ML20038B856
| ML20038B856 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/30/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20038B854 | List: |
| References | |
| PROC-811130, NUDOCS 8112090179 | |
| Download: ML20038B856 (206) | |
Text
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CONT 10_LD C0?Y 45 0 OFFSITE DOSE CALCULATION MANUAL 0DCM O
g @ commonwealth Edison Company gmue .
O LA SALLE COUNTY STATION l
i OFFSITE DOSE CALCULATION i
MANUAL COMMONWEALTH EDISON COMPANY O
FEBRUARY 1979 Revision 3 November 1981 DOCKET NUMBERS 50-373 AND 50-374 O
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REVISION 2 AUGUST 1980 4-
'OFFSITE DOSE CALCULATION MANUAL CONTENTS' I' PAGE
1.0 INTRODUCTION
- 1.0-1 2.0' OFFSITE DOSE LIMITS 2.1-1 2 .1 - AIRBORNE RELEASES 2.1-1
- 2.2 RADIOACTIVITY IN LIQUID RELEASES 2.2-1 2 ~. 3 -ENVIRONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE 2.3-1
- . 3.0 ATMOSPHERIC TRANSPORT, DIFFUSION, AND DOSE
- MODELS 3 .1-l' f
3.1 METEOROLOGICAL DATA FOR MODELS- 3.1-1 f
i 3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS 3.2-1 3.3 MODELS FOR CALCULATING DOSE FROM NOBLE GASES 3.3-1 .
% 3.4 MODELS FOR CALCULATING DOSE FROM RADIOIODINES, l "PARTICULATES," AND OTHER RADIONUCLIDES 3.4-1 J
4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1-1
- 4.1 AQUATIC TRANSPORT 4.1-1 l
i 4.2 AQUATIC DOSE MODEL 4.2-1 l 4.3 AQUATIC TRANSPORT DURING TANK OVERFLOW i
CONDITIONS 4.3 5.0
SUMMARY
5.1-1 5.1 AIRBORNE EFFLUENTS 5.1-1
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i 5.2 LIQUID RELEASES 5.2-1 l
5.3 URANIUM FUEL CYCLE 5.3-1 i 5.4 PRIMARY DRINKING WATER STANDARDS 5.4-1 i
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6.0 REFERENCES
6.0 4 7.0 DATA FOR DOSE ASSESSMENT MODELS 7.0-1 l
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( )'-
'7.1 DATA COMMON TO ALL NUCLEAR STATIONS 7.1-1 1
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REVISION 3 NOVEMBER 1981 CONTENTS (Con t ' d )
[ PAGE 7.2 DATA _ SPECIFIC TO EACH NUCLEAR STATION 7.2-1
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8.0 RADISACTIVE EFFLUENT TREATMEttr SYSPEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMEttrAL RADIOLOGICAL MONITORING 8.1-1 8.1 GASEOUS ' RELEASES 8.1-1 8.2 LIQUID RELEASES 8.2-1 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROtt PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 s
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REVISION 2 AUGUST 1980
1.0 INTRODUCTION
TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
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j -!e i REVISION 2
.l AUGUST 1980 i
1.0 INTRODUCTION
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- LIST OF FIGURES 1
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NUMBER TITLE i 1.0-1 Flow Chart for Offsite Dose Calculations I i
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REVISION 2 AUGUST 1980
1.0 INTRODUCTION
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This document provides a concise description of the environmental dose models and techniques used to calculate the offsite doses resulting from the release of radioactive material from Com-monwealth Edison's nuclear power plants. A flow chart of these dose models and techniques is given in Figure 1.0-1.
Documentation for both airborne (Sections 2.1 and 3.0) and aquatic pathways (Sections 2.2 and 4.0) are included.
The models consider two release modes: airborne and liquid.
Airborne releases are further subdivided into two subclasses:
(1) radioiodines, particulates, and other nonnoble gas nuclides, and (2) noble gases.
Radiciodines, Particulates, and Other Nuclides In this model it is assumed that there is an adult and infant living in each of 16 sectors around the g-)#
'- station. Infant exposure occurs through inhalation and any actual milk pathway. Adult exposure derives from inhalation, assumed leafy vegetable and produce pathways, and any actual milk and meat pathways, -
Doses to each of seven organs listed in Regulatory Guide 1.10. (bone, liver, total body, thyroid, kidney, lung, and GI-LLI) are computed from individual nuclide contributions in each of the sectors. Searching over sector and organ, the largest organ dose is compared to the 10 CFR 50, Appendix I design objectives. This dose calculation is performed monthly for infants and annually for adults. (The adult dose is computed annually to confirm the premise that the infant is the critical person. The adult will be substituted for the infant in the monthly schedule if found to be the critical person.) As necessary, the release
-)
rates of these nuclides will be converted to dose rates for comparison to the limits of 10 CFR 20.
1.0-1 i
REVISION 2 AUGUST 1980 Noble Gases O Exposure to the beta and gamma radiations of the noble gases will result in a whole body and skin dose.
The maximum whole body and skin doses for each offsite sector are determined from the individual nuclide con-tributions and the maximum dose values are compared to the 10 CFR 50, Appendix I design objectives. This calculation is performed monthly. As necessary, the noble gas release rate will be converted to dose rates for comparison to the limits of 10 CFR 20.
For liquid releases it is assumed that liquid effluents discharged into a river undergo mixing prior to consumption as either potable water or fish by adults. For releases to Lake Michigan a finite plume dilution factor is computed for the potable water path-way and a hypothetical river model is created for the fish !
pathway. Doses to the seven critical organs are determined
{ from individual nuclide contributions and the largest organ dose is compared to the 10 CFR 50 design objectives. Compliance with the 10 CFR 20 maximum permissible concentrations is done on a batch-by-batch basis prior to discharge. Compliance with the various regulatory limits for offsite doses is demonstrated with the techniques of Section 5.0. - All site independent data used in the calculations are given in Section 7.1. Site specific data are given in Section 7.2. The models and techniques used to establish the alarm and trip setpoints of the gaseous and liquid effluent monitors are described in Section 8.0. 1.0-2
- O O O~ ;
4 i i 4 i 1 , Release Radionuclide Critical Environmental Critical Regulatory Compliance Frequency of Mode Class Person Pathway Orgq Limit l'e thodolory Calculation
-lnh'tla tion -10 CFR 50 Doce Calculation Monthly Infant -Tny roid
- 4 -Milk -10 CFR 20 Release Rate Calculation - When Necessary 3
Rsdiciodines, 1 -Particulatec -Inhslation
- i. & Other Nuclides 4
sdult Meat Tnyroid* Airborne- ]_
, -Leafy Vegetablee -10 CFR P^ Release Rate Calculation When Necessary
-Produce rWhole Body -10 CFR 50 Dose Calculation :-:onthly
-noble Cases All Plume Exposure y -
,s Persons LSkin - -10 CPR 20 Release Rate Calculation-When Necessary
[ o - 1 6 Adult Water Various 10 CFR 20 10 CFR 20, App. B, Each "able 2, Col. 2 Batch i d Liquid - All -Fich Thyroid j Adult - or - - 10 CFR 50 Dose Calculation : onthly } '-Water Bone
- 1 1
1 I l 1 i :> :n 85! j i Most likely "ritical organ; however, dose is computed for 7 organs. @y sw A The computation of dose to the adult is performed annually to confirm the premise that the infant is the s@
- critical person. L o
FIGURE 1.0-1 FLOW CHART FOR OFFSITE DOSE CALCULATIONS
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s REVISION 2 AUGUST 1980
~ 2.0 OFFSITE DOSE LIMITS (d TABLE OF CONTENTS PAGE 2.0 OFFSITE DOSE LIMITS 2.1-1 2.1 AIRBORNE RELEASES 2.1-1 2.1.1 Noble Gases 2.1-1
- 2.1.1.1 10 CFR 50, Appendix I Design Objectives 2.1-1 2.1.1.1.1 Air Dose 2.1-1 2.1.1.1.1.1 Gamma Air Dose 2.1-1 2.1.1.1.1.1.1 Gamma Air Dose, Calendar Quarter 2.1-1 2.1.1.1.1.1.2 Gamma Air Dose, Calendar Year (Four Consecutive Quarters) 2.1-3 2.1.1.1.1.2 Beta Air Dose 2.1-3 2.1.1.1.1.2.1 Beta Air Dose, Calendar Quarter 2.1-3 2.1.1.1.1.2.2 Beta Air Dose, Calendar Year (Four Consecutive Quarters) 2.1-6 2.1.1.1.2 Whole Body Doso 2.1-6 2.1.1.1.2.1 Whole Body Dose, Calendar Quarter 2.1-6 2.1.1.1.2.2 Whole Body Dose, Calendar Year (Four Consecutive Quarters) 2.1-7
( 2.1.1.1.3 Skin Dose 2.1.1.1.3.3 Skin Dose, Calendar Quarter 2.1-7 2.1-7 2.1.1.1.3.2 Skin Dose, Calendar Year (Four Consecutive Quarters) 2.1-8 2.1.1.2 10 CFR 20 Release Rate Limits 2.1-8 2.1.1.2.1 Whole Body Dose Rate 2.1-8 2.1.1.2.2 Skin Dose Rate 2.1-9 2.1.2 Radioiodines, "Particulates," and Other (Nonnoble Gas) Radionuclides 2.1-10 2.1.2.1 10 CFR 50, Appendix I Design Objectives 2.1-10 2.1.2.1.1 Inhalation + Food Pathways Dose, Calendar Quarter 2.1-10 2.1.2.1.2 Inhalation + Food Pathways Dose, Calendar Year (Four Consecutive Quarters) 2.1-17 2.1.2.2 10 CFR 20 Release Rate Limit 2.1-17 2.1.3 Symbols Used in Section 2.1 2.1-20 2.1.4 Constants Used in Section 2.1 2.1-23 2.2 RADIOACTIVITY'IN LIQUID RELEASES 2.2-1 2.2.1 10 CFR 50, Appendix I Design Objectives 2.2-1 2.2.2 10 CFR 20 Maximum Permissible Concentrations in the Unrestricted Area 2.2-3 2.2.3 10 CFR 20 Maximum Permissible Concentrations at the Nearest Surface Water Supply 2.2-4 2.2.4 Symbols Used'in Section 2.2 2.2-8 2-i
, REVISION 3 NOVEMBER 1981
; I
{} TABLE OF CONTENTS (Cont ' d) i PAGE
; 2.2.5 Constants Used in Section 2.2 2.2-9 2.3 ENVIRONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE 2.3-1 2.3.1 Sources of Radiation and Radioactivity 2.3-1 2.3.1.1 Uranium Fuel Cycle - Definition 2.3-1 2.3.1.2 Radiological Impact of Uranium Fuel Cycle Operation 2.3-2 2.3.1.2.1 Milling 2.3-2 2.3.1.2.2 Conversion 2.3-2
, 2.3.1.2.3 Enrichment 2.3-2 ! 2.3.1.2.4 Fabrication 2.3-3
- 2.3.1.L 5 Generation of Electricity 2.3-3 2.3.1.2.6 Reprocessing 2.3-6 2.3.1.2.7 Waste Disposal Sites 2.3-6 2.3.1.2.8- Transportation 2.3-7 2.3.1.2.9 Storage of Spent Fuel in Offsite J Facilities 2.3-7 l 2.3.1.2.10 Long-Term Storage of High Level Radioactive Wastes l
p/- (_ 2.3.1.3~ Summary 2.3 2.3-8 2.3.2 Numerical Models 2.3-8 2.3.2.1 Airborne Releases and Direct Radiation 2.3-8 2.3.2.1.1 Whole Body Dose 2.3-8 2.3.2.1.2 Thy,roid Dose 2.3-10 2.3.2.1.3 Any Other Organ. Dose 2.3-10 2.3.2.2 Radioactivity in Liquid Releases 2.3-10 l 2.3.3 Symbols Used in Section 2.3 2.3-11 l 2.3.4 Constants Used in Section 2.3 2.3-12 i e i i i O 2-11.
REVISION 2
, AUGUST 198G i
I 2.0 OFFSITE DOSE LIMITS ] i LIST OF TABLES l l 1 NUMBER TITLE PAGE i 4 e l 2.3-1 Numerical Models for Computing Radiation Dose from Uranium Fuel Cycle Operations 2.3-13 i . I t I
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REVISION 2 AUGUST 1980 2.0 OFFSITE DOSE LIMITS 2.1 AIRBORNE RELEASES 2.1.1 Noble Gases 2.1.1.1 10 CFR 50, Appendix I Design Objectives 2.1.1.1.1 Air Dose The average air dose in unrestricted areas due to noble gases released in gaseous effluents from each reactor shall be limited to the following expressions: 2.1.1.1.1.1 Gamma Air Dose 2.1.1.1.1.1.1 Gamma Air Dose, Calendar Quarter
-8 3.17 x 10 S A gg +V A +G A <5 mrad ( 2.1) g i
-0 3.17 x 10 Conversion Constant (years /second)
Converts seconds to years. Sg Gamma Dose Constant, (mrad /yr per ' pCi/sec) Stack Release The gamma ray air dose constant for each identified noble gas radionuclide released from a stack (Tables 7. 2-8 or 7. 2-11) . The constant is evaluated for a finite plume using the methods explained in Subsection 3.3.1.2. A gg Accumulative Radionuclide (pCi) Release, Stack Release i The accumulative release of radionuclide ! i from a stack. Releases shall be cumulative 2.1-1
REVISION 2 AUGUST 1980 pS over the calendar quarter or year (four '~# consecutive quarters) as appropriate. V f Gamma Dose Constant, (mrad /yr per Vent Release pCi/sec) The gamma ray air dose constant for each identified noble gas radionuclide released from a vent (Tables 7. 2-8 or 7. 2-11) . Tno plume may be elevated part of the time as determined by the criteria of Regulatory Guide 1.111 (Reference 6.4), part C.2.b. The constant is evaluated for a finite plume using the method explained in Subsection 3.3.1.2. A gy Accumulative Radionuclide (pCi) Release, Vent Release The accumulative release of radionuclide 1 () from a vent. Releases shall be cumulative over the calendar quarter or year (four consecutive quarters) as appropriate. G i Gamma Dose Constant, (mrad /yr per Ground Level Release UCi/sec) The gamma ray air dose constant for each identified noble gas radionuclide released from a ground level release point (Tables 7.2-8 or 7. 2-11) . The constant is evaluated for a finite plume using the method explained in Subsection 3.3.1.2. A Accumulative Radionuclide (pCi) gg Release, Ground Level Release The accumulative release of radionuclide ( i from a ground level release point. Releases 2.1-2
N REVISION 2 AUGUST 1980 O shall be cumulative-over the calendar quarter or year (four consecutive quarters) as appropriate. 2.1.1.1.1.1.2 Gamma Air Dose, Calendar Year (Four Consecutive Quarters) V' - 3.17 x 10-8 ,i [. g his + Yi Aiv + Gt A ig i 10 mrad i . (2.2) 2.1.1.1.1.2 Beta Air Dose . 2.1.1.1.1.2.1 Beta Air Dose, Calendar Quarter
~
3.17 x 10-8 L (X/Q) s his + (X/Q), Aty + (X/Q)g A!(g
! 110 mrad (2.3) bi Beta Air Dose Constant (mrad /yr per 3
ECi/m ) The air dose f actor due to beta emissions for each identified noble gas radionuclide (Table 7.1-13) . (X/Q)s Relative Effluent (sec/m ) ! Concentration, Stack Release The highest calculated annual average re-lative concentration in a given direction l ! at or beyond the restricted area boundary for stack releases (Table 7.2-6 or Table 7.2-9) . l () 2.1-3 1 I i
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REVISION 2 AUGUST 1980 A{s Accumulative Radionuclide (UCi)
) Release from Stack, Adjusted for Radiodecay The accumulative release of radionuclide i from a stack, adjusted to account for radiodecay in transit.
Afs"A ls X exp (- Ai R/3600 us) (2.3a) a A i Radiological Decay (hr~1) Constant The radiological decay constant for radionuclide i. See Tables 7.1-9 and 7.1-11. R Downwind Range (m) () The distance downwind to the point of interest. See Tables 7.2-6, 7.2-7, and 7.2-8. 3600 Constant (sec/hr) Converts hours to seconds u Average Wind Speed (m/ sac) s The average wind speed for a stack release. See Table 7.2-6. , (X/Q)y Relative Effluent (sec/m ) Concentration, Vent Release The highest calculated annual average relative concentration in a given direction at or beyond the restricted area boundary for ({) vent releases. The partially elevated plume model of Regulatory Guide 1.111, part C.2.b 2.1-4
REVISION 2 AUGUST 1980 (Reference 6.4) is used when necessary. See Subsection 3.2.'2.3 and Table 7.2-6 or Table 7.2-9. A gy Accumulative Radionuclide (pCi) - Release from Vent, Adjusted for Radiodecay The accumulative release of radionuclide i from a vent, adjusted for radiodecay in transit. A gy =A gy x exp (- A g R/3600 uy) (2.3b) uy Average Wind Speed (m/sec) The average wind speed for a vent release. See Table 7.2-6. (X/Q)g Relative Effluent (sec/m ) Concentration, Ground Level Release O The highest calculated annual average relative concentration in a given direction at or beycnd the restricted area boundary for ground level releases. (See Table 7.2-6 or Table 7.2-9.) A g Accumulative Radionuclide (UCi) Release at Ground Level, Adjusted for Radiodecay The accumulative release of radionuclide i from ground level, adjusted for radiodecay in transit. A gg =A gg x exp (- A g R/3600 ug) (2.3c) u g Average Wind Speed (m/sec) The average wind speed for a ground level release. See Table 7.2-6. 2.1-5 \ ,
REVISION 2 AUGUST 1980 2.1.1.1.1.2.2 Beta Air Dose, Calendar Year (Four Consecutive ( Quarters)
-8 '
* ' ~
3.17 x 10 Li (X/Q)g Ais + (X/Q)y A gy + (X/Q)g A 1 . gg I 20 mrad (2.4) 2.1.1.1.2 Whole Body Dose The average dose to individuals in unrestricted areas due to noble gases released in gaseous effluents from each reactor shall be limited to the following expressions: 2.1.1.1.2.1 Whole Body Dose, Calendar Quarter
~
(0.7) (1.11) (3.17 x 10-8) S A +V g A gy +G i A gg i- -
-< 2.5 mrem (2.5) 0 0.7 Shielding and Occupancy Factor The shielding and occupancy factor for pro-tection against gamma radiation.
1.11 Conversion Constant (mrem / mrad) Converts rads in air to rems in tissue. 5g Gamma Whole Body Dose (mrad /yr per Constant, Stack Release UCi/sec) 5 g is the constant S g multiplied by the - shielding factor afforded by 5 cm of tissue; used to evaluate whole body dose. (See Sub-section 3.3.1.2; also, see Tables 7.2-8
- or 7.2-11.)
O v 2.1-6
REVISION 2 AUGUST 1980 Vg Gamma Whole Body Dose (mrad /yr per Constant, Vent Release pCi/sec) The constant Vi multiplied by the shielding factor afforded by 5 cm of tissue; used to evaluate whole body dose. (See Subsection 3.3.1.2; also, see Tables 7.2-8 or 7.2-11.) Gg Gamma Whole Body Dose (mrad /yr per Constant, Ground Level Release pCi/sec) The constant G g multiplied by the shielding factor afforded by 5 cm of tissue; used to evaluate whole body dose. (See Subsec-tion 3.3.1.2; also, see Tables 7.2-8 or 7.2-11.) l 2.1.1.1.2.2 Whole Body Dose, Calendar Year (Four Consecutive Quarters) (0.7) (1.11) (3.17 x 10~0) Sg Als + vi A iv + Gg A gg i -
-< 5 mrem (2.6) 2.1.1.1.3 Skin Dose The average skin dose to individuals in unrestricted areas due to noble gas released in gaseous effluents from each reactor shall be limited to the following expressions:
1 2.1.1.1.3.1 Skin Dose, Calendar Quarter
-8 3.17 x 10 1.0 L ( X/Q) s A's + (X/Q)y A' y + (X/0)g A' +
i . i g] l (0. 7) (1.11) (S g Als + Vi A h+Gg A fg) <, 7.5 mrem O l (2.7) l 2.1-7 t >
l l REVISION 2 ; AUGUST 1980 j
. (/ 1.0 Shielding and Occupancy Factor The shielding and occupancy factor for pro-tection against beta radiation.
E Beta Skin Dose Constant (mrem /yr per 1 3 ECi/m ) The skin dose factor due to beta emissions for each identified noble gas radionuclide (Table 7.1-13). Accounts for attenuation of beta radiation during passage through 7 mg/cm2 of dead skin. 2.1.1.1.3.2 Skin Dose, Calendar Year (Four Consecutive Quarters)
-0 3.17 x 10 1.0 E g !(X/Q)s A'is + (X/Q)y Ai'y + A +
i - \ (X/Q)g 'ig} () ( 0. 7) (1.'ll) (S i Als + Yi Aiv + Gi A gg) i 15 mrem (2.8) 2.1.1.2 10 CFR 20 Release Rate Limits The maximum dose rate to individuals in unrestricted areas due to noble gases released in gaseous effluents from the site shall be limited to the following expressions: 2.1.1.2.1 Whole Body Dose Rate 1.11 x 51 Qis + i Qiy +dQ i ig
< 500 mrem /yr
, i .
. (2.9)
(10 CFR 20.105 limit) Q is Release Rate, Stack Release (pCi/sec) 1 l The release rate for radionuclide i due to a stack release. (} 2.1-8
REVISION 2 AUGUST 1980 Q gy Release Rate, Vent Release (pCi/sec) The release rate for radionuclide i due to a vent release. Q gg Release Rate, Ground Level (pCi/sec) Release
; The release rate for radionuclide i due to a ground level release.
2.1.1.2.2 Skin Dose Rate Lg (X/Q)s Ois + (X/Q), Q{y +
+ (X/Q)g Q g 1 -
\ gl-1.11 x (S g Qis + Yi Oiv + Gi Qig) 1 3000 mrem /yr (10 CFR 20.105 limit)
(2.10) Qg's Release Rate, Stack Release, (pCi/sec) Q Adjusted for Radiodecay The release rate for radionuclide i from a stack adjusted for radiodecay in transit. 4 Q{s" Dis X eXP (- A i R/3600 us) (2.10a) I Q[y. Release Rate, Vent Release, (UCi/sec) Adjusted for Radiodecay The release rate for radionuclide i from a vent, adjusted for radiodecay in transit. Q{y = O gy x exp (- A g R/3600 uy) ( 2.10b) Q[g Release Rate, Ground Level, (pCi/sec) Adjusted for Radiodecay The release rate for radionuclide i from ground level, adjusted for radiodecay in C transit. Q;, . Q1, x exp (- x 1 R/3600 ug) (2.10c) i 2.1-9
REVISION 3 NOVEMBER 1981. O 2.1.2 Radiciodines, "Particulates", and Other (Nonnoble Gas) Radionuclides 2.1.2.1 10 CFR 50, Appendix I Design Objectives The average dose to an individual in the unrestricted area f rom radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents released from each reactor with half-lives greater than 8 days, shall be limited to the following expressions: 2.1.2.1.1 Inhalation + Food Pathways Dose, Calendar Quarter 3.17 x 10 -8 x 10 6 R DFA (X/0)s his + (X/0) , A iy + a ija i - I /OI g A + f + + Q ig 365 ija P U[f y Cf+Ua Cf <_7.5 mrem ( 2.11) 10 6 Conversion Constant (pci/pci) Converts UCi to pCi. Conversion Constant (yrs / day) 365 Converts days to years. R Individual Air Intake Rate (m /yr) The air intake rate for individuals in group a. See Tables 7.1-2 and 7.1-3. t r Deposition Time or Release (days) Period O Length of time for deposition. 2.1-10
4 f
$ REVISION 2 j
AUGUST 1980 ( DFA g3, Inhalation Dose Factor (mrem /pCi) j The inhalation dose commitment factor for radionuclide i, organ j, and age group a. See Table 7.1-1. { ( X/Q) s See Table 7.2-6 or Table 7.2-9. ! i ( X/Q) , See Table 7.2-6 or Table 7.2-9. (X/Q)g See Table 7.2-6 or Table 7.2-9. j DFI gg, Ingestion Dose Factor (mrem /pCi) ! The ingestion dose commitment factor for radionuclide i, organ j, and age group a. See Table 7.1-1. () U,U, U,U Foodstuff Consumption Rates (kg/yr, liters /yr, kg/yr, kg/yr, respectively). The annual consumption rates (usages) of pro-
' duce (nonleafy vegetables, fruits, and grain) ;
l milk; leafy vegetabicc; and meat (flesh), '; respectively, for individuals in age group a. See Tables 7.1-2 and 7.1-3. f p, fy Produce, Leafy Vegetable Fractions ( l l The respective fractions of the ingested produce and leafy vegetables that are grown i in the garden of interest; dimensionless. I i See Table 7.1-2. Cf, Cf, Cf, Cf Foodstuff Concentrations (pCi/kg, pCi/ liter, PCi/kg, pCi/kg, h respectively) 2.1-11 _. l
REVISION 2 AUGUST 1980 0 The average concentrations of radionuclide i in produce (nonleafy vegetables, fruits, and grain); milk; leafy vegetables; and meat (flesh), respectively. C{andC{arecal-culated from Equation 2.12 below. Cg Concentration in Vegetation (pCi/kg) The concentration of radionuclide i in vegetation. Cg= 1 - eXP (- A DI exp (- A t tI h
- Ei e_
dixr _ Y A f 9 v Ei (2.12) dg Deposition Rate (pCi/m - hr) The deposition rate of radionuclide i onto Q the ground, 6 A ls (D/Q) s + Aiv (D/Q)y + d. 1
= 10 24 x t r A gg (D/Q)g
( 2.13) 24 Conversion Constant (hr/ day) Converts days to hours. (D/Q) s Relative Deposition (m" ) Factor, Stack Release The calculated annual average relative deposition factor in a given direction at or beyond the restricted area boundary for stack releases. (See Subsection 3.2.3.3; see Table 7.2-6 or Table 7.2-9 for 2.1-12
l REVISION 2 AUGUST 1980 .O produce and leafy vegetable pathways;- and see Table 7.2-7 or Table 7.2-10 for milk and meat pathways.) (D/O ) Relative Deposition (m-2) Factor, Vent Release The calculated annual average relative deposition factor in a given direction at or beyond the restricted area boundary for vent releases. The partially elevated plume model of Regulatory Guide 1.111, part C.2.b is used. (See Subsection 3.2.3.3; see Table 7.2-6 or Table 7.2-9 for produce and leafy vegetable pathways; and see Table 7.2-7 or Table 7.2-10 for milk and meat pathways.) (D/Q)g Relative Deposition (m~2) Factor, Ground Level , Release The calculated annual average relative deposition factor in a given direction at or beyond the restricted area boundary for ground level releases. (See Sub-section 3.2.3.3; see Table 7.2-6 or Table 7.2-9 for produce and leafy vegetable pathways; and see Table 7.2-7 or Table 7.2-10 for milk and meat pathways. O 2.1-13
I REVISION 2 AUGUST 1980 r Crop Retention Fraction The fraction of deposited activity retained on crops; dimensionless; see Tables 7.1-2 and 7.1-3. A Ei Effective Decay Constant (hr-1) The effective removal rate constant for radionuclide i from crops. A Ei Ai+A w (2.13a) A, Weathering Decay Constant (hr-1) The removal constant for physical loss by weathering. See Tables 7.1-2 and 7.1-3. ({} t, Effective Crop Exposure Time (hr) The effective crop exposure time. See Tables 7.1-2 and 7.1-3. t h Harvest to Consumption Time (hr) The time between harvest and consumption. See Tables 7.1-2 and 7.1-3. f Seasonal Growing Factor f A factor which accounts for seasonal growth of vegetation. See Tables 7.1-2 and 7.1-3. yy Productivity Yield (kg/m ) The agricultural productivity yield. See Tables 7.1-2 and 7.1-3. O 2.1-14
REVISION 2 AUGUST 1980 ( Milk Concentration (pCi/ liter) The concentration of radionuclide i in milk. CM is calculated from the following equation (af ter Regulatory Guide 1.109 [ Reference 6.5] ) : (=FM Cf W g exp (- A g tM) (2.14) F Milk Fraction (days / liter) M The average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk. See Table 7.1-4. Cf Feed Concentration (pCi/kg) The average concentration of radio-nuclide i in animal feed. For milk and meat pathways, the following expression is to be used (after Regulatory Guide 1.109, [ Reference 6.5]) : Cf=f g f g Cy+(1-f)f Cs+fg (1-f g) Cf (2.15) f g Pasture Gracs Fraction The fraction of daily feed that is pasture grass when the animal grazes on the pasture. See Tables 7.1-2 and 7.1-3. 2.1-15
REVISION 2 AUGUST 1980 C 9g Pasture Grass (pCi/kg) Concentration The concentration of radionuclide i is pasture grass (calculated using Equation 2.12 for cf with fg = 1; other parameters, including f g for use in Equation 2.15, are given in Tables 7.1-2 and 7.1-3) . s C Stored Feed (pCi/kg) Concentration The concentration of radionuclide i in stored feed (calculated using Equation 2.12 for C y with fg = 1; other parameters, including f g for s use in Equation 2.15, are given in Tables 7.1-2 and 7.1-3. Wg Feed Consumption (kg/ day) The amount of feed consumed by the animal each day. See Tables 7.1-2 and 7.1-3. t M Milk Transport Time (hr) The average time from the production of milk to its consumption. See Tables 7.1-2 and 7.1-3. Meat Concentration (pCi/kg) Cf The concentration of radionuclide i in meat. F f r Cg=Fp Cg W g exp (- At) gs (2.16) 2.1-16
REVISION 3 NOVEMBER 1981 Fp Meat Fraction (days /kg) The fraction of the animal's daily intake of radionuclide i which appears in each kilogram of flesh. See Table 7.1-4. t s Slaughter to Consumption Time (hr) The time from slaughter consumption, See Table 7.1-2. 4 I 2.1.2.1.2 Inhalation + Food Pathways Dose, Calendar Year (Four Consecutive Quarters) 3.17 x 10-8 x 10 6 R, DFA g3, ( X/Q) s A s
+ ( X/0), A[y + ( X/0) A[g +
i - O DFI ija U P f +U C + 0, fy C +U F C{ <l5 mrem 365 a p (2.17) 2.1.2.2 10 CFR 20 Release Rate Limit The maximum dose rate to an organ of an infant from all radio-nuclides, radioactive materials in particulate form, and radio-nuclides other than noble gases with half-lives greater than i 8 days shall be limited to the values given by the equations i which follow. For purposes of demonstrating compliance with the Technical Specifications, the dose to the infant shall be considered limiting. O 2.1-17
REVISION 2 AUGUST 1980 6 + 10 R, DFA i$, (X/Q)g Qf, + ( X/Q), Q y + ( x/Q) g Q g i _ K DFI t$, U Cf < 1500 mrem /yr (2.18) K Seasonal Adjustment Factor K is a seasonal adjustment factor to account for nongrazing during the winter and partial grazing during the summer; K = 0 for November to April and 0.5 for May to October. M C Milk Concentration (pCi/ liter) The concentration of radionuclide i in milk. Cf Wg exp (-Ai t) (2.19) Cf=FM M O Feed Concentration (pCi/kg) Cf The concentration of radionuclide i in feed. Cg=d p xr _ 1 - exp (- AEi D l e- s (2.20) A Yv Ei (Note that this assumes feed to be 100% pasture grass.) d Deposition Rate (pCi/m x hr) i 6 ' dg = 3600 x 10 x Ofs (D/Q)s+Q[y (D/Q), + Q ig (D/Q)g ( 2. 21) O 2.1-18
REVISION 2 AUGUST 1980 (D/Q) s See Table 7.2-7 or Table 7.2-10 for milk pathway. (D/Q)y See Table 7.2-7 or Table 7.2-10 for milk pathway. (D/Q)g See Table 7.2-7 or Table 7.2-10 for milk pathway. O
'O 2.1-19
REVISION 2 s
" AUGUST 1980 3 s
. me-
'2.1.3 Symbols Used In Section 2.1 0 SYMBOL NAME UNIT Sg Gamma Dose Constant, Stack Release (mrad /yr per pCi/sec)
, A ls
. Accumulative Radionuclide Release 1 - (,- StaEk Release (pCi) i Vg Gamma Dose Constant, Vent Release (mrad /yr per ECi/sec)
A iy Accumulative Radionuclide Release, Vent Release (UCi) Gg Gamma Dose Constant, Ground Level Release (mrad /yr per UCi/sec) A gg Accumulative Radionuclide Release, Ground Level Release (pCi) ! L. . Beta Dose Constant (mrad /yr per ECi/m ) 1 ,, , ( X/Q) s= ' Relative Ef fluent Concentration, Stack Release (sec/m ) A Accumulative Radionuclide Release s s' from Stack, Adjusted for Radiodecay (pCi) ( X/0) y Relative Effluent Concentration, Vent Release (sec/m )
'r, , A y Accumulative Radionuclide Release i dj ,
from Vent, Adjusted for Radiodecay (pCi) Relative Effluent' Concentration, .{%
,(X/Q)9 3
i, Ground Level Release (sec/m ) P I '. Accumulative Radionuclide Release 3,9 % .
