ML20071C835
| ML20071C835 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/28/1983 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20071C831 | List: |
| References | |
| PROC-830228, NUDOCS 8303080157 | |
| Download: ML20071C835 (204) | |
Text
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O OFFSITE DOSE CALCULATION MANUAL 0DCM O
mm,,,
l BYRON STATION lO OFFSITE DOSE CALCULATION MANUAL l
COMMONWEALTH EDISON COMPANY O
FEBRUARY 1983 Revision - 5 l
DOCKET NUMBERS 50-454,50-455 O
1 -. - -
+
1 REVISION 2 AUGUST 1980 OFFSITE DOSE CALCULATION MANUAL
() CONTENTS PAGE
1.0 INTRODUCTION
1.0-1 i
2.0 OFFSITE DOSE LIMITS 2.1-1 2.1 AIRBORNE RELEASES 2.1-1 2
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 3.1-1 3.1 METEOROLOGICAL DATA FOR MODELS 3.1-1 3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS 3.2-1 3.3 MODELS FOR CALCULATING DOSE FROM NOBLE GASES 3.3-1 l 3.4 MODELS FOR CALCULATING DOSE FROM RADIOIODINES,
! "PARTICULATES," AND OTHER RADIONUCLIDES 3.4-1 4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1-1 4.1 AQUATIC TRANSPORT 4.1-1 l 4.2 AQUATIC DOSE MODEL 4.2-1 i
4.3 AQUATIC TRANSPORT DURING TANK OVERFLOW CONDITIONS 4.3-1 5.0
SUMMARY
5.1-1 5.1 AIRBORNE EFFLUENTS 5.1-1 5.2 LIQUID RELEASES 5.2-1 5.3 URANIUM FUEL CYCLE 5.3-1 5.4 PRIMARY DRINKING WATER STANDARDS 5.4-1 l
I
6.0 REFERENCES
6.0-1 7.0 DATA POR DOSE ASSESSMENT MODELS 7.0-1 7.1 DATA COMMON TO ALL NUCLEAR STATIONS 7.1-1
)
1 i
REVISION 3 l NOVEMBER 1981
, CONPEffr S (Cont ' d)
PAGE
- 7.2 DATA SPECIFIC TO EACH NUCLEAR STATION 7.2-1 i
8.0 RADIOACTIVE EFFLUENP TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID i EFFLUENT MONITOR ALARM AND TRIP SE*PFOINTS, AND ENVIRONMENTAL 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 CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 i
J
.f.
t 8
4 1
O 11
- . _ . . . . , ~ - - _ - . -
- REVISION 2 '
i l AUGUST 1980 i
l 1.0 INTROD'JCTION i
- i. TABLE OF CONTENTS k
PAGE 4
1.0 INTRODUCTION
1.0-1 I
2
! P I
f i
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I I
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- . . _ _ _ _ _ . _ . . , . . . _ _ _ _ _ _ . . _ _ _ _ _ . . _ . _ ,..,.._ -.. - _.~ _.__.._ ,-._- _ -----__ ... _.,_,
- . .__- . -. . - -. . . . . _ - . _ - - . _ . . . - . - - = - - - . . - . .
I l
i REVISION 2 '
AUGUST 1980
1.0 INTRODUCTION
l 4
LIST OF FIGURES i l l i
! NUMBER TITLE -
1.0-1 Flow Chart for Offsite Dose Calculations
. b k k l
k i i I
- i i
n i
+
i i.
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,-,.,,--n,,-w,-m..,.--- -.n,,,w~,,n..,~,-,. -,,,,__-_n_,-,,.-.
REVISION 2 AUGUST 1980
1.0 INTRODUCTION
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.
Radiolodines, 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
(~s\
( ,/ station. Infant exposure occurs through inhalation and any actual milk pathway. Adult exposure derives from inhalation, assumed leafy vegetaole and produce pathways, and any actual milk and meat pathways.
Doses to each of seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung, and GI-LLI) are computed from individual nuclide l
contributions in each of the sectors. Searching over l
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
. -_. _ ~ _ _ , _
REVISION 2 AUGUST 1980 Noble Gases
() Exposure to the beta and gartna radiations of the noble gases will result in a whola 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 gan 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 eifluents 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 O
1.0-2
A Release Radionuclide Critical Environmantal Critical Regulatory Compliance Frequency of Mode Class Person Pathway Organ Limit Methodolory Calculaticn
-Inhalation 40 CFR 50 Dose Calculation Monthly Infant -Thyroid *
-Milk -10 CFR 20 Release Rate Calculation - When Necessary Radiciodinee,
=Particulaces -Inhalation
& Other Nuclides
-Milk -10 CFR 50 Dose Calculation Annually A Adult Meat Thyroid
- Airborne-
-Leafy Vegetables -10 CFR 20 Release Rate Calculation When Necessary
-Produce
-Whole Body 10 CFR 50 Dose Calculation % nthly w
-Noble Gases All Plume Exposure - F
, Persons . Skin J 10 CFR 20 Release Rate Calculation - When Necessary Adult Water Various -10 CFR 20 10 CFR 20, App. B, - Each Table 2, Col. 2 Batch Liquid All -Fieh Thyroid Adult - or -
-10 CFR 50 Dose Calculation :bnthly
'-Wate r Bone *
- Most likely critical organ; however, dose is computed for 7 organs. 86 g p, e
A The compatation of dose to the adult is perfomed annually to confim the premise that the infant is the critical person. r@
g, o
FIGURE 1.0-1 FI M CHART FOR OFFSITE DOSE CALCULATIONS
REVISION 2 AUGUST 1980 2.0 OFFSITE DOSE LIMITS 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 Dose 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 2.1-7 O 2.1.1.1.3.1 Skin Dose, Calendar Quarter 2.1.1.1.3.2 Skin Dose, Calendar Year 2.1-7 (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 O
2-1 l
REVISION 3 NOVEMBER 1981 TABLE OF CONTENTS (Cont ' d) 1 PAGE 2.2.5 Constants Used in Section 2.2 2.2-9 2.3 ENVIRONMERFAL STANDARDS FOR THE URANIUM FUEL CYCL 2 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 2.3.1.2.5 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 i
2.3.1.2.8 Transportation 2.3-7 2.3.1.2.9 Storage of Spent Fuel in Offsite Facilities 2.3-7 2.3.1.2.10 Long-Term Storage of High Level Radioactive Wastes 2.3-8 2.3.1.3 Summary 2.3-8 2.3.2 Numerical Models 2.3-8 O. 2.3.2.1 Airborne Releases and Direct Radiation 2.3.2.1.1 Whole Body Dose 2.3-8 2.3-8 2.3.2.1.2 Thyroid Dose 2.3-10 2.3.2.1.3 Any Other Organ Dose ?.3-10 2.3.2.2 Radioactivity in Liquid Releases 2.3-10 2.3.3 Symbols Used in Section 2.3 2.3-11 2.3.4 Constants Used in Section 2.3 2.3-12 I
i O 2-11
REVISION 2 AUGUST 1980 i
2.0 OFFSITE DOSE LIMITS LIST OF TABLES NUMBER TITLE PAGE 2.3-1 Numerical Models for Computing ;
Radiation Cose from Uranium Fuel
- Cycle Operations 2.3-13
4 d
4 e
1 4
O t
i
{
l l
t
(
O 1
2-111 l
1
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
-0 3.17 x 10 Sg Ais + Vg A gy +G A 35 mrad ( 2.1) 1 gg i
-8 3.17 x 10 Conversion Constant (years /second)
Converts seconds to years.
Sg Gamma Dose Constant, (mrad /yr per Stack Release p /sec)
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.
l A gg Accumulative Radionuclide (pCi)
Release, Stack Release The accumulative release of radionuclide
- i from a stack. Releases shall be cumulative 1
2.1-1
REVISION 2 AUGUST 1980
() over the calendar quarter or year (four
, consecutive quarters) as appropriate.
Vg 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) . The 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.
Gg Gamma Dose Constant, (mrad /yr per Ground Level Release pCi/sec) i 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-J1). The constant is evaluated for a finite plume using the method explained in Subsection 3.3.1.2.
A Accumulative Radionuclide (pCi) fg Release, Ground Level Release The accumulative release of radionuclide i from a ground level release point. Releases 2.1-2
RFNISION 2 AUGUST 1980 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)
-8 3.17 x 10 S A +V i A ty + G i
A tg < 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 Li (X/Q)3 A ig + (X/Q)y A iy + (X/Q)g A tg i . .
<10 mrad
! (2.3) l bi (mrad /yr per Beta Air Dose Constant tiCi/m )
The air dose f actor due to beta emissions for each identified noble gas radionuclide (Table 7.1-13) .
(X/Q)g Relative Effluent (sec/m )
Concentration, Stack Release The highest calculated annual average re-
! lative concentration in a given direction at or beyond the restricted area boundary for stack releases (Table 7 2-6 or Table 7.2-9) .
2.1-3
REVISION 2 AUGUST 1980 Accumulative Radionuclide (uC1)
() A's Release from Stack, Adjusted for Radiodecay The accumulative release of radie . tide i from a stack, adjusted to accc- or radiodecay in transit. '
Als " Als X exp (- A, u) g (2.3a)
A i Radio secay (hr-1)
Cons' The radiological decay constant for i radionuclide i. See Tables 7.1-9 and 7.1-11.
R Downwind Range (m)
The distance downwind to the
,O point of interest. See. Tables l 7.2-6, 7.2-7, and 7.2-8.
3600 Constant (sec/hr)
Converts hours to seconds ug Average Wind Speed (m/sec)
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 reled os. The partially elevated plume Am/ model of Regulatory Guide 1.111, part C.2.b 2.1-4
I 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 y =A gy x exp (- A R/3600 uy) (2.3b) g 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 Le' vel Release The highest calculated annnal average relative concentration in a given direction at or beyond the restricted area boundary for ground level releases. (See Table 7.2-6 or Table 7.2-9.)
A gg Accumulative Radionuclide (mci)
Release at Ground Level, Adjusted for Radiodecay The accumulative release of radionuclide i from ground level, adjusted for radiodecay in transit.
A ig = Agg 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 r 3.17 x 10 g{ gyjg) g ,
{yjg)y 3 y + (X/Q)g A g
< 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 <
l 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 10~0) S t
A gg +V f
A gy +G g A gg i
i- -
I
< 2.5 mrem (2.5)
O o> 881e1ai e a occee cv 1 ceer
- The shielding and occupancy factor for pro-l tection against gamma radiation.
i 1.11 Conversion Constant (mrem /arad)
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 y 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 2.1-6
_ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ .__~ - - _ . _ . . . . . . - _ . . , _ _ _ . _ - _ _ _ .- - . _ - . --
REVISION 2 AUGUST 1980 V Gamma Whole Body Dose (mrad /yr per f
( Constant, Vent Release pCi/sec)
The constant Vg 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. )
di Gamma Whole Body Dose (mrad /yr per Constant, Ground Level Release pCi/sec)
The constant G y 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. )
2.1.1.1.2.2 Whole Body Dose, Calendar Year (Four Consecutive Quarters) l (0.7) (1.11) (3.17 x 10-8) g A +Y A s i Aiv + i ig l
~
< 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:
2.1.1.1.3.1 Skin Dose, Calendar Quarter
-8 '
3.17 x 10 l.0 L g + (X/Q)y A' y + +
( X/Q) s A s (X/Q)g A' 1 _
g/
( 0. 7) (1.11) (S g Als + Vf A gy +G g A gg) < 7.5 mrem (2.7) 2.1-7
REVISION 2 AUGUST 1980 1.0 Shielding and Occupancy Factor The shielding and occupancy factor for pro-tection against beta radiation.
Ei Beta Skin Dose Constant (mrem /,yr per UCi/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/cm of dead skin. ,
2.1.1.1.3.2 Skin Dose, Calendar Year (Four Consecutive Quarters)
-8 +
3.17 x 10 1.0 f (X/Q)s ^'is + (X/Q)y Ai'y A 1 -
t N
(X/Q)g 'ig]+
(0. 7) (1.11) (S t A gg +V A iy +G i Agg) 1 15 mrem i
(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:
4 2.1.1.2.1 Whole Body Dose Rate 1.11 x S t Qis + i Qiy +5Q1 ig
< 500 mrem /yr
, i _
_ (2.9)
(10 CFR 20.105 limit) l O is Release Rate, Stack Release (pCi/sec)
The re2 ease rate for radionuclide i due to a stack release.
l l
\ j) 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 (UCi/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 Q1 's + ( X/Q) y Q{y + (X/Q)g Q +
i '-
k gg[
1.11 x (Sg Qis + Yi Q 1y +G y Og) g 1 3000 mrem /yr (10 CFR 20.105 limit)
(2.10)
Q1 ', Release Rate, Stack Release, ( Ci/sec)
Adjusted for Radiodecay The release rate for radionuclide i from a stack adjusted for radiodecay in transit.
Q's " Ois X eXP (- l i R/3600 us) (2.10a)
Qg'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)
Q1'g Release Rate, Ground Level, (pCi/sec)
Adjusted for Radiodecay The release rate for radionuclide i from ground level, adjusted for radiodecay in transit.
