 1.84E-06 ,Nn DATA 1 89E-05 ftU105 6.45E-08 NO DATA 2. 34 E-0 8 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 OtTA 1.82E-04 AG110M 5.39E-07 3.640-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE125M 1.14E-05 3 09E-06 1.52E-05 3.20E-06 NO DATA NO DATA 1.10E-05 TE12TN 2.89E-05 7.78E-06 3.43E-06 6.91E-06 e.24E-05 NO DATA 2.34E-05 TE127 4.71E-07 1.27F-07 1. 01 E-0 7 3.26E-07 1 34E-06 NO DATA 1.84E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 T E 12 9"___4.
._ __ 8 7 E _-_....
-..-____......__ 5 __________.. _____... ______. ________ .
TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE131M 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 0E-0 6 6.51E-06 4 15E-05 NO DATA 4.50E-05 t 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73C-05 9.83E 06 5.72E-03 2.84E-05 NO DATA 1.54E-06
. _ ====__=- =_ ---_- __-=_- __ .___ ----__._-_-__.--
t 132 0.00E-07 1.47E-06 0.76E-07 6.82E-05 2.25E-06 NO DATA 1.73E-06 I 133 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 3.58 E-0 7 1.79E-05 1.19E-06 NO DAT4 5.16E-07 I 135 1.75E-06 3.15E-Ob 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 C5134 2.34E-04 3.84E-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 5 NO DATA 3.44E-05 5.13E-06 2.27E-06
==- ____- ___________
CS 13'7 3.27E-04 3.13E-04 4.6 E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS138 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 8.11E-05 7.28E-08 4.8SE-06 NO DATA 2.37t-08 4.34E-08 4.21E-05 SA141 2.00E-07 1.122-10 6.51E-09 NO DATA 9.69E-11 6.58E-10 1.14E-07 GA142 8.14E-08 6.29E-11 4.88F-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 L A140 1.01E-08 3.53E-09 1.19E-09 10 DATA NO DATA NO DATA 9.84E-05 LA142 5.?4E-10 1.67E-10 5.21E-11 NO DATA NO DAT4 NO DATA 3.31E-05 CE141 3.97E-08 1.98E-08 2. 94 E-0 9 NO DATA 8.68E-01 NO DATA 2.47E-05 CE143 6.990-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA S.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 1.18E-08 1. 9 5 E-0 9 NO DATA 6.39E-09 NO DATA 4.24E-05 PR144 1.29E-10 3.91E-11 6.49E-12 NO DATA 2.11E.11 NO DATA 8.59E-08 N0147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-0 7 NO OATA NO DATA NO DATA 3.57E-05
----- ____ .._....._....=. _........... .._ _______ ___-- _=.------- ___
[ nr ' 39 5.25E-09 3.77E-10 2.65t-10 NO DATA 1.096-09 NO DATA 2.79E-05 l I i _ _ . . . _ _y . . , _ . _ _ . _ _ , - . . _. _m . _ _ . . , . - . _ , - _ _ . - - . . - -__ _ _ _.._._.__,.m.._._ ..
OM12D: ODCM Page : 61 Rev. : 1 Table 3.2-13 Ingestion Dose Factors for Infant (crem/pCi ingested) NtlCLIDE SONE liver T . 60 DY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.08E-07 3. 0 0 E-0 7 3.0AE-07 3.00E-07 3.00E-07 3.08E-07 0 14 2.3TE-05 5.06E-06 5. 0 6 E-0 6 5.06E-06 5.06E-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 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1.41E-08 1.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 NO DATA 1.99E-05 4.5IE-06 NO DATA 4.4tE-06 NO DATA 7.31E-06 MN 56 NO DATA 8 18E-07 1.41 E-0 7 NU OATA 7.01E-07 NO DATA 7.43E-05 rE 55 1.39E-05 8.18E-06 2.4CE-06 NO DATA NO DATA 4.39E-06 1.14E-06 FF 59 3.08E-05 5.382-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8. 9 3 E-0 6 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.086-05 2. 5 5 E-0 5 NO DATA NO DATA NO DATA 2.57E-05 N163 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06
.._.._.. ....________.. _________ - _==.. __ ..._ ___.._......===___-- ==
NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 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 S.33E-05
- . _ _ = -
IN 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 3.63E-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 RB 86 NO DATA 1.70E-04 8. 4 0 E-0 5 NO DATA NO DATA NO DATA 4.35E-06 48 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 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.05E-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. 76 E-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 2.15 E-10 NO DATA NO DATA NO DATA 1.46E-04
....._-___ _____ - ...._ _..__..___...._.........._......_ ... ==---
Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50F-05 ER 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 1.73E-08 1.00E-08 NO DATA 1.74h-08 NO DATA 1.46E-05 MD 99 NO DATA 3.40E-05 6. 6 3 E -0 6 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10 E -0 8 NO DATA 4.26h-08 2.07E-09 1.15E-06 1
. . . - - - - - ---..d
1
)
l l 1 OM12D: ODCM ! Page : 62 Rev. : 1 Table 3.2-13 (Cont.) Ingestion Dose Factors for Infar.t LIVER T.000Y
- . . . . . - _ _ . . . . . . - . . . . - - - - _ . . . - - _ _ ' _ - G1.LLI NUCLICE BONE THYRC D KIDNEY LUNG 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 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 RU105 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 9496E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 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 2436E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129M 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
. I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06
[ 131 3.59E-05 4.23E-05 1. 8 6 E -0 5 1.39E-02 4.94E-05 NO DATA 1.51E-06 __ .._.= ____....-___ =.......__-....---... _- _ ... _-___= . _ _
! 132 1.66E-06 3.37E-06 1 2 0E-0 6 1.5SE-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. 3 3 E-0 7 4.15E-05 1.99E-06 NO DATA 1.84E-06
...= _ - - .
I 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 1.81E-04 7.42E-05 1.91E-06 CS136 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. 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 1.2SE-06 BA139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05
- - . . . . . - _ _ - - - . . . . . . . - - _ . - - - - - - _ _ . . . . _ _ _ - - . . _ - - _ - - - = = _- =.___._.._..--
BA140 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 1.34E-08 NO DATA 1.ISE-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 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 L A142 1.10E-09 4.04E-10 9.6/E-11 NO DATA NC DATA NO DATA 6.86E-05 o CE141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-0C NO DATA 2.48E-05 CE143 1.48E-08 9.82C-06 1.12E-09 NO DATA 2.966-09 NO CATA 5.73E-05 CE144 2.98E-06 1.22C-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-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. 3 8 E-11 NO DATA 3.84k-11 NO DATA 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.28E-07 2.17 E-0 7 NO DATA NO DATA NO DATA 3.69E-05 j NP239 1.11E-08 9.93E-10 5. 61 E -10 NO DATA 1.98E-09 NO DATA 2.87E-05 L L
~
OM12D: ODCM Page : 63 Rev. : 1 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 (kg/yr) -- 26 42 64 Milk (1 /yr) 330 330 400 310 Meat & poultry (kg/yr) -- 41 65 110 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.
Table 3.2-15 Annual Usage Factors for the Average Individual Calculations Pathway Child Teen Adult Fruits, vegetables, & grain (kg/yr)* 200 240 190 Milk ( 1/yr) 170 200 110 Meat & poultry (kg/yr) 37 59 95 Inhalation (m /yr) 3700 8000 8000
- Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.
l L
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OM12D: ODCM Page : 65 Rev. : 1 3.3 Compliance With 10CFR50 Appendix I - Gaseous 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 i 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: 't
- a. For gamma radiation, during any calendar quarter:
Dair : 5 mrads,
- b. For beta radiation, during any calendar quarter:
D, SE 10 mrads,
- c. For gamma radiation, during any calendar year:
10 mrads, Dair :
- d. For beta radiation, during any calendar year:
D 55 20 mrads. l 1 l l 1
OM12D: ODCM Page : 66 Rev. : 1 3.3.2 Radioiodines, 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 organ 5 7.5 mrems and,
- b. During any calendar year: dose to any organ :E 15 mrems.