- h" . 'Q~9 from Ground Level,(Adjusted for
^A T -- ' (pci)
( '; .- % Radiodecay hj[(b R- Downwind Rdnge , (m)
%[ ' u y, n ,Uu y g Average Wirad Speed, Stack, Vent, or
' 'A y 'i Ground Ldvel Release (m/sec)
.: 4 E i % Sg Gamma Whole Body Done Constant Stack Release (mrad /yr per pCi/sec)
~'
,[ Gamma Whole 5:1 C-:e Constant, Vent Releast (mrad /yr per pCi/sec) 4' . E Gamma Whole Body Dose Constant, Ground Level Release (mrad /yr per pCi/sec) 3 Lg Beta Skin Dose Constant (mrem /yr per pCi/m )
i-2.1-20
-t
_m
REVISION 2 AUGUST 1980 SYMBOL NAME UNIT O gg Release Fate, Stack Release .(pCi/sec) Q gy Release Rate, Vent Release. (UCi/sec) O gg Release' Rate, Ground Level Release (pCi/sec) Q s Release Rat'e from Stack, Adjusted for Radiodecay (pCi/sec)
.Q[y Release Rate from Vent,- (UCi/sec)
Adjusted for Radiodecay Q[g Release Rate at Ground Level, Adjusted for Radiodecay (pCi/sec) R Individual Air Intake Rate (m /yr) a DFA ija Inhalation Dose Factor (mrem /pCi) DFI Ingestion Dose Factor (mrem /pCi) ija t-r Deposition Time (day) U Produce Consumption Rate- (kg/yr) Milk Consumption Rate (liters /yr) U Leafy Vegetable Consumption Rate. (kg/yr) Ua Meat Consumption Rate (kg/yr) fp . Produce Fraction fy Leafy Vegetable Fraction C Produce Concentration (pCi/kg) Cf Milk Concentration (pCi/ liter) Cf Leafy Vegetable Concentration (pCi/kg) Cf Meat Concentration (PCi/kg) dg Deposition Rr.te (pCi/m .hr) C Vegetation Concentration (pCi/kg) f (D/Q)s Relative Deposition Factor, Stack (m" ) Release (D/Q)y Relative Deposition Factor, Vent (m- ) Release (D/Q)g Relative Deposition Factor, Ground (m" ) Level Release 2.1-21
REVISION 2 AUGUST.1980 SYMBOL NAME UNIT r Crop Retention Fraction A Ei Effective Decay Constant -(hr- ) A g Radiological Decay Constant (hr-1) A, Weathering Decay Constant (hr-1)
't e
Effective Crop Exposure Time (hr) t h Harvest to Consumption Time (hr) Yy Productivity. Yield. (kg/m )- F Milk Fraction (days / liter) M Cf Feed Concentration (pCi/kg) f Seasonal Growing Factor f f g
-Pasture Grass Fraction Pasture Grass Concentration (PCi/kg)
Cf Stored Feed Concentration (pCi/kg) Cf-O wf reea consu=9 tion (x9/aav> t M Milk Transport Time '(hr) Fp Meat Fraction (day /kg) t s Slaughter to'Censumption Time (hr) K Seasonal Adjustment Factor
'2.1-22
.. .. . . . . . . .-- . . . ... . . ~. .. . . . . . . ~
t REVISION 2
,i - AUGUST 1980 i 2.1.4. Constants Used In Section'2.1
~
i NUMERICAL VALUE NAME . UNIT
-8 (years /second) t 3.17 x 10 Conversion Constant 0.7 Gamma Radiation Shielding j and Occupancy Factor i 1.0 Beta Radiation Shielding i
and Occupancy Factor ! 1.11. Conversion Constant (mrem / mrad)- I 6
-10 Conversion Constant (pCi/pCi) 24- Conversion Constant (hr/ day)'
i 365 Conversion Constant (day /yr)- 4 3600 Conversion Constant (sec/hr) d 4 L i i i () ' 4 j 1 i i I f f i i. 4 1 l i 1 i (:) E h
- 2.1-23 4
-...A,_...,.,_._,., . . - . , , _ _ _ . . _ _ _ _ . . - . . . , _ .. - . _ _ , . _ . . ~ . _ , . . . , . _ , , , . . , _ , _ . . . . ~ _ . _ .
REVISION 2 AUGUST 1980 0 2.2 axDroxC21v1Tv 1N t1oo1D astexses
.2.2.1 10 CFR 50, Appendix I Design Objectives The dose contributions from measured' quantities of radioactive materials identified in liquid effluents released to unre-stricted areas from each reactor shall be calculated using the following expression:
-3 -
x 8760) U# A t") + ija **E (~ D DFI A 3 = (1.1 x 10 i 1 U A DFI ija B f exp (- A g t) F 1 - (2.22) D. Cumulative dose (mrem) J O rae cumutative aose or a se co==te eat to the total body or an organ j due to an adult- [ consuming water and fish. D i 1.5 mrem to the whole body j in a calendar quarter, (2.23) 1 5.0 mrem to any organ in a calendar f quarter, (2.24) 5 3.0. mrem to the whole body in any four l' consecutive quarters, and (2.25) i ( 1 10.0 mrem to any organ in any four consecutive quarters. (2.26) O 2.2-1 i
REVISION.2 AUGUST 1980 () U", U E Usage-Factor- (liters /hr, kg/hr) Average consumption rate of-water or fish. See Table 7.2-1. 1/M", 1/M Additional' Dilution Factor ! Additional dilution factor prior to withdrawal of potable water or-fish. See Table 7.2-1. F" Average Flow Rate (ft /sec) Average flow of receiving body of water. See Table 7.2-1. f F Near-Field Flow Rate (ft /sec) Near-field flow of receiving body of water. l See Table 7.2-1.
)
Ag Total Radionuclide Release (UCi) Total release of radionuclide i during period of release.
- DFI ija Ingestion Dose Factor (mrem /pCi)
The ingestion dose commitment factor for each identified gamma and beta emitter 1, organ j, and age group a. See Table 7.1-1. A g Decay Constant (hr-1) , Radiological decay constant of ith radionuclide. See Table 7.1-11. t", t E Elapsed Time (hr) Average elapsed time between release and consump-(-~ tion of potable water or fish. See Table 7.2-1. 2.2-2
REVISION 2 AUGUST 1980 B. Bioaccumulation Factor (liters /kg) O ' Bioaccumulation factor. See Table 7.1-12.
-3 1.1 x 10 = factor to convert from (pCi/yr)/(f t /sec) to pCi/ liters 8760 = number of hours per year '
2.2.2 10 CFR 20 Maximum Permissible Concentrations in the
. Unrestricted Area The concentration of nonnoble gas radioactive material released from.the site to unrestricted areas (Cg ) shall be limited to.the concentrations specified in.10 CFR 20, Appendix B, Table II, Column 2 (MPCg ). .The concentrations of dissolved or entrained l . noble gases shall be limited to the concentrations specified in l Table 7.1-10.
The sum of the fractional limits ( 1[ ~Cg + MPCg ) I ' must not exceed 1.0 for each release. - O-The concentration of each radionuclide in the unrestricted area is calculated as follows: F C. 1
=Cfx 1 pd ,,p r (2.27)
E andthecombinationofCf,F, and F must meet the condition that: 100 x M
= 100 x
- 1 100% (2.28) 1 i Fd+F r i M .
1 Cg Concentration in the Unrestricted (pci/ml) Area The concentration of radionuclide i at the-restricted / unrestricted area boundary. O 2.2-3
REVISION 3 NOVEMBER 1981 Cf Concentration in the Discharge Tank (pci/ml) O The concentration of radionuclide i in the (radwaste discharge or other similar) tank. E 3 l F Flow Rate, Radwaste Discharge (ft /sec) E The flow rate of radwaste from the discharge tank to the initial dilution stream. F 0
- Flow Rate, Initial Dilution Stream (ft /sec)
The flow rate of the initial dilution stream which carries the radionuclides to the un-restricted area boundary (e.g., the blow-down from cooling tower or lake or the circulating cooling water flow). MPC i Maximum Permissible Concentration (UCi/ml) The maximum permissible concentration of () radionuclide.i in water in the unrestricted area (from 10 CFR 20, Appendix B, Table II, Column 2 or Table 7.1-10) . 2.2.3 10 CFR 20 Maximum Permissible Concentrations at the Nearest Surface Water Supply The quantity of radionuclides, excluding tritium and dissolved ! or entrained noble gases, in outdoor tanks without overflow pipes connected to other storage tanks shall be limited to ensure that in the case of an overflow, the annual average con-centration of radioactivity in the potable water of the nearest surface water supply is less than the 10 CFR 20, Appendix B, Table II, Column 2 limits. The annual average concentration of each radionuclide in the potable water of the nearest surface water supply is calculated as follows: F (-} C{=Cf y t M" g exp (- A i x t") x 8760 (2.29) xs + F (F g 2.2-4
REVISION 2 AUGUST 1980 () Cf Concentration in Water Supply (pCi/ml) The annual average concentration of radionuclide i in the surface water supply due to tank overflow. Cf Concentration in Tank (pCi/ml) The concentration of radionuclide i in the outdoor tank of interest. t F Maximum Flow Rate from Tank (ft /sec) The maximum rate of overflow from the outdoor tank of interest (usually equal to the maximum tank feed rate). See Table 7.2-1. F Flow Rate, Receiving Body of Water (ft /sec) eq \_/ The minimum flow rate (from the most recent 10 year record) of the receiving body of water during overflow conditions. See Table 7.2-1. 1/M" Additional Dilution Factor Additional dilution factor of overflowed water prior to use as potable water. See Table 7.2-1. t" Elapsed Time (hr) The total time between overflow release and consumption of water, equal to the transit time, discharge point to intake, plus the process time at the water treatment plant. See Table 7.2-1. (s ,'t 2.2-5
- _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ ~
REVISIOI; 2 AUGUST 1980
. tg Release Time .
(hr) The total period of the overflow conditions, assumed to be no greater than one work shift of 8 hours. Hence the maxircum quantity of radionuclide 1 (Af, curie) in each tank of interest, excluding tritium and the dissolved or. entrained noble gases, which satisfies the limiting condition: v m C" 1 M C. 1 11 (2.30) is: A w F" g + F yt exp (- A xt)g <4I ( 2. 31) i MPC*. i , t w f} ) o Af Tank Radioactivity (Ci) The quantity of radionuclide i in the tank of interest. t V Tank Volume (gal) The volume of each tank without overflow pipes connected to other storage tanks. See Table 7.2-1. Equation 2.31 may also be written in terms of the con-centration of radionuclide i in the tank of interest.
+ F Cf exp (- A t
x t") -
< 1100 (2.32) i MPC g pt
/
M 2.2-6
REVISION 2 AUGUST 1980 'f Derivation of Equation 2.31 Since, by Equation 2.30, C{ < 1 i MPC f whereC{isgivenbyEquation2.29andCfinEquation2.29 is given by: 6 Afx10 pCi/Ci (2.33) ' 1 D V x 3785 ml/ gal then: gt" t A
= F M tg /8760 exp ( g) <1 (Iw+Ft MPC. MPC pd I 1 o / (2.34)
M A F 8 x 10 exp (- A t") g <1 pw,pt y t 8760 3785 g MPC g (2.35)
^
, 1 F exp (- A t") <1 4 gw,pt yt i MPC g Equation 2.36 on rearrangement gives:
A Fg +P yt
- exp (- Ag t") <4 (2.37) i MPC i pt
) (M" )
- O 9
2.2-7
.. . _. . =. .
REVISION-2 .
-AUGUST-1980 Q 2.2.4 Symbols Used In Section 2.2 SYMBOL NAME UNIT D. Cumulative Dose (mrem) 3 U",U Usage Factor (liters /hr, kg/hr) 1/M",l/Mf ,l/M" Additional Dilution Factor F" Average Flow Rate (ft /sec)
F Near-Field Flow Rate (ft /sec) A Total Radionuclide Release (pCi) i DFI Ingestion Dose Factor (mrem /PCi) ija A i Decay Constant (hr-1) t",t ,t" Elapsed Time (hr) Bg Bioaccumulation Factor (liters /kg)-
! C. Concentration at Unre-stricted Area (pCi/ml) t C
i Concentration in Discharge Tank (pCi/ml) F Flow Rate, Radwaste Discharge (ft /sec) l F Fjow Rate, Initial Dilution Stream (ft /sec)
- MPC g Maximum Permiss ble Concentration (pCi/ml) j Cf Concentration in Water Supply (uCi/ml)
- F Maximum Tank Overflow Rate (ft /sec)
F" Minimum Flow Rate, Receiving i Body of Water (ft /sec) tg Release Time (hr) Af1 Tank Radioactivity (Ci) O'# t V Tank Volume (gal) 2.2-8 _ . _ . . . . . . - _ . _ . . . . , . . _ _ . - . _ . . _ . _ _ _ . . , . _ . - _ . _ _ . . _ _ . _ - _ _ _ . . . _ , . _ . _ . . . . _ _ _ . ~
,.._ _ . _._. . -. .. . . . . . . _ . . . . . ~ . . . . _ . . . _ _ _ _ , _ _ _ . .. . . . _ _ . . A ( + REVISION-2 AUGUST 1980 i i 2.2.5 Constants Used In Section 2.2 b NUMERICAL VALUE NAME UNIT
-3 1.1 x 10 Conversion Factor (pCi/ liter) / (pCi/yr)/(ft /sec)
~
8760 Conversion. Factor (hrs /yr) 6 10 Conversion Constant (pCi/pCi) O O 2.2-9
d REVISION 3 NOVEMBER 1981 r~g D 2.3 ENVIRONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE In accordance with the requirements of.40 CFR 190 (Reference 6.12) , the annual dose commitment to any member of the public in the general environment (i.e., the unrestricted area) from all uranium. fuel cycle sources, except those specifically excluded by the regulation, is limited to 25 millirems to the
- whole body, 25 millirems to any organ but the thyroid, and
- 75 millirems to the thyroid. On the basis of results pro-jected by the NRC for all multi-unit sites presently committed, the conservative. nature of the design dose calculations as opposed-to the applicability of these standards to exposures actually received, and the operational flexibility available to' sites with multiple units, it is concluded that the standards can be readily achieved at all CECO sites by demonstrating-compliance with 10 CFR 50 Appendix I objectives.
O 2.3.1 Sources of Radiation and Radioactivity i 2.3.1.1 Uranium Fuel Cycle - Definition 4 The uranium fuel cycle is defined in 40 CFR 190 (Reference 6.12) to include: l a. operations of milling of uranium ore,
- b. chemical conversion of uranium,
- c. isotopic enrichment of uranium,
- d. fabrication of uranium fuel,
- e. generation of electricity by a nuclear power plant using uranium fuel, and
- f. reprocessing of spent uranium fuel.
Specifically excluded are: e a. mining operations, (f b. operations at waste disposal sites,
- c. transportation of ra ' aactive material, and
,t-I { 2.3-1
~~n- , .~---+c,e . - , . , - ,e,y-we--e w-.re.,r, , ,,-,,mn, ,,-+w,7,,m.,,,gc, v,r,w-,,-gn,~w- .m.------aw,,,c-m g,--p,, ,,7+ ,,- ,,---y , - , - - , - - - y p.,w---, ,- .,--s.
REVISION 2 AUGUST 1980
- d. the use of recovered nonuranium special nuclear
() or by-product materials from the cycle. 2.3.1.2 Radiological Imoact of Uranium Fuel Cycle Operation Environmental-Radiation Protection Standards, 40 CFR 190, require that the radiation dose'resulting from all operations lof the uranium fuel cycle (except the specific exclusions noted) be considered in~ determining compliance. Therefore, each of the operations will 1x3' discussed and the radiological impact in' the Commonwealth Edison Company (CECO) service area will be considered. 2.3.1.2.1 Milling Reference 6.13 (Page 4), Reference 6.14 (Section 2. 4) , . and Reference 6.15 (Page IV F-29) indicate that the maximum indi-vidual doses due to milling will be less than 10 CFR 20 limits. Therefore, the dose contribution to any person living in this () service area due to milling operations, all-nore-than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits.
~
2.3.1.2.2 Conversion Reference 6.14 (Section 3.4) and Reference 6.15 (Page IV F-40 and Table IV F-10) indicate that the maximum individual doses due to UF e nyersion will be less than 10 CFR 20 limits. 6 Therefore, the dose contribution to any person living in this service area due to UF 6 conversion operations, all more than
.100 kilometers distant, is expected.to be negligible compared to 40 CFR 190 limits.
2.3.1.2.3 Enrichment . Reference 6.14 (Section 4.4) and Reference 6.15 (Page IV F-51) indicate that the maximum individual doses due to uranium 2.3-2
REVISION 2 I AUGUST 1980 enrichment will be less than 10 CFR 20 limits. Therefore, (_m) the dose contribution to any person living in this service area due to uranium enrichment operations, all more than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits. 2.3.1.2.4 Fabrication 1 Reference 6.14 (Section 5.4) and Reference 6.15 (Page IV F-63) indicate that the maximum individual doses due to fuel element fabrication will be less than 10 CFR 20 limits. Therefore, l the dose contribution to any person living in this service area due to fuel fabrication operations, all more than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits. 2.3.1.2.5 Generation of Electricity The generation of electricity, using a nuclear power plant, {} results in radioactivity released in gaseous and liquid effluents. The radiological impact of these requires assessment (using the methodology of Sections 2.1 and 2.2 of this report) and comparison with 40 CFR 190 limits. Also, boiling water reactors (BWR' s) contain radioactive nitro-gen-16 (N-16) in their steamlines and turbines in sufficient enough quantities to result in measurable offsite doses. The magnitude of this so-called skyshine dose must also be considered in determining 40 CFR 190 compliance. Offsite doses due to other contained sources in the nuclear power plant are negligible compared to those due to effluents and N-16 skyshine. Measurements of the radiation environment due to N-16 have been made at the Dresden Station (Reference 6.19). An empirical fit to the measured data is given in Equation 2.38: (]) D(R,P1 = SF OP (2.28 x 10-5) P exp (-0.007 R) (2.38) 2.3-3 .
REVISION 2 ADGUST 1980
]) D(R,P). Dose Due to N-16 (mrem)
Skyshine The gamma dose.due to BWR N-16 skyshine. SF Shielding Factor The shielding factor for protection against gamma radiation.
.SF = 0.7 for a home.
OF Occupancy Factor The at-home occupancy factor:- For. fisherman 0.95 For all others 1.0 2.28 x 10 -5 {) Constant (mrem /MWe-hr) A constant to fit the equation to measured. data. P Electric Power. Generated (MWe-hr) I The total electric energy generated in the time period of interest. 0.007 Constant (m-1) A constant to fit the equation to
- . measured data.
d , R Distance (m) L Distance from the turii'ne to the dose point of interest.
-O s_-
2.3-4 i - _ . _ . - - _ _ . - .
REVISION 2. AUGUST 1980 This equation will be used at all CECO BWR's up to a distance of 1100 meters. Beyond that distance the fit (and data) are ~
. considered unreliable and, further, the dose at this range is,.
t at most, 0.1 mrem /yr.for CECO Stations. In certain situations, more than one. nuclear power plant site may contribute to a radiological-dose to be considered in making 40 CFR 190 dose assessment. At present (July 1979), the nuclear i-power stations in Ceco's service area are sufficiently distant from'one another that the radiological dose, if not negligible-compared to 40 CFR 190 limits, is due to'only one site.- Hence, adding dose components from several stations is not required. l However, within CECO's service area the following future additive f combination is considered. .At some point within the. triangle formed by the La Salle, Dresden, and Braidwood Stations, an { additive dose frcm airborne releases may-be postulated. .However,
~
the-distances are such (La Salle to Dresden,.39 kilometers; Dresden f to Braidwood, 18 kilometers; Braidwood to La Salle, 37 kilometers)
- that at any intermediate point postulated, the station-combined dose is less than that maximum calculated for an individual station.
I Therefore, the combined effect of airborne releases- will not be j' considered further. ! Such is not the case for future releases of radioactivity into f the aquatic environment, where, if more than one facility uses l the same receiving body of water, the station-combined dose must be considered. Dresden and (the future) La Salle County Stations-discharge their liquid waste into the Illinois River and (the ! future) Braidwood Station discharges into the Kankakee River i i which flows into the Illinois at Dresden. Quad Cities and (the
- future) Carroll County Stations use the Mississippi River and f (the future) Byron Station uses the Rock River which flows into l the Mississippi at Moline, Illinois, downstream of Quad Cities.
l
] For these two situations the combined impact from upstream liquid waste discharges must be considered at each downstream location. ]
1 2.3-5 l-i
REVISION 2 AUGUST 1980 (~} The dose contribution of nuclear power plants in other service areas need not be considered in CECO's 40 CFR 190 assessment.
~
The Duane Arnold Station is about 135 kilometers from Quad Cities; the Clinton Station is about 125 kilometers from Braidwood and La Salle; and the Bailly Station is about 100 kilometers from Dresden. 2.3.1.2.6 Reprocessing Reference 6.15 (Table IV E-12) indicates that maximum individual doses due to fuel reprocessing will be less than 10 CFR 20 limits. Therefore, the dose contribution to any person living in this service area due to fuel reprocessing operations, all more than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits. 2.3.1.2.7 Waste Disposal Sites o) The radiation dose associated with the burial of low level radio-active radwaste need not be considered in determining compliance with 40 CFR 190 as this source is specifically excluded by the law. Inasmuch as the licensed burial facility at Sheffield, Illinois, is near CECO's service area, at least a comment regarding it as a potential source is warranted. The radiological impact of burial sites is discussed briefly in Chapter IV, Section H, Part 3.1.2.1 of Reference 6.15 (Page IV H-28 ff). No significant movement of radioactivity into the general environment is expected, though some tritium has been found in groundwater near the Sheffield facility. However, no significant dose contribution to a person living in the vicinity of CECO's nuclear power plants is expected. (The Quad Cities Station is about 60 kilometers from Sheffield; Byron and La Salle are each about 90 kilometers from Sheffield.) 2.3-6
REVISION 2 AUGUGr 1980 2.3.1.2.8 Transportation (m (/ The radiation dose associated with the transport of low level radioactive waste and spent fuel is also excluded from consid-eration by the requirements of 40 CFR 190. This subject has been reviewed in References 6.16 and 6.17, and summarized again in Reference 6.15 (Chapter IV, Section G). The expected dose asso-
-3 ciated with transportation is 3.4 x 10 mrem / person / reactor / year.
2.3.1.2.9 Storage of Spent Fuel in Offsite Facilities The radiation doses associated with releases of radioactivity by independent spent fuel storage facilities (ISFSF) should also be considered in determining compliance with 40 CFR 190. One ISFSF is being operated within CECO's service area; that is, General Electric Company's Morris Operations Plant at Morris, Illinois, adjacent to CECO's Dresden Station. Minute quantities of Kr-85 and other radioactive particulates are released in air- {') borne effluents. A dose assessment was performed using typical release data provided by the General Electric Company and the Offsite Dose Calculation Manual (ODCM) environmental dose assess-ment models for Dresden. (The effluent is released through a 300-foot vent stack; hence the similarity between the two facilities. However, no adjustments were made for differences in site boundary ranges or ranges to dairies. These differences are not expected to affect the conclusion from the dose assessment.) The estimated annual airborne releases from the GE Morris Oper-4 6 ation plant are 6 x 10 PCi of tritium, < 55 x 10 pCi of Kr-85, 3 pCi of Co-60, and 1 pCi of Cs-137. The maximum whole body
-4 dose from these radionuclides is 4 x 10 mrem /yr. So long as this plant remains a spent fuel storage facility and does not reprocess l
the fuel the dose contribution to any person living in its vicinity will be negligible and not considered further in the Dresden 40 ('] CFR 190 analysis. 1 %_j 2.3-7
REVISION 3 NOVEMBER 1981 () 2.3.1.2.10 Long-Term Storage of High Level Radioactive Wastes The dose associated with the long-term storage of high level radioactive wastes is excluded from consideration as far as 40 CFR 190 is concerned. The radiological impact is discussed in Reference 6.15 (Chapter IV, Section H, Part 3. 2) and should be negligible in the CECO service area. 2.3.1.3 Summary The magnitude of radiological dose due to various operations of the uranium fuel cycle and its impact in the Commonwealth Edison Company service area has been reviewed with respect to the requirements of 40 CFR 190. The only dose components requiring consideration are those due to:
- a. radioactivity in nuclear power plant liquid and
() gaseous effluents, and
- b. the direct radiation due N-16 in BWR steam piping, turbines, and associated equipment.
2.3.2 Numerical Models 2.3.2.1 Airborne Releases and Direct Radiation 2.3.2.1.1 Whole Body Dose The maximum whole body (WB) dose from airborne releases and direct radiation will be determined by adding, for each sector, the dose contributions, if applicable, from all (1) noble gases; (2) airborne radioiodines, "particulates", and other nonnoble gas radionuclides with half-lives greater than 8 days; (3) direct radiation from BWR turbine N-16 skyshine im () as computed at the nearest actual residence in each sector 2.3-8
REVISION 2 AUGUST 1980 (Table 7.2-4) ; and at Dresden only, the contribution from U (4) noble gases, and (5) airborne "particulatza d from the Morris Operations plant if spent fuel-is reprocessed. At Zion, sectors whose site boundary is over Lake Michigan will not be considered in the 40 CFR 190 analysis.
-At Dresden and Quad Cities, Equations 2.39 and 2.40, respectively, will be used to compute the direct radiation dose in sectors whose restricted area boundary is over water. This dose, which accounts for possible fishing activities in the vicinity, will then be'added to the nearest residence dose computed with Equation 2.-38 using an at-home occupa,ncy factor of 0.95 rather than the usual 1.0. An occupancy factor of 0.05 is used for fishermen (0.025 at each of 'two locations at Quad Cities) and a boat shielding factor of 1.0.
At Dres, den: O -5 3 D (R, P) = (1. 0) (0.05) 2.28 x 10 P i exp (-0.007 x R )i l=1 (2.39) R y_ = 488 m R, 2 R3 = 610 m Pg Electric power generated (MWe-hr) by each unit in the year At Quad Cities: D(R,P) = (1. 0) (0. 0 2 5) 2.28 x 10 -5 P exp (-0.007 R y ) + exp (-0.007 R I 2, (2.40) Ry = 100 m R2 = 400 m y P Electric power generated (MNe-hr) by the station 2.3-9
. - . _ = .
REVISION 2 AUGUST 1980 Table 2.3-1 shows the methodology for determining the maximum whole body dose from airborne releases and direct radiation. 2.3.2.1.2 Thyroid Dose
- The maximum thyroid dose from airborne releases and direct radiation will be determined by adding, for each sector, the dose contributions from the various sources in a manner similar to that for the maximum whole body dose, as described above and in Table 2.3-1.
2.3.2.1.3 Any Other Organ Dose In this class, the dose from airborne releases and direct radiation to the GI-LLI, bone, liver, kidney, lung, and skin will be determined separately in each sector, and the maximum value 4 chosen to represent "any other organ" (AOO) for purposes of s determining compliance. The maximum AOO dose will be determined in a manner similar to that for the maximum whole body dose, as described in Subsection 2.3.2.1.1 and in Table 2.3-1. 2.3.2.2 Radioactivity in Liquid Releases The maximum whole body, thyroid and ADO doses from radioactivity in individual station liquid releases will be determined using, for the fish pathway, the near-field estimate of dilution at l the station; and using, for the drinking water pathway, the average flow of the receiving body of water at the nearest downstream community water system, if the water system is {. near the station. Otherwise, the drinking water pathway will l not be considered. For situations involving combined-station
- releases, for the fish pathway, for releases from all upstream CECO facilities, the tissue doses will be determined using i the average flow of the receiving body of water at the station.
- Table 2.3-1 shows the methodology for determining these doses.
l t 2.3-10
i i REVISION 2 AUGUST 1980 j Q 2.3.3 Symbo.ls Used in Section 2.3 j SYMBOL NAME UNIT D(R,P) Dose Due to N-16 - (mr em) Skyshine SF Shielding Factor 4 i , OF Occupancy Factor P, P. Electric Power Generated (MWe-hr) 1 by Station'or Unit 1 I i R Distance (m) 4 k 4 O i l ) i ? i l 1 i i t l l l !O l i ( . 2.3-11
,-~.%-,e_ .. .m... . 4,,m,-,,, ..m_v.ww.,,,. ,,,yym_w.,mwm,me..,,,%-,-ww-,ve.cg.-.--se-,v
i REVISION 2 AUGUST 1980
- O 2.3.4 conseents Usea in Section 2.3 NUMERICAL VALUE' NAME UNIT i
2.28 x 10-5 Fitted Constant (mrem /MWe-br) 4 t
~
0.007 Fitted Constant (m ) 0.7 Shi'elding Factor 4 at Home i 1.0 Shielding Factor on
. a Boat 0.05 Occupancy Factor
- While Fishing 0.95 Occupancy Factor at Home for Fishermen 1
1.0 Occupancy Factor at Home for Everyone 1 ] but Fishermen I 4 4 1 T l t 1 O l 2.3-12
,,-an.-r--- ,,m-,,n. ,,,,,-+,.,,..---,,,,,-..-,._,.,,,n,,-w_,..,.,,-o,m,,n,.. ,--.m,-.-nnen_e,,.. ,,,~,,-wnm.v,,..w.--...,--.-.,,.-
(') Q) {
\s' f
)
TABLE 2.3-1 NUMERICAL MODELS FOR COMPUTING RADI ATION DOSE FROM URANIUM FUEL CYCLE OPERATIONSa FUEL CYCLE CLASSIFICATION WHOLE ANY OTHER ORGAN FOOT-OPERATION OF RADIATION BODY THYROID GI-LLI DO NE LIVER KIDNEY LUNG SKIN NOTES REACTORS
- 1. Noble Gases Equation Equation -Equation 2.5 Equation -
2.5 2.5 2.7
- 2. Airborne Equation Equation Equation 2.11 Equation b Iodine and 2.11 2.11 2.11 WB F Particulates Component
- 3. Liquid Waste Equation Equation Equation 2.22 Equation c w
2.22 2.22 2.22 WB Component
- 4. Direct Equation Equation Equation 2.38 Equation d Radiation 2.38 2.38 2.38 FUEL STORAGE FACILITY
- 5. Noble Gases N/A N/A Not Applicable N/A e
- 6. Airborne N/A N/A Not Applicable N/A e >p Particulates
@Q
?n U
- a. The maximum sector doses for the whole body, thyroid, and any other organ, summed over all d5 wz classifications of radiation, will be added to similar tissue doses received from radioactivity gy in 11guld releases, or combined-station releases, if applicable. The maximum dose of each tissue class will be compared to the limits established in 40 CFR 190.10(a).
- . - - - - - - . , . - - , ----y-.- __ - - - - - - - - - -.._.w. TABLE 2.3-1 (Cont'd)-
- b. The dose to all organs will be determined first with Equation 2.11 then adjusted through multiplication by a factor 0.5/fg i 1 where fg is given in Table 7.1-2.
- c. .Only the fish ~ pathway portion of Equation 2.22 will be used unless the community water system is near the station. For combined aquatic pathway doses from more than one station the dose from each upstream CECO station will be determined with Equation 2.22, using MW /F" instead of Mf/F E at the individual station.
- d. Except for special. considerations of fishermen at Dresden and Quad Cities, direct radiation from BWR turbine N-16 will be computed at the nearest actual resident w
in each sector and not at the site boundary. A shielding and occupancy factor of y 0.7 will be used. 5
- e. So long as this plant remains a spent fuel storage facility and does not reprocess the fuel,-its contribution to the total dose will not be considered further.