O(-) Q{g=Ogg x exp (- A g R/3600 ug) (2.10c) 2.1-9
REVISION 3 NOVEMBER 1981
[~T 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)y A iy +
a ija 1 -
+
(X/0)g A gg 365 ija Ua.f p C[+U Cf+
. . 1 -
) U fy Cf+U,F Cf <7.5 mren (2.11) 10 6 Conversion Conctant (pCi/pci)
Converts WCi to pCi.
365 Conversion Constant (yrs / day)
Converts days to years.
R Individual Air Intake Rate (m /yr) 3 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 Length of tiiae for deposition.
O V
2.1-10
REVISION 2 AUGUST 1980 DPA Inhalation Dose Factor (mrem /pCi) f33 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.
( X/Q) y See Table 7.2-6 or Table 7.2-9.
(X/Q)g See Table 7.2-6 or Table 7.2-9.
DFI Ingestion Dose Factor (mrem /pCi) ia 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) ;
milk; leafy vegetables; and meat (flesh),
respectively, for individuals in age group a.
See Tables 7.1-2 and 7.1-3.
f,f p y Produce, Leafy Vegetable Fractions The respective fractions of the ingested produce and leafy vegetables that are grown in the garden of interest; dimensionless.
See Table 7.1-2.
Cf,Cf,C ,
Cf Foodstuff Concentrations (pCi/kg, pCi/ liter,
! PCi/kg, pCi/kg, respectively) 2.1-11 l
REVISION 2 I AUGUST 1980 '
The average concentrations of radionuclide i in produce (nonleafy vegetables, fruits, and
[^)h I
grain) ; milk; leafy vegetables; and meat (flesh), respectively.
C{andC{arecal-culated from Equation 2.12 below.
Cy Concentration in Vegetation (pCi/kg) l The concentration of radionuclide i in vegetation.
dixr 1 - eXP (-
C g= A tI
_ Ei e_ exp (- A t tIh *I f Y y A Ei ,
( 2.12) di Deposition Rate (pCi/m - hr)
The deposition rate of radionuclide i onto the ground.
() d 6 p = 2410x t -
A is (D/Q) s + Aiv (D/Q) , +
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 O 2.1-12
REVISION 2 AUGUST 1980 produce and leafy vegetable pathways; and see Table 7.2-7 or Table 7.2-10 for milk and meat pathways.)
(D/Qy ) Relative Deposition (m-2)
Factor, Vent Release 4
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 l.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 j 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 i leafy vegetable pathways; and
! see Table 7.2-7 or Table 7.2-10 for milk and meat pathways, i
2.1-13
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.
AEi
- 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.
I l
See Tables 7.1-2 and 7.1-3.
fg Seasonal Growing Factor 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.
2.1-14
REVISION 2 AUGUST 1980 Cf Milk Concentration (pCi/ liter) ,
The concentration of radionuclide i in milk.
Cf is calculated from the following equation (af ter Regulatory Guide 1.109 [ Reference 6.5] ) :
Cf=FM CfWg 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.
O V For milk and meat pathways, the following expression is to be used (after Regulatory Guide 1.109, [ Reference 6.5] ) :
Cf=f f f g Cy+(1-f) f Cs+f g (1-fg ) C s
(2.15) f g Pasture Grass Fraction l
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.
l l
t 2.1-15
REVISION 2 AUGUST 1980 Cy Pasture Grass (pCi/kg)
Concentration The concentration of radionuclide i is pasture grass (calculated using Equation 2.12 for cg 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 Cg 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.
O Wp 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 (br)
The average time from the production of milk to its consumption. See Tables 7.1-2 and 7.1-3.
Cf Meat Concentration (pCi/kg)
The concentration of radionuclide i in meat.
C[ = F p Cf Wg exp (- Ais t) (2.16)
J 2.1-16
.. - .-. -. -_ _ . ~ - . .
REVISION 5 FEBRUARY 1983 s 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.
2.1.2.1.2 Inhalation + Food Pathways Dose, Calendar Year (Four Consecutive Quarters) 3.17 x 10-0 x 10 6 R a DFA gg,
( X/Q) s A s + ( X/Q), Afy + ( X/Q) Afg +
i - -
DFI ija E + + E + $15 mrem 365 p V a (2.17) 2.1.2.2 10 CFR 20 Release Rate Limit The maximum dose rate to an organ of an adult from all radio-nuclides, radioactive materials in particulate form, and radio-l nuclides other than noble gases with half-lives greater than 8 days shall be limited to the values given by the equations which follow. For purposes of demonstrating compliance with the Technical Specifications, the dose to the adult from the inhalation pathway shall be considered limiting.
2.1-17
REVISION 5 FEBRUARY 1983 6 +
10 R DFAi ja ( VO) , 01 , + ( VO) y Q iy + ( #0) g Q ig K DFI ija U a Cf < 1500 mrem /yr (2.18)
K Seasonal Adjustment Factor K is a seasonal adjustment factor to account for nongrazing. For purposes of demonstrating technical compliance for the inhalation pathway, K = 0 throughout the year.
CM Milk Concentration (pci/ liter)
The concentration of radionuclide i in milk.
l Cf = FM Cf Wg exp (-A t t) M (2.19)
Cf Feed Concentration (pCi/kg)
The concentration of radionuclide i in feed.
Cf=d i xr 1 - exp (- A Ei tIe-A (2.20)
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 0 (D/0)g +0 (D/0)y Q ig (D/0) g ( 2. 21) 1 2.1-18
_ -.__ __-.___-_, _v
..-__ - _ = .- .-- - _ - . _ - . . . . - ...--. -- -. . -_ _ ..... __. ..- . .
i REVISION 2 l
AUGUST 1980 t l (D/Q) s See Table 7.2-7 or Table 7.2-10 for
- milk pathway. !
i i
See Table 7.2-7 or Table 7.2-10 for (D/Q) ,
milk pathway.
l (D/Q) See Table 7.2-7 or Table 7.2-10 for milk pathway.
i i
a 1
)
i i
i O
i a
I l
4 l
l a
2.1-19 l
l 4
,,--,,,yy, -,- er,-,--,-, - , ,
.,--=-,e w e,w aw,w w ,,-r-,..--wn-, m. -, - -,- , , , , - , . _ , .- _.-,n,_, m _ _ , , , , - , _.,,.a,,,_..-, a- ,, -,,,n,,, , -- - - -
REVISION.2 AUGUST 1980 t
2.1.3 Symbols Used In Section 2.1 SYMBOL NAME UNIT
- Sg Gamma Dose Constant, Stack Release (mrad /yr per UCi/sec)
A, g Accumulative Radionuclide Release Stack Release (pCl)
I V Gamma Dose Constant, Vent Release (mrad /yr per ECi/sec) 1 A gy Accumulative Radionuclide Release, t Vent Release (pCi)
Gg Gamma Dose Constant, Ground Level Release (mrad /yr per UCi/sec)
A gg Accumulative Radionuclide Release, Ground Level Release (UCi)
- Lg Beta Dose Constant (mrad /yr per UCi/m )
( X/Q) s Relative Effluent Concentration, Stack Release (sec/m )
A ls Accumulative Radionuclide Release from Stack, Adjusted for Radiodecay (pCi)
( X/Q)y Relative Effluent Concentration,
, Vent Release (sec/m )
A y Accumulative Radionuclide Release
- from Vent, Adjusted for Radiodecay (UCi)
I Relative Effluent Concentration, (X/Q)9 3 Ground Level Release (sec/m ) ,
A'g g Accumulative Radionuclide Release from Ground Level, Adjusted for Radiodecay
- R Downwind Range (m) u,u,uy Average Wind Speed, Stack, Vent, or x g Ground Level Release (m/sec)
{ Gamma Whole Body Dose Constant Stack Release (mrad /yr per DCi/sec) f
{ Gamma Whole Body Dose Constant, Vent Release (mrad /yr per UCi/sec)
{ Gamma Whole Body Dose Constant,
. Ground Level Release (mrad /yr per pCi/sec) 1
{ Beta Skin Dose Constant (mrem /yr per pCi/m )
2.1-20 4
REVISION 2 l AUGUST 1980 SYMBOL NAME UNIT Qh Release Rate, Stack Release (pCi/sec)
Og Release Rate, Vent Release (UCi/sec)
Og Release Rate, Ground Level Release (UCi/sec)
Q', Release Rate 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 (UCi/sec)
Ra Ind M dual Ah Intake Rate (m /yd DFA g$, Inhaladon Dose Factor (mrem /pCO DFI ija Ingestion Dose Factor (mrem /pCi) t r
Deposition Time (day)
U a Produce Consumption Rate (kg/yr)
(
U Milk Consumption Rate Leafy Vegetable Consumption Rate (liters /yr)
(kg/yr)
F U Meat Consumption Rate (kg/yr) a fp Produce Fraction fy Leafy Vegetable Fraction Cf Produce Concentration (pCi/kg)
Cf Milk Concentration (pci/ liter)
Cf Leafy Vegetable Concentration (PCi/kg)
Cf Meat Concentration (pCi/kg) d Deposition Rate (pCi/m .hr) i Cg Vegetation Concentration (pCi/kg)
(D/Q)s Relative Deposition Factor, Stack (m" )
Release (D/Q)y Relative Deposition Factor, Vent (m-2)
Release
~
(D/Q)g Relative Deposition Factor, Ground O Level Release (m )
2.1-21
REVISION 2 AUGUST 1980 SYMBOL NAME UNIT r Crop Retention Fraction A
Ei Effective Decay Constant (hr-1)
A f
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) fg Seasonal Growing Factor f
g Pasture Grass Fraction Cf Pasture Grass Concentration (pCi/kg) s C Stored Feed Concentration (pCi/kg)
Wg Feed Consumption (kg/ day) t M
ransport Mme @r)
F Meat Fraction (day /kg) 7 tg Slaughter to Consumption Time (br)
K Seasonal Adjustment Factor O
2.1-22
REVISION 2 AUGUST 1980
.l 2.1.4 Constants Used In Section 2.1
- O NUMERICAL VALUE NAME UNIT
-8 3.17 x 10 Conversion Constant (years /second) 0.7 Gamma Radiation Shielding and Occupancy Factor 1.0 Beta Radiation Shielding and Occupancy Factor 1.11 Conversion Constant (mrem / mrad) 6 10 Conversion Constant (PCi/pCi) 24 Conversion Constant (hr/ day) 365 Conversion Constant (day /yr) 3600 Conversion Constant (sec/hr)
O t
a 2.1-23
REVISION 2 AUGUST 1980 2.2 RADIOACTIVITY IN LIQUID RELEASES 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 U D
3 = (1.1 x 10 x 8760) A g DFI gj, exp (- A g t") +
1 U f A g DFI g$,By exp (- Ag t)
( 2. 22)
D Cumulative dose (mrem)
The cumulative dose or dose commitment to the total body or an organ j due to an adult consuming water and fish.
D 3
1 1.5 mrem to the whole body in a calendar quarter, (2.23) 1 5.0 mrem to any organ in a calendar quarter, (2.24)
$ 3.0 mrem to the whole body in any four consecutive quarters, and (2.25) 1 10.0 mrem to any organ in any four consecutive quarters. (2.26)
O 2.2-1
REVISION 2 AUGUST 1980 U", U Usage Factor (liters /hr, Os kg/hr) l 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 Near-Field Flow Rate (ft /sec)
Near-field flow of receiving body of water.
See Table 7.2-1.
Ag Total Radionuclide Release (UCi)
Total release of radionuclide i during period of release.
DFI g3, Ingestion Dose Factor (mrem /pCi)
The ingestion dose commitment factor for each l
identified gamma and beta emitter i, 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.
1 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 L______.__ _ _ -
I REVISION 2 AUGUST 1980 By Bioaccumulation Factor (liters /kg)
Bioaccumulation factor. See Table 7.1-12.
-3 1.1 x 10 = factor to convert from (pci/yr)/(f t3 /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 (MPCi ). 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 ( [ ~Cg + MPCg )
1 must not exceed 1.0 for each release. -
O The concentration of each radionuclide in the unrestricted area is calculated as follows:
t F (2.27) x Ci=C1 --
p d,p c and the combination of CD , F, E and F must meet the condition that:
100 x = 100 x * - 100% (2.28)
M i 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.
2.2-3
REVISION 5 FEBRUARY 1983 7_ Cf Concentration in the Discharge Tank (UCi/ml)
The concentration of radionuclide i in the (radwaste discharge or other similar) tank.
E 3 F Flow Rate, Radwaste Discharge (ft /sec)
The flow rate of radwaste from the discharge tank to the initial dilution stream.
F 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 (pCi/ml)
The maximum permissible concentration of nuclide i l'D (or unknown nuclide) in water in the unrestricted
(./
area (see Table 7.1-10; or 10 CFR 20, Appendix B, Table II, Column 2 including Note 3.c).
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 l water of the nearest surface water cupply is calculated as follows:
l t ) t
(} C"=Cf[F,+Ft F
(- A i x t")
Mg exp x 8760 (2.29) w g
)
2.2-4 i
l _ _ _ - _ . _ . _ . .
REVISION 2 AUGUST 1980 C{ Concentration in Water Supply (UCi/ml)
Cgs 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.