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: ODCM Page : 67 Rev. : 1
- a. Gamma Air Dose from Noble Gas Releases ir = 3.15 x 101
- X/Q * [Q g DF (3.3-1) 1 Where:
D7 = the annual gamma air dose due to noble gas 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 g = the release rate of radionuclide i, in uCi/s; X/Q = the normal relative dispersion factor, in s/m3 ; 1 3.15 x 10 = the conversion factor to convert (mrad
- uCi)/(Ci
- s) to mrad /yr.
- b. Beta Air dose from Noble Gas Releases D = 3.15 x 10I
- X/Q * [Q gDF i
Where: D = the annual beta air dose due to noble gas radionuclides, in mrad /yr; DF = the beta air dose factor for a uniform semi-infinite cloud of rgdionuclide i, from Table 3.3-1, in (mrad
- m )/(Ci
- s);
Q g = the release rate of radionuclide i, in uCi/s; X/Q = the normal relative dispersion factor, in s/m ; 3.15 x 10I = the conversion factor to convert (mrad
- uCi)/(Ci
- s) to mrad /yr.
3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated at least monthly. Calculations will be performed l to determine the maximum air dose as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. Monthly results should be added to the doses cumulated from other t 1
OM12D: ODCM Page : 68 Rev. : 1
, 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 Doses resulting from the release of gaseous effluents will be projected monthly when ventilation exhaust treatment systems are not being fully utilized. 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 will be calculated for the doses received resultant of all gaseous effluent releases. The population dose will be computed, taking into account geographically population distribution and pathway using the equations in Section 3.2. However, the dose factors, DF differ. Thepopulationdosefactorsarecalculatedina*mdEn,er similar to that 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 : 69 Rev. : 1 Figure 3.3-1 ,
' Gamma and Beta Air Dose Factors for Semi-Infinite Plume (mrad Ci
- s
*a ,
B Nuclide y q - 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 3.53+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 e
OM12D: ODCM Page : 70 Rev. : 1 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). PNPP does not intend to exceed 40 CFR190 limits during normal operation. However, if such a situation should occur, violations would be handed as per Technical Specification 3/4.11.4a. which require the following: With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a. , or 3.11.2.3b. , calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits.of Specification 3.11.4 have been exceeded. If s'uch is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year th'at includes the release (s) covered by this report. It shall also describe levels of radiation and concentratiosn of radioactive material 1.nvolved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not alredy been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a
, variance is granted until staff action on the request is complete.
1 This Special 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.
OM12D: ODCM Page : 71 Rev. : 1
- 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.
- 4. A determination of the dose resulting from direct radiation from the plant and storage facilities.
ine 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 PNPP 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. 0 Coolant activation by high energy neutrons, the 016 (n p)N reaction,isofinterestinBWRsgecauseitcanresultinturbine y skyshine and direct dose. The N present in the steam of a direct cycle BWR is carried with the steam into the turbine moisture separatorsI6 and associated equipment of the secondary cycle. 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. 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 surface of. buildings was calculated to be 2.2 x 10 mrem /yr.
f
OM12D: ODCM Page : 72 Rev. : 1 Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with analyses performed quarterly and annually. e h8 l l 1
/
I- , OM12D: ODCM Page : 73 Rev. : 1 i. 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM a 5.1 Monitoring Program o 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. , Ground water sampling will not be conducted as part of PNPP's REMP because this source is not tapped for drinking or irrigation purposes in the area of the plant and the hydraulic gradient is not suitable for useful groundwater contamination. The position of the plant and the underdrain system with respect to the hydraulic gradient is such that any leakage or overflow from the underdrain 3 . system will flow north towards Lake Erie. Local domestic wells ) outside the exclusion area boundary are up-gradient from the plant. As part of the REMP, samples will be routinely collected , from the closest potable water intakes on Lake Erie. The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent-i 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 exposures of individuals resulting from the station operation. The 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
- l A land use census will be conducted annually to identify the location of the nearest residence, the nearest vegetable garden
._ _. . . _ , , _ . _ . . . ~ , , _ _ - - _ _ . _ _ _ - . _ _ _ _ _ , m . . _ _ _ _ _ _ _ _ . _ _ _ . . _
OM12D: ODCM Page : 74 Rev. : 1 greater than 500 square feet, and the nearest milk-producing animal in each of the 22
- 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 being obtained the new location (s) will be added to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after 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 program. This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analysis of these crosscheck samples shall be included in the Annual Radiological Environmental Operating Report. If the results of a determinatien in the EPA crosscheck program (or equivalent program) are outside the specifi3d 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. 9
f I T Table 5.1-1 i PNPP Radiological Environmental Monitoring Program Analysis Sample Media Locations
- Sampling Frequency Type Frequency Airborne g) radioiodine 1,.3, 4, 5, 6, 35 Continuous sampler operation Radioiodine Weekly following l and with collection weekly or as I-131 canister change ;
;. particulates b) required by dust loading, ** 7' "'"E loading, whichever is more Particulates(d)
Gross Beta filter change frequent Camma Isotopic" Composite, by location ] quarterly Direct Radiation # .At each airborne Continuous sampling, one TLD Gamma Dose Quarterly (3 TLDs/ location) monitoring location exchanged quarterly 1 through 24, 35, Continuous sampling, one TLD Gamma Dose Annually 41, 42, 43, 45 exchanged annually Continuous sampling, one TLD Gamma Dose Quarterly or l exchanged quarterly or- under emergency under emergency situations situations , 28, 34, 36, 37 Composite (f) H-3 Composite, by WaterbornTb) surface i g location, quarterly ' drinking Cross Beta Monthly i
' t Gamma Isotopic Monthly ! Sediment from 25, 26, 27, 32 Semiannually -- Spring and Gamma Isotopic Semiannually
- shoreline Fall as weather permits i
i See footnotes at end of table. E2$
. f g ;; ,
. . .. .?
l .i i
~U$:r j
Table 5.1-1 (Cont.) PNPP Radiological Environmental Monitoring Program Analysis Sample Media Locations
- Sampling Frequency Type Frequency Ingestg 29, 30, 31, 33, 46 Monthly when animals are not I-131(a) , Monthly Milk on pasture Gamma l Isotopic g
29, 30, 31, 33, 46 Semimonthly when animals are I-131("}, Semimonthly on pasture Gamma g) Isotopic Fish ("} 25, 32 Semiannually -- Spring and Gamma Semiannually Fall as weather permits Isotopic (edible portion) Food Products ( 38, 39, 40, 44 Annually, at the time of I-131(* , Annually l harvest, broad leaf vegetation, Gamma g and fruits Isotopic Silage ( 29, 30, 31, 33 Annually, location determined by Gamma Isotopic Annually annual nilk - animal and' garden census Sampling locations were selected on the basis of local ecology, meteorology, physical charactizations of the region, and demographic and land use features of the site vicinity. Other factors considered were applicable regulatory guidelines (Appendix I to 10CFR50, Regulatory Guides 4.1, 4.2, and 4.8), population distribution (from environat.tal report), ease of access to sampling stations, security, future program integrity (e.g., not placing TLD's near areas under construction or where the potential for vandalism is high, and the NRC Radiological Assessment Branch Technical Position on radiological environmental monitoring as revised in Revision 1, November 1979 (reference 1). In addition, certain locations were PNPP operations are unlikely to affect levels of radiation or radioactivity were selected as control locations ya E$ 5
.a8
-8 9
Footnotes to Table 5.1-1 (Cont.) > (a) Sampling begins at least six months prior to PNPP operation, including one pasture season. (b) Sampling begins at laast 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 after sampling to allow for radon and thoron daughter decay. (e) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. If gress beta activity in air or water is greater than ten times the m
' ean of control samples for any medium, gamna 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 that are very short (e.g., hourly) relative to che compositing period (e.g., monthly). u ID Eu
< i: ;
-08 9
Table 5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples WATER AIRBORNEPARTICULgTE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/L) OR GASES (pCi/m ) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) H-3( 2 x 10 Mn-54 1 x 10 3 x 10 Fe-59 4 x 10 1 x 10 3 4 Co-58 1 x 10 3 x 10 Co-60 3 x 10 2 g.x 10 4 2 4 Zn-65 3 x 10 2 x 10 2 Zr-Nb-95 4 x 10 3 I-131 2 0.9 1 x 10 3 1 x 10 3 3 Cs-134 30 10 2 x 10 60 1 x 10 3 Cs-137 50 20 70 2 x 10 2 Ba-La-140 2 x 10 3 x 10 (1) For drinking water samples. The value given is the 40CFR part 141 value. E2$ s%- M8 9
Table 5.1 - Detection Capabilities for Environmental Sample Analysis and Lower Limit of Detection (LLD)'"' WATER AIRBORNE PARTICULgTE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS. (pCi/L) OR CASES (pCi/m ) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) _( pCi/kg, dry) Gross 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~ l 60 150
-2 Cs-134 15 5 x 10 130 15 60 180 -
Cs-137 18 6 x 10- 150 18 80 Ba-140 60 60 La-140 15 15 t
. CD D3
? % ;s
. . . . c.'