>m b
Su
*B G*
8"
REVISION 2 AUGUST 1980 O V 3.0 ATMOSPHERIC TRANSPORT, DIFFUSION, AND DOSE MODELS TABLE OF CONTENTS PAGE 3.0 ATMOSPHERIC TRANSPORT, DIFFUSION AND DOSE MODELS 3.1-1 3.1- METEOROLOGICAL DATA FOR MODELS 3.1-1 3.1.1 Current Record 3.1-1 3.1.2 Historical Record 3.1-2 3.1.2.1 Internal Dose 3.1-2 3.1.2.2 External Dose 3.1-4 3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS 3.2-1 3.2.1 Numerical Model 3.2-1 3.2.2 Source Configuration Considerations 3.2-2 3.2.2.1 Elevated Releases 3.2-2 g 3.2.2.1.1 Plume Rise (hrI *~
, ,/ 3.2.2.1.2 Terrain Correction (h p) 3.2-5 3.2.2.1.3 Downwash Correction (C) 3.2-6 3.2.2.2 Vent Stack. Releases 3.2-6 3.2.2.3 Ground Level Releases 3.2-7 3.2.3 Removal Mechanism Considerations 3.2 3.2.3.1 Radioactive Decay 3.2-7 3.2.3.2 Plume Depletion and Deposition 3.2-8 3.2.3.3 Relative Deposition Factor'(D/Q) 3.2-9 4 3.2.4 Symbols Used in Section 3.2 3.2-10 3.2.5 Constants Used in Section 3.2 3.2-11 3.3 MODELS FOR CALCULATING DOSE FROM NOBLE GASES 3.3-1 3.3.1 Gamma Radiation 3.3-1 3.3.1.1 Gamma Air Dose - Finite Cloud Model '3.3-1 3.3.1.2 Whole Body Dose Factors 3.3-4 3.3.2 Beta Radiation 3.3-5 3.3.2.1 Beta Particle Air and Skin Dose Factors 3.3-5 3.3.3 Symbols Used in Section 3.3 3.3-6 3.3.4 Constants Used in Section 3.3 3.3-7 3.4 MODELS FOR CALCULATING DOSE FROM RADIOIODINES, "PARTICULATES," AND OTHER RADIONUCLIDES 3.4-1 O
3-1 1 _ _ _ _ _ .- - 1
- . 3 m.[.s n'N.
i 't REVISION 2 s I // AUGUST 1980 q () 3.0 ATMOSPHERIC TRANSPORT, DIFFUSION, AND DOSE MODP.LS L 3.1 METEOROLOGICAL DATA FOR MODELS v, l .
'.1.1 3 Current Record f' Y
.Onsite meteorological data are used as input to all of the
- \ '/l airbotne dose calculations performed by a contractor. The
*i data are obtained by means of an instrumented meteorological t > tower that measures wind speed and wind directioncat several levels. The stability of-the atmosphere is determined by means of the' temperature lapse rate (differential temperature) between-two levels on the tower. The contractor's analyses are used to supplement dose analyses performed with historical meteorological records.
?
t , For elevated releases, a joint frequency table '(stability wind ( rose) of wind speed, wind direction, and stability is developed using the upper level wind data and the average lapse rate
- . measured on the tower.
o
'Tf.emixed-modemodelforventstackreleasesrequirestwo
[' ytadility wind roses: one to represent the elevated part of the release and one to represent the ground level portion of the release. 1
- h .These are deve'.oped jointly by considering the wind data hour
! '. by hour. The criteria for deciding how to proportion each
^x4 .
hour's data between a vent release and ground level release i depend on the ratio of the exit speed to the wind speed.
; . When the criteria (Subsection 3.2.2.2) indicate.part of the release should be considered as ground level,.the 10-meter f wind data are used.
( ' For ground level releases, the stability wind rose is developed using the. lower level wind data and lapse rate.
~ .
,z~ 3.1-1 4
p
REVISION 2 AUGUST 1980 () The wind direction, wind speed, and atmospheric stability classification schemes are described in Tables 7.1-5 and 7.1-8. Because the dispersion equations are very sensitive to low 4 wind speeds, the hourly record may require editing to reflect the measuring limitations of the wind sensors at low speeds. If the reported wind speed is less than the anemometer's threshold (Table 7.3-6), it is assigned a value equal to one-half of threshold speed. If the reported speed is less than the vane's threshold (calm), Table 7.1-6, a direction is assigned in proportion to the observed wind direction distribution of the lowest noncalm speed class. Diffusion estimates for monthly, calendar quarter, or i annual releases are determined by combining hourly stabil-ity and wind data in the form of stability wind rose tables. Wind speed, direction, and stability classifications are used to group the data and calculate the joint occurrences of the
) groups.
3.1.2 Historical Record Nuclear station operators will use the dispersion factors of Section 7.2 to demonstrate compiiance with the Technical Epe-cifications. Depending on the station, there may be three classes (elevated, mixed mode, and ground level) of' effluent release, each with four types of dispersion factors: (1) X/Q, (2) D/0, (3) Si, Vg , or G y, and (4) S g, Vg , or G g, where i = 1 to 15 which are wind direction dependent. The first two types of dispersion factors are used with the internal dose models; ( X/Q) and the last two types are used with the external dose models. 3.1.2.1 Internal Dose () The recipient of the internal dose can either be an adult 3.1-2
1 REVISION 2 l AUGUST 1980 t or an infant. If the recipient is an adult, the internal
) dose can consist of contributions from inhalation (X/Q) , leafy vegetables or produce (D/Q) , and milk or meat (D/Q). If the recipient is an infant, the total dose consists of contributions from inhalation (X/Q) and milk (D/Q). The dispersion factors for inhalation and leafy vegetable doses are calculated for I
the 16 wind directions. The dispersion factors for the milk cows and meat animals are only calculated for the direction (s) - where these animals are located in the unrestricted area and ] at a distance no greater than 5 miles. l Historical dispersion factors used in the internal dose models I are found in Section 7.2. There is a set of these tables for each station. Section 7.2 contains the dispersion fac-tors for the three possible classes of release and the 16 wind 1 directions for which X/Q (inhalation) and D/Q (leafy vegetables or produce) are calculated. The radius specifies the location at which the dose is calculated. Only maximum X/Q and D/Q values are used. Also in Section 7.2 are the dispersion factors used to calculate the doses resulting from milk and meat consumption. Entries occur only for those directions where the nearby milk cows - and meat animals are located. The internal dose models are:
- 1. adult inhalation;
- 2. adult consuming leafy vegetables;
- 3. adult consuming produce;
- 4. adult consuming meat;
- 5. adult drinking milk;
- 6. any combination of 1, 2, 3, 4, and 5;
- 7. infant inhalation;
! 8. infant drinking milk; and
- 9. sum of 7 and 8.
i 4 3.1-3 1 I i
- ,. - - , , - ,,,,m . ,,- - - .. ----,-..%-.--,.,,m, _,,..- _ .....-__ m _ - .r.. ,. .m .. ,..- .c _ ._. , , , , , , , , . - . . _ , _ - . . . - , _ .
i , REVISION 2
- AUGUST.1980 1
i Q 3.1.2.2 External Dose The wind direction dispersion factors used in the whole body and gamma air external dose models are found in Section 7.2. I For each station, the 15 tables correspond to the 15 radio-nuclides used to determine total external dose, which is the sum of the dose contributions from each radionuclide. The ! whole body (5 g
, Vg , or 5 g) and gamma air (Sg , Vg , or G g)
, dose factors are computed for each of the 16 wind directions and each release class. ! 4 L l The dose factors for beta skin dose (Lg ) and beta air dose (Lg ) , two other types of externa). dose, are constants which l do not vary with wind direction. However, they are combined j in the dose models with X/Q factors, which are wind direction j dependent. 1 O I i i 4 3 O i 3.1-4
REVISION 2 AUGUST 1980 3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS ({} 3.2.1 Numerical Model The model used is classed as a " constant mean wind direction model" by the NRC. Equation 3.1 shows how the concentration to emission ratio (X/Q) at any downwind range and direction
~
is calculated. X(R,0) - f(u,0,s) (uS z)~1eXP [he} 2
, 2.032 - 1/2 5{
u s ( 3.1) This model assumes that the effluent is uniformally distributed within each downwind sector and that the release rate is constant during the time period modeled. 1 X/Q Relative Effluent Concentration (sec/m ) The relative concentration within the cloud at point (R,0) . R Downwind Range (m) The distance downwind to point (R,0). O Direction (degree or sector) The downwind direction to point (R,0) . u Wind Speed (m/sec) The wind speed. s Stability Class The atmospheric stability class. O 3.2-1
REVISION 2 AUGUST 1980 () f Joint Frequency. The observed frequency in which the wind blows with speed u, downwind direction 0, and atmospheric stability class s. S Corrected Vertical Dispersion (m) 3 Coefficient The vertical dispersion coefficient, corrected for building wake effects. h, Effective Stack Height (m) The effective height at which effluent is released. 3.2.2 Source Configuration Considerations () The location of the source with respect to the buildings affects how the airborne effluent will disperse. The following describes the criteria used to model airborne releases from nuclear power plants and describes how the model evaluates each case. 3.2.2.1 Elevated Releases Release locations (chimneys, etc.) that are high enough to be out of the range of the effects caused by neighboring solid structures are classified as elevated releases. The concentra-tions at any range and direction can be calculated by Equation 3.1 when an appropriate value for the effective stack height (h,) is used to represent the height of the plume centerline above the ground. The effective stack height is calculated by the following () h e
=h s +h r
-h t (3.2)
- 3. 2- 2
REVISION 2 AUGUST 1980 Q h s Physical Stack Height (m) . The actual height of the stack above grade elevation. h r Plume Rise (m) The additional rise of the plume due to its bouyancy and/or momentum. h Terrain Correction Factor (m) t The elevation to account for ground points of interest being different than grade elevation near the stack. This equation states that the effective stack height (h e ) is equal to the physical stack height (h ) plus the plume rise s due to buoyancy and momentum (b ) less a correction for the r variation in terrain (h )t * {l 3.2.2.1.1 Plume Rise (hr ) The rise of an effluent plume is dependent on the stability of the atmosphere, the wind speed, the heat content of the i plume, and the exit velocity of the plume. The procedure chosen has been selected to provide a conservative (low) es-timate of the plume rise in order to maximize the resulting calculated doses. Under neutral and unstable atmospheric conditions the momentum-dominated plume rise equations are used. Equation 3.3 shows the basic relationship between h and other parameters. r (h l rl = 1.44d (Wg /u) 2/3 (R/d)1/3 -C (3.3) Wg Exit Velocity (m/sec) The effluent stream velocity at the discharge point. 3.2-3
REVISION 2 AUGUST 1980 d Stack Diameter (m) The diameter of the stack at the discharge point. C Downwash Correction Factor (m) The factor to account for stack downwash under certain atmospheric conditions. Equation 3.3 would allow the plume to continue rising forever which is contrary to observation. In order to limit the rise, Equation 3.4 is evaluated and the lesser of Equations 3.3 and 3.4 is used in the calculations. (br )2 = 3 (Wg /u)d (3.4) Therefore, h can be represented by the following formula for r neutral and unstable conditions: h r
= Min (br )1, (h r2 I (3.5)
Under stable atmospheric conditions, additional calculations are made as follows: (hr )3 = 4 (F/S) (3.6) S -! (3.7) (h Ir 4 = 1.5 (F/u)1/ F Momentum Flux Parameter (m /sec ) F=W g (d/2) 2 (3.8) S Stability Parameter (sec~) See following table. O 3.2-4
=_ .-. .
REVISION 3 NOVEMBER 1981 () Table of Values for Stability Parameter (S) (Sec
~
)
Stability Class S E 8.7 x 10-4 F 1.75 x 10-3 G 2.45 x 10-3 The smaller value computed from Equations 3.6 and 3.7 is compared to the value obtained from Equation 3.5 and the smallest value is used to represent h r under stable con-ditions. In other words, h r
- Min (hrl, I (hr2 I , (hr3, I (h )7 4 ( 3. 9) 3.2.2.1.2 Terrain Correction (h tI The topography of each site and immediate environs is charac-terized as relatively flat, little or no slope, and, with the exception of Zion, rural farmland. Zion terrain is comprised
() of marshy depressions and sandy ridges. Site-specific terrain correction factors, determined in the manner described below and used in the model to describe the offsite receptor points for each station, may be found in Table 7.2-5 of the site-specific data tables. The average difference in elevation H rs is computed for the point to be evaluated by subtracting the height of the terrain (H ) at the release point from the height of the terrain at s the receptor point (H ). The correction factor, h t, is computed r by Equaitons 3.10 and 3.11. H rs
=H r
-H s
(3.10) Hrs; M rs >0 h = ( 3.11) 0 ; H rs 10 H Terrain Height Difference (m) rs (') Net difference between grade elevation of i source and receiver locations.. i . 3.2-5
- . _ . . . _ , . - , . . . . _ . _ , , , - _ _ . . ~ . _ . . . , _ . . . ~ . . _ , . . , _ . _ _ , . . . , _ , . . . - , . . , _ . . . _ . _ _ . _ , . . ,
REVISION 2 AUGUST 1980 () H r Terrain Height At Re Jeptor- Point (m) Grade elevation at the point of interest. Hs Terrain Height At Source (m) Grade elevation at the release. 1 3.2.2.1.3 Downwash Correction (C)
~
If the ratio of the exit velocity to the wind speed is less than 1.5, the effluent can get caught in the downwash of the stack and the plume rise would be inhibited. This reduction is accounted for by the term (C) in Equation 3.3 and this term is computed by Equation 3.12. C = 3(1.5 - Wo /uid (3.12) 3.2.2.2 Vent Stack Releases The constant mean wind direction model has been modified into a " mixed-mode" model. In a mixed aode model the height of 7-) k/ the release is proportioned between an elevated release (stack , height equal to the vent height plus momentum plume rise) , and a ground level release (stack height equal to zero) . Separate wind and stability data are used for each release height and the WQ ratios are calculated. Subsection 3.1.1 describes how the meteorological data are prepared for this calculation. This model is recommended by Regulatory Guide 1.111. The fraction of the time that the plume is considered to be a ground level release (G t) is determined, from the ratio of the exit velocity of the vent (W o) to the wind speed (u), by the use of the following relationships: 9 1.00 ; Wg /u 1.0 U " 2.58-1.58 (W /u ; 1.0 /u 1.5 t 0.3-0.06 (W7u)) g
; 1.5 /u 5.0 0.00 ; W /u 5 0 o (3.13)
Gt Gr und Release Fraction () Fraction of time a vent release is considered a ground level release. 3.2-6
! REVISION 2 AUGUST 1980 j
[} Therefore, the release can be considered as a ground. level
- release 100G t percent of the time and as an elevated release 100(1-G ) percent of the time.
t 4
-j 3.2.2.3 Ground Level Releases I ;
1 To calculate the downwind concentrations resulting from ground ! level releases, Equation 3.1 is used with the effective-i stack height set to zero (h,=0). If the release'is.from a
~
structure of maximum height (D ) , a correction is made to the z dispersion parameter to account.for the increased mixing caused
, by the building's wake effect. Equation 3.14 shows how 4
this is accounted for in the model. , Oz 4
; no wake effect 3 . . .
og 2+D /(2x) b ; wake effect (3.14) o Vertical Dispersion Coefficient
- () The vertical dispersion coefficient for use in (m) i atmospheric dispersion models. See Table 7.1-7.
l l Dg Maximum Height Of Neighboring Structure (m) The maximum height of any neighboring structure causing
- downwind building wake effects.
l When the wake effect is used the factor S z will be restricted i by the condition: 1 S, < 3o g (3.13) 3.2.3 Removal Mechanism Considerations i 1 3.2.3.1 Radioactive Decay I () The loss of activity with time, due to radioactive decay, is accounted for by adjusting the. source term. This adjustment
- 3.2-7
, - . - - - - , - - . - ~ , . - - - - - , . , , - . , - - - . , ~ - - , , . - , - - . . . - - . - - . - , - - - ~ _--.--n,,..-.--,.----..
REVISION 2 AUGUST 1980 takes the fo'llowing form: Q[=Q 1 exp (- Ag t) =Q 1 exp (- Ag R/3600u) (3.16) Q' Corrected Release Rate -(pCi/sec) The release rate of radionuclide i corrected for radiodecay in transit. Qg Release Rate _ (pCi/sec) The release rate of radionuclide 1. A g Radiodecay Constant- (hr-1) The radioactive decay constant for.nuclide i. See Table 7.1-9. t Transport Time (hr) O The time reguired to trave 1 a distance R downwind. 3600 Conversion Constant (sec/hr) Converts hours to seconds. 3.2.3.2 Plume Depletion and Deposition As the plume travels downwind, the radioiodines and particulate material are deposited on the ground and thus removed from the plume. At all ranges (R) the model accounts for this , depletion by multiplying the (X/Q) ratios by a fraction that is a function of release height and stability. ( X/Q) = ( X/Q) g Pd (h,, s) (3.17) P Plume depletion coefficient d !O The funceton r, recommended by the NRC (Regu1atory cuide 1.111, Figures 2-5) is given in Section 7.1, Figures 7.1-1 to 7.1-4. I l 3.2-8 i
. , . ,. m _ .. ,_ ,,,, . m _ . - - ,.., - ,,, . - -- m ,<- . ,,, - ,- - ,,--m +,- -,w
REVISION 2 AUGrJST 1980 Q The plume depletion factors for the height closest. to the actual release height are used. 3.2.3.3 Relative Deposition Factor (D/Q) The value of D/0 is determined from one of the following , equations: D/0 = Dr(s, R, h) s (3.18) D/Q = f (0, s) D r (s, R, h) s (3.19) I s
~
D/Q Relative Deposition Factor (m ) The calculated relative deposition factor in a given direction. O D, Re1eeive Deposition Rete (m The relative deposition rate is the deposition rate per unit downwind distance _ (pCi s -1 m -1) divided by the soutce strength (pCi s-1) 6 For time periods At < 8 hours, Equation 3.18 is used. For time period at > 8 hours, when the meteorological data are in the form of a stability wind rose, Equation 3.19 is used. The values of D r from Regulatory Guide 1.111, Figures 6-9, are reproduced in Section 7.1 as Figures 7.1-5 to 7.1-8. Choose the value of D r closest to the release height (h s)* For mixed mode releases, (D I r
"O t (Drg I + ( -G t) (D rIs*
y (3.19a) O 3.2-9
REVISION 2 AUGUST 1980 <~) 3.2.4 Symbols Used In Section 3.2 SYMBOL NAME UNIT X/O Relative Effluent Concentration (sec/m ) R Downwind Range (m) 0 Direction (degrees or sector) u Wind Speed (m/sec) s Stability Class f Joint Frequency S Corrected Vertical Dispersion (m) z Coefficient h Effective Stack Height (m) e h Physical Stack Height (m) s h r Plume Rise (m) h Terrain Correction Factor (m) t W Exit Velocity (m/sec) d Stack Diameter (m) C Downwash Correction Factor (m) F Momentum Flux Parameter (m /sec )
~
S Stability Parameter (sec ) H Terrain Height Difference (m) rs H Terrain Height at Receptor Point (m) r H s Terrain Height at Source (m) G Ground Release Fraction t oz Vertical Dispersion Coefficient (m) D Maximum Height of Neighboring Structure (m) z Q[ Corrected Release Rate (p Ci/sec) Q. Release Rate (pCi/sec) A Radiodecay Constant (hr-1) t Transport Time (hr) P d Plume Depletion Coefficient O 3.2-10
~ . - _ . . - . _ _ . - _ _ _ _ _ _._ _ _ . _ . . . . _ . -
. _ , _ . . - - - - _ _ . _ . ~
REVISION 2 i , AUGUST 1980 3.2.5 Constants Used In Section 3.2 NUMERICAL VALUE NAME UNIT 3600 Conversion Constant (sec/ht)
-1 16/2n Sector Width (Radians" )
2.032 Conversion Constant A I O i 4 i O 3 2-11
-w- .m.mm, ,g,, ws m m-r -,,--e y ,- - - - +-s- - - -
- - + -+ -
- e --
~ -~
REVISION 2 AUGUST 1980 3.3 MODELS FOR CALCULATING DOSE FROM NOBLE GASES 3.3.1 Gamma Radiation 3.3.1.1 Gamma Air Dose - Finite Cloud Model The gamma air dose (D T) is calculated from either of the following formulae: DY (R,0 ) 260 x 10 -6 x 86400
= x R x 2n/16 t" l f(u,0,s)Q'y p,y -g E (Yy + Kg2 Y )i m u i s (3.20)
DY (R,0 ) = 260 x 10 1 f(u,0, s) x R 2n/16 u i s Af p ai yi I 1+ i 2) g ( 3. 21) DY (R,0) Gamma Air Dose (mrad) The dose at (R,0) due to gamma rays. i i R Downwind Range (m) i The distance downwind to point (R,0) . O Direction (degree or sector) i The downwind direction to point (R,0). 260 Conversion Constant (mrad-radians-m - disintegration / l sec-MeV-Ci) Reconciles units of Equation 3.20. 3.3-1
REVISION 2 AUGUST 1980
-6 10 Conversion Constant (Ci/pC1)
)
s Converts Ci to pCi. 86400 Conversion Constant (sec/ day) Converts days to seconds. 2n/16 Sector Width (radians) The sector width over which the plume meanders. m Index An index identifying the release period of interest. t* Length of Release (days) th The time over which the m release occurred. u Wind Speed (m/sec)
/{}}
The wind speed. 1 Index An index identifying the nuclide of interest.
-s Stability Class The atmospheric stability class.
i f Joint Frequency The observed frequency in which the wind blows with speed u, downwind direction 0, and atmospheric stability class s. Q Corrected Release Rate (pCi/sec) The release rate of nuclide i corrected for radiodecay in transit. 3.3-2
REVISION 2 AUGUST 1980 pai Air Energy Absorption Coefficient (m" ) The gamma ray energy absorption coefficient for air, for nuclide 1 (see Table 7.1-9) . 7 1 E yg Average Energy per (MeV/ Disintegration disintegration) The average gamma ray energy per disintegration of nuclide i (see Table 7.1-9). I 1+ i 2) Dimensionless Numerical Integration Cons: ant The dimensionless parameter resulting from numerical integration over the cloud defined in Section 7.5 of Reference 6.7. (For K g values, see Table 7.1-9) A Corrected Release (UCi)
) The release of nuclide i corrected for radio-decay in transit.
The basic form of the above equation was taken-from Meteorology and Atomic Energy (Equation 7.63) and is equi-valent to Equation 6 in Regulatory Guide 1.109. The summation over the index m represents'the summing of I the doses from all sources at the station (i.e., elevated releases and vent releases). l Equation 3.20 was used to compute the normalized gamma air dose factors (mrad /yr per pCi/sec) S y (for stack releases); V1 (for vent releases); and G g (for ground level releases). Site-specific values of S , V , and i 1 G, 1 using historical meteorological data, are given in Section 7.2. t i 3.3-3
RE7:SION 2
.e n.D ' c .: I !.980 3.3.1.2 Whole Body Dose Factors
(]} The whole body dose factors, si (for stack releases); V f (for vent releases) ; and 5[ (for ground level releases), in mrad /yr per UCi/sec, computed from DT(R,0) + (1.11 SFY 3.17 x 10-8), evaluated one nuclide at a time, are given in Section 7.2. The whole body dose DT(R,0), calculated for preselected ranges in each downwind sector, is given by the equation that follows: T (R,0) = 1.11 SFY i D D{(R,0) exp(-5 p ti l ' i D (R,0) Whole Body Dose (mrem) The dose to the whole body at downwind point (R,0) . 1.11 Conversion Constant (mrem / mrad) Converts mrad to mrem. SFT Shielding and Occupancy Factor for Gamma Radiation Accounts for reduction in gamma exposure to building shielding and occupancy at the point of interest. pti Tissue Energy Absorption (cm /9) 4 l Coefficient (Table 7.1-9) The gamma ray energy absorption coefficient in tissue for nuclide 1. 2 D (R,0) Gamma Air Dose (mrad) o (_) The gamma air dose at (R,0) due to nuclide i as evaluated from Equation 3.20. l 3.3-4
REVISION 2 AUGUST 1980 For this calculation, the thielding factor SFY is set to 0.7 and dosa ic computed at a depth of 5 cm in the tissile. The factor 1.11 is the ratio of tissue to air energy absorption coefficients. 3.3.2 Beta Radiation 3.3.2.1 Beta Particle Air and Skin Dose Factors ) The beta particle air dose factor L g, (mrad /yr per pCi/m ) and skin dose f actor L ,g mrem /yr per pCi/m ,3 are given in Reference 6.5 and included in Table 7.1-13. I O l i O 1 3.3-5 _ , _ , _ , - - _ _ _ _ . , . , , _ _ . , _ _ _ , , , . . - _ _ , . , , . . , , . , . - , - . , , , , . _ , _ , . . , _ _ _ . . _ _ . . _ _ _ , . , _ _ _ . - - - - . , _ , . , _ _ - . . . . , . ~ , - , . . - . . . , , , , , . , - -
REVISION 2. AUGUST 1980-O 3.3.3 Svmbo1s Used In Seceion 3.3 SYMBOL NAME UNIT DY(R,0) Gamma Air Dose (mrad) R Downwind Range (m) O Direction (degrees or sector) m Index t* Length of Release (days) u Wind Speed (m/sec) i Index s Stability Class f Joint Frequency Q' Corrected Release Rate (pCi/sec) pia Air Energy Absorption (m~1) Coefficient {g Average Energy per (MeV/ disintegration) Disintegration (Iy +K g2 I ) Dimensionless Numerical Integration Constant Af Corrected Release (pCi) D (R,0) Whole Body Dose (mrem) SF Y Shielding and Occupancy Factor for Gamma Radiation Df (R',0) Gamma Air Dose (mrad) uit Tissue Energy Absorption (cm /g) Coefficient O 3.3-6
REVISION 2 AUGUST 1980 3.3.4 Constants Used in Section 3.3 1 NUMERICAL VALUE NAME UNIT 260 3 Conversion Constant ([ mrad-radians-m _ disinte MeV-Ci]gration]/[sec-
)
~0 10 Conversion Constant (Ci/pCi) 86400 Conversion Constant (sec/ day) l 2n/16 Sector Width (radians) 1.11 Conversion Constant (mrem / mrad)
O 4 O (
, 3.3-7
REVISION 2 AUGUST 1980 (]) 3.4 MODELS FOR CALCULATING DOSE FROM RADIOIODINES, "PARTICULATES", AND OTHER RADIONUCLIDES The specific model for computing the dose to the various organs of an adult or infant is given in Equation 2.11. For the purpose of demonstrating compliance with the Technical Specifi-cations, the dose to an infant who inhales air and drinks milk containing radioactive material shall be limiting. How-ever, the dose model may be used to compute the dose to an adult who inhales radioactivity and ingests meat, milk, produce, or leafy vegetables containing radioactivity. The choice of the infant as the critical person is based on previous calculations of dose reported in semi-annual or annual reports. Annually, the dose to an adult will be computed to confirm the choice of an infant as " critical person". In the inhalation model, using historical meteorclogical informa-(]) tion, radioactive decay but not plume depletion was considered. Plume depletion was not considered at this time because depletion
- for the D atmospheric class, a class representative of average meteorology, reduces the inhalation dose by, at most, 10%
within the 3 kilometer range considered. O 3.4-1
t REVISION 2 AUGUST 1980 4.0 () AQUATIC TRANSPORT AND DOSE MODELS TABLE OF CONTENTS PAGE 4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1-1 i 4.1 AQUATIC TRANSPORT 4.1-1 4.1.1 River Model 4.1-1 l 4.1.2 Lake Michigan Model 4.1-1 4.1.3 Symbols Used in Section 4.1 4.1-2 4.2 AQUATIC DOSE MODEL 4.2-1 4.2.1 Symbols Used in Section 4.2 4.2-2 3 4.3 AQUATIC TRANSPORT DURING TANK OVERFLOW j CONDITIONS 4.3-1 4.3.1 River Model 4.3-1 4.3.2 Lake Michigan Model 4.3-1 4.3.3 Symbols Used in Section 4.3 4.3-2 i l l 4-i L
l REVISION 2 AUGUST 1980 4.0 AQUATIC TRANSPORT AND DOSE MODELS
~}
4.1 AQUATIC TRANSPORT Dose via the aquatic pathway is discussed in Section 2.2. Two dilution factors are considered; F, the flow of the receiving body of water; and 1/M, an additional dilution factor. 4.1.1 River Model For purposes of calculating the drinking water dose from liquid effluents discharged into a river, it is assumed that total mixing of the discharge in the river flow (F") occurs prior to consumption. No additional dilution is assumed to occur; thus 1/M" equals 1.0. The river flow is taken as the long-term (generally 10 years) average. For the fish consumption pathway, a near-field dilution flow F f { ') is used; 1/M = 1.0. 4.1.2 Lake Michigan Model For purposes of calculating dose from liquid effluents dis-charged to Lake Michigan, it is assumed that the concentra-tion of radioactivity is diluted initially in the condenser c cooling water of flow (F ) and then by an additional factor 1/M" of 60 prior to consumption as potable water. The dilution factor of 60 is the product of the initial entrainment dilution (factor of 10); the plume dilution (factor of 3 over approximately 1 mile); and the current direction frequency (annual average factor of 2) . For the fish ingestion pathway only, it is assumed the radio-activity is diluted fully in a hypothetical river of flow f f F; 1/M = 1.0. (-} m 4.1-1
REVISION 2 AUGUST 1980 () 4.1.3 . symbols Used In Section 4.1 SYMBOL NAME UNIT F Flow of the Receiving Body of Water 1/M Additional Dilution Factor F" Average Flow Rate (ft /sec) * (Drinking Water Pathway) 1/M" Additional Dilution Factor (Drinking Water Pathway)- F Near-Field Flow Rate (ft /sec) (Fish Ingestion Pathway) 1/M Additional Dilution Factor (Fish Ingestion Pathway) c Average Flow of the (gal / min) ' F Condenser Cooling Water i During the Period of Discharge 1 l l O 4.1-2
REVISION 2 AUGUST 1980 O 4.2 aoUxT1C ooSs moost 4 The general model used to calculate the dose from radioactive material released in liquid waste is given in Subsection , i 2.2.1. The maximum consumption rate of fish by an adult, , Uf = 2.4 x 10-3 kg/hr (21 kg/yr), given in Reference 6.5 (USNRC Regulatory Guide 1.109), is assumed for all nuclear stations except those sited along the Illinois River. For these stations, because of this river's very low productivity of desirable fish, a consumption rate one-tenth the maximum i is assumed. i l 4 O 1 l l r f O 4.2-1
REVISION 2 AUGUST 1980 /- h 4.2.1 Symbols Used in Section 4.2 SYMBOL NAME UNIT U Usage Factor (kg/hr) 5
* < . . p Y .,
$ ?f .
r
/
/
/
O ': .-
/
1' l. I T U
/-
o e* k ; e M
~
O -
.=
+ $
' 4.2-2
- i
t ,
}
+
(." REVISION 2
**- AUGUST 1980 g'n'k$?
s O ' '
;4 ;i s
^oo^r1c ra^"seoar oca1ao r^*x ovsartow cono121oas
.... . t _ frjSubsection 2.2.3, the limiting quantity of radionuclide i in tanks without overflow pipes connected to other storage u . tanks was determined to be a function of two dilution factors ' M , ', characteristic of the receiving body of water: F", the minimum
.:, ; i flow of the receiving body of water during overflow conditions, s i and 1/M", an additional dilution factor.
') 4.3.1 River Model
\g. For purposes of calculating the limiting quantity of tank a,' ,, radioactivity spilled into a river of flow, F", and with a dam between the release point and the intake, it is assumed
;, that-tdtal mixing of the discharge in the river occurs in theSinimumriverflowofthemostrecentpast10 years.
'No additional dilution is assumed to occur; thus 1/M" equals
( , 11 0 . 4.3.2 Lake Michigan Model
- For purposes of calculating .he limiting quantity of tank radioactivity spilled into Lake Michigan, it is assumed thatF", the initial dilution water, is zero and that the g
additional dilution factor, 1/M", is 1000. The 1000 factor represents an estimate of the dilution experienced by a
'l / shoreline-spilled water mass as it moves north along the
./ , shore and east into the lake, having to cross the northward moving lake current to reach the nearest water intake which 5 /
s is 65.00 feet northeast (1.1 miles north and 3000 feet out
, T in the lake) at a depth of 35 feet.
g 1
)' Q*
/
%;[ '
'//f
/ 4.3-1 V1% *q ,Q
.. M t .. .- - - . . , - - - , , - _ - - , . - . - - - - . . . - . - -. .. -
REVISION 2 AUGUST 1980 0 432 Svmbo1e usea in Section 4 3 SYMBOL NAME UNIT F" Minimum Flow Rate, (ft /sec) Receiving body of Water 1/M" Additional Dilution Factor Y p' s 4.3-2
REVISION 2 AUGUST 1980 5.0
SUMMARY
O- TABLE OF CONTENTS
.PAGE
'L. '5.0
SUMMARY
- 5.1-1
'5.l' AIRBORNE EFFLUENTS 5 .1-1.