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)
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.
I 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.
O 2.2-5
REVISION 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Hencethemaximumquantityofradionuclide1(Af, curie) in each tank of interest, excluding tritium and the dissolved or entrained noble gases, which satisfies the limiting ccndition:
Cg i 1 (2.30) is:
A A
F"+Fh g yt (2.31) i * *E (~ i* w) o <4' w MPC'.
o \ 't
) "o V
Af Tank Radioactivity (Ci)
The quantity of radionuclide i in the tank of intetest.
l 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 rsdionuclide i in the tank of interest.
Ci exp (- A g
w xt)o <~
!"+F)
F o
t 1100 (2.32)
MPC g i
(p t
/ M" O .
2.2-6
i REVISION 2 '
AUGUST 1980 ;
l Derivation of Equation 2.31 Since, by Equation 2.30,
< 1 i MPC g where C isgivenbyEquation2.29andCfinEquation2.29 is given by:
6 t
A x 10 Ci/Ci (2.33)
Ci ,
y t x 3785 ml/ gal then:
= Cf [ pt ) M" tg/8760 exp ( A gt"g) 11 MPC. MPC t I I 1 (w+ o / (2.34)
'F 8 x 10 6 Af exp (- Aggt") <1 pw,pt yt 8760 3785 g MPC g (2.35)-
^
, l_ F exp (- A t") .5 1 4 pw 4 p t yt i MPC g (2.36)
Equation 2.36 on rearrangement gives:
A F +F exp (- A gt"g) 14 yt (2.37) i MPC g pt
( ) (M" )
O 2.2-7
REVISION 2 AUGUST 1980 2.2.4 Symbols Used In Section 2.2 SYMBOL NAME UNIT D Cumulative Dose (mrem) 3 U",U f Usage Factor (liters /hr, kg/hr)
I 1/M",l/M ,l/M" Additional Dilution Factor F" Average Flow Rate (ft /sec) f F Near-Field Flow Rate (ft /sec)
Ag Total Radionuclide Release (pCi)
DFI g33 Ingestion Dose Factor (mrem /pCi)
A i Decay Constant (hr-1) t",t ,t" Elapsed Time (hr)
By Bioaccumulation Factor (liters /kg)
C. Concentration at Unre-stricted Area (pCi/ml)
C i Concentration in Discharge Tank (UCi/ml)
E F Flow Rate, Radwaste Discharge
- 3 0
(ft /sec)
F Flow Rate, Initial Dilution Stream (ft /sec)
MPC g Maximum Permiss ble Concentration- ( pCi/ml)
C" Concentration in Water Supply (NCi/ml)
F Maximum Tank Overflow Rate (ft /sec)
F" Minimum Flow Rate, Receiving Body of Water (ft /sec) tg Release Time (hr)
Af Tank Radioactivity (Ci)
Vt Tank Volume (gal) 2.2-8
1 REVISION 2 AUGUST 1980 2.2.5 Constants Used In Section 2.2
, NUMERICAL VALUE NAME UNIT i
1.1 x 10~3 Conversion Factor (pCi/ liter)/ (pCi/yr)/(f t /sec) 8760 Conversion Factor (hrs /yr) 0 I 10 Conversion Constant (pCi/p Ci) t s
O r
1 0
2.2-9 ,
REVISION 3 NOVEMBER 1981 2.3 ENVIRONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE In accordance with the requirements of 40 CFR 190 (Reference 1 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.
2.3.1 Sources of Radiation and Radioactivity 2.3.1.1 Uranium Fuel Cycle - Definition The uranium fuel cycle is defined in 40 CFR 190 (Reference 6.12) to include:
- 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 aaing uranium fuel, and
- f. eprocessing of spent uranfum fuel.
i Specifically excluded are:
- a. mining operations,
- b. operations at waste disposal sites,
- c. transportation of radioactive material, and 2.3-1
REVISION 2 AUGUST 1980
() the use of recovered nonuranium special nuclear d.
or by-product materials from the cycle.
2.3.1.2 Radiological Impact of Uranium Fuel Cycle Operation i Environmental Radiation Protection Standards, 40 CPR 190, require j that the radiation dose resulting from all operations of the j cranium fuel cycle (except the specific exclusions noted) be l considered in determining compliance. Therefore, each of the operations will be discussed and the radiological impact in 1
the Commonwealth Edison Company (CECO) service area will be considered.
i 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 more than 100 kilometere 31stant, is expected to be negligible compared j to 40 CFR 190 limits.
i 2.3.1.2.2 conversion l Referr ace 6.14 (Section 3. 4) and Reference 6.15 (Page IV F-40
- and Table IV F-10) indicate that the maximum individual doses t
due to UF conversion will be less than 10 CFR 20 limits.
6 Therefore, the dose contribution to any person living in this service area due to UF conversion operations, all more than 6
- .100 kilometers distant, is expected to be negligible compared I to 40 CFR 190 limits.
4 2.3.1.2.3 Enrichment -
1 i 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
.i
-- . - . . - - . , , ~ . . - - - - , - - - - . , - , . - - - - , - - - , , , , - . , . , . . - r--
REVISION 2 AUGUST 1980 enrichment will be less than 10 CFR 20 limits. Therefore, 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 Reference 6.14 (Section 5.4) and Reference 6.15 (Page IV F-03) indicate that the maximum individual doses due to fuel element fabrication will be less than 10 CFR 20 limits. Therefore, 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, O,-
s 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.
I 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:
V D(R,P) = SF OF (2.28 x 10-5) P exp (-0.007 R) (2.38) 2.3-3
REVISION 2 AUGUST 1980 D(R,P) Dose Due to N-16 (mrem)
C--)/ 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 (mr em/MWe-hr)
' \C A constant to fit the equation to measured data.
P Electric Power Generhted (MWe-br)
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.
R Distance (m)
Distance from the turbine to the dose point of interest.
A
. V 2.3-4
REVISION 2 AUGUST 1980 t
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, at most, 0.1 mrem /yr for CECO Stations.
I In certain situations, more than one nuclear power plant site may contribute to a radiological dose to be considered in making l
40 CFR 190 dose assessment. At present (July 1979), the nuclear 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.
However, within CECO's service area the following future additive l
combination is considered. At some point within the triangle l formed by the La Salle, Dresden, and Braidwood Stations, an additive dose from airborne releases may be postulated. However, the distances are such (La Salle to Dresden, 39 kilometers; Dresden
( 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.
Therefore, the combined effect of airborne releases will not be considered further.
Such is not the case for future releases of radioactivity into the aquatic environment, where, if more than one facility uses 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 which flows into the Illinois at Dresden. Quad Cities and (the future) Carroll County Stations use the Mississippi River and (the future) Byron Station uses the Rock River which flows into the Mississippi at Moline, Illinois, downstream of Quad Cities.
For these two situations the combined impact from upstream liquid
() waste discharges must be considered at each downstream location.
2.3-5 l
REVISION 2 AUGUST 1980 The dose contribution of nuclear power plants in other service S
s_.) 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
- 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 CEOa's service area, at least a comment regarding it as a potential souice is warranted.
i 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
[
l general environment is expected, though some tritium has been found in groundwater near the Sheffield facility. However, no significant M.ose 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.)
i o O
I
! 2.3-6 i
f l __ _ _ _ _ - . - - -- _ _ _ - _ _ - - - - - - - -
REVISION 2 AUGUST 1980 2.3.1.2.8 Transportation 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 .
I been reviewed in References 6.16 and 6.17, and summarized again in Reference 6.15 (Chapter IV, Section G). The expected dose asso-ciated with transportation is 3.4 x 10 -3 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 Eleccric Company's Morris Operations Plant at Morris, Illinois, adjacent to CECO's Dresden Station. Minute quantities of Kr-85 and other radioactive particulates ate 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 wero :nade 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-ation plant are 6 x 10 4 pCi of tritium, < 55 x 10 6 pCi of Kr-85, 3 pCi of Co-60, and 1 'pci of Cs-137. The maximum whole body dose from these radionuclides is 4 x 10 -4 mrem /yr. So long as this plant remains a spent fuel storage facility and does not reprocess 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.
2.3-7 m
REVISION 3 NOVEMBER 1981 2.3.1.2.10 Long-Term Storage of High Level Radioactive Wastes 7-s The dose associated with the long-term storage of high level radioactive wastes is excluded from consideration as far as 4C 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
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 as computed at the nearest actual residence in each sector l
2.3-8 1
.. . _ _ _ _ _ _ _ _ _ - _ _ - - - - - _ - - _ _ _ - _ - - _ _ ~
REVISION 2 AUGUST 1980 (Table 7.2-4) ; and at Dresden only, the contribution from (4) noble gases, and (5) airborne "particulates" from the Morris Operations plant if spent fuel is reprocessed.
i 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 doso 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 occupancy 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 Dresden:
3 D (R, P) =
(1. 0) (0. 0 5) 2.28 x 10 -5 Pg exp (-0.007 x Rg) i=1 (2.39)
Ry = 488 m R,
2 R3 = 610 m Py Electric power generated (MWa-hr)
, by each unit in the year At Quad Cities:
D(R,P) =
(1. 0) (0.0 25) 2.28 x 10 -5 P exp (-0.007 R y ) +
exp (-0.007 R ) (2.40) 2_
Ry = 100 m R2 = 400 m
. P Electric power generated (MWe-hr) by the station l
, 2.3-9
i REVISION 2 AUGUST 1980 Table 2.3-1 shows the methodology for determining the maximum I
() 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 j 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 eau.1 sector, and the maximum value i
chosen to represent "any other organ" (AOO) for purposes of j 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.
i 2.3.2.2 Radioactivity in Liquid Releases 2
The maximum whole body, thyroid, and AOO doses from radioactivity in individual station liquid releases will be determined using, for the fish pathway, the near-field estimate of dilution at 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 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
- the average flow of the receiving body of water at the station. -
) Table 2.3-1 shows the methodology for determining these doses.
LC) 2.3-10
. _ - - . - - .-=- . .- . - - . . _ - .- _ - . .
REVISION 2 AUGUST 1980 2.3.3 Symbols Used in Section 2.3 SYMBOL NAME UNIT I
D(R,P) Dose Due to N-16 (mrem)
Skyshine SF Shielding Factor i
OF Occupancy Factor P, Pg Electric Power Generated (MWe-hr) by Station or Unit R Distance (m) t I
O i
l i e
O 2.3-11
f REVISION 2 AUGUST 1980
, 2.3.4 Constants Used in Section 2.3 NUMERICAL VALUE NAME UNIT 2.28 x 10-5 Fitted Constant (mrem /MWe-hr) 0.007 Fitted Constant (m" )
- 0.7 Shielding Factor at Home 1.0 Shielding Factor on a Boat 0.05 Occupancy Factor While Fishing 0.95 Occupancy Factor at Home for Fishermen 1.0 Occupancy Factor at Home for Everyone but Fishermen l
t t
1 i
i C) 2.3-12 l
t
q y \
f (v~3 TABLE 2.3-1 NUMERICAL MODELS FOR COMPUTING RADIATION DOSE JROM URANIUM FUEL CYCLE OPERATIONS"
, FUEL CYCLE CLASSIFICATION WHOLE ANY OTHER ORGAN FOOT-OPERATION OF RADIATION BODY THYROID GI-LLI BONE LIVER KIDNEY LUNG SKIN NOTES REACTORS
- 1. Noble Gases Equation Equation Equation 2.5 Equation -
2.5 2.5 2.7
- 2. Airborne Equation Equat' ion Equation 2.11 Equation b Iodine and 2.11 2.11 2.11 WB 78 Particulates Component
' W
- 3. Liquid Waste Equation Equation Equation 2.22 Equation c 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 i
- 6. Airborne N/A N/A Not Applicable N/A e Particulates gg 5a
- a. NE:
The maximum sector doses for the whole body, thyroid, and any other organ, summed over all d5 classifications of radiation, will be added to similar tissue doses received from radioactivity wa g ,o in liquid 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) .
O O O l
TABLE 2.^-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 < 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 doces from more than one station the dose from each upstream CECO station will be determined with Equation 2.22, using M"/F" instead of M /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.
- $l 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.
si sa
- B
~z e
REVISION 2 AUGUST 1980
() 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 3.2.2.1.1 Plume Rise (h ) .2-3 r
3.2.2.1.2 Terrain Correction (h p) 0 3.2.2.1.3 Downwash Correction (C) 3.2.2.2 Vent Stack Releases 3.2-5 3.2-6 3.2-6 3.2.2.3 Ground Level Releases 3.2-7 3.2.3 Removal Mechanism Considerations 3.2-7 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 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 3-1
)
REVISION 2 AUGUST 1980 f-ss 3.0 ATMOSPHERIC TRANSPORT, DIFFUSION, AND DOSE MODELS b ,
3.1 METEOROLOGICAL DATA FOR MODELS 3.1.1 Current Record Onsite meteorological data are used as input to all of the airborne dose calculations performed by a contractor. The data are obtained by means of an instrumented meteorological tower that measures wind speed and wind direction at 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.
For elevated releases, a joint frequency table (stability wind l
(~T 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.
The mixed-mode model for vent stack releases requires two stability wind roses: one to. represent the elevated part of the release and one to represent the ground level portion of the release.