8 9
Table 5.1-3 (Cont.) - Table Notations i a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 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. b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, except for specification regarding energy dependence. Correction factors shall be provided for energy ranges not meeting the energy dependence speci-fication. "The methodology for determining the LLD is contained in Appendix B.
.< i: a
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~88 9
Table 5.1-4 Sampling Locations and Media for Environmental Monitoring Perry Nuclear Power Plant Location Distance No . - Description , (Miles) Direction Media ( l Redbird (Haines Road, North of West Chapel Road) 3.4 ENE APT, AI, TLD, On pole 3303609; first pole south of first driveway of left PR, SO l 2 Site Boundary; Tree line 0.7 E TLD, SO ! Ash tree 1000 feet NNW of second transmission tower from road l 3 Meteorological Tower 1.0 SE APT, AI, TLD I On fence surrounding the equipment shelter 4 On pole fW79/SPG5-30; inside auxiliary road gate of Parmly Road 0.7 S APT, AI, 1DJD , SO 5 Site Boundary, Quincy Substation 0.6 SW APT, AI, TLD On pole #L1283/9300, east side of substation 6 Concord Service Center (Control) 11.0 SSW APT, AI, TLD, Auburn Road south of Rt. 90; on inside rear fence next to gate PR, SO 7 Site Boundary; Lockwood Road Bus turnaround, on the right, 100 feet 0.6 NE TLD past the turnaround on tree with white dot. 8 Site Boundary; Tree Line, behind nursery off Antioch Road, follow 0.8 ENE TLD to end of nursery. On tree near creek with white dot. 9 Site Boundary; Transmission Line Tower 0.7 ESE TLD Third tower from Antioch Road toward the plant 10 South-southeast Corner Security Fence 0.8 SSE TLD on pole at turn in the fence 11 Transmission Line Tower 0.6 SSW TLD On tower at SW corner of Center and Parmly Roads 12 Site Boundary; Transmission Line Tower 0.6 WSW TLD, PR, SO Access road from N side of Parmly just W of location #5 13 Madison-on-the-Lake 4.7 ENE TLD At end of Whitewood Drive, N of Chapel Road, zmo NW side of turnaround on pole #835803 %$ $ 14 Hubbard Road (South of North Ridge Road) 4.9 E TLD, SO *
- UI On pole #28974 on W side of road, S side of McMackin Creek 15 Madison Substation (Eagle Street) 5.1 ESE TLD _. oo o On utility pole inside substation fence
~l
Table 5.1-4 (Cont.) Sampling Locations and Media for Environmental Monitoring Perry Nuclear Power Plant Location Distance No. Description (Miles) Direction Media 16 Dayton Road (North of Interstate 90) 5.0 SE TLD ", On pole f572203 on lef t af ter dirt driveway which is just ' after the sharp left on Dayton . 17 Chadwick Road (Cul de Sac South of Interstate 90) 5.2 SSE TLD i On pole #276222/118Z011; last pole on left l l 18 Blair Road 5.0 S TLD, SO On pole on lef t just af ter road makes 90 degree lef t curve down hill heading towards river 19 Lane Road and South Ridge Road 5.3 SSW TLD On pole #PC5648, 100 feet north of intersection 20 Nursery Road at Route 2 Overpass 5.3 SW TLD, SO On pole #828976 across from entrance to Route 2 21 Hardy Road at Painesville Township Park 5.1 WSW TLD On pole #378345, east of park entrance 22 Painesville 6.9 SW TLD On S side of Main Street across from Evergreen Cemetery on tree with white dot 60 feet west of pole IDBPG296 23 Fairport Harbor (High Street and New Street)' 7.9 WSW TLD On pole on rear substation facing street 24 St. Clair Ave. Substation (Control) 15.1 SW TLD In Mentor; on rear fence corner near railroad tracks 25 PNPP Discharge 0.6 NNW SED, FSH 26 Offshore at Redbird, vicinity of Ohio Water Service Company Intake 4.2 ENE S ED 27 Offshore, vicinity of Fairport Harbor Water Supply System Intake 7.9 WSW SED 28 Ashtabula (Control), CEI Generating Station Intake 22.0 ENE WTR m ms o 29 Deleted E$ 3 30 Milk Farm, Manley residence, North Ridge Road, Perry 2.3 SSW MLK ** **"U$ 31 Milk Farm, Hoffer residence, Antioch Road, Perry 1.4 ESE MLK 32 Mentor-on-the-Lake (Control) 15.8 WSW FSH , SED -- oo o 33 Brookglen Farm (Control), Greig residence, Callow Road, Leroy 10.2 S MLK 34 PNPP Intake 0.7 NW WTR "l
Table 5.1-4 (Cont.) Sampling Locations and Media for Environmental Monitoring Perry Nuclear Power Plant Location Distance No. Description (Miles) Direction Media ( 35 Site Boundary; north of transmission line, next to transformer, 0.6 E APT, AI, TLD follow tree line 36 Painesville Water Supply Intake 3.9 WSW WTR 37 Ohio Water Service Company Pump Station, 4.1 ENE WTR i Green Road, Madison l 38 Seith Farm, 2861 Antioch Road, 1.1 E FP l l 0.5 miles from North Ridge Road ! 39 Goldings Farm Stand 1.8 SSW FP l 3515 North Ridge Road ,! 40 Rideout residence, 2768 Antioch Road 1.1 E FP 0.7 miles from North Ridge Road , 41 Clark Road 1.1 SW TLD i One-half mile from Center Road. On pole No. 561969, ; I south side of road 42 Parmly. Road 0.8 S TLD j One-half mile from Center Road, located'on utility pole No. 582923 near southwest corner of plant fence 43 Parmly Road 1.0 SSE TLD Approximately 0.6 miles from Center Road next to utream. Tree with white dot 50 feet from road, left of stream. 44 Parmly Road 1.0 SSE VL Approximately 0.6 miles from Center Road. Green vegetation along roadside and field 45 Clark Road 0.9 SSW TLD Approximately 0.2 miles from Center Road on pole m mo No. 561960, south side "of road 0$3 [$ 46 4776 North Ridge Road 1.5 SE MLK (1) APT = Air particulate WTR = Water 'FP = Food Products -. oo o AI = Air iodine FSH = Fish SO = Soil "8* TLD = Ambient gamma dose rate MLK = Milk PR = Precipitation SED = Sediment k
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OM12D: ODCM
, Page : 86 Rev. : 1 Appendix A Atmospheric Dispersion and Deposition Parameters 4
,/
I
OM12D: ODCM Page : 87 Rev. : 1 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses will be calculated using the following equations. Dose calculations will be performed using hourly meteorological and effluent data. All atmospheric releases at PNPP are considered to be 4 ground-level releases,
- s. Constant Mean Wind Direction Relative Dispersion Factor X/Q = (A-1)
(u) (x) (CF) Where: 3 X/Q = the relative dispersion fac.or at ground level, in s/m ; T g = the terrain correction factor, from FSAR Table 2.3-26, dimensionless; u = the wind speed (measured at 10m), in m/s; l x = the distance of calculation, in m; l 2.032 = (2/7f)b divided by the width in radians of a 22.5' sector 2 (T= the lesser of (7
+ or CT** 3 27 Where:
l H = the building height (44.8m); 1 e t Cf* = the vertical dispersion coefficient, per Regulatory Guide 1.111, in m. 4 b. Depleted Relative Dispersion Factor (A-2) X/Qg = (X/Q)(DPL)) Where: X/Qd = the depleted relative dispersion fgetor (for airborne halogens and particulates), in s/m ; 4 I
I l OM12D: ODCM Page : 88 I Rev. : 1 DPL = the ground depletion factor for the jth distance, inter-d polated from Table A-1, dimensionless; X/Q = the relative dispersion factor, as per equation A-1.