5.1.1 10 CFR 50, Appendix I Design Objectives 5.1-1 5.1.2 10'CFR 20 Release Rate Limits '5.1-2 5.2 LIQUID RELEASES 5.2-1 5.2.1 10 CFR 50, Appendix I Design Objectives 5.2-1 5.2.2 10 CFR 20 Maximum Permissible Concentrations 5.2-1 5.2.2.1 Unrestricted Area 5.2-1 5.2.2.2 Nearest Surface Water Supply 5. 2 i ! 5.3 URANIUM FUEL CYCLE 5.3-1 5.4 PRIMARY DRINKING WATER STANDARDS 5.4-1
'. )
e O 5-l' _ _ _ . _ _ .__---_--__-____-_D
REVISION 2 AUGUST 1980 5.0
SUMMARY
)
LIST'OF TABLES NUMBER TITLE PAGE 5.1-1 Maximum Doses Resulting From Airborne Releases 5.1-3 5.1-2 Maximum Instantaneous Release Rates 5.1-4 5.2-1 Maximum Doses Resulting From Liquid Effluents 5.2-3 5.3-1 Compliance Status: Uranium Fuel Cycle Operations: 40 CFR.190 5.3-2 5.4-1 Projected Dose At Nearest Community Water System 5.4-2 O O 5-li
REVISION 2 AUGUST 1980 0 5.0 SU. ART 5.1 AIRBORNE EI?FLUENTS 5.1.1 10 CFR 50, Appendix I Design Objectives The 10 CFR 50, Appendix I technical specification design objectives for the nuclear stations are summarized in Table 5.1-1. To demonstrate compliance with the Appendix I objectives, the dose for each time period of the quarter.will be calculated using the dose equations noted in Table 5.1-1. The current quarter dose is the summation of the dose contribution from every effluent release during the quarter. The station will calculate the doses on a monthly basis. Each time the o station evaluates the dose equations, the new contribution is added to the current total for the quarter, and the new total is compared with the objective. Next, the new total for the () quarter is combined with the totals for the previous three quarters to determine the annual dose. The results of each calculational run will be summarized in a format similar to that shown in Table 5.1-1. The maximum dose is printed with the associated wind direction. The values calculated for each wind direction and range must be stored for calculation of the maximum period, quarter, and annual dose. For the organ dose, the computer will calculate doses to seven organs for up to 73 radionuclides, and select the maximum period, quarter, and annual organ doses. For each dose type and maximum value, the compliance status is calculated where the status (%) = 100 x maximum dose 4 dose objective. O 5.1-1
l REVISION 2 AUGUST 1980 0 5.1.2 10 CFR 20 Release Rate Limits The compliance status with respect to the 10 CFR 20 limits
; is determined in the following manner and reported in the i format of Table 5.1-2 for periods of unusually high release rate Q.
(d se rate from Eq. 2.9) x 100 C.S.WB
= (%) whole body (5.1) 500 mrem /yr
= (dose rate from Eq. 2.10) x 100 (%) skin (5.2)
C.S.3 3000 mrem /yr (dose rate from Eq. 2.18) x 100 C.S. = (%) organ (5.3) 1500 mrem /yr The value of C.S. must not exceed 100%. If it does, the station's release rate is too high and corrective action to reduce the release rate must be taken immediately. {]) l l l I l l O . 5.1-2
O o o j TABLE 5.1-1 ). (Name) Unit (number) ! MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES (PERIOD OF RELEASE FROM (DATE) TO (DATE). DATE OF CALCULATION (DATE)) i . CURRENT CURRENT THIRD SECOND FIRST j TYPE PERIOD QUARTER
- QUARTER QUARTER QUARTER ANNUAL
! Gamma Air (mrad) Eq.2.10 dose (dir.) - NOTE: This format should appear in all 30 entries 4 Beta Air (mrad) Eq.2.3 l Whole Body (mrem) Eq.2.5 Skin (mrem) Eq.2.7 ] i Organ (mrem) Eq.2.ll i l w
- g Last period of release from (date) to (date), calculated (date).
l .' b j COMPLIANCE STATUS ) 10 CFR 50 APP. I . 10 CFR 50 APP. I l TYPE QUARTERLY OBJECTIVE % OF APP. I YEARLY OBJECTIVE % OF APP. I l s Gamma Air (mrad) 5 10 j l Beta Air (mrad) 10 20 Whole Body (arem) 2.5 5 l
- Skin (mrem) 7.5 15 g Organ (mrem) 7.5 ** 15 *** gg aw 1; O
{ AThe equation number of the model used to compute.the dose for the period is listed here [2 om w
- ' for information only.
- Cumulative dose for the quarter including the current period.
i **The critical organ is (Name).
***The critical organ is (Name).
l
?
i
REVISION 2 AUGUST 1980 0 TAELE 5.1-2 (Name) Station MAXIMUM INSTANTANEOUS RELEASE RATES (PERIOD OF RELEASE FROM (DATE/ TIME)'TO (DATE/ TIME). DATE OF CALCULATION (DATE)) - DOSE RATE, 10 CFR 20 LIMIT, COMPLIANCE l ORGAN mrem / year mrem / year STATUS
- Whole Body 500 Eq. 5.1 Skin 3000 Eq. 5.2 4 (Name) Organa 1500 Eq. 5.3 2
!O I n i AThe organ with the maximum dose should be named.
*See text for definition. If C.S. > 100, add this or similar footnote to the table:
" Corrective action must be taken immediately to reduce the release rate." Also, perhaps, at the bottom of this table on a separate sheet, the radionuclides and their release *
! rate should be listed.
i O ; 4 5 5.1-4
REVISION 2 AUGUST 1980 0 5.2 LIQUID RELEASES 5.2.1 10 CFR 50, Appendix I Design Obiectives The total quarterly and annual whole body or organ doses due to radioactivity discharged in liquid wastes are computed in a manner similar to that for airborne effluents. The results, based on doses computed with Equation 2.22, are summarized in the manner of Table 5.2-1. 5.2.2 10 CFR 20 Maximum Permissible Concentrations 5.2.2.1 Unrestricted Area The concentration of nonnoble gas radioactive material released from the site to unrestricted areas (C ) gshall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 (MPC g ). The concentrations of dissolved or entrained noble gases shall be limited to the concentrations specified in Table 7.1-10. The sum of the fractional limits (C g + MPC g ) must not exceed 1.0 for each release. Hence: 100 x M 1 00% (50 g 5.2.2.2 Nearest Surface Water Supply At Zion, the quantity of radionuclides, excluding tritium and dissolved or entrained noble gases, in outdoor tanks without over-flow pipes connected to other storage tanks, shall be limited to ensure that in the case of an overflow, the annual average concentration of radioactivity in the potable water of the () nearest surface water supply is less than the 10 CFR 20, Appendix B, Table II, Column 2 limits. 5.2-1
- REVISION 2 n.
AUGUST 1980 O Hence: Af F" g + F yt (5.5) exp (- A x t,) < 4 - 1 MPC g i 0 (y t M"g and t C i exp (- A x t") <, [Fw+Ft)g 1100 (5.6) 1 MPC. i 0 - 1 L t w 4
\ F / Mg O
i l 3 i O 5.2-2
---,,-m.m.,--w-,w., ,,w.,+ e u m,wwe-,,, ,,w.,wr -. nw_ w,-,w,, ,wm--w.,,_e-,,-n--me,-,,-r-na-.,---- - - ,+,re,-rw--w,--,.,-
O O O TABLE 5.2-1 (Name) Unit (number) MAXIMUM DOSES RESULTING FROM LIQUID EFFLUENTS I (PERIOD OF RELEASE FROM (DATE) TO (DATE). DATE OF CALCULATION (DATE))
, CURREtif CURRENT THIRD SECOND FIRST
- TYPE PERIOD QUARTER
- QUARTER QUARTER QUARTER ANNUAL
, Whole Body (mrem) dose - NOTE: This format should appear in all 12 entries i Organ (mrem) dose ! Critical Organ name j During Period I , Last period of release from (date) to (date), calculated (date). un N l COMPLIANCE STATUS
! w 10 CFR 50 10 CFR 50, APP. I i TYPE QUARTERLY OBJECTIVE % OF APP. I YEARLY OBJECTIVE % OF AFP. I Whole Body (mrem) 1.5 3 Organ (mrem) 5 ** 10 ***
i i
- Cumulative dose in quarter to date O mm
**':he critical organ is (name) 8g
***The critical organ is (name) Ul*
gw i
REVISION 2 AUGUST 1980 l C 5.3 URANIUM FUEL CYCLE The compliance status, with respect to the 40 CFR 190 limits, is determined in the following manner and reported in the format of Table 5.3-1 at the end of each calendar year. In accordance with the numerical models described in Subsection 2.3.2, the maximum whole body, thyroid, and any other organ (AOO) doses to a member of the public in the general environment, , i.e., the unrestricted area, will be determined and compared to the 40 CFR 190 limits to determine the compliance status. I O i i t l ( 1 l 5.3-1 l l L
REVISION 2 AUGUST 1980 TABLE 5.3-1 (Name) STATION (S) COMPLIANCE STATUS: URANIUM FUEL CYCLE OPERATIONS: 40 CFR 190 Period of Release Date of This Calculation DOSE RATE 40 CFR 190 LIMIT COMPLIANCE ORGAN mrem / year (mrem / year ) STATUS (% )
- Whole Body 25 Thyroid 75 Any Other Organ (Name) 25
*If > 100%, this or a similar footnote must be added to the table. " Corrective action might be needed to bring the facility into compliance with the regulations. If a variance for unusual operations is required, petition the NRC in accordance with the requirements of 40 CFR 190.11."
5.3-2
REVISION 2 AUGUST 1980 5.4 PRIMARY DRINKING WATER STANDARDS The U.S. Environmental Protection Agency has promulgated regula-tions for the radioactivity content of community water systems (Reference 6.18). One part (40 CFR 141.16(a)) of these regula-tions involves man-made radioactivity, such as those in liquid waste from a reactor. It reads: "The average annual concen-tration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the whole body or any internal organ greater than 4 millirem per year." In 40 CFR 141.16(b) the method for calculating this dose is described. The EPA dose calculation method differs somewhat from that described in ODCM Subsection 2.2.1. Furthermore, the 40 CFR 141 regulation applies to the operator of the community water system and not to CECO. () If a special report defining corrective actions to reduce the releases of radioactive materials in liquid effluents is required by the technical specifications, it must include an analysis of the radiological impact on the down-stream drinking water source also. This analysis may include the data of Table 5.4-1. If confirmatory measurements of radioactivity attributable to plant operations found at the nearest community water system are available, the following concentrations, taken singularly or in combination (i.e. , the sum of the ratios of concentration to limit are > 1), shall define the 40 CFR 141 regulatory limit: strontium-90, 8 pCi/1; tritium, 20,000 pCi/1; gross beta activity, 50 pCi/1; and for any other nuclide, the con-centration given in NBS Handbook 69 as amended in August 1963. O 5.4-1
.._ _ . . _ . . _ _ _ _ . . . _ _ _ _ . . _ _ _ . _ _ . . _ . . . - . . . . _ . , . . ._.._. . _ _ . _ . - _ _ ._ . - . . . . , . _ . - . . _. . . _ . - _ _ _ _ ~ . _ . .
~
e .O TABLE 5 1 O-t 2 (Name) Station l PROJECTED' DOSE AT NEAREST COMMUNITY WATER SYSTEM
- f (PERIOD [OF-REL'3ASE FROM (DATE) TO (DATE). DATE OF CALCULATION (DATE))
CURRENT CURRENT THIRD SECOND -FIRST } TYPE PERIOD QUARTER ** . QUARTER QUARTER QUARTER ANNUAL-i i Whole Body (mrem) Dose . NOTE: ,This format should appear in all ! 12 entries 1 i Internal Organ Dose ] (mr em) * *
- l.
j Critical Organ Name Name Name Name Name Name-q During Period *** Last period of release from (date) to (date), calculated (date). 1 1m *
. COMPLIANCE STATUS 40 CFR 141 TYPE ANNUAL LIMIT 4 OF LIMIT l
- l. Whole Body (mrem) '4 Internal Organ (mr em) * *
- 4 i Critical. Organ
- During Year *** Name i
I . i
- This calculation of dose is based on techniques described in the Commonwealth Edison yw Offsite Dose Calculation Manual. These techniques differ from-those described in i .hh j
40 CFR 141. A projected dose of 2 mrem using Ceco's-techniques.is'approximately $$o-l
- 4. mrem'using EPA methods. Any planned action should be based on the requirements g:n
) of the regulation.and not'this report. $" a i ** Cumulative dose in quarter to date.
*** Either-thyroid, GI-LLI, bone, liver, kidney, or lung.
REVISION 2 AUGUST 1980
6.0 REFERENCES
TABLE OF CONTENTS PAGE
6.0 REFERENCES
6.0-1 O I l l i 4 O i 6-1 I
~--w---,,,,----,,--- ,,-n.,,n,.--,-n-,-n. . _ .
~ , , , .---,a.,,-m.,,,--n-
REVISION 2 AUGUST 1980 (])
6.0 REFERENCES
4 6.1 G. A. Briggs, " Plume Rise," U.S. Atomic Energy Com-mission, 1969. 6.2 J. F. Fletcher and W. L. Dotson, " HERMES. A Digital Computer Code for Estimating Regional Radiological Effects from Nuclear Power Industry," USAEC Report HEDL - TME 168, Hanford Engineering Development Laboratory, 1971. 6.3 " Radiological Health Handbook," U.S. Department of Health, Education, and Welfare, Public Health Service, Rockville, Maryland,.1970. 6.4 Regulatory Guide 1.111, " Methods for Estimating Atmo-spheric Transport and Dispersion of Gaseous Effluents (]) in Routine Releases from Light-Water-cooled Reactors," U.S. Nuclear Regulatory Commission, Washington, D.C., Revision 1, July 1977. 6.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Rel' eases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. Nuclear Regulatory Commission, ilashington, D.C., Revision 1, October 1977. i 6.6 J. F. Sagendorf, " A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station," U.S. Department of Commerce, Report No. NOAA TM ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, 1974. 6.7 D. H. Slade, " Meteorology and Atomic Energy 1968," U.S. Atomic Energy Commission, 1968. () 6.0-1
REVISION 2 AUGUST 1980 ({) 6.8 D. C. Kocher, Ed., " Nuclear Decay Data for Radionuclides Occorring in Routine Releases from Nuclear Fuel Cycle Facilities," ORNL/NUr.EG/TM-102, August 1977. 6.9 R. L. Heath, "Gammi.-Ray Spectrum Catalog," Aerojet Nuclear Co., ANCR-1000-2, third or subsequent editio . 6.10 NUREG-0172, " Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake," Battelle Pacific Northwest Laboratories, 1977. 6.11 D. B. Turner, " Workbook of Atmospheric Dispersion Estimates," U.S. Environmental Protection Agency, Office of Air Programs, Publication No. AP-26, revised, 1970. 6.12 U.S. Environmental Protection Agency, 40 CFR 190, Federal Register 42, 9, 2858, January 13, 1977. O 6.13 NUREG-0511 " Draft Generic Environmental Impact Statement on Uranium Milling," April 1979. 6.14 EPA-520/9-73-003-B, " Environmental Analysis of the Uranium Fuel Cycle," Part I, Fuel Supply, October 1973. ' 6.15 NUREG-0002, " Final Generic Environmental Statement on the Use of Recycled Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors," August 1976. 6.16 WASH-1248, " Environmental Survey of the Uranium Fuel Cycle," April 1974. 6.17 WASH-1238, " Environmental Survey of Transportation of Radioactive Materials To and From Nuclear Power Plants," December 1972. O 6.0-2
REVISION 2 AUGUST 1980 () 6.18 U.S. Environmental Protection Agency, 40 CFR 141, Federal Register 41, 133, 28402, July 9, 1976. 6.19 W. R. VanPelt, " Environmental Radiation Survey of the Dresden Nuclear Power Station," Environmental Analysis, Inc., December 1971. 6.20 G. S. Raynor and P. M. SethuRaman, " Recommendations for Meteorological Measurement Programs and Atmospheric Diffusion Prediction Methods For Use At Coastal Nuclear Reactor Sites," NUREG/CR-0936, BNL-NUREG-51045, October 1979. 6.21 J. F. Sagendorf and J. T. Goll, "XOQDOQ Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," NUREG-0324, Draft, August 1977. () l O 6.0-3
a _ n - - + - - ...n.-.21. - a --, REVIS. ION 2 7.0 DATA FOR DOSE ASSESSMEW MODELS TABLE OF COM ENTS PAGE ] 7.0 DATA FOR DOSE ASSESSMEMP MODELS 7.0-1 l 7.1 DATA COMMON TO ALL NUCLEAR STATIONS 7.1-1 7.2 DATA SPECIFIC TO EACH STATION 7.2-1 + O i l I O 7-i
REVISION 2 AUGUST 1980 () 7.0 DATA FOR DOSE ASSESSMENT MODELS LIST OF TABLES NUMBER TITLE PAGE 7.1-1 Dose Commitment Factors 7.1-2 7.1-E-7 Inhalation Dose Factors for Adults 7.1-3 7.1-E-10 Inhalation Dose Factors.for Infants 7.1-6 7.1-E-ll Ingestion Dose Factors for Adults 7.1-9 7.1-E-14 Ingestion Dose Factors for Infants 7.1-12 7.1-2 Miscellr.neous Dose Assessment Factors - Adult 7.1-15
- 7.1-3 Miscellaneous Dose Assessment Factors -
Infant 7.1-17 7.1-4 Stable Element Transfer Data 7.1-18 7.1-5 Atmospheric Stability Classes 7.1-19 7.1-6 Wind Sensor Threshold 7.1-20 7.1-7 Vertical Dispersion Parameters .7.1-21 7.1-8 Wind Speed and Wind Direction Classes 7.1-22 7.1-9 Airborne Isotope Data 7.1-23 7.1-10 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released From the Site to Unrestricted
. () 7.1-11 Areas in Liquid Waste Listing of Radiological Decay Constants 7.1-24 7.1-25 7.1-12 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data 7.1-27 7.1-13 Dose Factors For Exposure to a Semi-Infinite Cloud of Noble Gases 7.1-28 7.2- Indexes for Section 7.2 Tables will be found
, preceding the site-specific data for Dresden,
- La Salle, Quad Cities, and Zion Stations, i
respectively. - t i t f 7-ii l 4 l w-- na ws r -m-am
REVISION 2 AUGUST 1980 7.0 DATA FOR DOSE ASSESSMENT MODELS LIST OF FIGURES NUMBER TITLE 7.1-1 Plume Depletion Effect for Ground-Level Releases 7.1-2 Plume Depletion Effect for 30 m Releases 7.1-3 Plume Depletion Effect for 60 m Releases 7.1-4 Plume Depletion Effect for 100 m Releases 7.1-5 Relat'ive Deposition for Ground-Level Releases 7.1-6 Relative Deposition for 30 m Releases 7.1-7 Relative Deposition for 60 m Releases 7.1-8 Relative Deposition for 100 m Releases 7.2- Indexes for Section 7.2 Figures will be found preceding the site-specific data for Dresden La Salle, Quad Cities, and Zion Stations, respectively. , O v O 7-iii
REVISION 2 AUGUST 1980 7.0 DATA FOR DOSE ASSESSMENT MODELS lO Virtually all of the data to be used in the dose assessment l models is contained in this section of the ODCM. This organization will permit easy reference and facilitate future changes, should they be necessary. Section 7.1 contains data which is generically applicable to all stations. Section 7.2 contains site descriptions and data (particularly meteorological data) which is relevant only to a specific site. i i ? O 4 L 9 i i o 1 4 7.0-1 1 l i
LA SALLE REVISION 2 AUGUST 1980 0 71 o^r^ coaxon To att nocts^a sr^r ons This section contains data that is generically applicable to all stations. l [ O 7 .1- 1
REVISION 2 AUGUST 1980
-(]) TABLE 7.1-1 DOSE COMMITMENT FACTORS PATHWAY INFANT ADULT Inhalation See Table 7.1-E-10 See Table 7.1-E-7 Ingestion See Table 7.1-E-14 See Table 7.1-E-ll The following tables are from Tables E-7, E-10, E-ll, and E-14 of Appendix E of Reference 6.5. Each table contains seven organ dose factors for 73 radionuclides. For radio-nuclides not found in these tables dose factors will be derived from ICRP 2 (1959) or NUREG-0172 (Reference 6.10).
O O 7.1-2
T REVISION 2 AUGUST 1980 TABLE 7.1-E-7 s
}
INHALATION DOSE FACTORS FOR ADULTS (mrem per pCi Inhaled) 4 i 60NE LIVER T . P,0 Cy THYROID KIDNEY LONG GI-LLI 14UCL I CE y H 3 NO DATA 1.59E-07 1. 5 8 F-0 7 1.55E-0 7 1 58E-07 1.58E-0T 1.58E-07 C 14 '2.27E-06 4.26E-07 *.26E-07 4.26E-07 4.260-07 4.26E-07 4.26E-0T la 24 1.280-06 1.28E-06 1.26E-06 1.28E-06 1.28E-06 1.2RE-06 1.28E-06 P 1.65E-04 9.64E 6.20E-06 NO DATA NC DATA NO DATA 1.08E-05 32 LR 51 NO DATA NO DATA 1.25E-OH T.44E-09 2.ASE-09 1.80E-06 4.15E-07. MN 54 NO DATA 4.9)E-Ob 1. 81 E -01 NO DAIA. 1.23E-06 1 75E-04 -9.67E-06
- ......____....._.. ...___..______................__.... .._.......___..__... 2.53E-06
-MN 56 NO DATA 1.55F-10 2.21E-11 NO DATA 1 6 3E-10 1.18E-06
- 1.54E-07 FE 55 5.0FE-C6 2.12E-06 4.91E -0 7 NO OtTA NO DATA- 9.01E-06 FE 59 1.47E-06 1.47E-Oo 1.3/E-06 NO DATA NO DATA 1.27E-04 2.35E-05 NC OATA 1.9AF-07 2.59E-07 NO DATA NC DATA 1.16E-04 1.33E CD $8 1.56E-05 00 60 NO DATA 1.*4E-06 1 05E-06 NO DATA NC DAIA 7.46E-04 5.40E-05 3.73E-Co 1.01E-06 40 DATA NO DATA 2.23E-05 1.67E-06 11 61
.j~g -....._...______...___.____._..........._______........_.................-
1.92E-10 2.o2E-11 1.14r.11 No DATA NC DATA 7.00E-07 1.54E-06
- (_,) 41 65 5.T8E-10 e.48E-07 6.12E-06 CU 64 NO DATA 1.93t-10 T.6 )E-11 NO DATA 2N 65 4.05E-06 1.2 9F -05 . 5.82E-06 NO DATA R.62L-06 1.08E-04 6.68E-06
........._...____..__....____...... _______.. _....._____ 1.15E-07 2.04E-09~
IN 69 4.23t-12 8.14E-12 5.65E-13 Nu DATs 5.27E-12 40 04TA 3.01E-08 NO DATA NO CAT % NO DATA 2.90E-09
,l R 83 NO DATA NO DATA NO DATA' l . 91 E-O R -N0' DATA 40 DATA - NO- D AT A 2.05E-13 HR P4 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E-24 OR 85 60 DATA 2.08E-06 92 86 NO DATA 1.69f-05 7.510-06 NO DATA NO DATA i
4.P4E-08 2.41E-98 NO DATA NO OATA NO DATA 4.18E-19 10 88 NO DATA i _........___ ....... _.............__.................______.. ..._......... NU DATA 3.2Ct-08 2.126-08 NO DATA NO DATA NO DATA 1.16E-21 98 89 3.80E-05 NO CATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05
$d 89 SR 90 1.24E-02 NO DATA 7.62E-04 NO OATA NC DATA 1.20E-0 3 9.02 E-05 4 ___..._____. ..__.___.---.__..--_..._................._..... ..__.....__....
NO DATA 4.56E-06 2.39E-05 SR 91 7.74E-09 NO DATA 3. l lE-10 NO DATA 8.43E-lO NO CATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 SR 92 6.32E-05 10 DATA Y 90 2.61E-07 NO DATA 7.0lE-09 NO DATA 2.12E-05 [ _____.. ___......._..___..____.._ ._.._.._.NC...._. CATA 2.40E-07 1.66E-10 Y 91M 3.26E-11 NO DAIA l.27E-12 NO DATA l NO DATA 1 55E-06 NO DATA NO DATA 2.13E-04 4.8tE-05 L Y 91 5.78E-05 9.19E-06 N0 DATA s. 7 7E-11 NO DATA NC DATA 1.96E-06 i Y 92 1.29E-09 i i i l f i 7.1-3
REVISION 2 AUGUST 1980 o! t% / TABLE 7.1-E-7 (Cont'd) LTVFR T . iiUDY THYRblD KIONFY LONG GI-LLI
%UEllJL BONE
...__..__......__...........__...._____....._L ............... ...___ ..____.
Y 93 1.18E-06 NO UAIA S.26E-10 NO DATA NO CAft o.06E-96 5.27E-05 ER 95 1.34E 4.3CE-06 2. 91 E -0 6 NO DATA 6.77E-06 2.2tE-04 1.18E-05 ZR 97 1.21E-08 2.45E-09 1.13 E -0 9 NO CATA 3.7!E-09 9.8v'-06 6.54E-05 NH 95 1.76E-06 9.77L-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MD 99 40 CATA 1.51t-08 2. 8 7E-0 9 r,0 DATA 3.64E-08 1.14E-05 3.10E-05 it 91M 1.29E-13 3.64F-13 4. 61E -12 NO DATA 5.52E-12 9.55E-08 5.20E-07 fL101 5.J2E-15 7.52t *5 7. 3df -14 NO LATA 1.356-13 4.99E-08 1.36F-21
.4u101 1.91E-07 NO DATA d.23E-08 NO 04TA 7.29E-07 6.31E-05 1.38E-05 H0105 1.880-11 NG DATA 3.H9E-11 NO DATA 1.27L-10 1.37E-06 6.02E-06 RU106 8.b4E-06 NO DATA 1.0 K-06 NO DATA 1.67E-05 1. l ? L-O 's 1.14E-04 AGignF 1.35E-06 1.25i!-06 7.4 5E -0 7 NU OtTA 2.46E-06 5.74E-04 3.78E-05 3.9;E-05 8.83E-06 TCl25* 4.27E-07 1.99C-07 5.84E-03 1.nlE-07 1.55t-06 4.11E-07 1.20E-04 t.87E-05
(,,) TE127M 1.58E-06 7.21'_-07 P.Olt-il 1.96E-07 3.8TE-11 1.12E-10 5.72E-06 6.37E-10 8.14E-07 7.17E-06 N/ IF127 1.75E-10 4.79E-03 IE129* 1.22E-06 5.64E-07 1. 9aE -0 7 4.30E-07 4.57t-06 1.45E-04
- 4. 4 7t-12 2.34L-11 2.4?E-07 1.96E-08 IEl2? 6.22E-12 2.19E-12 1. 5'> E - 12 IE131M 8.74E-09 5.45E-19 3.63r-09 6.88F-09 3.86E-0A !.82E-05 6.95E-05 IF131 .l.39E-12 7.44E-11 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09
...__ _ .......___.______...____._..__...__...__................_ _._______. 6.37F-05 TE13/ 3.25E-08 2.69E-08 2.0/E-08 2.37C-08 1.82E-07 3.60E-05 1.68E-C6 6. 60E-0 7 1.42E-04 2.61E-C6 NO DATA 9.61E-07
! 130 5.7?E-07 4.4TE-Co 2. 5 6 E -0 6 1.49E-03 7.66E-06 NO DATA 7.85E-07 1 131 3.15E-06 I 132 1.45E-07 4.07L-07 1. 4 SE-0 7 1.43E-05 6.48E-07 .hD DATA 5.0SF-08 1.855-06 5.65E-0 7 2.69E-04 3.2 3E-06 NO DATA 1.11E-06 I 133 1.08F-06 R.05E-0a 2.16E-07 7.69E-08 3.73E-06 3.44E-07 43 OATA 1.26E-10 1 134
....___.. __________ _...__ ..____._...______.. .____..._...._____ ________. 6.56E-07 I 135 3.35E-07 8. 7 3t-07 3.210-07 5.000-05 1.59E-06 .NO DATA CS134 4.o6E-05 1.06E-04 9.10E-05 NG OATA 3.59E-05 1.22E-05 1.30E-06 CS136 4.88E-06 1. 8 3E -05 1.39E-05 NO DATA 1. 0 7 E -05 1.50E-06 1.46E-06
_____ _....__ .___. __..__.--_.._.__. ._____.______...................__... 9.40E-06 1.05E-06 CS13; 5.98E-05 7.76E-05 5. 3 '; E -0 5 NO DATA 2.78E-05 7.76E-08 4 . 0 > E -0 8 NO DATA 6.00E-08 6.07E-09 2. 3 3E-13 CS138 4.14E-08 1.12E-07 1.17E-10 8.32E-14 3.4 2 E-12 NO DATA 7.78E-14 4.70E-07
!!A139
\ x_sh 7.1-4 7 i __.__3.
i REVISION 2 AUGUST 1980 s
./ t
\.J 3
TABLE 7.1-E-7 (Cont'd) NUCLILE BONL tIVER T,cucy THYROID KIDNEY LuN- gg_ttg
; nA140 4.9At-C6 6.13F-09 5. 7 t E-01 NO CAIA 2.09E-09 1.59E-04 2.71F-05 nA141 1.25E-Il 9.4 J.-15 ' 20E-13 NO CATA e.75E-15 2.42E-07 1.45E-17 Aal42 3.29E-12 1.3R?-15 2.072-11 NO UAla 2.96E-15 1.*9E-07 1.96E-26
... .........,....m______________.. .____ . _____________....._____..._.....
LA140 4.iOE-C$ 7 2.l?E-03 5.7 4-91 NU DATA NO DATA 1.70E-05 5.73E-05 L A 14 2 8p';4t et t 3. F dE-11; 9. 6 's E - 1 2 NO LATA NC DATA 7.91E-07 2.64E-07 CE141 2.49E-Co 1.692 1.91 L-0 7 NO CATA 7.836-C7 4.52E-05 1.50E-05 JF143 2.11E-CR ' t .12'L- 0 3 1.91L-09 NO Dart 7.60E-d9 9.97E-06 2.83E-05
*E144 4.29E-04 1.79E-C4 2. 30F-0 5 NO D4it 1.06E-04 9.72E-04 1.02E-04 P4143 1.17E-C6 4.69E-07 5.99t-09 Nn DATA 2.70E-07 3.5IE-05 2.50E-05 i __2... _______..__.__J_ __. .___..___.____.....__________.............__.___
/ P R 14+, 1.76E-12 1.36r.g; g ,9 g t.13 NO OtTA 8.ag 13 1.27F-07 2.69E-18 1D541 6.59E-C7 7.62E-07 4. 5 6 E -0 8 NO DATA 4.45E-07 2.76E-05 2.16E-05
= 18f 1.06E-09 8. dy L 3.10E-10 NO DATT NC DATA 3.63E-06 1.94E-05
....____________..._,1,13 ....____. ______....________.. ______________________
(p_ ) NPP39 2.MTE-08 2.82f-09 1.35E-09 NO CATA P.75t-09 4.70r.06 1.49E-05 v s h s 3 9 i n f v' i 7.1-5 s 4 s _J
!./
t
\
REVISION 2 AUGUST 1980 TABLE 7.1-E-10 V, INHALATION DOSE FACTORS FOR INFANTS
' 7 <
(mrem per pCi Inhaled) g I
\
i it 9 in NU; LICE BUNE II/ER !.30CY THYR 010 K!DNEY LUNG GI-LLI P 3 NO DATA 4.62F-07 4.62 F-0 7 4.62F-07 4.6?E-07 4.62E-07 4.62F-07 0 14 1.81E-0) 1.19E-06 3.71E-Ob 3.796-66 5.79E-06 1.79E-06 1.79E-06 NA 24 1.54E-C6 1.542-06 7. 5* E-0 6 7.)*E-06 7.54E-06 7.54E-06 1.54E-06
. 0 12 1.45E-C1 R.C3E-05 5.53E-35 NO DtTA NO DATA A0 DATA 1.15F-05 LH 51 NO UATA NO DATA 6.51E-08 4.!!E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 N3 UATA 1.8tE-03 1.56E-06 NO DATA 1.56E-G6 7.14E-04 5.04E-06 PN 56 NO OATA 1.10E-09 1.53E-10 40 UATA 7.86E-10 P.95F-06 5.12E-05 FE 55 1.41E-05 H.19E-06 2. 3 3 F -0 6 NO DATA NO DATA 6.2tE-05 7.82E-07 FE 51 9.69E-06 1.682-05 6.776-06 v) DATA NO DATA 1.25E-04 1.77E-05 CO $8 10 UATA R.7tE-07 1. 3 nE - i s No DATA NO DATA 5.55E-04 7.95F-06 LC 60 90 UATA 5.73E-06 8.41t-06 NO CATA NO DATA 1.22E-03 2.28E-05 NI 69 2.42E-04 1.46k-0) U . 2 9t -0 6 NO DATA NO DATA 1.49E-04 1.73E-06 g'"') al 63 1.71E-01 2.0tE-10 d.71E-Il NO DATA NO DAIA 5.80E-06 3.58E-05 CU 64 NO CATA 1.34c-09 S.94F-10 NO CATA 2.84E-09 6.64E-06 1.07E-05 IN 65 1.18L-05 4.*7F-05 2.22F-05 NO :,AIA 2. 32 E-05 4.62C-04 3.67F-05
/N 69 3.PSE-Il 6.91E-11 5.11E-12 NO DATA 2.87E-11 1.0$E-06 9.440-06 H4 83 NO DATA NO DATA 2. 72E-0 7 No DATA NC CATA NO DATA Li E-24 69 94 NO DATA NO DATA 2. 86L-0 7 NU OATA NO DATA NO DATA LT E-24 fR 83 NO DATA NU OATA 1.46E-08 NO DATA NC DATA NO DATA LT E-24 13 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 10 88 NO DATA 3.48F-07 2.03E-3 7 NO DATA NO DATA NO DATA 2.42E-07 R9 89 NO DATA 2.21E-07 L.47E-07 NO DATA NO DATA NO DATA 4.87E-On SR 89 2.84E-04 No DATA 8.15E-06 No DATA NO DATA 1.45E-03 4.57E-05 54 90 2.92E-02 NO DATA 1.8df-03 NO DATA NO DATA 8.03E-03 9.16E-05 SR 91 6.83E-08 NO DSTA 2.47E-09 NO DATA NO D'ATA 3.76E-05 5.24E-05 SR 92 1.50E-09 Nd OATA 2. 79E-10 NO DATA NO DATA 1.70E-05 1.00E-04
, , Y 90 2.35E-06 NU OATA 6.30E-38 NO DATA NO DATA 1.92E-04 7.43E-05
- Y ll* 2.91E-10 Nu DATA 9.90E-12 NO DATA NO DATA 1.91E-C6 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO CATA NO DATA 1.75E-03 5.02E-05
( 92 1.17E-08 NU DATA 1.2)E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y
/r 7.1-6 ts
~
~.