These are developed jointly by considering the wind data hour by hour. The criteria for deciding how to proportion each hour's data between a vent release and ground level release 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 wind data are used.
s For ground level releases, the stability wind rose is developed
\ using the lower level wind data and lapse rate.
3.1-1
REVISION 2 AUGUST 1980
(~S 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 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 7.1-6), 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 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.
{
v 3.1.2 Historical Record Nuclear station operators will use the dispersion factors of Section 7.2 to demonstrate compliance with the Technical Spe-cifications. Depending on the station, there may be three classes (elevated, mixed mode, and ground level) of effluent I release, each with four types of dispersion factors:
(1) X/g, (2) D/Q, (3) S i, v , or G , and (4) S i, V g , or G i 1 1, 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
REVISION 2 AUGUST 1980 or an infant. If the recipient is an adult, the internal
() dose can consist of contributions from inhalation (X/0), 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 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.
Historical dispersion factors used in the internal dose models are found in Fection 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 directions for which X/O (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;
, 6. infant drinking mil!;; and
() 9. sum of 7 and 8.
3.1-3
. -. . - _. -. _ ._ .. . _=
REVISION 2 AUGUST 1980 3.1.2.2 External Dose ~
O The wind direction dispersion factors used in the whole body and gamma air external dose models are found in Section 7.2.
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 (Sf , Vg , or Gg) dose factors are computed for each of the 16 wind directions and each release class.
The dose factors for beta skin dose (Lg) and beta air dose (Lg ), two other types of external dose, are constants which do not vary with wind direction. Howev9r, they are combined in the dose models with X/O factors, which are wind direction dependent.
O
- O 3.1-4
REVISION 2 AUGUST 1980 '
3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS O 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)
[he} 2
, 2.032 f(u,0,s) (uS ) eXP z - 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.
X/Q Relative Effluent Concentration (sec/m )
(~T 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) l The downwind direction to point (R,0) .
l u Wind Speed (m/sec)
Ihe wind speed.
s Stability Class The atmospheric stability class.
I 3.2-1 1
REVISION 2 i
! AUGUST 1980 ;
l f . Joint Frequency.
i The observed frequency in which the wind blows with speed u, downwind direction 0, and atmospheric stability class s.
l ,
S, Corrected Vertical Dispersion (m)
Coefficient .
The vertical dispersion coefficient, corrected for building wake effects.
L l h, Effective Stack Height (m) l The effective height at which effluent t
j is released.
- l 3.2.2 Source Configuration Considerations The location of the source with respect to the buildings affects O how the airborne effluent will disperse. The following describes i
the criteria used to model airborne releases from nuclear power plants and describes how the model evaluates each case.
i
, 3.2.2.1 Elevated Releases l Release locations (chimneys, etc.) that are high enough to l 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 stac;. height is calculated by the following equation:
h, = h, + h r -h t (3.2) .
- 3. 2- 2
REVISION 2 AUGUST 1980 m h 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 t
Terrain Correction Factor (m)
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,) 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
varlation in tercain (h t)*
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 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 shown the basic relationship between h and other parameters.
r (h Ir l = 1.44d (Wg /u) (R/d) -C (3.3) 1 Wg Exit Velocity (m/sec)
The effluent stream velocity at the discharge point.
O 3.2-3
REVISION 2 AUGUST 1980 d Stach Diameter (m) 4 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.
l j 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 calculatiori.
(b Ir2=3 (Wg/u)d (3.4)
Therefore, h can be represented by the following formula for r
neutral and unstable conditions:
h = Min (hrl, I (hr2 I (3.5)
{' r Under stable atmospheric conditions, additional calculations are made as follows:
(h Ir3=4 (F/S) (3.6) 0 (h Ir 4 = 1.5 (F/u)I S- (3.7) 4 F Momentum Flux Parameter (.n /sec )
F=W*g (d/2) 2 (3.8)
S Stability Parameter (sec-2)
See following table.
O 3.2-4
REVISION 3 NOVEMBER 1981
~
Table of Values for St_ibility Parameter (S) (Sec )
O- 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 under stable con-r ditions. In other words, h
r
- Min (hr1, I (h Ir2, (h r) 3 , (h Ir4 (3.9) 3.2.2.1.2 Terrain correction (h It 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. Zinn terrain is comprised of marshy depressions and sandy ridges. Site-specific terrain i
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 (Hs ) at the release point from the height of the terrain at the receptor point (H r). The correction factor, h , is computed t
by Equaitons 3.10 and 3.11.
H rs
=H r
-H g (3.10) l Hrs; H rs >0 hg =
( 3.11) l H Terrain Height Dif ference (m) rs i Net difference between grade elevation of source and receiver locations.
3.2-5
REVISION 2 AUGUST 1980 H Terrain Height At Receptor Point (m)
() Grade elevation at the point of interest.
Hs Terrain Height At Source (m)
Grade elevation at the release.
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 i is accounted for by the term (C) in Equation 3.3 and this term is computed by Equation 3.12.
C = 3(1.5 - Wg/u)d ( 3.12) 3.2.2.2 Vent Stack Releases The constant mean wind direction model has been modified into
- a " mixed-moda" model. In a mixed-mode model the height of j % 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 I 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:
l -
4 1.00 ; Wg /u 1.0 l G =
- -l* I n/u) ; 1.0 /u 1.5 t 0.3-0.06 (Wg7u) ; 1.5 /u 5.0 l 0.00 ; W /u 5 0 o (3.13)
Gt Ground Release Fraction Fraction of time a vent release is considered a
() ground level release.
3.2-6
REVISION 2 AUGUST 1980 Therefore, the release can be considered as a ground level release 100G percent of the time and as an elevated release t
100(1-G ) percent of the time.
t 3.2.2.3 Ground Level Releases To calculate the downwind concentrations resulting from ground level releases, Equation 3.1 is used with the effective stack height set to zero (h =0). If the release is from a e
structure of maximum height (D z ), a correction is made to the dispersion parameter to account for the increased mixing caused by the building's wake effect. Equation 3.14 shows how this is accounted for in the model.
Oz ; no wake effect S = J- -
o 2 b z +D g / (2x) ; wake effect (3.14) a Vertical Dispersion Coefficient (m) z The vertical dispersion coefficient for use in atmospheric dispersion models. See Table 7.1-7.
Dg Maximum Height Of Neighboring Structure (m)
The maximum height of any neighboring structure causing downwind building wake effects.
When the wake effect is used the factor S z will be restricted ;
by the condition: '
S z
- U z (3.15) 3.2.3 Removal Mechanism Considerations 3.2.3.1 Radioactive Decay The loss of activity with time, due to radioactive decay, is accounted for by adjusting the source term. This adjustment 3.2-7
REVISION 2 AUGUST 1980 takes the following form:
Q' = O g exp (- gA t) =O g exp (- Ag R/3600u) (3.16)
Q' Corrected Release Rate (pCi/sec)
The release rate of radionuclide i corrected for radiodecay in transit.
Og Release Rate (pCi/sec)
The release rate of radionuclide 1.
A g Radiodecay Constant (hr~ )
The radioactive decay constant for nuclide 1.
See Table 7.1-9.
t Transport Time (hr)
The time required to travel a distance R downwind.
V 3600 Conversion Constant (sec/hr)
Converts hours to seconds.
3.2.3.2 Plume Depletion and Deposition As the plume travels downwind, the radiciodines 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)o Pd(he , s) (3.17)
P Plume depletion coefficient d
The function Pd recommcnded by the NRC (Regulatory Guide 1.111, l Figures 2-5) .is given in Section 7.1, Figures 7.1-1 to 7.1-4.
( 3.2-8 i
REVISION 2 AUGUST 1980 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/O is determined from one of the following equations:
D/Q = Dr(s, R, h) s (3.18)
D/Q = f (0, s) D r
(s, R, h) s (3.19) s D/Q Relative Deposition Factor (m )
The calculated relative deposition factor in a given direction.
D r
Relative Deposition Rate (m- )
The relative deposition rate is the deposition rate per unit downwind distance (pCi s-1 ,-1) divided by the source strength (pCi s-1)
For time periods At < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, Equation 3.18 is used. For t3me period At > 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, when the meteorological data are in uhe form of a atability 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 closest to the release height (h )*
r s For mixed mode releases, (D ) =
r y Gt (D Ir g + ( -G t ) (D rsI *
(3.19a)
A V
3.2-9
.. . = - . _ _ - - -. . . . . _ _ - - - - - - _ _ _ _ __ -
REVISION 2 AUGUST 1980 3.2.4 Symbols Used In Section 3.2 i
SYMBOL NAME UNIT i X/Q Relative Effluent Concentration (sec/m )
R Downwind Range (m)
O Direction (degrees or sector) l u Wind Speed (m/sec) ,
s Stability Class f Joint Frequency j S Corrected Vertical Dispersion (m) z l Coefficient h, Effective Stack Height (m) ,
h, Physical Stack Height (m)
! h r
Plume Rise (m) h Terrain Correction Factor (m) t l
Wg Exit Velocity (m/sec) i d Stack Diameter (m)
C Downwash Correction Factor (m)
F Momentum Flux Parameter (m /sec ) ~
S Stability Parameter (sec )
r H Terrain Height Difference (m) rs H Terrain Height at Receptor Point (m) r Hg Terrain Height at Source (m)
Gt Ground Release Fraction l oz Vertical Dispersion Coefficient (m)
D Maximum Height of Neighboring Structure (m) z Q[ Corrected Release Rate (pCi/sec)
Qg Release Rate -(pCi/sec)
A g Radiodecay Constant (hr-1)
Transport Time (hr) t P
d Plume Depletion Coefficient 3.2-10 d
_ _ _ _ _ _ _ - - _ - - - - ___. _ . - - - - _ - - , - _ , , . , , . . , . . - _ _ - ~ . . . _ , , , , _ . _ , . _ . - , _ , _ . _ _ , ___,___,r .
__e ,._ _ _
REVISION 2 AUGUST 1980 i
3.2.5 Constants Used In Section 3.2
- O
$HERICAL VALUE NAME UNIT j 3600 Conversion Constant I
(sec/hr)
-1 16/2x Sector Width (Radians
~
) j 2.032 Conversion Constant t
l
!O l
I t
O i
1 3.2-11 i
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 Y) is calculated from either of the following formulae:
DY (R,0 ) = 260 x 10-6 x 86400 x R x 2W/16 t* f(u,0,s)Q'; p ai ki III+ i 2)i m u i s (3.20)
DY (R,0 ) =
260 x 10 f(u,0, s) x R 2n/16 u i s O
Af p ai yi ( l+ i 2)g ( 3. 21)
DY (R,0 ) Gamma Air Dose (mrad)
The dose at (R,0) due to gamma rays.
1 R Downwind Range (m)
The distance downwind to point (R,0).
l 0 Direction (degree or sector)
The downwind direction to point (R,0).
260 Convers' ion Constant (mrad-radians-m3_
disintegration /
l sec-MeV-Ci)
Reconciles units of Equation 3.20.
O 3.3-1 i I
REVISION 2 AUGUST 1980
-6 10 Conversion Constant (Ci/pCi)
Converts Ci to ECi.
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)
The time over which the m th 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.
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 (p Ci/sec)
The release rate of nuclide i corrected I for radiodecay in transit.
3.3-2
REVISION 2 AUGUST 1980 pia Air Energy Absorption Coefficient (m-)
The gamma ray energy absorption coefficient for air, for nuclide 1 (see Table 7.1-9).
E p^ Average Energy per (MeV/
Disintegration disintegration)
The average gamma ray energy per disintegration of nuclide 1 (see Table 7.1-9) .
I 1+KT) g2 Dimensionless Numeric &l Integration Constant 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) x The release of nuclide i corrected for radio-decay in tre.nsit.
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 the doses from all sources at the station (i.e., elevated releases and vent releases).
Equation 3.20 was used to compute the normalized gamma air dose factors (mrad /yr per UCi/sec) S g (for stack releases); V g (for vent releases); and G y (for ground level releases). Site-specific values of S g , V g , and G,
y using historical meteorological data, are given in Section 7.2.
O 3.3-3
REVISION 2 AUGUST 1980 3.3.1.2 Whole Body Dose Factors O _ _
The whole body dose factors, S1 (for stack releases); vi (for vent releases) ; and G} (for ground level releases), in mrad /yr per DCi/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.
I The whole body dose DT(R,0), calculated for preselected ranges in each downwind sector, is given by the equation that follows:
DT (R,0) = 1.11 SFY D[(R,0) exp(-5 p ti 1
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.
SFY Shielding and Occupancy Factor for Gamma Radiation Accounts for reduction in gamma exposure to building shielding and occupancy at the point of interest.
uti Tissue Energy Absorption (cm /9)
Coefficient (Table 7.1-9)
The gamma ray energy absorption coefficient 4
in tissue for nuclide 1.
D (R,0) Gamma Air Dose (mrad)
The gamma air dose at (R,0) due to nuclide i as evaluated from Equation 3.20.
3.3-4 1
REVISION 2 AUGUST 1980 For this calculation, the shielding factor SFY is set to
() 0.7 and dose le computed at a depth of 5 cm in the tissue.