- c. Ground Deposition (DEP )(Tf )
J ofq . (A-3) 0.3927 x Where: l l D/Q=therelativedeposiegonperunitarea(forhalogensand l particulates), in m ; th DEP =thegrounddepositionfactor.fortgej distance, interpolated from Table A-1, in m ; 1 T g = terrain correction factor, from FSAR Table 2.3-26, dimensionless; E x = the j distance, in m; 0.3927 = radians per 22
- sector
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 Depletion Factors (DPL ) All 0.970 0.936 0.900 0.800 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 f2$
.%a*
-38 9
d
OM12D: ODCM Page : 90 Rev. : 1 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 site boundary for sectors overland shall be used for radioactive gaseous effluent monitor setpoint calculations. The dispersion model used was X0QD0Q, with PNPP FSAR site-specific terrain adjustment factors included. Dispersion values are based on-the seven years of meteorological data (May 1, 1972 to April 30, 1974 and September 1, 1977 to August 31, 1982), ground-level releases, sector spread for purge calculations, and twelve wind speed classes. 19 r
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l i* l OM12D: ODCM I Page : 91 Rev. : 1 l Table A-2 Site Boundary Atmospheric Dispersion and Deposition Parameters for PNPP Unit 1 X/G D/G SECTOR DISTANCE l (MILES) ( SEC. /. CUB. METER) (PER SG. METER) N O.18 5.7E-05 1.6E-07 NNE O.25 1.8E-05 7.9E-08 NE O. 42 5.8E-06 3.1E-08 ENE O. 67 2.1E-06 1.6E-08 E O.67 2.2E-06 1.8E-08 ESE O.67 1.6E-06 1.3E-08 SE O. 79 1.4E-06 1.1E-08 SSE O.82 2.2E-06 1.4E-08 S 0. 81 2.7E-06 1.6E-08 SSW O.80 1.3E-06 6.SE-09 SW O.65 2.3E-06 1.1E-08 WSW O.56 4.2E-06 1.SE-08 W O.27 2.5E-05 4.6E-08 WNW O. 18 5.9E-05 8.4E-08 NW O.17 6.6E-05 1.1E-07 NNW O.17 5.9E-05 1.2E-07 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) NE O. 8 2.2E-06 1.1E-08 ENE 1. 0 1.1E-06 8.2E-09 E ** 1. 2 5.9E-07 4.6E-09 ESE 1. 2 4.4E-07 3.4E-09 SE 1. 2 3.9E-07 2.9E-09 SSE O. 9 1.9E-Oo 1.2E S 0. 9 2.2E-06 1.3E-08 SSW 1 0 9.5E-07 4.7E-09 SW 1. 2 5.OE-07 2.2E-09 WSW 1. 1 8.7E-07 2.7E-09 l l l4 t
i OM12D: ODCM 4
- Page : 92 Rev. : 1 Table A 4 Atmospheric Dispersion (X/Q) as a Function of Distance (s/m )
SECTOR O. 2 0. 3 . O. 4 0. 5 0. 6 (MILES) (MILES) (MILES) (MILES) (MILES) N 4.904E-05 2.453E-05 1.525E-05 1.057E-05 7.918E-06 NNE 2.656E-05 1.360E-05 8.640E-06 6.082E-06 4.612E-06 i NE 1.859E-05 9.760E-06 6.293E-06 4.460E-06 3.383E-06 : ENE 1. 327E-OS 7.129E-06 4. 636E-06 3. 293E-06 2.490E-06 E 1.363E-05 7.362E-06 4.760E-06 3.367E-06 2.538E-06 ESE 1.025E-05 5.566E-06 3.602E-06 2.547E-06 1.916E-06 SE 1.113E-05 6. 061E-06 3. 935E-06 2. 788E-06 2.100E-06 SSE 1.894E-05 1. 022E-05 6. 647E-06 4. 718E-06 3. 560E-06 S 2.283E-05 1.227E-05 7.932E-06 5.615E-06 4.238E-06 SSW 1.142E-05 6. 079E-06 3. 925E-06 2. 777E-06 2. 097E-06 e SW 1.449E-05 7.663E-06 4.928E-06 3.479E-06 2.622E-06 WSW 2.151E-05 1.111E-05 7.031E-06 4.934E-06 3.733E-06 W 4.184E-05 2.081E-05 1.281E-05 8.833E-06 6.606E-06 WNW 4.669E-05 2.298E-05 1. 401 E-05 9. 573E-06 7. 093E-06 NW 4.909E-05 2.423E-05 1. 482E-05 1. 015E-05 7. 521E-06 NNW 4.580E-05 2.26'6E-05 1. 390E-05 9. 541E-06 7. 083E-06 SECTOR O. 7 0. 8 0. 9 1. 0 1. 1 (MILES) (MILES) (MILES) (MILES) (MILES) N 6.138E-06 4.968E-06 4.203E-06 3.636E-06 1.949E-06 NNE 3.622E-06 2.947E-06 2.481E-06 2.132E-06 1.278E-06 NE 2.662E-06 2.165E-06 1.815E-06 1.552E-06 9.269E-07 ENE 1.957E-06 1.588E-06 1.325E-06 1.129E-06 6.710E-07 E 1.991E-06 1.613E-06 1.343E-06 1.141E-06 6.768E-07 ESE 1.501E-06 1.215E-06 1. 010E-06 8. 571E-07 5. 000E-07 SE 1.647E-06 1.334E-06 1.100E-06 9.402E-07 4.456E-07 SSE 2.796E-06 2.266E-06 1.885E-06 1.601E-06 5.524E-07 5 3.327E-06 2.697E-06 2.247E-06 1.911E-06 7.340E-07 SSW 1.646E-06 1.335E-06 1.114E-06 9.486E-07 5.223E-07 4 SW 2.053E-06 1.664E-06 1.391E-06 1.188E-06 5.667E-07 WSW 2.927E-06 2.380E-06 2.OO2E-06 1.719E-06 8.671E-07 W 5.110E-06 4.135E-06 3.504E-06 3.036E-06 1.630E-06 WNW 5.434E-06 4.378E-06 3.719E-06 3.235E-06 1.845E-06 NW 5.764E-06 4.643E-06 3.941E-06 3.425E-06 1.952E-06 NNW 3.439E-06 4.385E-06 3.720E-06 3.230E-06 1.839E-06 1 I b