REVISION 2 AUGUST 1980 [ ,\
\_/
TABLE 7.1-E-10 (Cont'd) NUCLl(E RONE LIVER I. BODY THY 10!O k!DNEY LONG Gl-LL] Y 95 1.07E-01 40 DATA 2. 9 t E-0 9 NO DATA NO DATA 5.46E-05 1.19E-04 2R 95 d.24[-OS 1.19E-C5 1. 4 5 E -0 5 NO DATA 2.22t.n5 1.25E-03 1.55E-05 ER 91 1.07E-01 1.83E-08 8. lbE -0 9 40 DATA 1.85E-OR 7.88E-05 1.00E-04 N H 9 *. I '.12 L - 0 5 4.59E-06 2. 70E-O b NO DATA 3.lTE-06 3.42E-04 9.0$E-06 MO 99 NO UATA 1.iet-07 2.31E-08 NO Daft 1.99E-07 9.63E-05 1.48E-05
~
IC 99 9.9BE-11 2.06E-12 2.66E-!! NO DATA 2.22E-11 5.79E-07 1.45E-06 TE101 4.65t-14 5.99E-14 5.80~-13 40 OAin 6.99E-13 4.17E-77 6.03E-07 dU103 1.440-06 NJ UATA 4.85E-01 NO 04Ti 1.03E-06 3.94E-E4 1.15E-05
%U105 8.74E-10 NO OSTA 2.9 tE-10 NO DATA 6.42L-10 1.12E-05 3.46E-05 4b106 o.20L-05 Nd DATA 7. 7 7 E -0 6 NO DATA 7.61L.05 8.26F-03 1.1TE-04 4G110w T,13F-06 5.16E-06 3. 5 7E-0 6 NO DAT% 7.A0E-06 2.62E-03 2.36E-05 1El25" 3.40E-06 1.420-06 4 ;0E-0 7 4 1.16f-06 NO OATA 3.190-C4 9.22E-06
() TF12TP 1.19E-05 4.9 3E-06 t . 4 8 6 -0 6 3.48E-06 2.69E-05 9.37E-04 1.95E-05 TEI2T 1.59E-09 6.NIE-10 3.4 7E -10 1.12F-09 3.47E.n9 7.19E-06 1.74F-05 TE129* 1 01F-05 4.15L-06 1.51E-06 1.91E-06 2.27t-05 1.20E-03 4.93E-05 TE129 5.63E-Il 2.480-11 1.340-11 4.82E-Il 1.250-10 2.14E-06 1.98E-05 f[131F F.62E-04 1.13E-08 2.590-08 6.3RE-08 1.89L-07 1.42C-04 8.51E-05 TF131 1.24E-Il 5. 6 TE - 12 3.570-12 1.13E-Il 2.85E-Il 1.4TE-06 5.R7E-06 TE132 2.66E-07 1.6)F-07 1.26E-07 1.99E-07 7.196-0 7 2.43E-04 4.15E-05 1 150 4.54E-06 9.1tE-06 1.98F-06 1.14F-Ol 1.09E-05 NO DATA 1.42E-06 I til 2.712-05 3.11E-05 1. 4 9E -0 5 1.06E-r2 3.70t-05 NO DAir 7.56E-07 I 1 32 1.?!E-06 2.53E-06 8.99C-07 1.2tE-04 2."2C-06 NO DATA 1.36E-06 I 143 9.460-06 1.llE-05 4.000-06 2.549-03 1.60E-05 NO DAir 1.54E-06 1 134 6.5PF-0? 1.340-06 4.75E-37 9.18E-05 1.49f-06 f40 D AT A 9.21E-07 I 135 2.76E-06 5.4F-06 1.99E-06 4.970-04 6.05L-06 NO DAia 1.llF-06 CS134 2.8 3E-04 5.02E-04 5.3/E-05 NO DATA 1.16E-04 5.69E-05 9.53E-07 CS136 5.45E-05 9.olt-05 3. 79 E-0 5 NO DATA 4.01E-05 8.40E-n6 1.02E-06 C$li? 3.92F-04 4. l Tr-04 3.2;F-05 N0'OATA 1.?3L-04 5.09E-05 9.53r-07 C5138 1.6LE-07 9.SNE-07 2.R9 0-0 7 NC OATA 2.9)C-07 4.67E-08 6.26F-0T H Al l9 1.06L-09 7.91E-13 3.0lE-11 NO DATA 4.23E-13 4.25E-06 3.64F-05
, 4 \/
7.1-7
REVISION 2 AUGUST 1980 G TABLE 7.1-E-10 (Cont'd) , NUCLICE 00N[ LIvCP T . MlJilY IHYRUID KlDNtY L lJ C GI-LLI t . . - - - - - - - - - - - - - . . - - - - - - . . . . . - - - - _ - - . . - - - - - - - - . .------.----------- --------
't A 14 0 *.0CE-C5 4.00t-Ce /.C 70-0 6 NO DATA 9.59L-09 1.14F-03 2.745-05 FAl41 1.12E-10 T.700-14 3. 5 'a c - 1 2 '.0 U ?. i A 4.64L-14 2.12E-n6 l.39F-06 94142 2.04E-11 2.465-19 1.40t-12 40 DATA 1.36L-14 1.110-06 4.955-07 . IAl40 S.6lE-C7 1. 4 tt - 0 T 4.6 d -0 0 .0 DATA NO DATA ! 20E-04 6.06E-05 L A 14 2 T.36E-10 2. t< 9t - l O c. .
- c.t - 1 1 :40 DATA NO CATA 5.67F-06 4.250-05 CE141 1.18E-09 1.19t -05 1. 4 / L -O r, NO DATA t.75t-06 s.69f-04 1.540-05
--.---.--.-----------------------------------------~~-----------------------
CE143 2.390-Of 1.49L-07 1. 5 4f -0 8 Ntl 0ATA 4.03t-OH R.3CE-05 3.55E-05
;F144 2.28E-03 8.odt-04 1. 2 0 E -9 4 NO DATA 3.M4t-04 7.0 3E-0 3 1.960-04 e> 414 3 1.00E-05 3.74E-Oo 4.9 ar-0 7 N1 UAIA 1.41E-06 5.09r-04 2.66E-05 PR144 1.420-11 1.320-11 1. 7/ L -12 NO LATA 4.90t-12 1.15F-06 3.06F-06
'40141 5. b iL - Or, 5.Hlf-06 1. 5 7 E-0 f 40 DATA 2.25t-96 2.30E-04 2.23E-05 w 18F 9.26E-09 6.440-09 2.25C-07 NO Uti A NO DATA 2.01E-05 2.54f-05
,-~ ...-..------------------------------------------------.-------------------.
( ,y) *4P219 2.65E-07 2.lTL-09 ! . 3* t -0 9 NO 0A1% 4.71L-Oe 4.250-C5 1.78E-05 O V 7.1-8
REVISION 2 AUGUST 1980
/s)
V TABLE 7.1-E-ll INGESTION DOSE FACTORS FOR ADULTS (mrom per pCi Ingested)
- 4UCL i l.E HONt 1. ! v F R T .4 4Y THYROID K!DNEY LUNG GI-LLI H 3 'NO DATA 1.050-07 l .CS E-0 7 1.05E-97 1.95t-07 1,05E-07 1.05E-07 C 14 2.84E-06 5.69E-07 5.6 8E-0 7 5.686-77 5.68E-07 5.68F-07 5.68E-07 NA 24 1.70E-06 1.70F-C6 1.70E-06 1.70E-06 1. 7 0E -06 1.70E-06 1.70E-06 P 12 1.936-04 1.20F-05 7.4bE-Oc 10 UATA NC DATA NO DATA 2.17E-05 CR 51 NO DATA NO CATA 2.60E-09 1.59E-09 5.86E-10 3.51E-09 6.69E-07 MN $4 NO DATA 4.5 75-C6 9. 72E-0 7 NO DATA 1.36E ,C6 NO DATA 1.40E-05 MN 56 NO DATA 1.l>E-07 2.04c-OR NO DATA 1.466-07 NO DATA 3.67F-06 rE 55 2.75E-06 1.10F-06 4.4lE-07 '40 DATA NO DATA 1.06E-06 1.09E-06 F E 59 4.34E-C6 1.C2C-05 5.910-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 54 N0 DAIA 7.456-07 1.67E-06 40 UATA NO DATA NO DATA 1 51E-05 CO 60 NO DATA 2.14F-06 4.72C-36 NO DATA NO DATA NO DATA 4.02E-05 s
'41 65 1.30E-C4 9.01E-06 4.16E-06 NO UATA NO DATA NO DATA 1.68E-06
[V) .....___....... __... ....____..... ......__ .....____........ ......__..... NI 6 s 5.28E-07 e.o6E-OH 1.13 E -0 8 NO DATA NO DATA NO DATA 1.74E-06 LU 64 70 DATA 9.337-08 3.91E-Oe NO DATA 2.10E-07 NO DATA 7.10E-06 IN 69 4.84E-06 1.34f-03 c . 9nE -0 6 NO DATA 1.03E-05 NO DATA 9.70E-06 IN 69 1.016-08 1.77E-08 1. 3 7E-0 9 NO DATA 1.28E-08 NO DATA 2.96E-09 Ha 83 40 DATA NO DATA 4. 0 2 E -0 8 NO DATA NO DATA NO DATA 5.79E-08 HR 84 NO DATA N0 f;&TA 5. 21 E -0 8 NO DATA NO DATA NO DATA 4.09E-Il OR d4 NO DATA '40 UATA 2.14 E -0 9 NO DAT1 NC DATA NO DATA LT E-24 RH d6 NO DATA 2.111-95 9. R 5E-0 6 NO DATA NO DATA NO DATA 4.16E-06 RB 84 NO DATA 6.05E-03 1.21E-09 NO DATA 10 DATA NO DATA R.36E-19 48 89 NO DATA 4.01E-03 2. 87 E -0 9 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08L-C4 NO DATA 8. 84 E -0 6 10 DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 10 DATA 1.86E-01 NO Daft NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NU OATA 2.29E-97 10 CATA NC DATA NO DATA 2.70E-05 5R 92 2.150-C6 10 DATA 9. 40E -0 9 NO DAT4 NC DATA NO DAT*. 4.26E-05 Y 90 9.62E-01 40 UATA 2.5dt.10 No DATA NG OATA NO DATA 1.02E-04 Y 91F 9.09E-Il NO DATA 1. '2 2 C - 1 2 NO DATi NO DATA NO DATA 2 .6 'E-10 Y 91 1.41E-07 10 DATA 3. T TE -0 9 NO DATA NO DATA NO DATA .' - 76E-05 Y 92 8.45E-10 NO DATA 2.4TE-ll NO UAft NO DATA NO DATA 1.\8E-05 ____ .....__........ ..____........._ _...___ ..___..._........ .._____..... F t t V 7.1-9 t
REVISION 2 AUGUST 1980 O. TABLE 7.1-E-ll (Cont 'd) NULLltE euNE LIvi9 T. LOGY THY 901C KIDNEY LuNO GI-LLI Y 95 2.68E-09 No UATA 7.4 'JE -i l NU OATA NO DATA NO DATA 8.505-05 1R 95 3.04E-OP 9.75E-C9 6.60E-01 NO DATA 1.5;L-0R NO DATA 3.09E-05 IR 97 1.68E-09 l.392-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.0$E-04 N8 95 6.22E-09 3.46E-09 1.8bE-09 NO CATA 3.42E-C9 NO DATA 2.10E-05 MO 99 NO DATA 4.llE-06 8.20E-07 f40 DAT A 9.76k-06 NO DATA 9.99E-06 TC 91H 2.47E-10 6.982-10 9.89E-09 NO DAT4 1.06E-08 3.42E-10 4.13E-07 TClot 2.54E-10 3.66L-10 3.59E-09 NO DATA 6.59t-09 1.87E-10 1.10E-21 tul03 1.85E-07 NO DATA 7. 9 7E -0 8 NO DATA 7.06E-07 NO DATA 2.16E-05 Rul05 1.44E-08 NU CATA 6.0*L-09 NO DATA 1.99E-07 NO DATA 9.42E-06
'< U l 0 6 2.75r.06 NO DATA 3.49F-07 NC CtTA 5.31E-06 NO DATA 1.78E-04 e- A0110p 1.60t-07 1.46f-07 8.79E-08 NO DATA 2.9tE-07 NO DATA 6.04E-05 (N) TE125" 2.t9E-06 9. 71E n 7 3. 5 9E-0 7 8.06r.37 1,ogE.05 NO CATA 1.07E-05 TE127* 6.77E-06 2.42C-06 8.25 E-0 7 1.71E-0* 2.75E-05 NO DATA 2.27E-05 TEl27 1.10t-07 3.95E-08 2. 3H E -0 8 8.15E-08 4.48h-07 NU OATA R.68E-06 TE129M 1.15E-05 4.?9c-Ot 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 IEl29 5.14E-08 1.18E-08 7.o>E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TEL3lm 1.73E-06 A.46E-07 7.0$E-0 7 1.S*L-06 8.57E-06 NO DATA 8.40E-05 TEl31 1.9 7E -0 8 8.23E-E9 6.22E-09 1.02E-08 9.63L-08 NO Daft 2.79E-C9
( E 132 2.52E-06 1.6 3L-06 1.53E-06 1 80E-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.24E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I I ll 4.16E-06 d.95E-06 3.4tE-06 1.95F-03 1.02L-05 NO DATA 1.5FE-06
! 132 2.0lE-07 5.43F-07 1.90E-0 7 1.90E-05 8.65L-07 NO CATA 1.02E-07 I 13$ 1.42E-06 2.47r-06 7.56E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2. ear-07 1.0 S E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 ! 115 4.43E-07 1.166-06 4.23C-0 7 7.65E-05 1.86E-06 NO DATA 1.llE-06 C5tl4 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79L-05 1.59E-05 2.59E-06 CSI16 6.5tE-06 2.575-05 1. 8 5 E -0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06 C5137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70t.05 1.23E-05 2.IIE-06 C5138 5.52E-OR I.09E-07 5.40E-08 NO DATA 8.01t-08 7.9tE-09 4.65E-13 BA139 9. 70E-0 8 6.912-11 2.84E-09 NO DATA 6.46E-11 5.92E-11 1.72E-07 O
U 7.1-10
REVISION 2 AUGUST 1980 ,t , t v
/-
TABLE 7.1-E-ll (Cont'd) 4UCL !! E BONr LI/ER T.d THYWOID KIDNEY LUNG GI-LL1 _........................___.'EY ......____ ..__________. ____ .__ ,________
-)A149 2.t' S E-C5 2 35E-03 1. 5 sE -0 6 49 NATA 8.6Tt-09 1.46E-08 4.18E-05 Psl41 4.llE-08 4.56E-11 1. 5 '3 E -0 9 '40 U A T A 3.31E-11 2.02E-11 2.22E-17 HA142 2.15E-03 2.19E-Il 1.14 t -0 9 su DATA 1.95F-ll 1.24E-11 1.00E-26 LA140 2.50l-09 1.262-01 3.33E-10 NU DATA NC DAf4 NO DATA 9.2SE-05 LA142 1.28E-10 5.82E-11 1.45r-11 NO DATA NC DATA NO DaiA 4.25E-07
;tl41 9.36L-01 6.19r oq 7, g q[.! C NO Daft 2.94L-09 NO DATA 2.42E-05 CE143 1.65E-09 1.227-06 1. 55E -10 NO Dati 5.37E-10 NO DATA 4.56F-05 CE144 4.R8E-07 2.04:-07 2.62E-08 NO DATA 1.2tE-07 NO DATA 1.65E-04 PRI4 l 9.20E-09 3.69:-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 P1144 3.01E-Il 1.25E-L1 1.SSE-12 NO DATA 7.05E-12 NO DATA 4.35E-18 w NDl47 6.29E-C9 7.27c-09 4.15 E -10 NO DATA 4.25E-09 NO DATA 3.49E-05 h 19T 1.03E-07 E.61E-08 3.C1E-3e NU CATA NO DATA NO DATA 2.62E-05
(~J 'I ____........ ..___._...____........ ........................ .......__...... NP239 1.19E-01 1.17C-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 s h h \al 7.1-11
REVISION 2 AUGUST 1980 g TABLE 7.1-E-14 INGESTION DOSE FACTORS FOR INFAN'IS (mrem per pCi Ingested) WCLIct Bul4E L I VE R T . 'lo oY THY 1010 kl0NEY LONG GI-LLI H 3 Nb DATA 3.f6"-01 s.C it-S T $.69f-97 1.0SL-07 3.00E-0T 3.08E-07 L I4 2.lif-05 5.C6f-06 5. 00E-0 6 3.06E-P6 5.C6L-06 5.06F-06 5.06E-06 NA 24 1.0!t-05 1.o1E-02 1.Olt-95 1.012-55 1.01F-05 1.01E-05 1. ole-05 P 52 1.706-03 L.00;-04 0.21 -05 NU UATA NC DATA NO DATA 2.10E-Os
;d 51 NO DATA NU DATA 1.41t-08 1.200-99 /.01E-09 1.79E-08 4.11E-07 dN 44 NO OATA 1.995-02 4. S i t -0 6 NO DATA 4.4tt-06 NO CATA T.3tE-06 HN 56 Nta DATA A lHL-01 1.4Ir-01 NO DATA T.93L-07 NO DAT4 7.43r-05 fE 55 1.39E-05 6.182-06 2.4CE-06 NO DATA NG DAIA 4.19E-06 1.14E-06 rr 59 3.086-05 5.380-0) 2 12E-05 NO CATA NU DATA 1.59E-05 2.57F-05 60 5d N0 0%TA 3. fict -00 8. 9 'lf -0 6 NO DATA 10 DATA NO DATA 8.97E-06 NO OAIA 1.J8r-05 2.55E-05 40 UAIA NC DATA NO Dal% 2.5FE-05 ~') CG 60 (V NI 65 6.14E-04 3.92E-05 2.2nE-05 NO OAi% 10 UATA NO DATA 1.95E-E6 NI 63 4.70E-06 5.32E-01 2.42c-07 NO DATA NO DATA 40 U AT A 4.050-05 yu 64 NO DATA 6.G9t-Of 2.0/E-0? No DATA 1.olt-06 NO DAI% I.!SE-05 th 62 1.14E-05 6.21t-G) 2.9tE-0) '40 UATA l.06E-05 NO DATA 5.33E-05
_--__.---...-----.----- ---.------- .------~~~.----------------------------- f r4 69 9 33E-08 1.oHL-01 1.25f-01 NO DATA 6.1PE-08 NO D AT A 1.37F-05 HR 63 ., DATA NO. DATA 3.63E-0T No GATA '40 UATA NO L'ATA LT E-24 nR 9~ 40 DATA N0 UATA 3.8JL-O f NU DITA NO DATA NU l' AT A LT E-24 OR A, NO DATA NO DATA 1. 94 E -0 8 NO DATA NC OATA NO DATA LT E-24 Hn 36 NO DATA 1.10!-04 8.4JE-35 NO DATA NO DAIS NO DATA 4.15E-06
<n 88 40 DATA 4.98t-07 2.7sE-01 NO DAIA NO DAIA NO DATA 4.83r-07
......--.----.....-------------------------------------~~---------------~~--
9P 89 NO DATA 2.U6E-07 1.91E-97 NO vata NO Daft NO DATA 1.74E-08 53 81 2.51E-03 NG DATA 7.200-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.056-02 No UATA 4. 71 E -0 3 40 O AT A NO DATA NO DATA 2.)lE-04
..--.-.----------------------------------------- ----~~---------~~~-- .--~~--
sd 91 5.00E-C5 NO UtTA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 59 92 1 92E-05 NO DATA 7.136-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 R.69E-08 10 CATA 2.33E-09 NO CATA NO DATA NO DATA 1.20E-04 Y 9tp 8.lCE-lO NO DATA 2. 76c-l l 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 F40 DATA 1.46E-04 [ \ i
\.
- 7. 1- 12
REVISION 2 AUGUST 1980 m (x- ) TABLE 7.1-E-14 (Cont'd) T.000Y THY 4010 KIONEY LONG GI-ELI NUCLICE DONE LIVER 10 DATA NO DAit 1.92F-04 Y 93 2 41E-08 NO DAT A 6. 6 2 E -10 NO DATA 2.06E-07 5.02E-08 1.56E-58 NO DATA 5.41E-08 NO DATA 2.50F-05 2R 95 NO DATA 1.62E-04 1R 97 1.4SE-0A 2.54E-09 1.16E-09 NO DATA 2.56E-09 1.74E-08 NO DATA 1.46E-05 NB 95 4 20E-08 1.73E-08 1. 0 0 E -0 8 NO DATA NO DATA 3.4CE-05 6.61E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 MO 91 1.15E-06 iC 91k 1.92F-09 3.967-09 5.IOE-09 NO D A T P. 4.26t-0A 2.07E-09
- -....._.....____........_.................__________________......___ 1.56E-09 4.86E-07 IClot 2.27E-07 2.e6E-09 2.h3E-0C NO DATA 3.40E-09 1.*BE-06 NO UATA 4.95E-07 Nn DATA 1 08E-06 NO OATA 1.80E-05 90h03 5.41E-05 1u105 1.36E-07 NO DATA 4.51E-OR 30 CAIA 1.00E-06 ho D AT A
_____.....____..._______..__._____...._..____..__._________..__...........__ 1.R3F-04 NO b4TA l.01E-06 NP OATA 2.9$t-05 NO DATA 9U106 2.41E-05 3.77E-05 7.27E-07 4.PLE-07 NO DATA 1.04E-06 NO DATA
%G110M ?.96E-07 3.1 )E -0 6 7.84E-06 NC DATA NO DATA 1.llE-05
/~'T TE12de 2.43E-05 7.79E-06 \ ,/ _.___.___.-_................-_........_._. ....__._..........__............. 1.44E-04 NO DATA 2.36E-05 TE127M 5.85E-05 1.74E-05 7.0aE-06 1.69E-05 3.SSE-07 2.15E-07 A.14E-67 2.44t-06 NG DATA 2.10E-05 TEl27 1.00E-06 NO DATA 5.97E-05 TE129H 1.COE-C4 3.45c-05 1. 54 E-0 5 3.14E-05 2.506-04 7.07E-07 Na DATA 2.27E-05 TE129 2.84E-07 9.79E-08 6.61E-38 2.JPE-07 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE131* 1.52E-05 TE131 1.76E-07 6.50E-08 4. 94E-0 8 1.57t-07 4.50E-07 40 UATA 7.llE-06
..--_..__..__-- ......._.._........___.__.________........______... NO DATA 1.81E-OS 2.08E-05 1.01E-05 9.61E-06 1.52E-L5 6.44E-05 TE132 2.85E-06 I 130 6.00t-06 1.525-15 3. 30E -0 6 1.48E-11 1.45E-05 NO DATA 3.59E-05 4.21E-0) 1. 9 tA -0 5 1. 3 9r-02 4.94E-05 Nn DATA 1.51E-06 I 131 NU UafA 2.73C-06 1.66E-06 3.47E-06 1 20E-06 1.58E-04 3.76E-06 I 132 3.08E-06 8 133 1.25E-05 1.82E-05 5.3tE-06 1.31E-01 7.14E-35 NO DATA H.69E-07 1.78E-06 6.33E-07 4.152-05 1.99E-06 NO DATi 1.84E-06
! 134 NO DATA 2.62E-06 l 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 9.07E-06 3.77E-04 7.03E-04 7.19E-95 NU CATA 1.81E-04 7.42E-05 1.11E-06 C 5134 1.10E-05 2.050-06 C5136 4.59E-05 1.15E-04 5.04E-)5 NO UAta 5.3et-05 1.64E-04 6.64E-05 I.9tE-06 E3137 5./2C-04 6.llE-04 4.93E-05 NO DATA 7.02E-07 5.79E-07 10 DATA 3.90E-07 6.09E-08 1. SE-06 C$138 4.81E-07 3.54E-10 5.58E-05 HAI)? 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 Om 7.1-13 b
1 1 i REVISION 2 AUGUST 1980 ) l rx ( v) TABLE 7.1-E-14 (Cont'd) NUCL I JE unNE t!vER T..$CLY THY 40l0 MIDNEY LONG GI-LLI 3A140 1. TIE-04 1.71E-07 9.R1E-06 NO DATA 4.C6L-08 1.05E-G7 4.20E-05 PA141 4.25E-C7 2.112-10 1.)*t-09 Nn DATA 1.75t-10 1.TTr-IC 5.19E-06 FA142 1.84E-C7 1.45t-10 9.06E-09 NO DATA P.91E-11 9.26E-Il 7.59E-07 LA140 2.11E-08 8.426-C9 2.14E-09 NU OATA NC OAIA NO OATA 9.77f-05 L A 14 2 1.10E-09 4.06E-10 9.ctr-11 NO DATA NC OATA NO DATA 6.96F-05 CE141 7.87E-Od 4.N0^-08 5.o NO DATA 1.48t-09 NO DATA 2.48E-05
.__.......___......______ .___'et-09 CE143 1.48E-C9' 9.02E-Oc 1.1 > E -0 9 NO CATA 2.96t-09 NO DATA 5.73E-05 CE144 2.986-06 1.22E-06 t.6TE-07 No DATA 4.9 3E-n ? NO DATA 1.11E-04 PRl43 8.13E-0A 3.L4L-08 4.0lE-09 No DATA 1.13t-nB NO DATt 4.29E-05 PRl*4 2.74L-10 1.06E-10 1.31[.11 '40 DATA 3.84t-il NO DATA 4.9 3E-06 f_ tlD 14 T 5.53E-08 5.682-08 3. 4 H -0 9 No GATA 2.19t-OR f40 DATA 1.60E-05
( w 18? 9.03E-01 6.2dt-97 2.1TE-01 NO CalA NO DATA NO DATA 1.69E-05 x ____.....__.______....._..-..____...........___...........____...........__. NP251 1.!!E-02 9. '3 3 L - 10 5.618-10 40 UA T A 1.986-09 NO DATA 2.870-05 A \ t
%/
7.1-14
REVISION 2 AUGUST 1980 TABLE 7.1-2 - MISCELLANEOUS DOSE ASSESSMENT FACTORS - ADULT UM a
= 310 liters /yr
' 3 R = 8000 m /yr-1 a P U a = 520 kg/yr U[=64kg/yr e F U = 110 kg/yr , a , a i f = .76 p f = 1.0 () t = 0 for pasture grass -(milk and meat pathways) h I th = 24 hr (1 day for leafy vegetables)
- th = 1440 hr (60 days for produce) t = 2160 hr for stored feed (milk and meat pathways) h i t = 720 hr (30 days-for milk and meat) e t
e
= 1440 hr (60 days for produce or leafy vegetables) fg = 1.0 May-October f = 0.0 November-April f
() f g
= 0.5 A, = .0021 hr-1 7.1-15
_ ... . , - _ . . _ _ , . , _ . _ _ _ _ . . _ , , . . ~ _ _ _ . _ _ _ . , _ - _ . _ _ _ _ . . - - . _ . . - . _ _ _ . - . _ . . - .
- - . - _ - . - - _ . . - . .~ ._ - - - - -_- - _. . . . . - . . . . . - .
1 k i REVISION 2 AUGUST 1980 . i , O l TABLE 7.1-2 (Cont'd) 4 . 4 2 4 i Y = 2.0 kg/m for leafy vegetables and produce pathways v i , I Y V
= 0.7 kg/m~ for milk and meat pathways i t
i
- t = 480.hr (20 days) s l r = 1.0 (iodines) 1 l
I 0.2 (others) . i { W g = 50 kg/ day I t = ( ays) M O i i t { i . t + 4 l i I i .t I s d i O e I 7.1-16 k ww re w y , w,*w +,vr _ . _ _ . _ . n- w-e-s e- w--w eyw-w - _..e**=-wew-$w-*e--<-e==3,w-w= w _
REVISION 2 AUGUST 1980 TABLE 7.1-3 i
-()
MISCELLAN,EOUS DOSE ASSESSMENT FACTORS - INFANT U = 330 liters /yr U,U,U =0 a a 3 R = 1400 m /yr l Wg = 50 kg/ day r = 1.0 (iodines)
- 0.2 (others) t = 48 hr (2 days)
M
-1
! A, = 0.0021 hr
! () Y = 0.7 kg/m 2
v i t = 720 hours e t = 0 for pasture grass (milk pathway) h i i t = 2160 hr (stored feed and milk pathway) h ! fg = 1.0 May-October i. f = 0.0 November-April f f f = 0.5 g I K = 0.5 May-October () K = 0.0 November-April
' *The r factor provides for the non-deposition on grass of'the i organic forms of-iodine.
1 7.1-17 l
REVISION 2 AUGUST 1980 U TABLE 7.1-4 STABLE ELEMENT TRANSFER DATA
- F Fg(Cow) 7 Element Meat (d/kg) Milk (d/1)
H 1.2E-02 1.0E-02 C 3.lE-02 1.2E-02 Na 3.0E-02 4.0E-02 P 4.6E-02 2.5E-02 Cr 2.4E-03 2.2E-03 Mn 8.0E-04 2.5E-04 Fe 4.0E-02 1.2E-03 Co 1.3E-02 1.0E-03 Ni . 5.3E-02 6.7E-03 Cu 8.0E-03 1.4E-02 Zn 3.0E-02 3.9E-02 Rb 3.lE-02 3.0E-02 Sr 6.0E-04 8.0E-04 Y 4.6E-03 1.0E-05 Zr 3.4E-02 5.0E-06 O Nb 2.8E-01 2.5E-03 kd Mo 8.0E-03 7.5E-03 Tc 4.0E-01 2.5E-02 Ro 4.0E-01 1.0E-06 Rh 1.5E-03 1.0E-02 Ag 1.7E-02 5.0E-02 Te 7.7E-02 1.0E-03 I 2.9E-03 6.0E-03 Cs 4.0E-03 1.2E-02 Ba 3.2E-03 4.0E-04 La 2.0E-04 5.0E-06 Ce 1.2E-03 1.0E-04 Pr 4.7E-03 5.0E-06 f ) Nd 3.3E-03 5.0E-06 l W 1.3E-03 5.0E-04 Np 2.0E-04 5.0E-06 l i Br 2.9E-03** 1.4E-02*** I
- Data presented in this table are from NRC Regulatory Guide 1.109, Revision 1, (Reference 6.5), October 1977.