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/m3) and skin dose factor L g, mrem /yr per pCi/m , are given in Refe.e nce 6.5 and included in Table 7.1-13.
O l
3.3-5
REVISION 2 AUGUST 1980 p 3.3.3 Symbols Used In Section 3.3 SYMBOL NAME UNIT DT(R,0) Gamma Air Dose (mrad)
R Downwind Range (m) 0 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 )
Coefficient
{g Average Energy per (MeV/ disintegration)
Disintegration (Yy+Kg2T ) Dimensionless Numerical Integ;ation 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 (mradl pti Tissue Energy Absorption (cm /g)
Coefficient O
3.3-6
REVISION 2 AUGUST 1980 1
3.3.4 Constants Used in Section 3.3
. NUMERICAL VALUE NAME UNIT 260 Conversion Constant 3
([ mrad-radians-m -
4 disinte Mev-Ci]gration]/[sec-
)
10-6 Conversion Constant (Ci/pci) 86400 Conversion Constant (sec/ day)
, 2n/16 Sector Width (radians) '
, 1.11 Conversion Constant (mrem / mrad) i i
4 0 i
10 3.3-7 i
_ _ _ _ _ _ . _ = _ _ . _
M REVISION 2 AUGUST 1980 3.4 MODELS FOR CALCULATING DOSE FROM RADIOIODIjES, O "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-1 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 choicelof an infant as " critical person".
In the inhalation model, using historical meteorological informa-tion, radioactive decay but not plume depletion was considered.
O Plume depletion was not considered at this time because depletion j for the D atmospheric class, a class representative of a'rerage
! meteorology, reduces the inhalation dose by, at most, 10%
within the 3 kilometer range considered.
r 3.4-1
REVISION 5 FEBRUARY 1983
() 4.0 AQUATIC TRANSPORT AND DOSE MODELS TABLE OF CONTENTS PAGE 4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1-1 4.1 AQUATIC TRANSPORT 4.1-1 4.1.1 River Model 4.1-1 4.1.2 Lake Michigan Model 4.1-1 4.1.3 Symbols Used in Section 4.1 4.1-3 l 4.2 AQUATIC DOSE MODEL 4.2-1 4.2.1 Symbols Used in Section 4.2 4.2-2 4.3 AQUATIC TRANSPORT DURING TANK OVERFLOW 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 1
4-1
REVISION 5 FEBRUARY 1983 4.0 O AQUATIC TRANSPORT AND DOSE MODELS 4.1 AQUATIC TRANSPORT Dose via the aquatic pathway is discusssd 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. The nearest potable water intakes on the receiving bodies of water are described in a footnote to Table 7.2-1.
a For the fish consumption pathway, a near-field dilution flow F f is used; 1/M f = 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 cooling water of flow (F c ) 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).
O 4.1-1
, REVISION 5 FEBRUARY 1983 For the fish ingestion pathway only, it is assumed the radio-activity is diluted fully in a hypothetical river of flow F ; 1/Mf = 1.0. To determine F E , it was assumed that the near shore lake current (which can vary in width from 2 to 10 miles) constitutes a " river" 5 miles wide, 50 feet deep (the average lake depth from shore to 5 miles near Zion), and flows at the offshore, measured average speed of 0.2 mile per hour. This 3
results in Ff = 4.0 x 105 ft /sec.
i O
l l
l 4.1-2 l
l
.I REVISION 5 FEBRUARY 1983 4.1.3 Symbols Used In Section 4.1 O
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)
I 1/M Additional Dilution Factor
( (Fish Ingestion Pathway) c
{ F Average Flow of the (gal / min)
Condenser Cooling Water During the Period of Discharge
() 4.1-3
REVISION 2 AUGUST 1980 p 4.2 AQUATIC DOSE MODEL
'(/
The general model used to calculate the dose from radioactive material released in liquid waste is given in Subsection 2.2.1. The maximum consumption rate of fish by an adult,
-3
- U = 2.4 x 10 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 is assumed.
i l
I i
O 4.2-1
. 1
! i s REVISION 2 l l AUGUST 1980 I i
l i 4.2.1 Symbols Used in Section 4.2 l .
I' i
! SYMBOL NAME UNIT i ,
Uf Usage Factor (kg/hr)
I
! i I
i l e i
1 i
l t
r 4.2-2 I
REVISION 2 AUGUST 1980 4.3 AQUATIC TRANSPORT DURING TANK OVERFLOW CONDITIONS In Subsection 2.2.3, the limiting quantity of radionuclide i in tanks without overflow pipes connected to other storage tanks was determined to be a function of two dilution factors characteristic of the receiving body of water: F", the minimum flow of the receiving body of water during overflow conditions, and 1/M", an additional dilution factor.
4.3.1 River Model For purposes of calculating the limiting quantity of tank radioactivity spilled into a river of flow, F", and with a dam between the release point and the intake, it is assumed that total mixing of the discharge in the river occurs in the minimum river flow of the most recent past 10 years.
No additional dilution is assumed to occur; thus 1/M" equals 1.0.
O~
4.3.2 Lake Michigan Model For purposes of calculating the limiting quantity of tank radioactivity spilled into Lake Michigan, it is assumed i that F",g the initial dilution water, is zero and that the additional dilution factor, 1/M", is 1000. The 1000 factor represents an estimate of the dilution experienced by a 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 is 6500 faet northeast (1.1 miles north and 3000 feet out in the lake') at a depth of 35 feet.
O 4.3-1
. . . - _ _ - - - = .
REVISION 2 AUGUST 1980 4.3.3 Symbols Used in Section 4.3 0
SYMBOL NAME UNIT F Minimum Flow Rate, (ft /sec)
Receiving body of Water 1/M Additional Dilution Factor .
O i
O 4.3-2
REVISION 2 AUGUST 1980 5.0
SUMMARY
TABLE OF CONTENTS PAGE 5.0
SUMMARY
5.1-1 5.1 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-l' 5.2.2.2 Nearest Surface T.later Supply 5.2-1 5.3 URANIUM FUEL CYCLE 5.3-1 5.4 PRIMARY DRINKING WATER STANDARDS 5.4-1 O
l l
O 5-1 I _ . . _ _ . - . . -. _ ._--, -- __
REVISION 2 AUGUST 1980 5.0
SUMMARY
O LIST OF TABLES 4
NUMBER TITLE PAGE 4
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 i
. O 8
f l
I l
I O
5-ii
REVISION 2
, AUGUST 1980
,0 5.0
SUMMARY
5.1 AIRBORNE EFFLUENTS 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 guarter. The station will calculate the doses on a monthly basis. Each time the 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
- C, quarters to determine the annual dese.
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 j 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 l
doses.
For each dose type and maximum value, the compliance status is calculated where the status (%) = 100 x maximum dose
+ dose objective.
!O 5.1-1
REVISION 2 AUGUST 1980
() 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 format of Table 5.1-2 for periods of unusually high release rate Q.
( te from Eq. 2.9) x 100 C.S.WB (4) whole body (5.1) 500 crem/yr I f I C.S.S
= (%) skin (5.2) 3000 mrem /yr
( se rate from Eq. 2.18) x 100 C.S.g =
(%) 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 O
5.1-2
O O O TABLE 5.1-1 (Name) Unit (number [
MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES (PERIOD OF RELEASE FROM (DATE) TO (DATE). DATE OF CALCULATION (DATE))
, CURRENT CURRENT THIRD SECOND FIRST i TYPE PERIOD QUARTER
- QUARTER QUARTER QUARTER ANNUAL Gamma Air (mrad) Eq.2.10 dose (dir.) - NOTE: This format should appear in all 30 entries Beta Air (mrad) Eq.2.3 Whole Body (mrem) Eq.2.5 Skin (mrem) Eq.2.7 Organ (mrem) Eq.2.ll Last period of release from (date) to (date), calculated (date).
6 COMPLIANCE STATUS 10 CFR 50 APP. I 10 CFR 50 APP. I TYPE QUARTERLY OBJECTIVE % OF APP. I YEARLY OBJECTIVE % OF APP. I Gamma Air (mrad) 5 10 Beta Air (mrad) 10 20 Whole Body (mrem) 2.5 5 Skin (mrem) 7.5 15 $@
Organ (mrem) ** Q<
7.5 15 ***
gg o
aThe equation number of the model used to compute the dose for the period is listed here $2 for information only. mw
- Cumulative dose for the quarter including the current period.
- The critical organ is (Name).
- The critical organ is (Name).
REVISION 2 AUGUST 1980
( TABLE 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 ORGAN mrem / year mrem / year STATUS
- Whole Body 500 Eq. 5.1 Skin 3000 Eq. 5.2 (Name; Organa 1500 Eq. 5.3 O
AThe orgar with the maximum dose should be named.
- Fee text for definition. If C.S. > 100, add this or similar LJotnote 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.
O 5.1-4
REVISION 2 AUGUST 1980 5.2 LIQUID RELEASES 0
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 (Cg ) shall be limited to the concentrations specified in 10 CFR 20,
(^s Appendix B, Table II, Column 2 (MPC g). The concentrations cf dissolved or entrained noble gases shall be limited to the concentrations specified in Table 7.1-10. The sum of the fractional limits (Cf + MPC f) must not exceed 1.0 for each release.
Hence:
100 x < 100% (5.4)
MC g 5.2.2.2 Nearest Surface Watc.r 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, O( ,y Appendix B, Table II, Column 2 limits.
5.2-1
i REVISION 2 AUGUST 1980 ,
Hence:
A t [pw,p)t Yt exP (- A x t") 5 4 I - (5.5) I i MPC. i 1 F 1
! and Cf x t,)
[pw,pt) i exP (- A 1 g 1 o , 1100 (5.6)
MPC*.
kF t
/ M" O
f k
[
]
!O t
i I
i i
f I
O 5.2-2 l i m -~p,-, *w g-+ ..,y, , , , en._-g,.,,-,-,----,-.,v. -r,seww-,-, --,---,w-----.w ----,.,-+.--n, - , - - - - - - - - - - - - - - - - - - - - - -
O O O TABLE 5.2-1 (Name) Unit (number)
MAXIMUM DOSES RESULTING FROM LIQUID EFFLUEh"I'S (PERIOD OF RELEASE FROM (DATE) TO (DATE). DATE OF CALCULATION (DATE))
CURRENT CURRENT THIRD SECOND FIRST TYPE PERIOD QUARTER
- QUARTER QUARTER QUARTER ANNUAL Whole Body (mrem) dose - NOTE: This format should appear in all 12 entries Organ (mr em) dose Critical Organ name During Period Last period of relaase from (date) to (date), calculated (date).
y COMPLIANCE STATUS w
10 CFR 50 10 CFR 50, APP. I TYPE QUARTERLY OBJECTIVE % OF APP. I YEARLY OBJECTIVE % OF APP. I Whole Body (mrem) 1.5 3 Organ (mrem) 5 ** 10 ***
l l 5" l
- Cumulative dose in quarter to date @ -
mm
- The critical organ is (name) 8g
- The critical organ is (name) Ul*
gw
REVISION 2 AUGUST 1980 5.3 URANIUM FUEL CYCLE 0
The compliance status, with respect to the 40 CFR 190 limits, is determined in the following manner and reported in the i dormat 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 i (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.
l l
l O
5.3-1 l
i
_ . _ , ~ . _ _ ___
- = = . _ _ . . _
REVISION 2 AUGUST 1980 TABLE 5.3-1 0
(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 mig'ht 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 gg the requirements of 40 CFR 190.11."
O 5.3-2
REVISION 2 AUGUST 1980 5.4 PRIMARY DRINKING WATER STANDARDS 0
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.
l 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 l 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 limitt 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.
4 O
5.4-1 l
J 1 a
f l
TABLE 5.4-1 l (Name) Station
- PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM *
(PERIOD OF RELEASE FROM (DATE) TO (DATE) . DAT* OF CALCULATION (DATE))
i
! CURRENT CURRENT THIRD SECOND FIRST TYPE PERIOD QUARTER ** QUANTER QUARTER QUARTER ANNUAL i
Whole Body (aren) Dose NOTE: This format should appear in all 12 entries Internal Organ Dose (aren)***
Critical Organ Name Nama Name Name Name Name During Period ***
Last period of release from (date) to (date), calculated (date).
m
., COMPLIANCE STATUS 40 CFR 141 TYPE ANNUAL LIMIT 4 OF LIMIT Whole Body (area) 4 Internal Organ (ares) *** 4 Critical Organ During Year *** Name
- This calculation of dose is based on techniques described in the Commonwealth Edison Offsite Dose Calculation Manual. These techniques differ from those described in 40 CFR 141. A projected dose of 2 arem using Ceco's techniques is approximately $$
4 mrem using EPA methods. Any planned action shou 3d be based on the requirements gO
] of the regulation and not this report. @"
- Cumulative dose in quarter to date.
- Either thyroid, GI-LLI, bone, liver, kidney, or lung.
a -.,.2,a w +- -- - -' A6,- & < _ _ n'- +-
_ 41&aam -e .
REVISION 2 AUGUST 1980 1
6.0 REFERENCES
l tO TABLE OF CONTENTS PAGE i
6.0 REFERENCES
6.0-1 M
i l
l lO j
6-1
- - = . - -
REVISION 2 AUGUST 1980
6.0 REFERENCES
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.