_. __ __ __ _. _ . _ . . _ _ _ m __ ._ _ . ___ _ __._ . _ _ _ _ _ . _ _ _ Olu2D: ODCM Page : 93 Rev. : 1 Table A-4 ((%nt.) 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 1.729E-06 1.549E-06 1.399E-06 1.273E-06 1.166E-06 i NNE 1,128E-06 1.OO6E-06 9.050E-07 8.202E-07 7 485E-07 NE 8.150E-07 7.243E-07 6.494E-07 5.867E-07 5.340E-07 , ENE 5.878E-07 5.'20SE-07 4.652E-07 4.190E-07 3.803E-07 E 5.917E-07 5.230E-07 4.667E-07 4.197E-07 3.804E-07 ESE 4. 437E-07 3. 919E-07 3. 494E-07 3.140E-07 2. 843E-07 l SE 3.891E-07 3.436E-07 3.062E-07 2.751E-07 2.491E-07 SSE 4.829E-07 4.267E-07 3.807E-07 3.423E-07 3.102E-07 S' 6.424E-07 5 684E-07 5.076E-07 4.569E-07 4.145E-07 SSW 4.576E-07 4.054E-07 3.624E-07 3.266E-07 2.965E-07 : SW 4.976E-07 4.417E-07 3.955E-07 3 570E-07 3.246E-07 WSW 7.649E-07,6.G14E-07 6.125E-07 5.547E-07 5.060E-07 i W 1.44SE-06 1.299E-06 1.175E-06 1.070E-06 9.809E-07 i WNW 1.644E-06 1.479E-06 1.341E-06 1.224E-06 1.124E-06 ! NW 1.739E-06 1.563E-06 1.416E-06 1.292E-06 1.186E-06 NNW 1.637E-06 1.471E-06 1.332E-06 1.214E-06 1.115E-06 l l I SECTOR 1. 7 1. G 1. 9 2. 0 2. 1 (M!LES) (M!LES) (M!LES) (MILES) (MILES) N 1.074E-06 9.931E-07 9.226E-07 8.604E-07 8.052E-07 NNE 6.867E-07 6.331E-07 5.864E-07 5.453E-07 5.090E-07 i NE 4. 886E-07 4. 494E-07 4.153E-07 3. 854E-07 3. 263E-07 ENC 3.471E-07 3.184E-07 2.936E-07 2.718E-07 2.526E-07 E 3.467E-07 3.177E-07 2.925E-07 2.705E-07 2.283E-07 ESE 2.590E-07 2.371E-07 2.182E-07 2.017E-07 1.871E-07 ' SE 2.268E-07 2.076E-07 1.910E-07 1.765E-07 1.637E-07 SSE 2 827E-07 2.590E-07 2.384E-07 2.203E-07 1.407E-07 5 3.780E-07 3.466E-07 3.194E-07 2.955E-07 1.373E-07 SSW 2.706E-07 2.494E-07 2.290E-07 2.121E-07 1.409E-07 SW 2.968E-07 2.727E-07 2.518E-07 2.335E-07 2.173E-07 WSW 4.639E-07 4.275E-07 3.957E-07 3.678E-07 5.303E-07 W 9.037E-07 8.365E-07 7.777E-07 7.258E-07 1.050E-06 WNW 1.038E-06 9.622E-07 8.960E-07 8.375E-07 1.142E-06 NW 1.095E-06 1.015E-06 9.445E-07 8.826E-07 8.275E-07 1 NNW 1.028E-06 9.527E-07 8.865E-07 8.281E-07 7.761E-07 , l
=
9 e e. ,
OM12D: ODCM Page : 94 Rev. : 1 i Table A-4 (Cont.) Atmospheric Dispersion (X/Q) as a Function of Distance 3 (s/m ) SECTOR 2. 2 2. 3 . 2. 4 2. 5 2. 6 , (MILES) (M!LES) (MILES) (MILES) (MILES) N 7.560E-07 7.118E-07 6.720E-07 6.359E-07 6.033E-07 < NNE 4.766E-07 4.477E-07 4.217E-07 3.982E-07 3.770E-07 NF 3 050E-07 2.859E-07 2.688E-07 2.534E.-07 2.395E-07 ENE 2.356E-07 2.205E-07 2.069E-07 1.947E-07 1.837E-07 E 2.127E-07 1.988E-07 1.864E-07 1.752E-07 1.652E-07 ESE 1.743E-07 1.62BE-07 1.52SE-07 1.433E-07 1.351E-07 SE 1.524E-07 1.424E-07 1.334E-07 1.253E-07 1.181E-07 SSE' 1.311E-07 1.225E-07 1.149E-07 1.080E-07 1.018E-07 S 1.280E-07 1.197E-07 1.123E-07 1.056E-07 9.963E-08 SSW 1.314E-07 1.230E-07 1.154E-07 1.087E-07 1.025E-07 SW 2.030E-07 1.902E-07 1.787E-07 1.683E-07 1.590E-07 WSW 4.964E-07 4.661E-07 4.388E-07 4.142E-07 3.920E-07 W 9.867E-07 9.296E-07 8.780E-07 8.313E-07 7.891E-07 i WNW 1.075E-06 1.014E-06 9.587E-07 9.088E-07 8.636E-07 NW 7. 782E-07 7. 339E-07 6. 939E-07 6. 376E-07 6. 247E-07 NNW 7. 297E-07 6. 879E-07 6 502E-07 6.161E-07 5. 852E-07 SECTOR 2. 7 2. 8 2. 9 3. 0 3.1 (MILES) (MILEG) (MILES) (M!LES) (MILES) N 5.734E-07 5.460E-07 5.200E-07 4.976E-07 4.762E-07 NNE 3.576E-07 3.398E-07 3.235E-07 3.086E-07 2.948E-07 NE 2.268E-07 2.152E-07 2.046E-07 1.949E-07 1.859E-07 " ENE 1.737E-07 1.645E-07 1.562E-07 1.485E-07 1.415E-07 E 1.560E-07 1.477E-07 1.401E-07 1.331E-07 1.267E-07
- ESE 1.275E-07 1.207E-07 1.144E-07 1.087E-07 9.399E-08 SE 1.115E-07 1.054E-07 9.996E-08 9.493E-08 9.031E-08 SSE 9.613E-08 9.099E-08 8.630E-08 8.OOOE-OB 7.805E-08 S 9.415E-08 8.917E-08 8.462C-08 8.044E-08 7.661E-08 SSW 9.697E-OG 9.189E-OG 0.725E-08 8 299E-08 7.907E-08 SW 1.50SE-07 1.428E-07 1.357E-07 1.291C-07 1.231E-07 WSW 3.716E-07 3.531E-07 3.360E-07 3.204E-07 2 520E-07 W 7.503E-07 7.147E-07 6.820E-07 6.519E-07 5.874E-07 l
WNW 8.220E-07 7.830E-07 7.487E-07 7.164E-07 7 722E-07 . ! NW 5.945C-07 5.668E-07 5.413E-07 5 178E-07 5.412E-07 i NNW 5.567E-07 5.307E-07 5 067E-07 4 846E-07 4.642E-07 l l
r 1 OM12D: ODCM Page : 95 Rev. : 1 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 4.563E-07 4.379E-07 4.200E-07 4.047E-07 3 899E-07 NNE 2.820E-07 2.702E-07 2.592E-07 2.489E-07 2 395E-07 NE 1.77'/E-07 1.700E-07 1.629E-07 1.562E-07 1 SO1E-07 ENE 1.3SOE-07 1.290E-07 1.234E-07 1.182E-07 1.135E-07 E 1.208E-07 1.154E-07 1.103E-07 1.OS6E-07 1.013E-07