**Used value for I (no literature available).
***W. C. Ng " Transfer Coefficients for Prediction of the Dose b^ to Man V1a the Forage-Cow-Milk Pathway From Radionuclides Released to the Biosphere," UCRL-51939.
- 7. 1- 18
0 v (Vh O V TABLE 7.1-5 ATMOSPilERIC STABILITY CLASSES PASQUILL TEMPERATURE CIIANGE U STABILITY 0 WITil llEIGHT DESCRIPTION CLASS (SEE NOTE, BELOW) ( C/100 m) Extremely A >22.5' <l.9 Unstable Moderately B 17 . 5
- to 2 2.5 ' -1.9 to -1.7 Unstable y Slightly C 12.5 to 17.5 -1.7 to -1.5 Unstable Y
D 7.5* to 12.5o -1.5 to -0.5 $ Neutral Slightly E 3.8
- to 7.5 -0.5 to 1.5 Stable Moderately F 2.10 to 3.8o 1.5 to 4.0 Stable Extremely G 0* to 2.lo >4.0 Stable CH
$$0 HZ NOTE: 0 is the standard deviation of horizontal wind direction fluctuation over a $w p$riod of 15 minutes to 1 hour. o
h 1 1 REVISION 2 " AUGUST 1980 1 e i i i f i 4 TABLE 7.1-6 t WIND SENSOR THRESHOLD i ANEMOMETER VANE WIND SPEED (mph) WIND DIRECTION (mph) i LOCATION 4 i Dresden 0.3 09 4 Quad Cities 0. 0 0,8 l Zion 0.5 0.7 1 g LaSalle 05 0.7 Eraidwood 0.8 0,8
- Byron 0.8 0.8 i
l Carrell County 05 0.7 I I l h i } 1 i f 7.1-20
- m-w,n,--. e, . a. . ..ww-~-- . _ . - - - - - --- - - - - .- ~~
REVISION 2 AUGUST 1980 0 TABLE 7.1-7 HORIZONTAL AND VERTICAL DISPERSION PARAMETERS
- Horizontal Dispersion Parameters, a y, meters **
o y = aR R = downwind range, meters STAtILITY C LASS a b A 0.3658 0.9031 B 0.2751 0.9031 C 0.2089 0.9031 D 0.1471 0.9031 E 0.1046 0.9d31 F 0.0722 0.9031 () G 0.0481 0.9031 Vertical Dispersion Parameters, o ,g meters ** z
= aR +C STABILITY 100 < R < 1000 R> 1000 CLASS a b c a b c A 0.00066 1.941 9.27 0.00024 2.094 - 9.6 B 0.0382 1.149 3.3 0.055 1.098 2.0 C 0.113 0.911 0.0 0.113 0.911 0.0 D 0.222 0.725 -1.7 1.26 0.516 -13.0 E 0.211 0.678 -1.3 6.73 0.305 -34.0 F 0.086 0.74 -0.35 18.05 0.18 -48.6 G 0.052 0.74 -0.21 10.83 0.18 -29.2
() *From Reference 6.21.
** Values of a and are also limited to a maximum of 1000 meters.
z 7.1-21
REVISION 2 AUGUST 1980 TABLE 7.1-8 WIND SPEED AND WIND DIRECTION CLASSES Wind Direction Classes , N WlHD DIRECTION GT 348.75 AND LE 11.25 WIND DIRECTION CLASS (DEG) NNE WIND DIRECTION GT 11.25 AND LE 33 75 WIND DIRECTION CLASS (DEG) NE WIND DIRECTION GT 33 75 AND LE 56.25
' WIND DIRECTION CLASS (DEG)
ENE WIND DIRECTION GT 56.25 AND LE 78.75 WIND DIRECTION CLASS (DEG) E WIND DIRECTION GT 78.75 AND LE 101.25 WIND DIRECTION CLASS (DEG ESE WIND DIRECTION GT 101.25 AND LE 123 75 WIND DIRECTIDN CLASS (DEG) SE WIND DIRECTION GT 123 75 AND LE 146.25 WIND DIRECTION CLASS (DEG) SSE WIND DIRECTION GT 146.25 AND LE 168.75 WIND DIRECTION CLASS (DEG) S WIND DIRECTION GT 168.75 AND LE 191.25 WIND DIRECTION CLASS (DEG) SSW WIND DIRECTION GT 191.25 AND LE 213 75 WIND DIRECTION CLASS (DEG) SW WIND DIRECTION GT 213 75 AND LE 236.25 WIND DIRECTION CLASS' (DEG) WSW WIND DIRECTION GT 236.25 AND LE 258.75 WIND DIRECTION CLASS (DEG) W WIND DIRECTION GT 258 75 AND LE 281.25 WIND DIRECTION CLASS (DEG) WNW WIND DIRECTION GT 281.25 AND LE 303 75 WIND DIRECTION CLASS (DEG) NW WIND DIRECTION GT 303 75 AND LE 326.25 ' WIND DIRECTION CLASS (DEG) NNW WIND DIRECTION GT 326.25 AND LE 348.75 (DEG) {WINDDIRECTIONCLASS m Wind Speed Classes WIND SPEED GE 0.0 AND LT ST* WIND SPECD CLASS (MPH) 1 2 WIND SPEED GE ST AND LE 3.5 WIND SPEED CLASS (MPH) WIND SPEED CLASS (MPH) 3 WIND SPEED GT 35 AND LE 75 4 WIND SPEED GT 75 AND LE 12 5 WIND SPEED CLASS (HPH) 5 WIND SPEED GT 12.5 AND LE' 18 5 WIND SPEED CLASS (HPH) 6 WIND SPEED GT 18.5 AND LE 24 5 WIND SPEED CLASS (MPH) 7 WIND SPEED GT 24.5 AND LE 31 5 4 WIND SPEED CLASS (MPH) (MPH) 8 WIND SPEED GT 31 5 AND LE 38 5 WIND SPEED CLASS 9 WIND SPEED GT 38.5 AND LE 46.5 WIND SPEED CLASS (MPH) 10 WIND SPEED GT 46.5 AND LE 99 8 WIND SPEED CLASS (MPH) i l
- ST: Speed Threshold Value 7.1-22
- . - _ _ _ . ~- . . _ _ - _ . _ . _ _ _ _ _ _ _ _ . . - . _ __ _ . - _ _ . . _ . - - _ . . -
p) (~
%/
(
%./
TABLE 7.1-9 AIRBORNE ISOTOPE DATA 0 0 Tissue Energy ** Isotope Decay
- Average Energy
- Linear Energy Linear Constant Per Disintegration Absorption Attenuation Absorption Coeff.
(1/hr) (Mev/ dis) in air in air 1:1
*i (1/ meter) = u - u a y EG EB (1 eter)
Kr-83m 3 79E-1 2 58E-3 3.82E-2 37 37 0 h.87 Kr-85 7.38E-6 2.23E-3 2 51E-1 50 50 0 4.87 Kr-85m 1 55E-1 1 58E-1 2 55E-1 0.0033 0.017 4.15 0.0279 Kr-87 5.45E-1 8.04E-1 1 33 0.0037 0.0092 1.49 0.0318 Kr-88 2.44E-1 1 98 3.49E-1 0.0031 0.0058 0.87 0.0259 Kr-89 1 31E+1 1.71 1 31 0.0029 0.0054 0.86 0.0251 ElKr-90 7.72E+1 1.26 1 30 0.003 0.0056 0.87 0.0254 xe-131" 2.43E-3 2.00E-2 1.42E-1 0.065 0.098 0 51 0 533 xe-133 5 51E-3 4.60E-2 1 35E-1 0.0066 0.028 3 24 0.0566 xe-1335 1 32E-2 4.15E-2 1 90E-1 0.0076 0.03 2 95 0.0574 xe-135 7.63E-2 2.48E-1 3 17E-1 0.0036 0.015 3 17 0.0305 xe-135m 2.66E40 4.31E-1 9 58E-2 0.0038 0.012 2.16 0.0326 ,, CM xe-137 1.09E+1 1.82E-1 1.78 0.0035 0.016 3 57 0.0293 85 mm Xc-138 2 93E+0 1.13 6.32E-1 0.0035 0.0075 1.14 0.0301 *5 Ar-41 3 79E-1 1.28 4.64E-1 0.0034 0.0072 1.12 0.030 g"
- Computed from data in Reference 6.8
**The Constants ( Table xxii).t) were obtained from Radiation Dosimetry, Vol. I, Attix and Roesch, editors,1958, Academic Press 60ther values from Radiological Health Handbook, Revised Edition, January 1970.
REVISION 2 AUGUST 1980 L) TABLE 7.1-10 MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENI' RAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE MPC(pC1/ml)* Kr 85 m 2E-4 85 SE-4 87 4E-5 88 9E-5 (] Ar 41 7E-5 7E-4 Xe 131 m 133 m SE-4 133 6E-4 135 m 2E-4 135 2E-4
- Computed from Equation 20 of ICRP Publication 2 (1959),
adjustedforinfinitecloudsubmegsioninwater,and R = 0.01 rem / week, p = 1.0 gm/cm , and P /P = 1.0. g t (g~~'b . 7.1-24
REVISION 2 AUGUST 1980 TABLE 7.1-11 (' LISTING OF RADIOLOGICAL DECAY CONSTANTS (Ai)A DECAY CONSTANT ISOTOPE A4(hrs-1)* H-3 6.40E-6 c-14 1 38E-8 Na-24 4,62E-2 P-32 2.02E-3 cr-51 1.04E-3 Mn-54 9 24E-5 Mn-56 2.69E-1 Fe-55 2 93E-5 Fe-59 6.47E-4 co-58 4.08E-4 co-60 1 50E-5 Ni-63 8.23E-7 Ni-65 2 75E-1 cu-64 - 5 46E-2 Zn-65 1.18E-4 zn-69 7.29E-1 Br-83 2 90E-1 Br-84 1 31Et0 ([) Br-85 Rb-86 1.45E 1 1 55E-3 Rb-88 2.34E'O Rb-89 2.74E+O sr-89 5 71E-4 sr-90 2.77E-6 sr-91 7.29E-2 sr-92 2 56E-1 Y-90 1.08E-2 Y-91M 8.36E-1 Y-91 4.94E-4 Y-92 1 96E-1 Y-93 6.86E-2 Zr-95 4.51E-4 Zr-97 4.10E-2 Nb-95 8.21E-4 Mo-99 1.05E-2 Tc-99M 1.15E-1 Tc-101 2 93E+0 RU-103 7.34E-4 Ru-105 1 56E-1 s-7.1-25
REVISION 3 NOVEMBER 1931 TABLE 7.1-11 (Cont'd) DECAY ISOTOPE CONSTA]-)* Ai(hrs Ru-106 7.84E-5 Ag-110M 1.15E-4 Te-125M 4 98E-4 Te-127M 2.65E-4 Te-127 7.41E-2 Te-129M 8.59E-4 Te-129 5 97E-1 Te-131M 2 31E-2 Te-131 1.66EFO Te-132 8.86E-3 I-130 5.61E-2 I-131 3 59E-3 I-132 3.01E-1 1-133 3 33E-2 1-134 7.90E-1 I-135 1.05E-1 Cs-134 3.83E-5 Cs-136 2.20E-] (-] Cs-137 2.62E-b v Cs-138 1.29E+0 Ba-139 5 03E-1 Ba-140 2.26E-3 Ba-141 2.28E+0 Ba-142 3.89E+0 La-140 1.72E-2 La-142 4.49E-1 Ce-141 8.88E-4 Ce-143 2.10E-2 Ce-144 1.02E-4 Pr-143 2.13E-3 Pr-144 2.41E+0 Ud-147 2.61E-3 W-187 2 90E-2 Np-239 1.23E-2 Sb-124 6.94E-4
- Ai = Radiological Decay Constant Ti = Radiological Half-life A i= (693 / Tifrcm Reference 6.8)
,- A For unlisted nuclides, see References 6.8 and 6.9.
(_)s 7.1-26
REVISION 3 l NOVEMBER 1981 TABLE 7.1-12 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (pci/kg per pCi/ liter)* ELEMENT FRESHWATER FISH H 9.0E-01 C 4.6E+03 Na 1.0E+02 P 1.0E+05 Cr ,2.0Ef02 Mn 4.0E+02 i Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 , Cu
- 5.0E401 1
Zn 2.0E403 Br .4.2E402 Rb 2.0E+03 Sr 3.0E401 Y 2.5E+01 Zr 3.3E400
. Nb 3.0E404 Mo 1.0E401 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E401 Te 4.0E+02 I 1.5E+01 Cs 2.0E403 Ba 4.0E+00 La 2.5E401 Ce 1.0E400 Pr 2.5E+01 Nd 2.5E+01 W 1.2E+03 Np 1.0E401 Ag 2.3E400**
l
- Table A-1, of Reference 6.5. ,
** S. E. Thompson, " Concentration Factors of Chemical Elements in Edible Aquatic Organisms," UCRL-50564, Revision 1, 1972.
7.1-27
O O O TABLE 7.1-13 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- BETA AIR BETA SKIN GAMMA AIR GAMMA WHOLE DOSE FACTOR DOSE FACTOR DOSE FACTOR BODY DOSE FACTOR L Ei X i i Xi-NUCLIDE ad/yr per trCi/m 3) (arem/yr per pCi/m 3) (mrad /yr per vCi/m 3 ) (mrem /yr per DCi/m3 )
Kr-83m 2.88E+02 ** -- 1.93E+01 7.56E-02 Kr-85m 1.97E+03 1.46E+03 1.23E+03 1.17E+03 Kr-85 1.95E+03 1.34E+03 1.72E+01 1.61E+01 w Kr-87 1.03E+04 9.73E+03 6.17E+03 5.92E+03 Kr-88 2.93E+03 2.37E+03 1.52E+04. 1.47E+04 m Kr-89 1.06E+04 1.01E+04 1.73E+04 1.66E+04 Kr-90 7.83E+03 7.29E+03 1.63E+04 1.56E+04 Xe-131m 1.IlE+03 4.76E+02 1.56E+02 9.15E+01 Xe-133m 1.48E+03 9.94E+02 3.27E+02 2.51E+02 Xe-133 1.05E+03 3.06E+02 3.53E+02 2.94E+02 Xe-135m 7.39E+02 7.llE+02 3.36E+03 3.12E+03 Xe-135 2.46E+03 1.86E+03 ._.92E+03 7.81E+03 Xe-137 1.27E+04 1.22EM 4 1.51E+03 1.42E+03 Xe-138 4.75E+03 4.13E+03 9.21E+03 8.83E+03 gg Ar-41 3.28E+03 2.69E+03 9.30E+03 8.84E+03 $g a e-. Gr-999*** 4.00E+03 4.00E+03 6.37E+03 3.43E+03 g@
?o n
- From Table B-1 of Refgrence 6.5.
** 2.88E+02 = 2.88 x 10 *** Farameters to assess a " gross" noble gas release, E ~ 0.8 Mev. E g~ 0.56 MeV.
REVISION 2 AUGUST 1980 k,), A o
' 8 I e
/
/
/
/
/
/ E t;
) o8 l ee
/ M i y
/ z 1
r
' w b
! O
[ i$ O / 3 w E i 3 f ' o' i i I ! I I I I I r
'~.
o q 9 9 h 9 9 w- M N -
- o o o o o e o o 6 3Wfrid NI DNINIVW3B NOl10VW3 'P d !
l FIGURE 7.1-1 PLUME DEPLETION EFFECT FOR GROUND-LEVEL RELEASES (ALL ATMOSPHERIC STABILITY CLASSES) (FROM FIGURE 2 0F REFERENCE 6.4)
t O O O l l I 1.0
% % [% STABLE 0.9 Al NEUTRAL (D) lE,F,G) am g
wa s Ds d ggg m 0.8 b6
'8m ; 0.7 b, <
=
w =a m e %3 mg2 g 2 w$m E z 06 (A,B,C) \ b' N o c= m m 4 % q A E !0.s \, \\' 3 AWB A z AE" o N k
$F$ H 0 .4
*G N P*A E 3P5 0.3 OO M0 .o' O
- 0.2 0.1 0.1 1.0 10.0 100.0 EA o<
PLUME TRAVEL DISTANCE (KILOMETERS) EG e 8"
mQb9"
>8 4 $
E L) B G, b A F, r O r g (E
, ( ( 0 0
' \ i
\ 0 1
N \
' t T L-
\
A R T
\ \
U E Nw h\E L B A )C, ) S
\N T S 8, U (A R
E T E
\ 0 M 01 L O
% I K
; (
' % E C
N A
%- T S
I D
% L E
V O w A R m, T E M U L 0 P 1 1 0 0 9 8 ' 6 s. 4 3 2 1 1 0 0 0 0 0 0 0 0 y 3a.E E 57 3e2St; $ ,m 4 O 28$ N.7w
?imgkmEm5h mgmym$ M" em ggc3 ug~Cu 2MO%
j 9OJm~ n j2ckaomQg@Qm5 v .i'I ;i1 ,' I i ;4 I il }
xGb9" 28h $ O %
\ ;
N ( 0 0 0 1
\ (,\
% \
3gT
)
D ( L A N 3E _
)
S R L R T B E U A T T )C, E N q hN S B, N U (A 0 M 0 1 E OL I
) K
% (
- N ,; 0 1
=
E C N
% G A N T
% I N S I
I A D
% ) d 4 L E
^N G, N , E V
FO R A O I T E E, N R ( L O I T E P T E LE C M BD A U A TO SN R F ( 0 1 L P 1 0 0 3 8 7- e. s. 4 3 2 1 1 g 0 0 0 0 0 0 0 0
,e, n!g u z5z5Es= z9$ku. o O
nggm ". a E* gya5z q h n
;q
_U5w g@- ggM yRchrdg8B ?r9Mmn oE* m % mm99
. s s' .
i REVISION 2 AUGUST 1980 10-3
. ()
~
10-4 _\.. g s , (
- 'j x g 's a T w \
E E i h N N l w
$ 10-5 E \ __.
W , \ m O i
\\
b) 5 P
$ \N g
10-6
- x 4
O 10-7 ! 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
,,m FIGURE 7.1-5 s
'J
'- RELATIVE DEPOSITION FOR GROUND-LEVEL RELEASES
.(ALL ATMOSPHERIC STABILITY CLASSES)
(FROM FIGURE 6 0F REFERENCE 6.4)
. m l
REVISION 2 10-3 AUGUST 1980 i
,r b,
4 t . UNSTABLE (A,B.C) es t 10-4 1 i h -/ ( e W
/ 't -
=
'g i i f EN w .
[ \\ NEUTRAL i 4
/
(I
% T T z NEU TRAL (D) \\gN
,.s
'T 9 10-5 1 Q STABLE ys ,
q r S r 7% 't g c < w' x w / / \% % \ J / f A ' t k
\_J i
e
/ / N K%
K SI , STABLE (E,F,G)
- v. ,
. u ,
l l N. i * [ '. ' O I I I_ i
]
/
b l 10-7 1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMLTERS) 1 FIGURE 7.1-6 1 n RELATIVE DEPOSITION FOR 30m RELEASES () , (LETTERS DEN 0TE PASQUILL STABILITY CLASS) (FROM FIGURE 7 0F REFERENCE 6.4)
+
f
REVISION 2 AUGUST 1980
.._.._. T_l.
~
p a w UNSTABLE (A,B,C) [ \
/ h s f %
10-5 / NEUTRAL (D) k ' l l . k I I % :_ f / N%
$ / \ ^ w UNSTABLE
$ / \ s
! NEUTRAL
's
\
B / , S 8 '0-s a
]: h 2 / /
E I l E I I Ov p 5 i u
.10-7 j
( STABLE (E,F,G)
$ l f J l . ..
I __, f 10-8 1 0.1 1.0 10.0' 100.0 200.0 PLUME TRAVEL DISTANCE (KlLOMETERS) (~] FIGURE 7.1-7 ' ~ ' RELATIVE DEPOSITION FOR 60m RELEASES (LETTERS DENOTE PASQUILL STABILITY CLASS) (FROM FIGURE 8 0F REFERENCE 6.4)
REVISION 2 AUGUST 1980 10-4 A V UNSTABLE (A,B,C) f
\N 10-5 j p -% b - l &
h [ f EUTRAL (D) xg E / / \ w N N s. g / / S / / N NT T s Q 10-6 ) ' E h .. [ E i i E I J
=
I' I O $
.a
/
y [ STABLE (E,F,G) NO DEPLETION f a10-7 ; c" I I I I l 10-8 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOME TERS) FIGURE 7.1-8 v RELATIVE DEPOSITION FOR 100m RELEASES (LETTERS DENOTE PASQUILL STABILITY CLASS) (FROM FIGURE 9 0F REFERENCE 6.4)
LA SALLE REVISION 2 AUGUST 1980 (]) LIST OF TABLES FOR SECTION 7.2 NUMBER TITLE PAGE 7.2-1 Aquatic Environment Dose Parameters 7.2-2 7.2-2 Annual Design Objectives Set by 10 CFR 50, Appendix I for Each Reactor 7.2-3
- 7.2-3 Station Characteristics 7.2-4 7.2-4 Critical Ranges 7.2-5 7.2-5 Terrain Correction Fm; tors (h ) 7.2-6 t ,
7.2-6 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary 7.2-7 7.2-7 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles 7.2-9 7.2-8 Maximum Offsite Finite Plume Gamma Dose Factors For Selected Nuclides 7.2-10 O l l l l 7.2-1
t i i LA SALLE REVISION 3 NOVEMBER 1981 O LISP OF FIGURES FOR SECTION 7.2 NUMBER TITLE 7.2-1 Unrestricted Area Boundary j O 1 i j
- 4 4
O 7.2-11 i
..--,__,-.__---.-._._,..,.-.__.~.,--.-_-.m..-,--m__._ . _ _ _ _ _ . . - _ _ . - . . . _ _ , _ _ - _ _ , , - . _ . - . . . _ _ , - . _ , _ , - . -
LA SALLE REVISION 2
- AUGUST 1980~
~
7.2 DATA SPECIFIC TO EACH STATION This section contains site descriptions and data (particularly meteorological data) that is relevant only to a specific site. [ 1 I i e O . $~ I I f O 7.2-1 i
4 LA SALLE REVISION 2 AUGUST 1980 {} TABLE 7.2-1 AQUATIC ENVIRONMENT DOSE PARAMETERS PARAMETER LA SALLE U", water usage, liters /hr 0.042
~4 U , fish consumption, kg/hr 2.4 x 10 1/M" 1 I 1 1/M l
F", ft /sec 1.37 x'10 4 Ff, ft /sec 1.37 x 10 f 24 t, hr* t", hr** 97 B. 1
- Regulatory Guide 1.109, Revision 1, October 1977, Table A-1, Column 2 for freshwater fish. See Table 7.1-12.
() F , ft /sec F", ft /sec 1/M" Not Applicable. No outdoor tanks y without overflow pipes connected t ther storage tanks. t", hr t V, gal tg,hr s
*t (hr) = 24 hr (all stations) for the fish ingestion pathway
**t" (hr) = 97 hr (distance to Peoria is 97 miles; flow rate of 1 mph assumed) 7.2-2
LA SALLE REVISION 2 AUGUST 1980 0 TABLE 7.2-2 ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, APPENDIX I FOR EACH REACTOR TYPE OF DOSE ANNUAL DESIGN OBJECTIVES Airborne Releases Gamma Air Dose 10 mrad Beta Air Dose 20 mrad Whole Body Dose 5 mrem Skin Dose 15 mrem Infant Thyroid Dose 15 mrem Liquid Releases l Whole Body Dose 3 mrem Thyroid Dose 10 mrem Bone Dose 10 mrem L Skin Dose 10 mrem l l 7.2-3
. . - , - . - . . - . . . . - . . - ~ . . . . . . - , - . . . - - - - . . . - - . . _ . - - . - . . _ - - - . , - - - - - - . - - . . - . - - . - .
LA SALLE REVISION 3-NOVEMBER 1981 TABLI: 7.2 ' O stati0s: te Se11e LOCATION: 6 miles south of Marseilles, Illinois - La' Salle County CHARACTERISTICS 0F ELEVATED RELEASE POINT
- - 1)-Release Height = 112.8 m 2) Diameter = 5.6 m
- 2) Exit Speed 18.3 -1 1.1E4 KCal s-I
= ms 4) Heat Content =
J CHARACTERISTICS OF VENT STACK RELEASE POINT (NA) j 1) Release Height = m 2) Diameter = m
- 3) Exit Speed = ms-1 i
O CHARACTERISTICS OF GROUND LEVEL RELEASE (NA)
- 1) Release Height = 0 m
- 2) Building Factor (D) = 56 m i
j- .i METEOROLOGICAL DATA I A 400 ft. Tower is Located 300 m SSW of elevated release point Tower Data Used in Calculations Release Point Wind Speed and Differential Direction Temperature Elevated 375 ft 375-33 ft i O- vent (NA) (NA) 33 ft 200-33 ft . Ground t i 7.2-4
7,- g SALLE REVISION 2 AUGUST 1980 0 TABLE 7.2-4 CRITICAL RANGES Direction Site Nearest Nearest Dairg Fam Boundary' ~ Resident Range'- (m) (m)' (m) N 1022 6155 NNE -1330 2253 NE 2408 3058. ENE 4450 5311 E' 1996 5150 '8047 ESE 838 2948 SE 884 2736 SSE 838 4506 S 829 966 SSW 829 2736 SW 610 1609 WSW 509 1448 W 509 1448 WNW- 625 1448 NW 732 2736 NNW 848 2414
*Within 5 miles 7.2-5
LA SALLE REVISION 2 AUGUST 1980 0)1 TABLE 7.2-5 TERRAIN CORRECTION FACTORS (h )* (ht = 0 to Stated Range, Then ht = Given Value) DIRECTION RANGE _ ht, I
- O N
- 0 HNE
- O NE
- O
> ENE
- O E
- 0 SE
- 0 SSE um O S s.5 m1
- 0 SSW l.5 mi 17m SW 1.0 mi 17m WSW 1.0 mi 17m W
i 1.0 mi 17m WNN 2.75 mi 17m UW 0 Nhv
- Within 10 miles O
7.2-6
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' TABLE 7.2-6 x/O AND D/O MAXIMA AT OR BEYOND THE UNRESTRICTED AREA BOUNDARY 00WNWIND ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION RADIUS x/O+ RADIUS D/O A RADIUS X/ O+ D/0 6 RADIUS X/O + D/O A (METERS) (SEC/M**3) (METERS) (1/M**2) (METERS) (SEC/M**3) (1/M**2) (METERS) (SEC/M**3) (1/M**2) l N 2800. 2.552-08 1022. 9.928-10 1022. 1.179-07 2.654-09 1022. 9.073-07 1.190-08 NNE 3000. 2.446-08 1330. 8.077-10 1330. 8.105-08 1.786-09 1330. 6.512-07 7.358-09 p
-J NE 2600. 2.420-08 2408. 4.660-10 2408. 4.772-08 7.377-10 2408. 2.444-07 2.349-09 >
ENE 4450. 2.374-08 4450. 2.845-10 4450. 3.055-08 3.566-10 4450. 9.947-08 8.018-10 E 2800. 3.322-08 1996. 8.853-10 1996. 6.215-08 1.328-09 1996. 3.575-07 3.941-09 h) ESE 2800. 3.199-08 838. 1.107-09 838. 1.522-07 3.538-09 838. 1.267-06 1.708-08 t"
-a 2.005-09 884. 8.673-07 1.052-08 td SE 2800. 2.207-08 884. 6.366-10 884. 9.527-08 1000. 4.681-10 838. 7.312-08 1.506-09 838. 9.195-07 8.921-09 td SSE 3000. 2.234-08 S 2600. 2.248-08 829. 5.442-10 829. 6.32E-08 1.272-09 829. 7.524-07 7.582-09 SSW 2800. 2.775-08 829. 7.249-10 829. 5.667-08 1.355-09 829. 9.809-07 7.715-09 SW 2600. 2.486-08 610 9.944-10 610. 9.495-08 2.336-09 610. 1.403-06 1.372-08 WSW 2800. 1.986-08 509, 8.853-10 509. 1.144-07 2.673-09 509. 1.345-06 1.643-08 W 509, 1.751-08 509. 8.196-10 509. 1.255-07 2.657-09 509. 1.459-06 1.573-08 WNW 2800. 1.404-08 625. 4.956-10 625. 9.074-08 1.777-09 625. 9.893-07 1.102-08 NW 3000. 2.156-08 732. 5.425-10 732. 9.384-08 1.901-09 732. 1.247-06 1.128-08 NNW 3000. 1.856-08 848. 7.826-10 848. 9.261-08 2.129-09 848. 9.930-07 1.048-08 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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I i REVISION 2 s LA SALLE AUGUST 1980
- ,e s j N]
i TABLE 7.2-6 (Cont'd) l LA SALLE COUNTY 1&2 J i AVERAGE WIND SPEED FOR EACH RELEASE MODE , 4 i l 4 ,' Downwind _ Wind Speed (m/sec) ; i Direction Elevated Release N 8.2 j NNE 8.2
- NE 7.9 i
l ENE 7.7 i E 8.0
<~
f j ESE 8.2 i SE 7.5 l SSE 6.8 S 6.1 SSW 5.5 SW 6.1 WSW 6.6 W 6.9 WNW 6.9 NW 7.1 NNW 7.7 (")h 7.2-8
-- . _ . ~_._ . _ _ _ . _ . _ .
() V Q) (.. U l l i l TABLE 7.2-7 1 D/O AT THE NEAREST MILK COW AND MEAT ANIMAL LOCATIONS WITHIN 5 MILES DOWNWIND NEARESr MILK COW D/O(1/M**2) NEAREST MEAT ANIMAL D/O(1/M**2) DIRECTION RADIUS ELEVATED mixed GROUND RADIUS ELEVATED MIXED GROUND (METERS) RELEASE RELEASE RELEASE (METERS's RELEASE RELEASE RELEASE N 8047. 1.244-10 1.566-10 3.299-10 2253. 6.165-10 9.949-10 3.075-09 NNE 8047. 1.133-10 1.454-10 3.196-10 2275. 5.751-10 9.306-10 2.929-09 NE 8047 9.414-11 1.223-10 2.813-10 3219. 3.389-10 4.954-10 1.414-09 ENE 8047, 1.192-10 1.419-10 2.0s7-10 4506. 2.803-10 3.506-10 7.847-10 M
%J E 8047. 1.633-10 1.891-10 3.419-10 5150. 3.241-10 3.863-10 7.539-10 >
- ESE 8047. 1.603-10 1.885 *0 3.445-10 4345. 3.896-10 4.864-10 1.022-09 N SE 8047. 1.018-10 1.195-10 2.309-10 4345. 2.470-10 3.071-10 6.851-10 U2 yh SSE 8047. 9.2O3-11 1.026-10 1.799-10 5472. 1.663-10 1.891-10 3.557-10 h5 S 8047. 8.057-11 8.809-11 1.503-10 2575. 3.381-10 4.188-10 1.108-09 t1 SSW 8047. 8.487-11 9.057-11 1.529-10 2897. 3.325-10 3.836-10 9.167-10 D1 SW 8047. 9.830-11 1.050-10 1.669-10 1287. 6.657-10 1.024-09 4.064-09 WSW 8047. 7.451-11 8.355-11 1.498-10 1448. 4.907-10 7.794-10 2.984-09 W 8047. 5.574-11 6.705-11 1.435-10 1770. 3.618-10 5.698-10 2.030-09 WFJW 8047. 5.588-11 6.623-11 1.393-10 1609. 3.171-10 5.624-10 2.318-09 NW B047. 7.190-11 8.684-11 1.834-10 1609. 3.896-10 7.292-10 3.051-09 NNW 8047. 8.559-11 1.041-10 2.153-10 1287. 5.964-10 1.243-09 5.242-09 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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TABLE 7.2-8 LASALLE COUNTY 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 83M MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE G8AR S8AR RADIUS V V8AR RADIUS G DIRECTION AREA BOUND RADIUS S (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) 1022. 1022. 2.556-06 2.308-07 1022. 1.388-05 1.253-06 1022. 9.844-05 8.889-06 e N 1330. 2.373-06 2.143-07 1330. 9.525-06 8.601-07 1330. 6.766-05 6.109-06 > %J NNE 1330. 2408. 2.489-05 2.248-06 2408. 2408. 2.265-06 2.045-07 2408. 4.842-06 4.372-07
- NE 8.937-06 8.070-07
# ENE 4450. 4450. 2.038-06 1.841-07 4450, 2.754-06 2.486-07 4450. h) 2.931-07 1996. 6.632-06 5.988-07 1996. 3.579-05 3.232-06 p E 1996. 1996. 3.246-06 1.240-05 td ps 2.740-07 838. 1.808-05 1.633-Di 838. 1.373-04 c) ESE 838. 838. 3.035-06 8.553-06 M 884. 1.965-06 1.775-07 884. 1.136-05 1.026-G3 884. 9.472-05 SE 884. 9.610-05 8.678-06 838. 1.627-06 1.470-07 838. 8.950-06 8.082-07 838.