4.3 " Radiological Health Handbook," U.S. Department of Health, i Education, and Welfare, Public Health Service, Rockville, Maryland, 1970.
6.4 Regulatory Guide 1.111, " Methods for Estimating Atac-l spheric Transport and Dispersion of Gaseous Effluents l in Routine Releases from Light-Water-cooled Reactors,"
! - U.S. Nuclear Regulatory Commission, Washington, D.C.,
i Revision 1, July 1977.
l 6.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for i
the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. Nuclear Regulatory Commission, Washington, D.C., Revision 1, October 1977.
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 Atc:aic Energy 1968,"
U.S. Atomic Energy Commission, 1968.
O 6.0-1 1
REVISION 2 AUGUST 1980 6.8 D. C. Kocher, Ed., " Nuclear Decay Data for Radionuclides O. Occurring in Routine Releases from Nuclear Fuel Cycle Facilities," ORNL/NUREG/TM-102, August 1977.
6.9 R. L. Feath, " Gamma-Ray Spectrum Catalog," Aerojet Nuclear Co. , ANCR--1000-2, third or subsequent edition.
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.
N-- 6.13 NUREG-0511 " Draft Generic Environmental Impact Statement on Uranium Milling," April '.979.
6.14 EPA-520/9-73-003-B, " Environmental Analysis of the Uranitim 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.
l 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.
6.0-2
, REVISION 2
, AUGUST 1980 4
i 6.18 U.S. Environmental Protection Agency, 40 CFR 141, O Federal Register 41, 133, 28402, July 9, 1976.
W. R. VanPelt, "
6.19 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.
O t
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O 6.0-3 l
-w w-,wq -- -
y , --+--w v-- -
g- , , -
REVISION 2 AUGUST 1980 7.0 DATA FOR DOSE ASSESSMENT MODELS TABLE OF CONTENTS PAGE 7.0 DATA FOR DOSE ASSESSMENT MODELS 7.0-1 7.1 DATA COMMON TO ALL NUCLEAR STATIONS 7 .1- 1 7.2 DATA SPECIFIC TO EACH STATION 7.2-1 O
O 7-i
_-,y,f.mv , ,,yr..-..--, ---. ,-,m,y,_ m-,,---..,._,y-..-w-, -w-, ~-, ,, - . _._-. __ - m _ _ -
REVISION 2 AUGUST 1980 7.0 DATA FOR DOSE ASSESSMENT MODELS LIST OF TABLES NUMBER TITLE PAGE t
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 Miscellaneous 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 i 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 4
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 Areas in Liquid Waste 7.1-24 Listing of Radiological Decay Constants 7.1-11 7.1-25 l
7.1-12 Dioaccumulation 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,
( respectively.
l l
7-il l
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 Relative 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 O .
7-lii
REVISION 2 AUGUST 1980 t
7.0 DATA FOR DOSE ASSESSMENT MODELS Virtually all of the data to be used in the dose assessment 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 4 to all stations.
I Section 7.2 contains site descriptions and data (particularly meteorological data) which is relevant only to a specific site.
a l
O 7.0-1
~ .. . -_ __..- . .. ...- - .. . - _. .. . . . . -. . ..-- -_.._ .- .__ . . - - . . . - -
REVISION < l MARCH 19 82 l I
f i
4 7.1 DATA COMMON TO ALL NUCLEAR STATIONS
- This section contains data that is generically applicable to all stations.
t i
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1 1
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4 J
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- 7.1-1 1
a
-r-,,-enw-w.-- rg,.e---mw,,m-,---,--,---r,.,,,e, m-a.--,nn,--wn.,,--~,,w--,,. - - . ., - ,,n- -e nn . - - - . _,-- , - - - - - - . - - . . - - - - - . - - - - - -- - - - - -
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 I
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 I
L l
O 7.1-2
REVISION 2 AUGUST 1980 TABLE 7.1-E-7 (4"'y4 J
INHALATION DOSE FACTORS FOR ADUI-T_ S. -
(mrem per p0i Inhaled)
HUCLICE 60NE liver T.ROCY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.58L-07 1. 5 8 F-0 7 1.59E ",7 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-0 7 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.26E-06 1.28E-06 1.28E-06 1.?RE-06 1.28E-06 P 32 1.65E-04 9.64E-06 6.26C-06 NO DATA NC DATA NO DATA 1.0aE-05 LR 51 NO DATA NO DATA 1. 2 5 E -0 8 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN $4 NO DATA 4.95E-06 f.81E-0T NO DATA 1.23L-06 1.75E-04 9.67E-06 MN $6 NO DATA 1.55F-10 2.21E-11 NO DATA 1.63t-10 1.18E-06 2.53E-06 FE 55 1.07E-06 2.12E-06 4. 9 5 E-0 7 NO DATA NO DATA 9.010-06 1.54E-07 FE 59 1.475-06 3.4 7E-Oo 1.3/E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.9P'-07 2. 59E-0 7 NO DATA NC DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.*4E-06 1.85E-36 NO DATA NO DATA T.46E-04 3.56E-05 NI 6 5 5,40E-05 3.9 3E-06 1.81E-06 40 DATA NO DATA 2.23E-05 1.67E-06
_ ._..._____. ..........._. _____ ..._______ _....___==. - _ _ . _ _ _ . . _.....
) il 65 1.92E-10 2.02E-11 1.14 F -1 1 NO DATA NO DATA 7.00E-07 1.54E-06
'N / CU 64 NO DATA 1.936-10 T.61F-11 NO DATA 5.18E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29F-05 5.82C-06 NO DATA R.62E-06 1.08E-Ce 6.68E-06 ZN 69 4.23t-12 8.140-12 5.65E-13 NO DAT4 5.27L-12 1.15E-07 2.04E-09 dR 83 NO DATA JU DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 HR 84 NO DATA NO DATA 1.9tE-08 NO DATA NO DATA NO DATA 2.05E-13 3R 85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E-24 12 8b NO DATA 1.61E-05 7. 31E-0 6 NO DATA NO DATA ho DATA 2.08E-06 90 88 NO DATA 4.P45-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 R8 89 NO DATA 3.2CE-08 2.12E-08 NO DATA NO DeTA NO DATA 1.16F-21 SA 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24t-02 NO DATA 7.62E-04 NO DATA NC DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3. I lE-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43C-10 NO CATA 1.64E-11 40 DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 40 DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3./6E-11 NO DATA 1. 2 7 E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.18E-05 NO DATA 1. 5 5 E -0 6 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DSTA 3.77C-11 NO DATA NO DATA 1.96E-06 9.19E-06 k
v 4) 7.1-3
REVISION 2 AUGUST 1980
\
l J
TABLE 7.1-E-7 (Cont'd)
NUCLIJL BONE LivFR T. BODY THYROID KIONFY LUNG GI-LLI Y 93 1.18E-05 NO UAIA 3.26E-10 NO DATA NC OATA 6.06E-06 5.27E-05 2R 95 1.34E-05 4.3CE-06 2.91E-06 NO DATA 6.77E-06 2 21E-04 1.38E-05 ZR 97 1.21E-08 2 45C-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9. 7 7L-0 7 5.26E-07 Nn DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 40 CATA 1. 51 E- 08 2. 8 7E-0 9 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99P 1.29E-13 3.64E-13 4.65E-12 40 DATA 5.52E-12 9.55E-08 5.20E-07 IC101 5.22E-15 7.52E-15 7. 3 d E -14 NO CATA 1.35d-13 4.99E-08 1.36F-21
.RU103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.3tE-05 1.38E-05 RU105 9.880-11 NO DATA 3.89E-11 NO DATA 1.27L-10 1.17E-06 6.02E-06 RUl06 8.64[-06 NO DATA 1.01E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AC110P 1.35E-06 1.2SE-06 1.45[-07 NO DATA 2.46E-06 5.79C-04 3.78E-05 TC125M 4.27E-07 1.99E-07 5.84E-08 1.51E-07 1.556-06 3.92E-05 8.83E-06 TE127M 1.58E-06 7.21C-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05
) TE127 1.75E-10 .H.054-11 3.87E-11 L.12E-10 6.37E-10 8.14E-07 7.17E-06 N_s/ IC129r 1.22E-06 5.b4C-07 1. 9 a E -0 7 4. 30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22C-12 2.19E-12 1.55E-12 4. 8 7t-12 2.34E-11 2.42E-07 1.96E-08 IE131M 8.14E-09 5.45E-09 J.63r-09 6.88F-09 1.86E-08 1.82E-05 6.91E-05 IF131 1.39E-12 7.44E-Il 4.49E-13 1.17E-12 5.46E-l? 1.7%E-07 2.30E-09 TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37F-05 I 130 5.72E-07 1.68E-06 6.600-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 l 131 3.15E-06 4.47E-Oo 2.560-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 l I 132 1.45E-07 4.07E-07 1. 4 5 E -0 7 1.43E-05 6.48E-07 NO DATA 5.08F-08 1 133 1.08E-06 1.855-06 5. 65E-0 7 2.69E-04 3.23E-06 NO DATA 1.11E-06 1 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10
____..__.....____.----..._______________...__________z - - -- =
I 135 3.35E-07 8. 7 3E-07 3.210-07 5.00E.05 1.39E-06 NO DATA 6.56E-07 CS134 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30f-06 CS136 4.88E-06 1. 8 3E -05 1.38E-05 10 CATA 1.07E-05 1.50E-06 1.46E-06
_....______..____.___....__..._...___...--._....____....=- - - - - _ - _ - -
CS137 5.98E-05 7.76E-05 5. 3 5 C-0 5 NO DATA 2.78E-05 9.40E-06 1 05F-06 CSI)U 4.14E-08 7.76E-08 4.0iE-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 HA139 1.17E-10 8.32E-14 3.42C-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 l ...._____.. ______ ...._____.._........____......_ ...._________............
t
\
7.1-4 l
I
REVISION 2 AUGUST 1980 n
v TABLE 7.1-E-7 (Cont'd)
NUCL!cE BUNE LIVER T.dOGY THYROID KIDNEY LONG GI-LLI HAl40 4.98E-C6 6.13F-09 1./1E-0T NO calA 2.09E-09 1.59E-04 2.73F-05 MA141 1.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42t-07 1 45E-17 R4142 3.29E-12 3.JPM-15 2.07E-Il NO DATA 2.96E-15 1 49E-07 1.96E-26 L A 14 0 4.10E-C8 2.17E-08 5. TIE-09 NU OATA NO DATA 1.70E-05 5.73E-05 LA142 8.54E-11 S.88E-Il 9.64E-12 NO DATA NC DATA 7.91E-07 2.64E-07 CEl41 2.49E-06 1.692-06 1. 91 L-0 7 NO CATA 7.R36-07 4.52E-05 1.50E-05 CF143 2.llE-CA 1. 72E-O d 1.91L-09 NO DATs 7.60E-d9 9.97E-06 2.83E-05
- E144 4.29E-04 1.79E-04 2. 30F .0 5 NO DAT4 1.06E-04 9.72E-04 1.02E-04 PRt43 1.17E-06 4.69E-07 5. 99t -0 8 *4n DATA 2.70E-07 3 5tE-05 2.50E-05 PR144 3.76E-12 1.369-12 1.91E-13 NO CATA 8.RIE-13 1.27F-07 2.69E-18 ND14 7 6.59E-07 7.62E-07 4. 5 6 E -0 8 NO DAT4 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-13 3.10E-10 NO DATA NC DATA 3.63E-06 1.94E-05
. NP239 2.B7E-08 2.82E-09 1. 5 5 E -0 9 NO DATA 8.75t-09 4.70F-06 1.49E-05 l
i i
i t
7.1-5
REVISION 2 AUGUST 1980 TABLE 7.1-E-10 (h
Gl INHALATION DOSE FACTORS FOR INFANTS (mrem per pCi Inhaled)
NUELICE BUNE LIVER T..tnDY THYROID KIDNEY LUNG GI-LLl H 3 NO DATA 4.62E-07 4.620-07 4.62F-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79C-06 3. 79E-0 6 3.79E-06 3.79E-06 5.79E-06 3.79E-06 NA 24 7.54E-C6 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 12 1.45E-03 8.CJE-05 5.53E-OS NC DATA NO DATA NC DATA 1 15E-05 CR 51 NO DATA NO DATA 6.51E-08 4.11E-08 9.45E-09 9 17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7 14E-04 5.04E-06 NN 56 NO DATA 1.10E-0's 1. 5 8 E-10 40 UATA 7.86E-10 R.95E-06 5.12E-05 FE 55 1.4tE-05 H.39E-06 2. 3 S E-0 6 Nn DATA NO DATA 6.21E-05 7.82E-07 9.69E-06 1.682-05 6. 7 TE-0 6 NO DATA NO DATA 7.2SE-04 1.77E-05
,o 40 DATA 8. 71t-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95F-06 60 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 N1 6 s 2.42E-04 1.46E-05 8. 2 9E -0 6 NU DATA NO DATA I.49E-04 1.73E-06
..______..______..__....... . .._____...._______ .._______ ..._ ....___=-
NI 65 1.71E-09 2.050-10 U.79E-11 NO DATA NO DATA 5 80E-06 3.58E-05
/"'N -CU 64 NO DATA 1.34E-09 5.5 3 F-10 40 DATA
()--
IN 65 1.38E-05 4.4 7F-L 5 2.22E-05 NO DATA 2.84E-09 6.64E-06 1.07E-05 2.32E-05 4.62E-04 3.67E-05 IN 69 3.85E-11 6.91E-k1 5.11E-12 NO DATA 2.R7E-11 1.05E-06 9.44E-06 RR 83 NO DATA NO DATA 2. 72E-0 7 NO DATA NC DATA NO DATA LT E-24 3R 84 NO DATA NO DATA 2. 86E-0 7 NO DATA NO DATA NO DATA LT E-24 r.R 82 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 30 86 NO DATA 1.36E-04 6.30E-OS NO DATA NO DATA NO DATA 2.17E-06 10 88 NO DATA 3.98E-07 2.036-0 7 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 No DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NU DATA 1.85F-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 1,76E-05 5.24E-05 SR 92 7,50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 y 90 2.35[-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y 91F 2.91E-10 NO DATA 9.90E-12 NO DATA ND DATA 1.99E-Ca 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 F
\_-
7.1-6
REVISION 2 AUGUST 1980 m i TABLE 7.1-E-10 (Cont'd) i BONF LIVER T.800Y THY 20lO KIDNEY LONG GI-LLI
.'JU CL I C E Y 91 1.07E-0F NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 LR 95 d.24E-05 1.19E-05 1.45E-05 NO DATA 2.22t-05 1.25E-01 1 55E-05 2R 9T 1.070-07 1.83E-08 8.16E-09 NU DATA 1 85E-08 7.88E-05 1.000-04 NR 95 1.12E-05 4. 5 9 t-06 2.70E-06 NO DATA S.57E-06 3.42E-04 9.05E-06 MO 99 NO UATA 1.18t-0T 2. 31 E-0 8 NO Daft 1.89E-07 9.63E-05 1.48E-05 IC 99M 9.98t-11 2.06E-12 2.66E-11 NO DATA 2 220-11 5.79E-07 1.45E-06 TC101 4.65t-14 5.99E-14 5.80E-13 NO DATA 6.9?E-13 4.17E-07 6.03E-07 RU103 1.440-06 40 DATA 4.85C-0F NU OATA 1.01E-06 3.94E-04 1.15E-05 T4U105 8.74E-10 NU OATA 2.9 sE-10 NO DATA 6.42E-10 1.120-05 3.46E-05 RUl06 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1 17E-04 AG1104 7,13E-06 5.160-06 1.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 1C125M 3.40E-06 1.42C-06 4. 70E-0 7 1.16E-06 NO DATA 3.19E-04 9.22E-06 3 ...............________._ --- ...._............____.. _..____ ......___.....