.ESE 8. 958E-08 8. SSOE-08 8.173E-08 7. 021E-08 7. 499E-08 SE 8.606E-08 8.213E-08 7.849C-08 7.510E-08 7.2OOE-08 SSE 7.441E-08 7.10SE-08 6.794E-08 6.SO3E-08 6.237E-08 S 7.307E-08 6.980E-08 6.678E-08 6.395E-08 6.136E-08 SSW 7.546E-08 7.212E-08 6.902E-08 6.613E-08 6.348E-08 SW 1.176E-07 1.125E-07 1.077E-07 1.033E-07 9.922E-08 WSW 2.410E-07 2.300E-07 2.214E-07 2.12SE-07 2.044E-07 W S.631E-07 S.406E-07 S.196E-07 4.999E-07 4.018E-07 WNW 7.409E-07 7.118E-07 6.848E-07 6.593E-07 6 359E-07 NW S.192E-07 4.987E-07 4.797E-07 4.618E-07 4.454E-07 NNW 4.452E-07 4.276E-07 4.112E-07 3.958E-07 3.817E-07 3, 7 3, e 3, 9 4, o 4, t SECTOR (MILES) (MILES) (MILES) (MILES) (MILES)
N 3.759E-07 3.628E-07 3.*04E-07 3.388E-07 2.981E-07 NNE 2 336E-07 2.222E-07 2.144E-07 2.070E-07 1.819E-07 NE 1.441E-07 1.390E-07 1.339E-07 1.292E-07 1.247E-07 ENE 1.090E-07 1.048E-07 1.009E-07 9.718E-08 9.373E-08 E 9.722E-08 9.342E-08 8.987C-08 8 653E-08 8.341E-08 ESE 7.196E-08 6.912E-08 6.647E-08 6.399E-08 6.166E-08 SE 6 900E-08 6 635E-08 6.380E-08 6 140E-00 S.378E-08 SSE S 987E-00 S.753E-08 S.533E-08 5.328E-08 5 13SE-08 5 S 692E-08 5.664E-08 5.451E-08 5 251E-08 S.063E-08 SSW 6.098E-00 S.86SE-08 S.646E-08 5 441E-08 S.248E-08 SW 9.537E-08 9.178E-08 0.841E-08 8 S2SE-08 8,228E-08 WSW 1.967E-07 1.896E-07 1.028E-07 1.76SE-07 1.462E-07 W 4.646E-07 4.48SC-07 4.334E-07 4.191E-07 3 043E-07 WNW 6.137E-07 5.929E-07 S.733E-07 S 540E-07 4.180E-07 NW 4. 298E-07 4.151E-07 4. 013E-07 3. 883E-07 3. 761E-07 NNW 3.682E-07 3 SS6E-07 3 438E-07 3.326E-07 2.928E-07
r OM12D: ODCM Page : 96 Rev. : 1 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) p N 2.887E-07 2.798E-07 2.714E-07 2.634E-07 2.559E-07 NNE 1.759E-07 1.703E-07 1.650E-07 1.599E-07 1.552E-07 NE 1.205E-07 1.166E-07 1.128E-07 1.093E-07 1.059E-07 ENE 9.047E-08 8.740E-08 8.451E-08 8.176E-08 7.921E-08 E 8.046E-08 7.769E-08 7.508E-08 7.260E-08 7.03CE-08 ESE 5.946E-08 5.740E-08 5.545E-08 5.361E-08 5.189E-08 SE 5.186E-08 5.OO5E-08 4.835E-08 4.673E-08 4.523E-08 SSE 4.954E-08 4.783E-08 4.622E-08 4.469E-08 4.327E-08
, S 4.886E-08 4.719E-08 4.562E-08 4.413E-08 4.274E-08 l SSW 5.067E-08 4.896E-08 4.735E-OS 4.581E-08 4.439E-08 I SW 7.948E-08 7.684E-08 7.435E-08 7.198E-08 6.978E-08 WSW 't.413E-07 1.368E-07 1.325E-07 1.284E-07 1.246E-07 W 2.948E-07 2.858E-07 2.773E-07 2.691E-07 2.616E-07 WNW 4.051E-07 3.930E-07 3.815E-07 3.706E-07 3.603E-07 NW 3.645E-07 3.536E-07 3.432E-07 3.333E-07 3.241E-07 NNW 2.837E-07 2.752E-07 2.671E-07 2.593E-07 2.521E-07 SECTOR 4, 7 4. 8 4. 9 5. 0 (MILES) (MILES) (MILES) (MILES) N 2.487E-07 2.419E-07 2.354E-07 2.292E-07 NNE 1.507E-07 1.464E-07 1.423E-07 1.384E-Cf NE 1.028E-07 9.975E-08 9.689E-08 9.416E 't.' l ENE 7. 676E-08 7. 443E-08 7. 223E-08 7. 014E-c.R
. E 6.809E-08 6.600E-08 6.402E-08 6.214E ?.tl ESE 5.025E-08 4.869E-08 4.722E-08 4.592E-08 SE 4.379E-08 4.244E-08 4.115E-08 3.992E-00 SSE 4.191E-08 4.063E-08 3.941E-08 3.82SE-00 S 4.141E-08 4.015E-08 3.896E-08 3.782E-08 SSW 4.302E-08 4.173E-08 4.050E-08 3.934E-08 SW 6.767E-08 6.567E-08 6.377E-08 6 196E-08 WSU 1.210E-07 1.175E-07 1.142E-07 1.110E-07 W 2.543E-07 2.474E-07 2.408E-07 2.345E-07 WRW 3.505E-07 3.411E-07 3.322E-07 3 237E-07 NW 3.152E-07 3 068E-07 2.987E-07 2.910E-07 NNW 2 452E-07 2 386E-07 2 323E-07 2 263E-07
Old2D: ODCM Page : 97 Rev. : 1 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 1.396E-07 7.578E-08 4 836E-08 3.383E-08 2.516E-08 NNE 1.107E-07 6.OO8E-08 3.834E-08 2.682E-08 1.995E-08 NE 9.733E-08 5.284E-08 3.372E-08 2.359E-08 1.755E-08 ENE 1.067E-07 5.795E-08 3.698E-08 2.587E-08 1.924E-08 E 1.184E-07 6.429E-08 4.103E-08 2.870E-08 2.135E-08 ESE 8.865E-08 4.813E-08 3.071E-08 2.149E-08 1.598E-08 SE 9.402E-08 5.105E-08 3.258E-08 2.279E-08 1.695E-08 SSE 1.338E-07 7.266E-08 4.637E-08 3.244E-08 2.413E-08 S 1.429E-07 7.757E-08 4.951E-08 3.463E-08 2.576E-08 SSW 6.094E-08 3.309E-08 2.111E-08 1.477E-08 1.099E-08 SW 7.267E-08 3.945E-08 2.518E-08 1.761E-08 1.310E-08 WSW 7.117E-08 3.864E-08 2.466E-08 1.725E-08 1.283E-08 W 7.129E-08 3.870E-08 2.470E-08 1.728E-08 1.285E-08 WNW 6.970E-08 3.784E-08 2.415E-08 1.689E-08 1.236E-08 NU 8 904E-08 4.834E-08 3.085E-08 2.158E-08 1.605E-08 NNu 9.623E-08 5.225E-08 3.334E-08 2.332E-08 1.735E-08 SECTOR O. 7 0. 8 0. 9 1. 0 1. 1 (MILES) (MILES) (MILES) (MILES) (MILES) N 1.954E-08 1.560E-OP 1.277E-08 1.068E-08 5.545E-09 NNE 1.549E-08 1.237E-08 1.013E-08 8.465E-09 4.945E-09 NE 1.362E-08 1.088E-08 8.907E-09 7.445E-09 4.350E-09 ENE 1.494E-08 1.193E-08 9.768E-09 8.164E-09 4.770E-09 E 1.658E-08 1.323E-08 1.084E-08 9.058E-09 5.292E-09 ESC 1.241E-08 9.905E-09 8.112E-09 6.781E-09 3.961E-09 SE 1.316E-08 1.051E-08 8.605E-09 7.192E-09 3.361E-09 SSE 1.874E-08 1.496E-08 1.225E-08 1.024E-08 3.480E-09 S 2.OOOE-08 1.597E-08 1.308E-08 1.093E-08 4.128E-09 SSW 8.531E-09 6.810E-09 5.577E-09 4.662E-09 2.521E-09 SW 1.017E-08 8.120E-09 6.651E-09 5.559E-09 2.598E-09 WSW 9.963E-09 7.953E-09 6.513E-09 5.444E-09 2.678E-09 W 9.980E-09 7.966E-09 6.524E-09 5.453E-09 2.832E-09 WNW 9.757E-09 7.788E-09 6 379E-09 5.332E-09 2.932E-09 NW 1 246E-08 9.949E-09 8.148E-09 6.811E-09 3.745E-09 NNW 1 347E-08 1.075E-08 8.807E-09 7.361E-09 4.047E-09