SSE 838. 829. 8.048-05 7.268-06 829. 2.319-06 2.094-07 829. 7.535-06 6.804-07 S 829. 829. 1.004-04 9.065-06 829. 829. 2.392-06 2.160-07 829. 7.049-06 6.365-07 SSW 1.023-06 610. 1.517-04 1.370-05 SW 610. 610. 2.563-06 2.314-07 610. 1.132-05 2.081-07 509. 1.386-05 1.252-06 509. 1.542-04 5.'92-05 WSW 509. 509. 2.305-06 1.624-04 1.466-05 509. 2.369-06 2.140-07 509. 1.484-05 1.340-06 509. W 509. 1.100-04 9.937-06 WNW 625. 625. 1.799-06 1.625-07 625. 1.073-05 9.686-07 625. 732. 1.133-05 1.023-06 732. 1.320-04 1.192-05 NW 732. 731. 1.691-06 1.527-07 9.466-06 NNW 848. 848. 1.968-06 1.777-07 848. 1.108-05 1.000-06 848. 1.048-04 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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O m ( V i b td - i TABLE 7.2-8 (Cont'd) LASALLE COUNTY 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85M 1 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 1.438-04 7.665-05 1022. 1.940-04 1.022-04 1022. 5.816-04 2.999-04 M
,a
. NNE 1330. 1330. 1.145-04 6.100-05 1330. 1.473-04 7.775-05 1330. 4.292-04 2.217-04 >
bJ NE 2408. 2408. 6.027-05 3.197-05 2408. 7.299-05 3.849-05 2408. 1.787-04 9.267-05 4 1 ENE 4450. 4450. 3.374-05 1.780-05 445C. 3.794-05 1.996-05 4450. 7.695-05 4.007-05 h! E 1996. 1996. 8.722-05 4.628-05 1996. 1.047-04 5.527-05 1996. 2.617-04 1.358-04 tg fj 8.036-04 4.141-04 t4 ESE 838. 838. 1.915-04 1.021-04 838. 2.585-04 1.363-04 838. D2
- ' SE 884. 884. 1.292-04 6.887-05 884. 1.708-04 9.010-05 884. 5.459-04 2.812-04 SSE 838. 838. 1.299-04 6.933-05 838. 1.628-04 8.607-05 838 5.638-04 2.904-04 S 829. 829. 1.221-04 6.507-05 829. 1.456-04 7.705-05 829. 4.859-04 2.507-04 SSW 829. 829. 1.514-04 8.070-05 829. 1.730-04 9.176-05 829. 6.214-04 3.205-04 SW 610. 610. 1.875-04 1.000-04 610. 2.264-04 1.198-04 610. 8.484-04 4.363-04 1 WSW 509. 509. 1.723-04 9.191-05 509. 2.204-04 1.164-04 509. 8.171-04 4.196-04 W 509. 509. 1.682-04 8.973-05 509. 2.181-04 1.150-04 509. 8.254-04 4.230-04 l WNW 625. 625. 1.246-04 6.647-05 625. 1.616-04 8.527-05 625. 5.801-04 2.978-04 I NW 732.. 732. 1,572-04 8.391-05 732. 1.976-04 1.044-04 732. 7.297-04 3.750-04
- NNW 848. 848. 1.327-04 7.076-05 848. 1.720-04 9.078-05 848. 5.865-04 3.015-04 l
LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375. FT LFVEL I
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i ? (3 G3 w (~')' w. 1 l l l l l l l TABLE 7.2-8 (Cont'd) LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85 MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE G GBAR S 58AR RADIUS V VBAR RADIUS DIRECTION AREA BOUND RADIUS (METERS) (METERS) (MRAD /YP)/(UCI/SEC) (METERS) (MR AD/,Vp )/(UCI/SEC ) (METERS) (MRAD /YR)/(UCI/SEC) 1022. 2.390-06 1.479-06 1022, 6.395-06 3.958 f.164-06 N NNE 1022. 1330. 1022. 1330, 1.881-06 1.511-06 9.355-07 1330. 1.846-06 1.143-06 1330. 4.827-06 2.988-06 1.266-06 h.
-J 4.982-07 2408. 9.347-07 5.786-07 2408. 2.045-06
- NE 2408. 2408. 8.049-07 5.870-07 U3 b# 4450. 4.736-07 2.931-07 4450. 5.161-07 3.195-07 4450. 9.484-07 ENE 4450. 1996. 2.993-06 1.853-06 1996. 1996. 1.162-06 7.193-07 1996. 1.339-06 8.288-07 f$
, E 1.974-06 838. 8.870-06 5.491-06 t<
i ESE 838. 838. 2.505-06 1.550-06 838. 3.189-06 3.703-06 M b) 884. 884. 1.684-06 1.043-06 884. 2.109-06 1.305-06 884. 5.982-06 SE 1.270-06 838. 6.290-06 3.894-06 838, 838. 1.716-06 1.062-06 838. 2.052-06 SSE 5.385-06 3.333-06 S 829. 829. 1.597-06 9.885-07 829. 1.837-06 1.137-06 829. 829. 2.23,6-06 1.384-06 829. 7.013-06 4.341-06 SSW 829. 829. 2.014-06 f.247-06 2.472-06 1.530-06 610. 2.866-06 '1.774-06 610. 9.339-06 5.781-06 SW 610. 610. 5.490-06 1.395-06 509, 2.742-06 1.697-06 509. 8.869-06 WSW 509. 509. 2.254-06 8.993-06 5.567-06 W 509. 509. 2.212-06 1.369-06 509. 2.719-06 1.683-06 509. 1.239-06 625. 6.313-06 3.908-06 WNW 625. 625. f.625-06 1.006-06 625. 2.002-06 8.111-06 5.021-06 NW 732. 732. 2.084-06 1.290-06 732. 2.496-06 1.545-06 732. 2.148-06 1.330-06 848. 6.504-06 4.026-06 NNW 848. 848. 1.747-06 1.081-06 848. LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL is<= CH V) U)
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'rABLE 7. 2-8 (Cont'd)
LASALLE COUNTY 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 87 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA 80UNO RADIUS S 584R RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 6.081-04 4.444-04 1022. 7.471-04 5.442-04 1022. 1.780-03 1.285-03 t1
-J NNE 1330. 1330. 4.687-04 3.424-04 1330. 5.593-04 4.074-04 1330. 1.287-03 9.295-04 38 NE 2408. 2408, 2.356-04 1.720-04 2408. 2.700-04 1.966-04 2408, 5.395-04 3.899-04 ENE 4450. 4450. 1.236-04 9.011-05 4450. 1.344-04 9.784-05 4450. 2.247-04 1.626-04 h0 pa E 1996. 1996. 3.445-04 2.514-04 1996. 3.916-04 2.853-04 1996. 7.848-04 5.673-04 t*
La ESE 838. 838, 8.102-04 5.923-04 838. 9.967-04 7.261-04 838. 2.451-03 1.769-03 t*
-1.212-03 U2 SE 884 884 5.514-04 4.031-04 884. 6.671-04 .4.861-04 884. 1.679-03 SSE 838. 838. 5.399-04 3.947-04 838, 6.312-04 4.602 04 838. 1.672-03 1.207-03 5 829. 829, 5.106-04 3.732-04 829, 5.758-04 4.200-04 829. 1.484-03 1.071-03 SSW 829. 829. 6.131-04 4.481-04 829. 6.730-04 4.911 829. 1.813-03 1.308-03 SW 610. 610. 7.946-04 5.809-04 610. 9.027-04 6.584-04 '610. 2.543-03 1.836-03 7.514-04 5.494-04 -509. 8.860-04' 6.460-04 509, 2.511-03 1.813-03 WSW 509. 509.
W 509. 509. 7.274-04 5.319-04 509. 8.676-04 6.326-04 509. 2.510-03 1.811-03 WNW 625. 625, 5.393-04 '3.944-04 625. 6.429-04 4.687-04 625, 1.784-03 1.288-03 NW 732. 732. 6.563-04 4.799-04 732. 7.693-04 5.610-04 732. 2.157-03 1.557-03 NNW 848. 848. 5.580-04 4.080-04 849 6.677-04 4.867-04 848. 1.754-03 1.266-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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TABLE 7.2-8 (Cont'd) LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 88 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL REtFARF DIRECTICN AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) .(METERS) (MRAD /VR)/(UC1/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 1.526-03 1.177-03 1022. 1.841-03' 1.415-03 1022. 4.243-03 3.229-03 NNE 1330. 1330. 1.193-03 9.205-04 1330. 1.399-03 1.076-03 1330. 3.130-03 2.383-03 h) %J
- NE 2408. 2408. 6.086-04 4.690-04 2408. 6.873-0J 5.285 D4 2408. 1.328-03 1.013-03 3.544-04 2.725-04 4450. 5.809-04 4.437-04 01 h3 ENE 4450. 4450. 3.292-04 2.534-04 4450.
1.476-03 ># 1 E 1996. 1996. 8.846-04 6.817-04 1996. 9.921-04 7.6?O-04 1996. 1.936-03 $( ESE 838. 838, 2.040-03 1.574-03 838. 2.461-03 1.832-03 838. 5.843-03 4.446-03 h SE 884. 884, 1.379-03 1.064-03 884. 1.641-03 1.262-03 884 3.977-03 3.025-03 M' SSE 838. 838. 1.381-03 1.066-03 838. 1.587-03 1.221-03 838. 4.061-03 3.090-03 S 829. 829. 1.291-03 9.963-04 829. 1.439-03 1.107-03 829. 3.546-03 2.699-03 SSW 829. 829. 1.592-03 1.228-03 829. 1.727-03 1.330-03 829. 4.469-03' 3.401-03 SW 610, 610. 2.000-03 1.550-03 610. 2.252-03 1.734-03 610. 6.116-03 4.651-03 WSW 509. 509. 1.868-03 1.442-03 503. 2.173-03 1.672-03 509. 5.919-03 4.500-03 W 509. 509. 1.823-03 1.407-03 509. 2.140-03 1.646-03 509. 5.961-03 4.530-03 WNW 625, 629 1.344-03 1.038-03 625. 1.579-03 1.214-03 625. 4.210-03 3.201-03 NW 732. 732. 1.682-03 1.299-03 732. 1.938-03 1.491-03 732. 5.239-03 3.983-03 NNW 848, 848. 1.417-03 1.093-03 848. 1.664-03 1.260-03 848, 4.237-03 3.223-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
' 38 8<:
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k-m TABLE 7.2-8 (Cont'd) LASALLE COUNTY 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KQ 89 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022, 6.786-04 5.005-04 1022. 8.728-04 6.410-04 1022. 1.992-03 1.450-03 p %J NNE 1330. 1330. 4.270-04 3.149-04 1330, 5.392-04 3.960-04 1330. 1.170-03 8.519-04 7 NE 2408. 2408. 1.232-04 9.078-05 2408, 1.504-04 1.105-04 2408. 2.940-04 2.142-04 " EJ 4450. 4450. 2.630-05 1.935-05 4450, 2.999-05 2.202-05 4450. 4.808-05 3.510-05 ENE [. Ln E ESE 1996. 838. 1996, 838. 2.265-04 9.713-04 1.669-04 7.165-04 1996. 838. 2.703-04 1.250-03 1.985-04 9.180-04 1996. 838, 5.104-04 2.915-03 3.720-04 2.123-03 h td 884. 6.310-04 4.655-04 884. 7.964-04 5.851-04 884. 1.910-03 1.390-03 U3 SE 884. SSE 838. 838. 5.533-04 4.082-04 838. 6.826-04 5.017-04 838. 1.665-03 1.212-03 S 829. 829. 4.984-04 3.676-04 829. 5.891-04 4.332-04 829. 1.462-03 1.064-03 SSW 829. 829. 5.179-04 3.820-04 829. 5.982-04 4.400-04 829. 1.478-03 1.076-03 SW 610. 610. 8.875-04 6.547-04 610. 1.055-03 7.756-04 610. 2.731-03 1.989-03 WSW 509. 509. 9.934-04 7.330-04 509. 1.215-03 8.937-04 509. 3.258-03 2.372-03 W 509. 509. 9.133-04 6.739-04 509. 1.147-03 8.434-04 509. 3.113-03 2.266-03 WNW 625. 625. 6.671-04 4.923-04 625. 8.308-04 6.107-04 625. 2.201 1.602-03 NW 732. 732. 6.690-04 4.936-04 732. 8.424-04 6.151-04 732. 2.157-03 1.570-03 NNW 848. 848. 6.055-04 4.467-04 848. 7.674-04 5.638-04 848. 1.843-03 1.342-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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TABLE 7.2-8 (Cont'd) LASALLE COUNTY 182 _HAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 90 MIXED MODEfVENT) RELEASE GROUND LEVEL RELEASE.- DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE RADIUS G GBAR S SBAR RADIUS V VBAR OIRECTION AREA BOUNO RADIUS 6 (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) 9.601-05 1022. 3.031-04 2.138-04 1022. 1022. 9.738-05 6.981-05 1022. 1.348-04 N 2.527-05 1330. 4.800-05 3.419-05 1330. 1.036-04 7.307-05 h)
-J NNE 1330. 1300. 3.526-05 1.437-06 3.976-06 2.808-06
- 2408. 2408. 1.552-06 1.112-06 2408. 2.017-06 2408.
1.473-08 03 g, NE 4450. 1.299-08 9.260-09 4450. 2.081-08 1.111-08 7.939-09 g ENE 4450. 1996. 4450. 1996. 5.791-06 4.144-06 1996. 7.210-06 5.137-06 1996. 1.332-05 6.073-04 9.416-06 4.284-04 f[ Fa E 1.961-04 1.406-04 838. 2.685-04 1.913-04 838. e. 04 ESE 838. 838. 3.078-04 2.171-04 b2 884. 9.875-05 7.080-05 884. 1.340-04 9.549-05 884. SE 884. 838. 1.073-04 7.649-05 838. 2.496-04 1.760-04 SSE 838. 838. 8.074-05 5.789-05 5.446-05 829. 1.775-04 1.252-04 5.836-05 4.104-05 829. 7.640-05 S 829. 829. 829. 6.493-05 4.631-05 829. 1.480-04 1.045-04 SSW 829. 829. 5.203-05 3.729-05 1.597-04 610. 5.466-04 3.855-04 610. 1.724-04 1.236-04 610. 2.240-04 SW 610. 509. 3.623-04 2.583-04 509. 9.256-04 6.526-04 WSW 509. 509. 2.701-04 1.937-04. 9.490-04 6.690-04 509. 509. 2.640-04 1.893-04 509. 3.658-04 2.607-04 509. 3.592-04 W 2.021-04 1.440-04 625. 5.095-04 625. 1.462-04 1.048-04 625. WNW 625. 732. 1.787-04 1.273-04 732. 4.373-04 3.083-04 NW .732. 732. 1.258-04 9.097-05 1.035-04 848. 3.368-04 2.376-04 848. 848. 1.049-04 7.523-05 848. 1.453-04 NNW LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
>N b54 c: U)
U) g H O ldZ W CD PJ O s
Ov 3 (v' TABLE 7.2-8 (Cont'd) LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE131M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 5.171-06 1.843-06 1022. 1.506-05 3.184-06 1022. 9.205-05 1.366-05 p' 'T NNE 1330. 1330. 1330. 4.426-06 1.509-06 1.072-05 2.371-06 1330. 6.609-05 9.985-06 7 h) NE 2408. 2408. 3.332-06 8.918-07 2408. 5.649-06 1.216-06 2408. 2.488-05 3.942-06
- ENE 4450. 4450. 2.663-06 5.844-07 4450, 3.338-06 6.840-07 4450. 1.011-05 1.694-06 n) 1996. 1996.
y, Fs E 4.682-06 1.274-06 1996. 7.730-06 1.708-06 1996. 3.641-05 5.777-06 ts - 'J ESE 838. 838. 6.599-06 2.431-06 1.972-05 838. 4.214-06 838. 1.286-04 1.900-05 t* SE 884. 884. 4.388-06 1.629-06 884 1.259-05 2.741-06 884 8.763-05 1.291-05 D3 SSE 838. 838. 4.146-06 1.632-06 838. 1.055-05 2.503-06 832. 9.261-05 1.361-05 S 829. 829. 4.589-06 1.587-06 829, 9.154-06 2.209-06 829. 7.573-05 1.132-05 SSW 829. 829. 5.308-06 .1.957-06 829. 9.403-06 2.520-06 829. 9.912-05 1.479-05 SW 610. 610. 6.104-06 2.351-06 610. 1.374-05 3.387-06 610. 1.430-04 2.073-05 WSW 509. 509, 5.500-06 2.134-06 509. 1.548-05 3.462-06 509. 1.401-04 2.007-05 W 509. 509. 5.506-C6 2.103-06 509. 1.623-05 3.512-06 509. 1.483-04 2.090-05 WNW 625. 625. 4.112-06 1.557-06 625, 1.183-05 2.582-06 625. 1.001-04 1.431-05 NW 732. 732. 4.795-06 1.955-06 732. 1.314-05 3.067-06 732. 1.258-04 1.812-05 NNW 848. 848. 4.456-06 1.680-06 848. 1.238-05 2.745-06 848. 9.977-05 1.443-05 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
> :n c b1 O<
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O O O TABLE 7.2-8 (Cont'd) LASALLE COUNTY'1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAt;fYR)/(UCI/SEC)
-N 1022. 1022. 2.274-05 1.121-05 1002. 3.868-05 1.563-05 1022. 1.631-04 5.029-05 M. -J NNE 1330. 1330. 1.857-05 9.044-06 1330. 2.883-05 1.192-05 1330. 1.192-04 3.744-05 >
[, 1.089-05 4.904-06 6.017-06 4.715-05 1.550-05 ' NE 2408. 2408. 2408. 1.475-05 2408. g)
;- ENE 4450. 4450. 7.061-06 2.909-06 4450. 8.249-OG 3.274-06 4450. 2.021-05 6.943-06 p Fa E 1996. 1996. 1.557-05 7.054-06 1996. 2.074-05 8.576-06 1996. 6.908-05 2.276-05 td l 03 ESE 838. 838. 3.001-05 .1.491-05 838. 5.121-05 2.080-05 838. 2.268-04 6.963-05 b4 884. 884 2.011-05 1.021-05 884. 3.334-05 1.368-05 884. 1.541-04 4.713-05 M i SE 838. 3.052-05 1.306-05 838. 1.622-04 4.948-05 l SSE 838. 838. 2.016-05 1.016-05 S 829. 829. 1.955-05 9.659-06 829. 2.695 1.162-05 829. 1.352-04 4.198-05 SSW 829. 829. 2.412 1.199-05 829. 3.083-05 1.388-05 829. 1.764-04 5.471-05 SW 610. 610, 2.904-05 1.459-05 610. 4.136-05 1.801-05 610. 2.470-04 .7.424-05 WSW 509. EO9. 2.639-05 1.328-05 509. 4.216 05 1.754-05 509. 2.392-04 7.096-05 W 509. 509. 2.598-05 1.302-05 509, 4.271-05 1.747-05 509. 2.488-04 7.242-05 WNW 625. 625. 1.924-05 9.626-06 625. .3.141-05 1.291-05 625. 1.706-04 5.046-05 NW 732. 732. 2.417-05 1.230-05 732. 3.738-05 1.588-05 732. 2.158-04 6.441-05 l NNW 848. 848. 2.074-05 1.036-05 848. 3.340-05 1.384-05 848. 1.719-04 5.155-05 LASALLE SITE METEOROLOGICAL OATA 10/1/76 - 9/30/78 375 FT LEVEL 1
> #3 C CG C1 *O cH t/) 01
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i TABLE 7.2-8 (Cont'd) I } LASALLE COUNTY 1A2 i 1 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133 DOWNWIND RESTRICTED ELEVATED (STACM) RELEASE _ MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA 800ND RADIUS S 58AR RADIUS V V8AR RADIUS G G8AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 2.329-05 9.006-06 1022. 4.138-05 1.403-05 1022. 1.830-04 5.346-05 tv I 4 NNd 1330. 1330. 1.928-05 7.397-06 1330. 3.098-05 1.067-05 1330. 1.345-04 3.978-05 l> NE 2408. 2408. 1.163-05 4.236-06 2408. 1.607-05 5.502-06 2408. 5.352-05 1.<327-05 g y ENE 4450. 4450. 7.840-06 2.709-06 4450. 9.213-06 3.114-06 4450. 2.308-05 7.199-06 4 Fa E 1996. 1996. 1.666-05 6.095-06 1996. 2.263-05 7.818-06 1996. 7.857-05 2.392-05 p I W ESE 838. 838. 3.074-05 1.196-05 838. 5.482-05 1.865-05 838, 2.545-04 7.416-05 t* SE 884. 884. 2.058-05 8.019-06 884. 3.559-05 1.218-05 884. 1.725-04 5.012-05 M SSE 838. 838. 2.048-05 8.058-06 838. 3.228-05 1.134-05 838. 1.819-04 5.277-05 S 829. 829. 2.020-05 7.770-06 829. 2.862-05 1.012-05 829. 1.522-04 4.469-05 ? SSW 829. 829. 2.474-05 9.629-06 829. 3.242-05 1.179-05 829, 1.988-04 5.834-05 1 SW 610. 610. 2.946-05 1.155-05 610. 4.342-05 1.542-05 610. 2.754-04 7.909-05 WSW 509. 509. 2.678-05 1.051-05 509. 4.443-05 1.531-05 509. 2.653-04 7.546-05 W 509. 509. 2.635-05 1.032-05 509. 4.493-05 1.530-05 509. 2.741-04 7.694-05 I WNW 625. 625. 1.947-05 7.609-06 625. 3.312-05 1.132-05 625. 1.892-04 5.375-05 NW 732. 732. 2.432-05 9.621-06 732. 3.916-05 1.367-05 732. 2.405-04 6.878-05
! NNW 848. 848. 2.110-05 8.241-06 848. 3.539-05 1.217-05 848. 1.914-04 5.484-05 I
I LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL t i > C 3 O t CH-in tn
- f. >g m 4 FO W
2: CD PJ C3
O O O 4 i TABLE 7.2-8 (Cont'd) 1 LASALLE COUNTY 1&2 1 MAXIMUM OFFSITE FINITE PLUME GAMMA DdSE FACTORS FOR XE135M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S 58AR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) i N 1022. 1022. 2.872-04 1.776-04 1022. 3.782-04 2.328-04 1022, 9.935-04 6.065-04 ld NNE 1330. 1330. 2.117-04 1.309-04 1330. 2.699-04 1.662-04 1330. 6.753-04 4.127-04 h I hJ NF 2408. 2408. 9.614-05 5.948-05 2408. 1.167-04 7.184-05 2408. 2.562-04 1.568-04 U1
- I ENE 4450. 4450. 4.210-05 2.595-05 4450. 4.754-05 2.926-05 4450. 8.430-05 5.167-05
- h3 E 1996, 1996. 1.482-04 9.149-05 1996. 1.769-04 1.090-04 1996. 3.829-04 2.344-04 h$
- CD ESE 838. 838. 3.805-04 2.353-04 838. 5.045-04 3.106-04 838. 1.368-03 8.351-04 t1
- SE 884. 884. 2.620-04 1.620-04 884. 3.381-04 2.083-04 884 9.497-04 5.797-04 D2 l SSE 838, 838. 2.387-04 1.476-04 838. 2.S89-04 1.842-04 838. 8.694-04 5.307-04 S 829. 829. 2.309-04 1.427-04 829. 2.738-04 1.688-04 829. 8.031-04 4.904-04 SSW 829. 829. 2.540-04 1.570-04 829. 2.932-04 1.808-04 829. 8.790-04 5.369-04 SW 610. 610. 3.613-04 2.234-04 610. 4.333-04 2.672-04 610. 1.351-03 8.241-04 WSW 509. 509. 3.643-04 2.253-04 509. 4.548-04 2.802-04 509. 1.449-03 8.833-04 W 509. 509. 3.415-04 2.112-04 509. 4.358-04 2.683-04 509. 1.404-03 8.555-04
; WNW 625, 625. 2.592-04 1.603-04 625. 3.283-04 2.022-04 625. 1.024-03 6.244-04 NW 732. 732. 2.854-04 1.765-04 732. 3.606-04 2.222-04 732. 1.112-03 6.783-04 NNW 848, 848. 2.537-04 1.569-04 848. 3.263-04 2.009-04 848. 9.335-04 5.696-04 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL 38 to C3 DG C) <G C: >4 U1 tn
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(,/ f% d 4 9 0 4 TABLE 7.2-8 (Cont'd) l LASALLE COUNTY 1&2 1 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE135 1 1 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA 80UND RADIUS 5 5BAR RADIUS V VBAR RADIUS G G8AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 2.028-04 1.097-04 1022. 2.692-04 1.452-04 1022. 7.871-04 4.222-04 M
-J NNE 1330. 1330. 1.624-04 8.780-05 1330. 2.059-04 1.111-04 1330. 5.865-04 3.148-04 >
NE 2408. 2408. B.581-05 4.637-05 2408. 1.028-04 5.545-05 2408. 2.161-04 1.322-04 ENE 4450. 4450. 4.879-05 2.634-05 4450. 5.445-05 2.937-05 4450. 1.092-04 5.869-05 h) ha E 1996. 1996. 1.239-04 6.697-05 1996. 1.473-04 7.949-05 1996. 3.610-04 1.939-04 t1 - Ed ESE 838. 838. 2.703-04 1.462-04 838. 3.589-04 1.936-04 838. 1.088-03 5.835-04 t1 i SE 884. 884. 1.819-04 9.840-05 884 2.370-04 1.279-04 884. 7.367-04 3.951-04 DU
- SSE 838. 838. 1.843-04 9.972-05 838, 2.278-04 1.230-04 838. 7.674-04 4.116-04 5 829. 829. 1.724-04 9.325-05 829. 2.035-04 1.099-04 829. 6.588-04 3.535-04 SSW 829. 829. 2.156-04 1.166-04 829. 2.443-04 1.320-04 829. 8.508-04 4.565-04 i SW 610. 610. 2.650-04 1.434-04 610. 3.164-04 1.709-04 610. 1.148-03 6.155-04 i WSW 509. 509, 2.423-04 1.311-04 509. 3.057-04 1.650-04 509. 1.097-03 5.881-04 W 509. 509. 2.371-04 1.283-04 509. 3.028-04 1.634-04 509. 1.109-03 5.941-04 WNW 625. 625. 1.753-04 9.485-05 625. 2.241-04 1.209-04 625. 7.793-04 4.176-04 NW 732. 732. 2.232-04 1.207-04 732. 2.764-04 1.492-04 732. 9.905-04 5.310-04 NNW 848. 848. 1.877-04 1.015-04 848. 2.397-04 1.293-04 848. 7.952-04 4.263-04
{ LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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TABLE 7.2-8 (Cont'd) LASALLE COUNTY 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE137 DOWNWIND RESTRICTED ELEVATEC'. STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V . VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) . (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 9.192-05 5.953-05 1022. 1.227-04 7.926-05 1022. 3.048-04 1.960-04 NNE 1330. 1330. 5.984-05 3.874-05 1330. 7.806-05 5.042-05 1309. 1.839-04 1.183-04 h [d NE 2408. 2408. 1.898-05 1.228-05 2408. 2.376-05 1.535-05 2408. 4.989-05 3.209-05 CO ha ENE 4450, 4450. 4.730-06 3.058-06 4450, 5.476-06 3.536-06 4450. 9.264-06 5.964-06 I E 1996. 1996. 3.389-05 2.192-05 1996. 4.135-05 2.671-05 1996. 8.391-05 5.398-05 f5 -_ [j ESE SE 838. 884. 838. 884. 1.291-04 8.501-05 8.360-05 5.506-05 838. 884. 1.728-04 1.112-04 1.116-04 7.183-05 838. 884. 4.409-04 2.927-04 2.835-04 1.882-04 tg D3 SSE 838. 838. 7.478-05 4.844-05 838. 9.532-05 6.161-05 838. 2.566-04 1.650-04' S 829. 829. 6.855-05 4.440-05 829. 8.301-05 5.366-05 829. 2.286-04 1.469-04 SSW 829. 829. 7.181-05 4.651-05 829. 8.'471-05 5.478-05 829. 2.331-04 1.499-04 _ SW 610, 610. 1.187-04 7.686-05 610. 1.447-04 9.355-05 610. 4.158-04 2.673-04 W5W ' 509. 509, 1.300-04 8.422 509. 1.641-04 1.061-04 509. 4.873-04 3.132-04
- W 509. 509, 1.195-04 7.743-05 509. 1.553-04 1.004-04 ' 509. 4.654-04 2.991-04 WNW 625. 625. 8.843-05 5.729-05 E2M. 1.138-04 7.352-05 625. 3.328-04 2.139-04 NW 732, 732. 8.980-05 5.818-05 732. 1.168-04 7.549-05 732. 3.307-04 2.126-04 NNW 848. 848. .8.141-05 5.274-05 ~848. 1.OG8-04 6.903-05 848. 2.822-04 1.814-04..
~'
LASALLE' SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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g & <- i ' TABLi -8 (Contid) LASa..J COUNTY 182 MAXIMUM OFFSITE FINITy PLOME GAMMA DOSE'FACTGR$ FOR XE'38 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXEO MODE (EkNT) RELEASE GROUND LEV 5L REL' EASE - DIRECTION AREA BOUND RADIUS S .58AR RADIUS V VBAR- _ RADIUS _ - ac _ G8AR .