TE127* 1.19E-OS 4.93E-06 1.406-06 1.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3. 4 9E-10 1.32E-09 3.47E-09 7.39E-06 1.74F-05 TE129r 1.01E-05 4.35E-06' !.596-06 1.91E-06 2.27E-05 1.20E-03 4.93E-05
.........._____ .==_ _=__________ _. ____._.... ___ ._.....................
TE129 5.63E-Il 2.48E-11 1.34E-11 4.82E-11 1.2SE-10 2.14E-06 1.88E-05 TE131N 7.620-08 1.73E-08 2.51E-08 6.38E-08 1 89E-07 1.4?E-04 8.51E-05 TE131 1 24E-Il 5.87E-12 3.57E-12 1.13E-Il 2.85E-Il 1.47E-06 5.87E-06 TE132 2.66E-07 1.69F-07 1. 26E-0 7 1.99E-O' 7.19E-07 2.43E-04 l.15E-05 1 130 4.54E-06 9.91E-06 3.98E-06 1.14E-01 1.09E-05 NO DATA 1.42E-06 1 131 2.71E-05 3.11E-05 1.49E-05 1.06E-02 3.70E-05 NO DATA T.56E-07 I 132 1.?!E-06 2.5 3E-06 8.99E-07 1.216-04 2 82C-06 NO DATA 1.36E-06 I Ils 9.46E-06 1.51E-05 4.00E-06 2.546-03 1 60E-05 NO DATA 1.54E-06 I 13* 6.58E-07 ! . 3 %C-06 4. 75E-0 7 1.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.4]E-06 1.99E-06 4.97E-04 6.05E.06 NO DATA 1.31E-06 C5134 2.83E-04 5.02E-04 5.32E-95 NO DATA 1 16E-04 5.69E-05 9.53E-07 C5136 3.45E-05 9. ole-05 3.1B E-0 5 NO DATA 4. 01E -0 5 8.40E-n6 1.02E-06 CS137 3.92E-04 4.lTF-04 3.25E-05 N0*0ATA 1.23E-04 5.09E-05 9.530-07 C5138 3.6tE-07 5.58E-07 2.84E-07 NO DATA 2.9)E-07 4.67E-08 6.26F-07 UA159 1.060-09 7.01E-13 3.0TE-Il NO DATA 4.21E-13 4.25E-06 3.64F-05 k
(
s 7.1-7
l 4
l l
REVISION 2 4
AUGUST 1980 ,
I A
\ ,
t .
TABLE 7.1-E-10 (Cont'd)
J NOCLICI DONE LIVER T . tt uuY lHYRulD KtDNLY LONG GI-LLI BA140 4.00E-05 4.00E-08 '2.07F-OL NO DATA 9.59E-09 1.14F-03 2.74E-05 84141 1.12E-10 f.70r-14 3.55c-12 NO DATA 4.64L-14 2.12E-06 5.19F-06 4A142 2.04E-11 2.365-t* 1.4cE-l? NU OATA 1.36L-14 1.tlE-06 4.95E-07 LAt40 1.6tE-C7 1. ' 3t-4 7 5.6dE-03 No DATA NO DATA 1.20E-04 6.06E-05 LA142 7.36E-10 2 . t.9 t - 10 c. 4on-11 40 DATA NO DATA 5. 8 FF-06 4.25E-05 CE141 1.18E-05 1.19E-05 1.4/L-06 NO DAIA 1.F5t-06 1.09F-04 1.54E-05 CE143 2.090-07 1.151t -0 7 1. 5 H F -0 8 'JO DATA 4.03t-08 8.30E.ns 3.55E-05
~.E144 2.28E-03 8.oSE-04 1.20E-04 NO DATA 3.H4E-04 7.0lE-03 1.96E-04 68 R 14 3 1.00E-05 1.74E-Oc 4.910-07 NO DATA 1.4 t tia06 3.09E-04 2.66E-05
- PR144 3.42E-Il 1.32[-!! l.120-12 NO CATA 4.90E-12 1.15F-06 3.06F-06 l
10141 5.6TE-Ot> 5.8tF-06 5.57E-01 40 DATA 2.25t-96 2.30E-04 2.23E-05 W 187 9.26E-09 6.440-09 2.2SE-01 NO UAIA NO DATA 2.83E-05 2.54F-05 NP239 2.65E-07 2.liC-09 1.14E-09 NO DATA 4.73L-08 4.25E-C5 1.78E-05 s
7.1-8
-y-- - r e - m - - - - , - - - --. - - - - - - -- .-=
REVISION 2 AUGUST 1980
,m e \
. (V' TABLE 7.1-E-ll INGESTION DOSE FACTORS FOR ADULTS (mrem per pCi Ingested)
HUCLILE 90NE LIVER T. HOLY THYROID KIDNEY LONG GI-LLI H 3 No DATA 1.050-O/ 1.CSE-0 7 1.056-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.6 8E-0 7 5.6eE-97 5.68E-07 5.6EE-07 5.68E .07 NA 24 1.70F-06 1.70F-06 1.70E-06 1.10E-06 1.70E-06 1.70E-06 1.70E-06 9 32 1.93E-04 1.20F-05 7. 4 6 E -O b 10 UATA NC OATA NO DATA 2.17E-05 CR 51 NO DATA NO CATA 2.6cE-09 1 51E-09 5.86E-10 3.53Es09 6.69E-07 MN 54 NO UATA 4.575-06 9.72E-01 NO DATA I.56E-06 NO DATA 1.40E-05
.................... .........___... .__ ___...........____..__ .== ._...
MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67F-06 rC 55 2.75E-06 1.70F-Oc 4.4 3E-0 7 10 DATA NO DATA 1.06E-06 1.09E-06 FE $9 4.34E-06 1.02C-05 3.9tE-06 No DATA NO DATA 2.85E-06 3.40E-05 C0 56 NO DATA 7.456-07 1. 6 7 E -0 6 in DATA NO DATA NO DATA 1.51E-05 CO 60 40 DATA 2.14F-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05
/"% NI 63 1.30E-C4 9.01E-Oo 4.36E-06 NO UATA NO DATA NO DATA 1.c8E-06
( .,_.......................... ._................................_ ..........
N NI 6s 5.28E-07 6.66E-08 1.13 E -0 8 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 9.332-08 3.91E-08 'NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 63 4.84E-06 1.>45-05 c . 90 E -0 6 NO DATA 1.03E-05 NO DATA 9.70E-06
....._.._ ._.........___.................................<-._ ==._ .....
ZN 69 1.01E-08 1.7?E-08 1.3FF-09 NO DATA 1.28E-08 NO DATA 2.96E-09 HR 83 40 D ATA NO DATA 4.02E-OH NO DATA NO DATA NO DATA 5.79E-08 RR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14 E -0 9 NO DAT1 NO DATA NO DATA LT E-24 R8 86 NO DATA 2.11E-95 9. 6 3 E -0 6 NO DATA NO DATA NO DATA 4.16E-06 R8 Bf - NO DATA 6.05E-08 4.21E-08 NO DATA NO DATA NO DATA 8.36E-19 R4 89 NO DATA 4.01E-08 2. 8 7 E-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.J8E-C4 NO DATA 8. 8 4 E -0 6 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.21E-9T NO DATA NC DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NC CATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2. S a E -10 NO DATA NG DATA NO DATA 1.02E-04
-=............
Y 9tM 9.09E-11 NO DATA 3.52E-12 NO DAT% NO DATA NO DATA 2.67E-10 Y 91 1.41E-C7 40 DATA 3. 7 7E-0 9 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO CATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 7.1-9
REVISION 2 -
AUGUST 1980 At i V
TABLE 7.1-E-ll (Cont 'd)
NULLluE 80NE LIVER T.h0CY THY 90lc KIDNEY LUNG GI-LLI Y 95 2.68E-09 NO DATA F.400-11 No GAIA NO DATA NO DATA 8.50E-05 ER 95 3.04E-OP 1.75E-09 6. 6 0 L- 01 NO DATA 1.53L-08 NO DATA 3.09E-05 ZR ?T 1.68E-09 3.$9E-10 1.55E-LO NO DATA 5.12E-10 NO DATA 1.05E-04 NR 95 6.22E-09 3.46E-09 1. 86 E-0 9 NO CATA 3.42E-09 NO DATA 2.10E-05 MD 99 NO DATA 4. 31E-06 8.200-07 10 DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.9AE-10 8.89E-09 NO DATA 1 06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 5. 5 9 E -0 9 NO DATA 6.59E-09 1.87E-10 1.10E-21 4U103 1.85E-07 NO DATA 7.97E-08 NO DATA i.06E-07 NO DATA 2.16E-05 Rul05 1.54E-08 NO CATA 6. 0 9 E -0 9 NO DATA 1.99E-07 NO DATA 9.42E-06 3010s 2.15E-06 NO DAit 3. 4 9 E-0 7 NO DtTA 5.31E-06 $0 DATA 1.78E-04 AG110M 1.60E-07 1.4 8 F , / 8.790 08 NO DATA 2.9tE-07 NO DATA 6.04E-05
. TE125M 2.69E-06 9.flE.07 3. 59L -0 7 8.06F-37 1.09E-05 NO CATA 1.07E-05 s .............. ____..........__.............__ ... ____ ..._........__._....
} TE12Fw 6.77E-06 2.42C-06 8.250-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 N- ' TE127 1.10E-0T 3.95E-08 2.3HE-08 8.15E-08 4.48E-07 NO PATA 8.68E-06 TE129u 1.15E-05 4.29c-Co 1.R2E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 IE129 3.14E-08 1.18E-08 F.e>E-09 2.4tE-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-0 7 1.340-06 8.57E-06 NO DATA 8.40E-C*
TEl31 1.97E-08 8.23C-09 6.22E-09 1.62E-08 S.63L-08 NO DATA 2.79E-09
) ....._. __....._______.... .... ._ .____.. __..... ________._.........__....