OM12 D: ODCM Page . 98 Rev. : 1 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) N 4.777E-09 4.163E-09 3.664E-09 3.252E-09 2.910E-09 NNE 4.260E-09 3.713E-09 3.268E-09 2.900E-09 2.595E-09 NE 3.747E-09 3.265E-09 2.874E-09 2.551E-09 2.283E-09 ENE 4.109E-09 3.581E-09 3.151E-09 2.797E-09 2.503E-09 E 4.559E-09 3.973E-09 3.497E-09 3 104E-09 2.777E-09 ESE 3. 413E-09 2. 974E-09 2. 617E-09 2. 323E-09 2. 079E-09 SE 2.E96E-09 2.524E-09 2 221E-09 1.971E-09 1.764E-09 SSE 2.998E-09 2.612E-09 2.299E-09 2.041E-09 1.826E-09 s 3.556E-09 3.099E-09 2.727E-09 2.421E-09 2.166E-09 SSU 2.172E-09 1.892E-09 1.666E-09 1.478E-09 1.323E-09 SW 2.238E-09 1.950E-09 1.717E-09 1.524E-09 1.363E-09 WSW 2.307E-09 2.011E-09 1.770E-09 1.571E-09 1.406E-09 W 2.440E-09 2.126E-09 1.871E-09 1.661E-09 1.486E-09 WNW 2.525E-09 2.201E-09 1.937E-09 1.719E-09 1.538E-09 NW 3.226E-09 2.811E-09 2.474E-09 2.196E-09 1.965E-09 NNN 3.487E-09 3.039E-09 2.674E-09 2.374E-09 2.124E-09 SECTOR g,7 g, g g,9 2. 0 2. 1 (MILES) (MILES) (MILES) (MILES) (MILES) N 2.619E-09 2.371E-09 2.158E-09 1.973E-09 1.012E-09 NNE 2.336E-09 2.115E-09 1.925E-09 1.760E-09 1.616E-09 NE 2.055E-09 1.860E-09 1.693E-09 1.548E-09 1.292E-09 ENE 2.253E-09 2.040E-09 1.856E-09 1.697E-09 1.558E-09 E 2.500E-09 2.263E-09 2.059E-09 1.883E-09 1.572E-09 ESE 1.871E-09 1.694E-09 1.542E-09 1.410E-09 1.294E-09 SE 1.588E-09 1.437E-09 1.308E-09 1.196E-09 1.098E-09 SSE 1.644E-09 1.488E-09 1.354E-09 1.238E-09 7.816E-10 S 1.950E-09 1.765E-09 1.606E-09 1.469E-09 6.743E-10 SSW 1.191E-09 1.078E-09 9.810E-10 8.969E-10 5.883E-10 SW 1.227E-09 1.111E-09 1.011E-09 9.244E-10 8.488E-10 WSW 1.265E-09 1.145E-09 1.042E-09 9.530E-10 1.352E-09 W 1.338E-09 1.211E-09 1.102E-09 1.OOBE-09 1.430E-09 WNW 1.085E-09 1.254E-09 1.141E-09 1.043E-09 1.393E-09 NW 1 769E-09 1.601E-09 1.457E-09 1.333E-09 1.223E-09 NNW 1.912E-09 1.731E-09 1.575E-09 1.440E-09 1.322E-09
OM12D: ODCM l Page : 99 Rev. : 1 Table A-5 (Cont.) Atmospheric Deposition (D/Q) as a Function of Distance (m- ) SECTOR 2. 2 2. 3 . 2. 4 2. 5 2. 6 (MILES) (MILES) (MILES) (MILES) (MILES) N 1.670E-09 1.544E-09 1.433E-09 1.334E-09 1.245E-09 NNF 1.489E-09 1.377E-09 1.278E-09 1.189E-09 1.110E-09 NE 1.191E-09 1.101E-09 1.022E-09 9.511E-10 8.879E-10 ENE 1.436E-09 1.328E-09 1.233E-09 1.147E-09 1.071E-09 E 1.449E-09 1.340E-09 1.243E-09 1.157E-09 1.080E-09 ESE 1.193E-09 1.103E-09 1.024E-09 9.528E-10 8.895E-10 SE 1.012E-09 9.362E-10 8.687E-10 8.085E-10 7.548E-10 SSE 7.204E-10 6.663E-10 6.183E-10 5.754E-10 3.372E-10 S 6.215E-10 5.749E-10 5.334E-10 4.964E-10 4.634E-10 SSW 5.422E-10 5.015E-10 4.653E-10 4.331E-10 4.043E-10 SW 7.823E-10 7.236E-10 6.714E-10 6.249E-10 5.834E-10 WSW 1. 246E- 09 1.153E-09 1.070E-09 9.956E-10 9.294E-10 W 1.318E-09 1.219E-09 1.131E-09 1.053E-09 9.827E-10 WNW 1.284E-09 1.18SE-09 1.102E-09 1.026E-09 9.573E-10 NW 1.128E-09 1.043E-09 9.678E-10 9.OO7E-10 8.409E-10 NNW 1.219E-09 1.127E-09 1.046E-09 9.735E-10 9.089E-10 SECTOR 2. 7 2. 8 2. 9 3. 0 3. 1 (MILES) (MILES) (MILES) (MILES) (MILES) N 1.163E-09 1.092E-09 1.026E-09 9.666E-10 9.120E-10 NNE 1.039E-09 9.742E-10 9.155E-10 8.621E-10 8.134E-10 NE 8.307E-10 7.789E-10 7.320E-10 6.893E-10 6.504E-10 ENF 1.OO2E-09 9.396E-10 8.830E-10 8.315E-10 7.845E-10
. E 1.011E-09 9.477E-10 8.906E-10 8.387E-10 7.913E-10 ESE 8.332E-10 7.804E-10 7.334E-10 6.906E-10 5.923E-10 SE 7.061E-10 6.622E-10 6.223E-10 5.860E-10 3.529E-10 SSE 5.026E-10 4.713E-10 4.429E-10 4.171E-10 3.935E-10 5 4.336E-10 4.066E-10 3.821E-10 3.598E-10 3.395E-10 SSW 3.782E-10 3.547E-10 3.333E-10 3.139E-10 2.961E-10 SW 3.459E-10 5.118E-10 4.810E-10 4.529E-10 4.273E-10 WSW 8.695E-10 8.154E-10 7.663E-10 7.216E-10 5.607E-10 W 9.194E-10 8.621E-10 8.102E-10 7.630E-10 6.775E-10 WNW 8.958E-10 8.400E-10 7.894E-10 7.434E-10 7.890E-10
. NW 7.867E-10 7.377E-10 6.933E-10 6.528E-10 6.719E-10 ! NNW 8,303E-10 7.973E-10 7.493E-10 7.056E-10 6.657E-10 t t e . . ,. - . . _ . - - , _ _ . , - - - ,, - -- v. -.