~~
(METERS) (METERS) (MRAD /YR)/(UCI/SEC), !_ METERS) ( MR AD/YR ) /(UC I / SE CJ .. ' (MST ER S ) (MRAD /YR)/guCI/SFC) _ / N 1522. 1022. 7.062-04 5.142 04 - 1o?2. 8.855-04 6.413-04 1022. 2.092-03 1.497-03
, 3 NNE 1330. 1330. 5.154-Ce 3.75L-04 1330. 6.294 f04 4.559-04 1330. ~ 1.419-03 1.015-03 h NE 2408. 2408, 2.283-04'14660-04 74C8. -' 2.679-04 1.940-04 2408. 3.375-04 3.850-04 bJ ENE 4450. 4450. 'J.599-05 6.369-05 4350. 1.065-04 7.713-05 4450. 1.766-04 1.268-04 D)
> I E 1996. ,1996. 3.523-04 2.561-04 1396. 4.085-04 2.959-04 1996. 8.082-04 5.790-04 ' fl ESE 838. 838. 9.410-04 6.854-04 838. 1.184-03 8.579-04 839. 2.869-03 2.052-03 tg [# SE 884. 884. 6.470-04 4.713-04 884 7.969-04 5.775-04 884. 1.993-03 1.425-03 D3 SSE 838. 838. 5.896-04 4.295-04 838. 7.075-04 5.130-04 838. 1.815-03 1.298-03 5 829. 829. 5.682-04 4.138-04 829. 6.521-04 4.733-04 829. 1.680-03 1.201-03 SSW 829. 829. 6.224-04 4.533-04 829. 6.990-04 5.075-04 829. 1.830-03 1.309-03 SW E10. 610. 8.907-04 6.488-04 610. 1.033-03 7.494-04 610. 2.823-03 2.018-03 ASW 509. 509. 9.041-04 6.588-04 509. 1.083-03 7.858-04 509. 3.038-03 2.171-03 W 509. 509. 8.464-04 6.168-04 509. 1.034-03 7.495-04 509. 2.938-03 2.100-03 WNW 625. 625. 6.430-04 4.685-04 625. 7.797-04 5.654-04 625. 2.147-03 1.534-03 NW 732. 732. 7.058-04 5.143-04 732. 8.540-04 6.193-04 732. 2.317-03 1.656-03 NNW 848. 848. 6.270-04 4.567-04 848. 7.698-04 5.579-04 848. 1.954-03 1.397-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL 8 <hh: CH U2 tn
>9 H O
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TABLE 7.2-8 (Cont'd) LASALLE COUNTY 142 MAXIMUM OFFSITE,71 NITE PLUME GAMMA DOSE FACTORS FOR AR 41 ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DOWNWIND RESTRICTED GSAR I DIRECTION AREA BDUND RADIUS S $8AR RADIUS V VBAR RADIUS G (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) N 1022. 1022. 9.121-04 6.430-04 1022. 1.128-03 7.954-04 1022. 2.759-03 1.945-03 p NNE 1330. 1330. 7.085-04 4.995-04 1330, 8.496-04 5.989-04 13J0. 2.011-03 1.418-03 7 -J 5.961-04
- NE 2408. 2408, 3.586-04 2.528-04 2408. 4.127-04 2.909-04 2808. 8.455-04 4450. 3.586-04 2.528-04 hh j) ENE E
4450. 1996. 4450. 1996. 1.929-04 5.228-04 1.360-04 3.686-04 4450. 1996. 2.101-04 5.968-04 1.481-04 4.207-04 1996. 1.230-03 8.672-04 t* og 4 ESE 838. 838, 1.218-03 8.596-04 838. 1.508-03 1.063-03 838. 3.002-03 2.681-03 t* D2 SE 884 884 8.260-04 3.823-04 884. 1.006-03 7.091-04 884 2.596-03 1.830-03 838. 8.186-04 5.771-04 838. 9.605-04 6.771-04 838. 2.623-03 1.889-03 SSE 838. 829. 829, 7.699-04 5.428-04 829. 8.713-04 6.143-04 829. 2.304-03 1.625-03 S SSW 829. 829. 9.379-04 6.613-04 829. 1.031-03 7.270 04 829. 2.862-03 2.018-03 610. 1.198-03 P.449-04 610. 1.366-03 9.628-04 610. 3.965-03 2.795-03 SW 610. 509. 509." 1.126-03 7.938-04 509. 1.334-03 9.403-04 509. 3.869-03 2.727-03 WSW 509. 3.888-03 2.741-03 W 509. 509. 1.094-03 7.711-04 509. 1.311-03 9.239-04 WNW 625, 625. 8.059-04 5.681-04 625. 9.663-04 6.812-04 625. 2.754-03 1.942-03 732. 732. 9.951-04 7.016-04 732. 1.171-03 8.25J-04 732. 3.388-03 2.389-03 NW 848. 8.424-04 5.939-04 848. 1.013-03 7.139-04 848. 2.742-03 1.933-03 NNW 848. LASALLE SITE METEDROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL
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LA SALLE RE5/ISION 3 NOVEMBER 1981 O 8.0 RADIOACTIVE EFFLUEMP TREATMENP SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENP MONITOR ALARM AND TRIP SETPOINPS , AND ENVIRONMENT RADIOLOGICAL MONITORING TABLE OF CONTENPS PAGE 8.1 GASEOUS RELEASES 8.1-1 r 8.1.1 System Design 8.1-1 8.1.1.1 Gaseous Radwaste Treatment System 8.1-1 8.1.1.2 Ventilation Exhaust Treatment System 8.1-1 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Station vent Stack Monitor 8.1-3 8.1.4 Standby Gas Treatment Stack Monitor 8.1-4 8.1.5 SJAE Of f-Gas Monitors 8.1-5 8.1.6 Allocation of Effluents from Common Release Points 8.1-6 (]) 8.1.7 8.1.8 Symbols Used in Section 8.1 Constants Used in Section 8.1 8.1-7 8.1-8 8.2 LIQUID RELEASES 8.2-1 8.2.1 System Design 8.2-1 8.2.2 Alarm Setpoints 8.2-1 8.2.3 Liquid Effluent Monitors 8.2-2 8.2.4 Allocation of Effluents from Common Release Points 8.2-3 8.2.5 Administrative and Procedural Controls for Radwaste Discharges 8.2-4 8.2.6 Determination of Initial Dilution Stream Flow Rates 8.2-4 8.2.7 Symbols Used in Section 8.2 8.2-5 . 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENPAL RADIOLOGICAL MONITORING 8.4-1 O 8-i
. _ - - - _ . - _ - - . . - - . . . . . . ~ . --- -- . . .. ._ .._ .- -
.2 i_ LA SALLE REVISION 3 NOVEMBER 1981 O i 8.0 RADIOACTIVE EFFLUEM TREATMEM SYSTEMS , MODELS FOR SETTING GASEOUS AND LIQUID EFFLUEM MONITOR ALARM AND TRIP SETPOIMS, i AND -ENVIRONMEMAL RADIOLOGICAL MONITORING r . LIST OF TABLES ~ c NUMBER TITLE PAGE~ 8.4-1 Radiological Monitoring Program
- (1982-1983) 8.4-2 8.4-2 Radiological Monitoring Program (1984 and Later) 8.4-5 8.4-3 Practical Lower Limits.of Detection (LLD) for Environmental Radiological Monitoring Program . . 8.4-8 8.4-4 Environmental Radiological Monitoring
, Sampling Codes 8.4-9 O. 4 7
- 0 h
I i i. O 8-11 _u..-_,--,__.,.-,.._-.,- . , . _ , _ . . _ _ _ _ . - , _ . _ . _ . . _ . _ _ . _ _ _ _ _ _ , . _ _ _ . , _ . _ _ . . -__._.._,._s
LA SALLE REVISION 3 NOVEMBER 1981 8.0 RADIOACTIVE EFFLUEW TREATMER SYSTEMS ,. MODELS FOR SETTING GASEOUS AND LIQUID EFFLUEW MONITOR ALARM AND TRIP SETPOINPS, AND ENVIRONMEWAL RADIOLOGICAL MONITORING LISP OF FIGURES NUMBER TITLE 8.4-1 ' Fixed Air Sampling Sites and Outer Ring
- TLD Locations 8.4-2 Inner Ring TLD Locations O
a I i 8-111
LA SALLE REVISION 3 NOVEMBER 1981 O 8.o RAo10aCT1vE ErFouEn TREATME- SvsrEMS. MODELS FOR SErTING GASEOUS AND LIQUID EFFLUEW MONITOR ALARM AND TRIP SETPOIMS, AND ENVIRONMENT RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES 8.1.1 System Design 8.1.1.1 Gaseous Radwaste Treatment System A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collec-ting primary coolant syctem off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. () 8.1.1.2 Ventilation Exhaust Treatment System A ventilation exhaust treatment system shall be any system designed and installed to reduce gaseous radioiodine or radio-active material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered
~'
to have any effect on noble gas effluents) . Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. 8.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air con-( taining radioactivity are established'to ensure that the i release limits of 10 CFR 20 are not exceeded. The setpoints 8.1-1
LA SALLE REVISION 3 NOVEMBER 1981 are-found by solving Equations 2.9 and 2.10 for each class of release. For this evaluation the radioactivity mixture in the exhaust air is assumed-to have the composition of gases listed in Table 3-3 from " Technical Derivation of BWR 1971 Design Basis ^ Radioactive Material S,ource Terms," NEDO-10871, March 1973, General Electric Company. This mixture of radioactive gases is representative of the activity found at the point of release from the fuel; radioactive decay has not been included. Equation 2.9 is rewritten using the fractional composition
- of each nuclide, ft, and a total release rate, O t , f r station vent stack
- releases (the principal point of release of ventila-tion exhaust air containing radioactivity):
Q l.11 O ts k*fi ) < 500 (8.1) f t Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides. O ts Total Release Rate, (11Ci/sec) Vent Stack Release The release rate for all radionuclides due to a station vent stack release. O t3 = O ts fi (8.2) Equation 8.1 can be solved for Q for release Mmit determinations. t
*The term " vent stack", as used in this section, is to be considered synonymous with " stack" as used in Section 2.1.
8.1-2
LA SALLE REVISION 3 NOVEMBER 1981 Similarly, Equation 2.10 can be re-written: L i P/0)s Qts ifexp(- A R/3600u i s)
+
i - 1.11 S gQ ts fi < 3000 (8.3) Equation 8.3 can be solved for Q and a corresponding release ts limit be determined. The most conservative release limit determined from Equations 8.1 and 8.3 will be used in selecting the appropriate alarm ar.d trip setpoints for a vent stack release. The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded. Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.3.6.11-1 of the Technical Specifications. Calibration methods will be consistent with the definitions O couaa ta secetoa 1 o or ene rechaicet specietcettoae-8.1.3 Station Vent Stack Monitor l Releases of radioactive noble gases from the station vent stack release point are monitored by an offline monitoring system consisting of two instrument channels, each of which uses a G-M tube sensing element. Samples of the effluent stream are taken by an isokinetic probe just prior to dis-charge into the atmosphere. Gas flow through,the monitoring system, located largely on panel OD18-P001, is ensured by the ram effect of the gas on the probe tips and by the vacuum pumps through a constant flow network. Each monitoring channel consists of a G-M tube detector, a shielded sampling chamber, a pre-amplifier, and a log count rate monitor. The log count rate monitor includes an integral O vower uvetv, ror grovidias nish vo1eese to ene aetector. 8.1-3
LA SALLE REVISION 3 ("3 NOVEMBER 1981 V and trip relays, whose output initiates high radiation alarm annunciators. The channels share a common two-pen recorder. The recorder, alarm annunciators, and remote control switches, for the station vent stack monitoring system, are located in the main control room. The sample panel, with pumps, detec-tors, and local controls, is located in the auxiliary building on elevation 815 feet just outside the turbine building exhaust fan room. Power is supplied to the station vent stack radiation monitors from the Unit 1 125-Vdc battery systems via inverters. The monitor display has logarithmic scale with a range of 10-1 6 to 10 counts per second. The equipment identification numbers for the monitors are OD18-K602A and OD18-K602B. 8.1.4 Standby Gas Treatment Stack Monitor (m u) l Release of radioactivity from the standby gas treatment system (SGPS) stack is monitored by the SGTS monitoring system. Each SGTS monitoring channel consists of a beta sensitive scintillation detector for particulate; a beta sensitive scintillation detector for low-range noble gas; a beta sensitive scintillation detector , for high-range noble gas; and a gamma sensitive scintillation detector for iodine. Provisions are made for system inlet and outlet grab samples. The monitoring system uses a microprocessor to analyze the data from the beta and gamma scintillation detectors. This micro-processor performs background subtraction and compares the radi-ation values against operator entered alarm limits. A four-pen strip chart recorder records the monitoring system output. Alarms are located in the main control room. 3 (^Y 8.1-4
LA SALLE REVISION 3 NOVEMBER 1981 1 O-Power is supplied to this monitor subsystem from Division 2 power. The equipment for each monitoring channel is skid mounted and located on the 786 ft 6.in.-elevation in the auxiliary building. 8.1.5 SJAE Off-Gas Monitors l The steam jet air ejector (SJAE) monitor subsystem continually measures and~ records the gamma radiation in the off-gas as it is drawn from the main condenser by the steam jet air ejectors
~
before it passes through the holdup line and carbon beds enroute to the station vent stack. A continuous representative sample is drawn from the off-gas system via a stainless steel sample line. A 14 cc serum vial is inserted into the sample chamber, evacuated, then filled
~
with a representative sample of off-gas. This sampling equip-
-O mene 1e tocated on gene 1 1D18-J034 (2D18-3034).
This- monitor system consists of two channels. One channel contains a_ gamma sensitive ionization chamber and a linear radiation monitor and the other channel contains a gamma sensitive ionization chamber and a logarithmic radiation monitor. The ion chambers sensitivity I is 1 to 10 6 mR/hr. The gamma sensitive ionization chamber , RE-lD18-N002 (RE-2D18-N002) is connected to the logarithmic readout i channel. This channel has alarm functions but no trip functions. l Power is supplied from Unit 1 (2) 125-Vdc power supply via N l inverters and from the 120-Vac instrument bus for the recorder. The gamma sensitive ionization chamber RE-lD18-N012 (RE-2D18-N012) is connected to the linear readout channel. Power is supplied to
- this channel from-Unit 1 (2) 24-Vdc power supply and from the l 120-Vac instrument bus for the recorder. Both channels measure the radiation levels in the off-gas and their recorders are located in the control room.
O: f 8.1-5
l-LA SALLE REVISION 3 NOVEMBER 1981 O 8.1.6 Allocation of Effluents from Common Release Points l Radioactive gaseous effluents released from the plant vent stack are comprised of contributions from both units. Estimates of noble gas contributions from each unit will be allocated by considering appropriate operating conditions and measured SJAE off-gas activities. Allocation of radioiodine and radioactive particulate releases to a specific unit is not as practical and is influenced greatly by in-plant leakage. Under normal operating conditions, allocation will be made using reactor coolant iodine activities. During unit shutdown or periods of known major in-plant leakage, the apportionment will be adjusted accordingly. The allocation of the ef fluents will be estimated on a monthly basis, e e (_/ ' 8.1-6
LA SALLE REVISION 3 NOVEMBER 1981 O 8.1.7 Symbols Used in Section 8.1 l SYMBOLS NAME UNIT Q ts Total Release Rate, Vent Stack Release (pCi/sec) 5g Gamma Whole Body Dose Constant, Vent Stack Release (mrad /yr per pCi/sec) fg Fractional Radionuclide Composition Lg Beta Skin Dose Constant (mrem /yr per pCi/m ) (X/Q)s Relative Effluent Concentration' sec/m ) 3 Vent Stack Release Q Ag Radiological Decay Constant (hr~1) R Downwind Range (m) u Average Wind Speed, Vent Stack Release (m/sec) s i Q is Release Rate of Nuclide i, Vent Stack , i Release (pCi/sec) Sg Gamma Dose Constant, Vent Stack Release (mrad /yr per ECi/sec) O 8.1-7
LA SALLE REVISION 3 NOVEMBER 1981
.O 8.1.8 Constants Used In Section 8.1 NUMERICAL VALUE NA _ME UNIT 1.11 Conversion Constant (mrem / mrad) 3600 Conversion Constant (sec/hr)
O d f I I I l l O 8.1-8
LA SALLE REVISION 3 NOVEMBER 1981 8.2 LIQUID RELEASES 8.2.1 System Design A liquid radwaste treatment system shall be a system designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer or a concentrator for the purpose of reducing the total radioactivity prior to release to the environment, t 8.2.2 Alarm Setpoints Alarm setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area. The concentra-() tion limit (Cyg ,) in the discharge line prior to dilution in the initial dilution stream is: - - E F F ave + max Clim = MPC pr max (8.5) C lim Limiting Concentration (UCi/ml) in Discharge Line The maximum concentration in the discharge line per-mitted to be discharged to the initial dilution stream. MPC Weighted Maximum Permissible (pCi/ml) Concentration The lowest maximum permissible t.oncentration calculated using liquid ef fluere isotopic data. O 8.2-1
- . . _ _ . ~ _ _ _ _ _ _ _ . . _ _ - . . _ - _ . _ - _ _ - _. .. _ _ _ , _ _ _ _ _ . ,_ _ . . .
LA SALLE REVISION 3 NOVEMBER 1981 (-)s
's F 3x Maximum Flow Rate, 3 (ft /sec)
Radwaste Discharge The maximum flow rate of radwaste from the dis-charge tank to the initial dilution stream. d F ve Average Flow Rate, (ft /sec) Initial Dilution Stream The average flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary. Surveillance frequencies for liquid effluent monitors will be as stated in Table 4.3.6.10-1 of the Technical Specifications. Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications. (ms,) 8.2.3 Liquid Effluent Monitors l The radwaste discharge line, Unit 1(2) service water effluent header and Unit 1(2) RHR service water effluent headers are continuously monitored for radioactivity by an offline mon-itoring system which uses a NaI (Tl) activated scintillation detector. Liquid effluent flow through each monitoring system is ensured by a pump and a flow control valve located on local l sample panels. . Each monitoring system consists of a scintillation detector, shielded sampling chamber, a preamplifier, and a log count rate monitor. The log count rate monitor includes an integral power supply, for providing high voltage to the detector, and trip relays, whose outputs initiate high radiation alarm annunciators. In addition, the radwaste discharge effluent monitor's trip relays initiate isolation of the liquid radwaste p (_) discharge header. 8.2-2
l LA SALLE REVISION 3 NOVEMBER 1981 O The service water effluent monitor provides a signal to a two-pen recorder which it shares with the RBCCW process radiation monitor. The RHR service water ef fluent monitors share a common two-pen recorder in the main control room. The radwaste discharge effluent monitor provides signals to a recorder in the main control room and a recorder in the radwaste control room. All the process liquid monitors have logarithmic scales with a range of 10 -1 to 10 6 CPM. The monitors are powered from the Unit 1(2) 125-Vdc batteries via inverters, with the excep-tion of the radwaste discharge monitor which is supplied from a local 120-Vac source through a d-c power supply. The equipment identification numbers for the monitors are OD18-K606, radvaste monitor; 1D18-K608 (2D18-K608), service water effluent monitor; 1D18-K604 (2D18-K604), RHR service water A effluent; and 1D18-K605 (2D18-K60 5 ) , RHR service water B effluent. 8.2.4 Allocation of Effluents from Common Release Points a Radioactive liquids released from the radwaste treatment system are comprised of contributions from both units. Under normal . operating conditions, it is difficult to apportion the radio-activity between units. Consequently, allocation will normally be made evenly between units. During refueling outages or periods of known major in-plant leakage, the apportionment will be adjusted accordingly. The allocation of the effluents will be estimated on a monthly basis. (J
~b.
8.2-3
LA SALLE REVISION 3 NOVEMBER 1981 8.2.5 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been designed to ensure proper control of radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits. The discharge rate for each batch is calculated by a technician and then independently verified by operating staff personnel. All liquid radwaste discharges will be from one of two river discharge tanks, lWFOST or 2WF05T . The keylock hand switch, OHS-WF048, used for selecting high or low discharge flow is kept locked except when discharging. The key for this switch and the locked valves is under the administrative control of the Shift Engineer.
- A documented valve checklist is prepared for each batch discharge.
' The proper valve line-up is made by the Operator and rechecked by the Radwaste Foreman. The actual discharge is authorized by the Shift Engineer. The system is equipped with a radiation trip point which alarms and initiates automatic valve closure on the radwaste discharge line to prevent the violation of 10 CFR 20 limits. 8.2.6 Determination of Initial Dilution Stream Flow Rates l For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine the flow rate of the initial dilution stream. This instrumenta-tion will be operated and maintained as prescribed by the Tech-nical Specifications. For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as
-)
pump curves, differential pressures, or valve position indication. 8.2-4
LA SALLE REVISION 3 NOVEMBER 1981 O 8.2.7 Symbols Used In Section 8.2 l SYMBOL NAME UNIT
~
C yg, Limiting Concentration in (pci/ml) Discharge Line MPC Weighted Maximum Permissible (pCi/ml) Concentration I F ,x Maximum Flow Rate, Radwaste (ft /sec) Discharge d F,y, Average Flow Rate, Initial (ft /sec) Dilution Stream O i O 8.2-5
LA SALLE REVISION 3 NOVEMBER 1981 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. 4 t O l l O 8.3-1
----,--+-+-,w --e ,# , - - , , - - - . - , - - - - . - - - , - - --,ne -men--m--,....,, --,er.- ~---,we en,~,-,,--n-eo.-,.. -,.,.---.,-~,---een ,,mn..-.--, w.-,,wn.,~-
LA SALLE REVISION 3 NOVEMBER 1981 O 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs around La Salle County Station is given in Table 8.4-1 for the years 1982-1983, and in Table 8.4-2 for 1984 and later. Figure 8.4-1 shows the 14 fixed air sampling sites and TLD locations; also shown are the " outer ring" (approximately 5 miles distant) TLD locations. Figure 8.4-2 shows the
" inner ring" TLD locations. The TLD's are code numbered as follows: XYY-N.
Where: X=1 means inner ring, X=2 means outer ring, and - ! YY-N is an identification code. The practical lower limits of detection for this program are given in Table 8.4-3. 0 8.4-1
O O O TABLE 8.4-1 + l RADIOLOGICAL MONITORING PROGRAM (1982 - 1983) 1 TYPE AND FREQUENCY FREQUENCi NONROUTINE SAMPLE MEDIUM 0F ANALYSIS
- COLLECTION SITES OF COLLECTING REPORTING LE'!ELS
- 1. Airborne
- a. Particulate Gross beta - W. Seneca, Marseilles, Weekly Cs-134, 10 pC1/m Filter Sr 89, 90 - Q. comp. Ottawa, Grand Ridge Cs-137, 20 pCi/m 3 Gamma Spec. - Q. comp. Streator, Ransom, Route 6 at Gonnam Road, Kernan, and six stations near the site (see g Figure 8.4-1)
Sn y, E
- b. Charcoal I-131 Same as for la Every 2 weeks 0.9 pCi/m 3 E
! Cartridge r
- 2. Gama TLD Same as for la, plus 40 Quarterly None Radiation other sites distributed j ,
near the site boundary
- and at 5 miles (see
; Figures 8.4-1 and 8.4-2)
EM i 3. Surface Water Sr-89, 90 - Q. comp. Illinois River at intake Weekly M;5 4 Gama Spec. - M. comp. of Illinois Nitrogen Corp. @!C Gross beta - W. Illinois River at Marseilles 99 1 Tritium - Q. comp. Illinois River at Ottawa -w Illinois River at Seneca g
~
i South Kickapoo Creek Cooling lake near recreation area N
O O O' TABLE 8.4-1 (Cont'd) TYPE AND FREQUENCY FREQUENCY NONROUTINE SAMPLE MEDIUM 0F ANALYSIS
- COLLECTION SITES OF COLLECTING REPORTING LEVELS
- 4. Intake / Discharge Gross beta - W. I/D Pipes if pumping; if Weekly None pipes -Sr-89, 90 - M. comp. not pumping, collect in Tritium - M. comp. Illinois River near I/D Gama Spec. - M. comp. structures
- 5. Precipitation Gama Spec. - Q. comp. Same 3 sites as Monthly None l Sr-89, 90 - Q. comp. milk collections l Cross beta - M.
l Tritium - Q. comp. l ! 6. Well Water: Gama Spec. Marseilles, Seneca, Quarterly ** g P Offsite Sr-89, 90 Ottawa, m
? Gross beta Ransom, -
p l w Tritium Illini State Park p l.
- 7. Well Water: Gama Spec. - Q. comp. Monthly **
One onsite well (the Onsite Sr-89, 90 - Q. comp. one chosen for pro-l Gross beta - M. viding drinking Tritium - Q. comp. water) l I l l 8. Vegetables Gross beta Farms within 10 miles As available at
- f Sr-89, 90 harvest time gg ,
Gama Spec. g< l I-131 (for green gm leafy vegetables only) gg G"
- 9. Cattle Feed Gross beta Same three sites as Quarterly: None 3
- and Grass Sr-89, 90 milk collections Grass
- Sumer i Gama Spec. Feed: Winter f
O O O l TABLE 8.4-1 (Cont'd) TYPE AND FREQUENCY FREQUENCY NONROUTINE , ) SAMPLE MEDIUM 0F ANALYSIS
- COLLECTION SITES OF COLLECTING REPORTING LEVELS i
, 10. Milk Gamma Spec. 3 nearby dairies or Monthly - Nuclide pCi/l j Sr-89, 90 - M. private animals, November to April including the nearest, Weekly - May I 131 3 1-131 (Pasture Cs 134 70
, Season) if possible to October 60 Cs-137 l Ba/La-140 300 i
] 11. Sediment, Gross. beta Just upstream of cooling Three times a
- Aquatic Plants Gama Spec. lake inlet structure year, if available
'. Just downstc?am of l cooling lake discharge 3 structure r-Cooling lake near 2" [ recreational area .
.[2, i E !
- 12. Fish Gross beta Marseilles pool of Three times a year
- Gama Spec. Illinois River Sr-89, 90 Cooling Lake
.I g If frequency of analysis is not given, it is the same as frequency of collection; l W. - Weekly; M. - Monthly; Q. - Quarterly; Comp. - Composite.
- o 4 *pCi/kg wet weight ** Nuclide pCi/l Nuclide pCi/1 SEQ 4 *~
Mn-54 3 x 10 4 H-3 20,000 Zr-Nb-95 400 E!C , Co-58 3 x 10 Mn-54 1,000 I-131 2 99 Zn-65 2 x 10 3 Fe-59 100 Cs-134 30 ,_. w Cs-137 2 x 10 4 Co-58 600 Cs-137 50 $ Fe-59 1 x 10 4
- Co-60 300 ~
Ba/La-140 100 i Co-60 1 x 10 3 Zn-65 200 Cs-134 1-x 10 i I s (
O O O TABLE 8.4-2 RADIOLOGICAL MONITORING PROGRAM (1984 and Later) NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **
- 1. Air a. Onsite and near field
- a. Filter - a. Weekly Cs-134, 10; Monitoring gross beta *** Cs-137, 20 pCi/m 3
- 1. Nearsite Station 1
- 2. Onsite Station 2 b. Charcoal - b. Biweekly +' O.9 pCi/m 3
- 3. Onsite Station 3 I-131
- 4. Nearsite Station 4
- 5. Onsite Station 5 c. Sampling c. Weekly Not Applicable
- 6. Nearsite Station 6 Train - E co Test and v, y Maintenance -
E
- b. Far Field *
- 7. Seneca a. Filter a. Weekly Cs-134, 10;
- 8. Marseilles Exchange Cs-137, 20 pCi/m 3
- 9. Grand Ridge when analyses
- 10. Streator are made
- 11. Ransom
- 12. Kernan b. Charcoal b. Biweeklyi 0.9 pC1/m3
- 13. Route 6 at Exchange when analyses Gonnam Road are made 8l8 14 Ottawa 25
- c. Sampling c.* Weekly Not Applicable $;C Train - 9@
Test and .w Maintenance 8
(~) v O- (~) u TABLE 8.4-2 (Cont'd) NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **
- 2. TLD a. Same as Item 1, Air Gamma Quarterly None Monitoring Sites
- Radiation
- b. Plus 40 other sites distributed about the site boundary and at 5 miles *5
- 3. Fish a. Marseilles Pool of Ganna Semi-annual pCi/kg wet weight Illinois River Isotopic Mn-54 Co-58 3x10f Zn-65 2 x 10 3x10l 9 P Cs-137 2 x 10 4 v,
? Fe-59 1 x 10 E
- Co-60 1 x 10 43 Cs-134 1 x 10
- 4. Milk a. Three nearby dairies I-131tt a. Weekly pCi/l or private animals during I 131 3 including the nearest, grazing Cs-134, 70 if possible season, May Cs 137 60 to October Ba La-140, 300
- b. Monthly, Same as above 5A November M5 to April $$
SS m
.O O O.
TABLE 8.4-2 (Cont'd) N0fR00 TIME SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS -FREQUENCY REPORTING LEVELS **
- 5. Surface a. Illinois River Gama Monthly Nuclides pCi/l Water at Marseilles, Isotopic analysis of H-3 20,000
- b. Illinois River weekly Mn-54 1,000 at Ottawa composites Fe-59 100
- c. Illinois River Co-58 600 at Seneca
- d. South Kickapoo Creek
- e. Illinois Nitrngen Corp. Zr-Nb-95 400
- f. La Salle County Cooling I-131 2 Lake near recreation area Cs-134 30 Cs-137 50 Ba-La-140 100 5 h
- 6. Cooling a. Inlet ttt Gross Beta Weekly None E Water Sample b. Dischargetti
- 7. Sediment a. Downstream of Cooling Gama Annual None Lake Discharge Structure Isotopic
*See Figure 8.4-1
** Average concentration over calendar quarter. 5A
***A gama isotopic analysis snall be performed whenever the gross beta concentration ir a sample exceeds M5 by five times (5x) the average concentration of the preceding calendar quarter for the sample location. @i$
tBiweekly shall mean that the frequency is once every other week. 93 ttA gama isotopic u.alysis shall be performed if I-131 from the plant is found above the i.LD. -w tttProvided by station personnel. $
~
SSee Figure 8.4-2 - i t
1 i LA SALLE REVISION 3
.s NOVEMBER 1981 TABLE 8.4-3 PRACTICAL LOWER LIMITS OF DETECTION (LLD)
FOR ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM LLD SAMPLE MEDIA ANALYSIS (4.660) UNITS , 3 Airborne Gross Beta
- 0.01 pCi/m
" Particulate" Gamma Isotopic 0.01 pCi/m 3 Sr-89, 90 0.01 pCi/m p01/m 3 Airborne I-131 Iodine-131 0.10 Liquids Sr-89 10 pCi/l Sr- 90 2 pCi/1 I-131 5** pCi/l Cs-134 10 pCi/l Cs-137 10*** PCi/l Tritium 0.2 pCi/ml Gross Beta
- 5 pCi/l
{) t Gamma Isotopic <20 pCi/1/nuclide Vegetation Gross Beta
- 2 pCi/g wet I-131 0.03 'pCi/g wet Sr-89, 90 1 pCi/g wet Gamma Isotopic 0.2 pCi/g wet Soil, Sediment Gross Beta
- 2 pCi/g dry Sr-89, 90 1 pCi/g dry Gamma Isotopic 0.2 pCi/g dry Animal Tissue St-89, 90 0.1 pCi/g wet I-131 - Thyroid 0.1 pCi/g wet Cs-134, 137 0.1 pCi/g wet Gross Beta
- 1.0 pCi/g wet Gamma Isotopic 0.2 pCi/g wet
- Referenced to Cs-137.
**0.5 pCi/l on milk samples collected during the pasture season.
***5.0 pCi/l on milk samples.
g a 8.4-8 I .
, ,.~ ,
~
C> O '
<= O
'~
- j- TABLE 8.4-4. -
~
ENVIRONMENTAL RADIOLOGICAL MONITORING SAMPLING CODES 7
~
SL'RFACE WELL AQUATIC PLANTS PRECIPITATION,
- MONITORING SITES AIR TLD WATER WATER FISH AND SEDIMENT MILK FEED, GRASS VEGETABLES ,
}
l L-01 Nearsite No. 1 X X - L-02 Onsite No. 2 X X e l L-03 Onsite No. 3 X X _ }- L-04 Nearsite No. 4 X X
- f. L-05 Onsite No. 5 X X
- L-06 Nearsite No. 6 X X L-07 Seneca X X g
- . t L-08 Marseilles X X , y L-09 Grand Ridge X X E
] L-10 Streator X X ,
! L-11 Ransom X ; L-12 Kernan X X
- L-13 Route 6 at Gonnam Road X X a
l L-14 Ottawa X X
! zx
- L-15 Johnson Dairy X X eQ ,
m
- L-16 Lowery Dairy X X 3$ ,
; L-17 Norsen Dairy X X mE m
l i L-18 Sunny Isle Farm X X [ 1 i i .
O O O TABLE 8.4-4 (Cont'd) SURFACE-WELL AQUATIC PLANTS PRECIPITATION, MONITORING SITES AIR TLD WATER WATER FISH AND SEDIMENT MILK FEED, GRASS VEGETABLES L-19 Illinois River at Marseilles X L-20 Illinois River at Ottawa X L-21 Illinois River at Seneca X L-22 South Kickapoo Creek X L-23 Illinois Nitrogen Corporation X L-24 La Salle County Station (LSCS) cooling lake near recreation area X X L-25 LSC5 intake pipe / river X L-26 LSCS discharge pipe / river X r 2 -p
- w h L-27 LSCS onsite well 'X f L-28 Marseilles well water X L-29 Seneca well water X L-30 Ransom well water X L-31 Ottawa well water X L-32 Illinois State Park X L-33 Just upstream of cooling gg lake inlet structure X g<
L-34 Just dcwnstream of cooling kU
- = E lake discharge structure X L-35 Marseilles pool of Illinois River X
[ L-36 Farm A - vegetchles X 1-37 Farm B - vegetables X
REVISION 3 NOVEMBER 1981 O Ottcwo "i jg d2 m sm 55
~
I-
. /, Marseilles South 14 -w Riv8f Ottawa Seneca ,
\3 215-1 216-1 201-1 202-1 203-1 215-2 16-2g1g202-2 I203-2 3 2i4-2 . .
213-2 214-1 a l e204 -1 213-1 8 g gp204'2 PLANT 212-2 m 6' -
"M '
4 205 -1 212-1 * *205/2 , g3 SITE PROPERTY O 2 Grand Ridgea 11:1,,zio-i '*E~l Verona 210-2 209-1 m207-1 as 209-2 e207-2 i
,,208-1 208-2 Kinsman li. Ransom ,
12 i Kernan Streator _ ' 10 '
~
LA SALLE ~ COUNTY ~ GRUNDY COUN
~
OVINGST0N C0lfNTY SCALE: N LA SALLE COUNTY STATION MILES FIGURE 8.4-1 FIXED AIR SAMPLING SITES AND OUTER RI:lG TLD LOCATIONS am,-,me-.,,,w--,-e.,-----e,,e,- -
,,-><----,-n w----, . - - , - - . - - - , ,,--,.,,,..,_a- , - , , . . , . _ , - - . . , , . . . . . , - - . - - , - . , , . . , . . . , . , , - . - _ . - , , - - . , ,
North 22nd Road --- i
/ .
. .,-- g .
Aa
- 7 REVISION 3 d" fl0VEMBER 1981 C)i" ,
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GJade@ ADSL-enaaest
.[ (i North 21st Road scale: 1" - 400' LA SALL C COUNTY STATION l O
v FIGURE 8.4-2 li4NER RING TLD LOCATIONS 1
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