Old2D: ODCM Page : 100 Rev. : 1 Table A-5 (cont.) Atmospheric Deposition (D/Q) as a Function of Distance (m" ) SECTOR 3. 2 3. 3 . 3. 4 3. 5 3. 6 (MILES) (MILES) (MILES) (MILES) (MILES) N 8.620E-10 8 161E-10 7.739E-10 7.347E-10 6.991E-10 NNE 7.688E-10 7.279E-10 6.902E-10 6.552E-10 6.235E-10 NE 6.147E-10 5.820E-10 5.518E-10 5 239E-10 4.985E-10 ENE 7.415E-10 7.020E-10 6 657E-10 6.320E-10 6.014E-10 E 7.479E-10 7.081E-10 6.714E-10 6.374E-10 6.066E-10 ESE 5.598E-10 5.3OOE-10 5.026E-10 4.771E-10 4.541E-10 SE 5.225E-10 4.947E-10 4.691E-10 4.454E-10 4.238E-10 SSE 3.719E-10 3.521E-10 3.339E-10 3.170E-10 3.016E-10 S 3.209E-10 3.038E-10 2.880E-10 2.735E-10 2.602E-10 SSW 2.799E-10 2.650E-10 2.513E-10 2.386E-10 2.270E-10 SW ' 4.039E-10 3.824E-10 3.626E-10 3.442E-10 3.276E-10 WSW 5.299E-10 5.017E-10 4.757E-10 4.516E-10 4.298E-10 W 6.403E-10 6.062E-10 5.749E-10 5.458E-10 5.193E-10 WNW 7.457E-!O 7.060E-10 6.695E-10 6.356E-10 6.048E-10 NW 6.351E-10 6.013E-10 5.702E-10 5.413E-10 5.151E-10 NNW 6.292E-10 5.957E-10 5.649E-10 5.363E-10 5.103E-10 SECTOR 3. 7 3. 8 3. 9 4. 0 4. 1 (MILES) (MILES) (MILES) (MILES) (MILES) N 6.657E-10 6.347E-10 6.059E-10 5.791E-10 5.036E-10 NNE 5.937E-10 5.661E-10 5.404E-10 5.165E-10 4.492E-10 NE 4.747E-10 4.526E-10 4.321E-10 4.129E-10 3.951E-10 ENE 5.727E-10 5.460E-10 5.212E-10 4.981E-10 4.766E-10 E 5.776E-10 5.507E-10 5.257E-10 5.024E-10 4.807E-10 ESE 4.324E-10 4.122E-10 3.935E-10 3.761E-10 3.598E-10 SE 4.036E-10 3.848E-10 3.673E-10 3.510E-10 3.053E-10 SSE 2.872E-10 2.739E-10 2.614E-10 2.498E-10 2.390E-10 S 2.478E-10 2.363E-10 2.255E-10 2.155E-10 2.062E-10 SSW 2.162E-10 2.061E-10 1.968E-10 1.880E-10 1.799E-10 SW 3.119E-10 2.974E-10 2.839E-10 2.713E-10 2.596E-10 WSW 4.093E-10 3.902E-10 3.725E-10 3.SeOE-10 2.919E-10 W 4.945E-10 4.715E-10 4.501E-10 4.302E-10 3.087E-10 WNW 5.759E-10 5.491E-10 5.242E-10 5.010E-10 3.728E-10 NW 4.905E-10 4.677E-10 4.464E-10 4.266E-10 4.082E-10 NNW 4.859E-10 4.633E-10 4.423E-10 4.227E-10 3.676E-10
-_ _. . . _ _ , . . - . _ , . _ . - , - - _ _ . _ . , . . _ . ,m._ . _ _ , , , . , _ _ , . _ _ . , , . . _ _ . . _ , . , . , _ , - . _ _ - . - - - _ .
. OM12D: ODCM Page : 101 Rev. : 1 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 4.823E-10 4.624E-10 4.437E-10 4.260E-10 4.097E-10 NNE 4.302E-10 4.124E-10 3.957E-10 3.800E-10 3.654E-10 NE 3.784E-10 3.627E-10 3.480E-10 3.342E-10 3.214E-10 ENE 4.564E-10 4.375E-10 4.198E-10 4.031E-10 3.877E-10 E 4.603E-10 4.413E-10 4.234E-10 4.066E-10 3.910E-10 ESE 3.446E-10 3.333E-10 3.170E-10 3.044E-10 2.927E-10 SE 2.924E-10 2.803E-10 2.690E-10 2.583E-10 2.484E-10 SSE 2.289E-10 2.195E-10 2.106E-10 2.022E-10 1.944E-10 S 1.975E-10 1.893E-10 1.817E-10 1.744E-10 1.677E-10 SSN 1.723E-10 1.652E-10 1.585E-10 1.522E-10 1.463E-10 SW 2.486E-10 2.333E-10 2.287E-10 2.196E-10 2.112E-10 WSW 2,796E-10 2.690E-10 2.372E-10 2.469E-10 2.375E-10 W 2.956E-10 2.834E-10 2.719E-10 2.611E-10 2.511E-10 WNW 3.570E-10 3.422E-10 3.284E-10 3.153E-10 3.032E-10 NW 3.909E-10 3.747E-10 3.596E-10 3.453E-10 3 320E-10 NNW 3. 521E-10 3. 375E-10 3. 239E-10 3.110E-10 2. 991E-10 SECTOR 4, 7 4. 8 4. 9 5. O (MILES) (MILES) (MILES) (MILES) N 3.941E-10 3.795E-10 3.656E-10 3.525E-10 NNE 3.515E-10 3.334E-10 3.261E-10 3.144E-10 NE 3.092E-10 2.977E-10 2.868E-10 2.765E-10 ENE 3.729E-10 3.591E-10 3.460E-10 3.336E-10 E 3.762E-10 3.622E-10 3.489E-10 3.364E-10 ESE 2.816E-10 2.711E-10 2.612E-10 2.519E-10 SL 2.339E-10 2.300E-10 2.216E-10 2.137E-10 SSE 1.871E-10 1.801E-10 1.735E-10 1.673E-10 S 1.614E-10 1.554E-10 1.497E-10 1.443E-10 SSN 1.408E-10 1.355E-10 1.306E-10 1.259E-10 SW 2.031E-10 1.956E-10 1.884E-10 1.817E-10 WSW 2.285E-10 2.199C-10 2.119E-10 2.043E-10 W 2.415E-10 2.326E-10 2.241E-10 2.160E-10 WNW 2.917E-10 2.809E-10 2.706E-10 2.609E-10 NW 3.194E-10 3.075E-10 2.963E-10 2.857E-10 NNW 2.877E-10 2.770E-10 2.669E-10 2.573E-10
l' OM12D: ODCM Page : 102 ' Rev. : 1 APPDIDIX B Lower Limit of Detection
OM12D: ODCM Page : 103 Rev. : 1 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 scintillation, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to sample activity: f*b +
*b (B-1) 3.3 l 1 l LLD =
s b/ (C)(E)(V)(Y ) exp (-g gt) j 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 count rate in units of transformations ' b per unit time; t = the counting time of background; b
; t, = the counting time of the sample; V = the sample size, in units of mass or volume; i Y = the fractional radiochemical sample collection or concen-c tration yield (when applicable);
bt=forplanteffluents,theelapsedtimebetweenthemidpoint
- of sample collection and time of counting; for environ-mental samples, the elapsed time between sample collection (or end of the sample collection period) and time of counting; k=theradioactivedecayconstantfortheradionuclidein question. '
k
-~_. . . _
OM12D: ODCM Page : 104 Rev. : 1 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(0.693dt/tq) D (C)(E)(t)(V)(Y )(Y ) Where: LLD = the lower limit of detection, in uCi or pC1 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; t g = the half-life of the radionuclide in question; V = the sample size, in units of mass or volume; Y = the fractional radiochemical, sample collection, or con-C centration yield (when applicable); Y 7=theyieldofthegammarayinquestion; dt=forplcnteffluentstheelapsedtimebetweenmidpoint 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 D"** *** " "'
=k2+2 1+" 2}ls (B g+B)+I+
2 I j ( - a) 2n 2n j Where: B; = the number of counts in n background channels below the peak due to Compton scattering, etc., determined at the same time a photopeak is measured;
i OM12D: ODCM Page : 135 Rev. : 1 B2 = the number of counts in the n background channels abore 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; (T7 = the standard deviation of I. Typical values of E, V, Y, and t shall be used in the calculation. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g. , potassium-40 in milk samples). Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11.1.1.1-1, 4.11.2.1.2-1, and 4.12.1-1 of the Radiological l Effluent Technical Specifications for the Perry Nuclear Power Plant will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the 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 the Annual Radiological Environmental Operating Report or the Semiannual Radioactive Effluent Release Report. E
OM12D: ODCM Page : 106 Rev : 1
. 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. 20555, 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
- t. 1977.
- 9. Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous 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 Implementing Appendix I," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, April 1977.
II me n . OM12D: ODCM Page : 107 - LAST Rev. : 1 REFERENCES (Cont.)
- 11. Regulatory Guide 4.15. " Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Ef fluent 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, 19.84. ,
- 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.
- 17. Yocher, D.C. , " Radioactive Decay Data Tables ," Technical 7
Information Center, U.S. Department of Energy, Springfield, Virginia 22161, September, 1985. DW/0DCM1/ cap a___________________.}}