IE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.210-06 8.80E-07 1.89C-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 j I 132 2.01E-07 5.43F-07 1.90E-07 1.90E-05 8.65L-07 NO DATA 1.02E-07 l
1 133 1.42E-06 2.4FE-06 7.53E-0 7 3.63E-04 4.310-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.O sE-0 T 4.99E-06 4.58E-07 NO DATA 2.51E-19 l 135 4.43E-07 1.16E-06 4. 2 SE-0 7 7.65E-05 1.86E-C6 NO DATA 1.31E-06 C5134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79t-05 1.595-05 2.59E-06 CSl36 6.5tE-06 2.57E-05 1. 8 5 E -0 5 40 DA TA 1.43E-05 1.96E-06 2.92E-06 C515T 7.97E-05 1.09E-04 7.14 E -0 5 NO DATA 3.70t-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-Op NO DATA 8.01E-08 7.9tE-09 4.65E-13 BA139 9.70E-08 6.91E-11 2. 84 E -0 9 NO DATA 6.46E-11 5.92E-11 1.72E-07 s
i
\
- %s /
7.1-10 t
. _ . . _ . . _ , -. ~ , -
REVISION 2 AUGUST 1980 s
)
TABLE 7.1-E-ll (Cont'd) 1UCL i t'E BONE L IVER T.dODY THYR 010 KIDNEY LUNG GI-LLI 6A149 2.01E-05 2.55E-09 1. 3 3 E-0 6 40 NATA 8.67t-09 1.46E-08 4.18E-05 cA141 4.llE-08 4.56E-11 1 51E-0 9 NO DATA 3.3tE-11 2.02E-11 2.22E-17 MAh,2 2.13E-08 2.19E-Il 1.34E-99 40 DA?A 1.35F-11 1.24E-11 1.00E-16 LA140 2.50L-09 1.262-01 J.33E lO NO DATA NO DATA NO DATA 9.25E-05 L A142 1.20E-10 5.02E-Il 1.450-11 NO DATA NC DATA NO DATA 4.25E-07 OE141 9.360-0T 6.35E-09 1.19E-10 NO Daft 2.94E-09 NO DATA 2.42E-05
............ 4 .............................................................
CE143 1. 6 5 t =41 1.22f-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.566-05 CE144 4.48E-07~ 2.046-07 2.62E-08 NO DATA 1.2t(-07 NO DATA 1.65E-04 PR141 9.20E-09 3.692-09 4.56E-10 NO DATA 2elli-09 40 DATA 4.03E-05
.............................n..............................................
4 Ptl44 3.01E-11 1.255-11 1.S50-12 NO DATA 7.05E-12 NO DATA 4.33E-18 NDl41 6.29E-C9 7.27E-09 4. 4 5E-10 NO DATA 6.25E-09 NO DATA 3.49E-05
,. h 19T 1.03E-07 9.6th-08 3.01E-06 NO DATA NO DATA NO DATA 2.82E-05 ;
\ ............................................................................
,,/ HP239 1.19E-01 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 l.
l l
t l
7.1-11 i _ _ . _ _ _ _ _ _ - _ - - . - _ _ . - - _ . _ - - - - _ _ _ - - - - _ __ __
REVISION 2 AUGUST 1980 O i TABLE 7.1-E-14 sJ INGESTION DOSE FACTORS FOR INFAN'IS (mrem per pCi Ingested) 1 1HCLicL LIVER GI
.................................................................._....-LLI BUNE T . t10bY THY 1010 MIONEY LONG H 3 NO DATA ~ 3.0d*-07 s.06E-0 T s.09F-07 1.03L-07 3.COE-0F 3.08E-07 L 14 2.1FF-05 5.060-06 5. 0 0 E -0 6 5.06f-06 5.06t-06 5.06F.06 5.06E-06 NA 24 1 01E-05 1.01E-02 L . Ol t -9 5 , l . 012 -65 1.9tE-05 1.01E-05 1.01E-05 v 32 1.70E-03 1.002-04 6.59t-05 NU UATA NO DATA NO DATA 2.10E-05 Od 51 NO DATA 40 DATA 1.41E-08 9.200-99 /.01E-09 1.79E-08 4.11E-07 AN 54 TJ DATA 1.99E-02 4.51t-06 NO DATA 4.41E.06 NO DATA T.31E-06
.......- ~.........................._-_........................_......._...
HN 56 Nu DATA 8.18E-07 1.41F-07 Nu UATA 7.01E-07 NO DAT4 7.43F-05 FE 55 1.39E-05 8.'38I- 06 2.4EE-06 NO DATA NO DATA 4.19E-06 1.14E-06 FF 59 3.08E-05 5.385-Os 2.12E-05 NO CATA NU DATA 1.59E-05 2.57F-05 CD 58 NO OtTA 3.60f.nb 8.910-06 NO bATA NO DATA NO DATA 8.9FE-06 CG 60 Nn 0AIA 1.00t-05 2.55E-05 NO DATA NO DATA NO DAT4 2.5FE-05 NI 61 6.14E-G4 3.92E-05 2.20E-05 NO DAT4 NO DATA NO CATA 1.95E-06
('~s'"-) NI 63
%U 64 4.70E-06 NO DATA
?.32E-OF 6.09L-07 2.426-07 2.8/E-07 NO DATA NO DATA f0 4 DATA 1.03E-06 NO DATA NO Daft 4.05E-05 1.25E-05 (N 63 1.54C 6.21E-05 2.91E-03 NO DATA 1.06E-05 NO DATA 5.33E-05 (N 61 9.33E-08 1 08E-Of 1.250-08 NO DATA 6.98E-08 NO DATA 1.3FF-05 HR 83 NO DATA NO DATA 3.63 E-0 7 NO DATA NO DATA NO DATA LT E-24 bR 8* NO DATA NG UATA 3.820 07 NO DATA NO DATA NO DATA LT E-24 OR 85 NO DATA NO DATA 1 94 E-0 8 NG DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.105-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 dB 88 NO DATA 4.986-07 2.73E-0T NO DATA NO DATA NO DATA 4.43r-07 RP 89 NO DATA 2.U6E-07 1 97E-97 NO DATA NO DATL NO DATA 9.74E-08 SR 89 2.51E-03 ND DATA 7. 20E-0 5 NO DATA NO DATA NO DATA 5.16E-05 >
SR 90 1.056-02 NO DATA 4.71E-C3 10 DATA NO DATA NO DATA 2.)lE-04
...... _ . _ . __...______________..___ ..............................u..._.
SR 91 5.00E-05 NO D%TA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 53 92 1.92E-05 NO DATA 7.13E-0 7 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 10 DATA 2.3sE-09 NO CATA NO DATA NO DATA 1.20E-04 Y 91M 8.tCE-10 NO DATA 2.76F-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA un DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DITA NO DATA NO DATA 1.46E-04
(_
- 7. 1- 12
REVISION 2 AUGUST 1980
/^'s 3
V TABLE 7.1-E-14 (Cont'd)
NUCLICE 80 1 LIVER T.000Y THYROID KIDNEY LONG GI-LLI Y 93 2.41E-08 NO DATA 6.62F-10 NO DATA NO DATA NO DAin 1.92F-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.stE-08 NO DATA 2.50F-05 2R 97 1.48E-08 2.54E-09 1.160-09 NO DATA 2.56E-09 NO DATA 1.62E-04 Nu 95 4.20E-08 1.FIE-0J 1. 0 3 E -0 8 NO DATA 1.74b-08 NO DATA 1.46E-05 MO 99 NO DATA 3.4C2-05 6.6tE-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 91F 1.92E-09 3.965-09 5.10E-09 N0'OATA 4.26t-08 2.07E-09 1.15E-06 TC101 2.27E-01 2.86E-09 2.83E-0C NO DATA 3.40E-OR 1.56E-09 4.86E-07 RU103 1.48E-06 NO UATA 4.95E-0 7 NO DATA 3.08E-06 NO DATA 1.80E-05 10105 1.36E-07 NO DATA 4.51E-08 10 DATA 1.00E-06 NO DATA 5.41E-05 9U106 2.41E-05 NO DATA 1.016-06 NO DATA 2.85k-05 NO DATA 1.83F-04 4G110M 9.96E-07 7.2FC-0T 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE12)M 2.33E-05 7.79E-06 3.12 E-0 6 7.84E-06 NO DATA NO DATA 1.11E-05 TEl27M 5.85E-05 1. ME-05 7.0aE-06 1.69E-05 1.44E-04 ho DATA 2.36E-05 f)/
s, TEl27 1.00E-06 3.355-07 2.15E-07 8.14E-07 2.44e.06 NO DATA 2.10E-05 TE129M 1.00E-04 3.45F-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE129 2.84E-07 9.79E-08 6.65E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE131* 1.5?E-05 6.12E-06 5. 05 E-0 6 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE131 1.76E-07 6.50E-08 4.940-08 1.37E-07 4.50E-07 NO UATA 7.11E-06 TE132 2.08E-05 1.03E-05 9. 61 E -0 6 1.570-05 6.44E-05 NO DATA 3.81E-05 t 130 6.00t-06 1.12E-15 5. 30E -0 6 1.48E-93 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-0) 1.9eE-05 1.39r-02 4.94E-05 NO DATA 1.51E-06 I 132 1.66E-06 3. 4 7F-06 1. 2 C E-0 6 1.58E-04 3.76E-06 NO DATA 2.73E-06 1 133 1.25E-05 1.82r-05 5. 3 SE-06 1.31E-03 2 14E-35 NO DATA 3.08E-06 ,
t 134 6.69E-07 1.78E-06 6.33E-OF 4.152-n5 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.490_04 9.07E-06 NO DATA 2.62E-06 C5134 3.77E-04 7.03E-04 7.10E-0 5 NO DATA 1.810-04 T.42E-05 1.11E-06 CS136 4.59E-05 1.55E-04 5.04E-05 NO DATA 5.38L-05 1.10E-05 2.05E-06 C5137 5 22E-04 6.11E-04 4.43E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 C5138 4.816-07 7.02C-0T 3. 79E -0 7 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07 5.e4E-10 2. 5 5E-0 8 Nu DATA 3.StF-10 3.54E-10 5 58E-05 (v
7.1-13
REVISION 2 AUGUST 1980 en k
TABLE 7.1-E-14 (Cont'd) wuCLIJE BONF t!VER T . .t C LY THYWOID KIDNEY GI-LLI 3A14u 1.TLE-04 1.71E-07 9.RIE-06 LUNG ...............
NO DATA 4.06E-08 1.0SE-G7 4.20E-05 pal 41 4.250-C7 2.912-10 1. 3
- t J' 8 NO DATA 1.75E-10 NAl42 1.84E-07 1. Sit-10 I.7TF-lC S.19E-06 9.06E-09 NO DATA B.91E-11
..................................s.........................26E-Il LA140 2.11L-08 8.32s-09
- 9. 7.59E-07 2.140-09 NU UATA NU OAIA NO DATA 9.77F-0$
L A142 1.10E-09 4.u'E-10 9.6 /F -11 NO DATA NC DATA NO DATA CCl41 7.87E-08 6.867-05 4.n05-08 S.69E-09 NO DATA 1.48E-08 NO DATA CE145 1.48E-08 9.c2C-Oo 1.17E-09 2.48E-05 ........
NO CATA 2.96t-09 NO DATA 5.73E-05 CE144 2.982-06 1 22E-06 1.6TE-07 NO DATA 4.93E-07 NO DATA PRl*) s.13E-08 1.flE-04 3.c4L-08 4.0lE-09 NO DATA 1.13E-08
................................................................TA PR144 2.74L-10 1.06E-10 NO DA 4,29E-05 1.310 11 NO DATA j.84t-11 NO DATA 4.9 3E-06 14D14 7 S.53E-08 5.68E-G8 1.4nE-09 NO GATA 2.19t-08 rio DATA 1.60E-OS w 187 9.03E-07 6.2de-07 2.1 ?f -0 7 NO CAIA NO DATA N NO DATA 1.69C-05
) NP259 1.1tE-02 9.93L.10 S . 61 F -10 '40 UATA 1.98E-09 NO DATA 2.8 7F-o i
{
i I N d
- 7. 1- 14
REVISION 2 AUGUST 1980 TABLE 7.1-2 MISCELLANEOUS DOSE ASSESSMENT FACTORS - ADULT
(=310 liters /yr 3
i R, = 8000 m /yr P
U a = 520 kg/yr U = 64 kg/yr U,F = 110 kg/yr p = .76 f
fy = 1.0 th = 0 for pasture grass (inilk and meat pathways) th = 24 hr (1 day for leafy vegetables) th = 1440 hr (60 days for produce) t h
= 2160 hr for stored feed (milk and meat pathways) t, = 720 hr (30 days for milk and meat) t, = 1440 hr (60 days for produce or leafy vegetables) fg = 1.0 May-October fg = 0.0 November-April g = 0.5 f
O Ay = .0021 hr-1 7.1-15
REVISION 2 AUGUST 1980 TABLE 7.1-2 (Cont'd) ,
2 j Y y = 2.0 kg/m for leafy vegetables and produce pathways )
I 2
Y y = 0.7 kg/m for milk and meat pathways l
i s = 480 hr (20 days) t r = 1.0 (iodines) 0.2 (others) i 1 W g = 50 kg/ day l
l t = 48 hr (2 days)
M O ;
/
O 1 7.1-16
REVISION 2 AUGUST 1980 TABLE 7.1-3 MISCELLANEOUS DOSE ASSESSMENT FACTORS - INFANT l ( = 330 liters /yr U ,#, U , U,# =0 3
2 R, = 1400 m /yr Wg = 50 kg/ day r = 1.0 (iodines)
- 0.2 (others) t M
= 48 hr (2 days) n -1 A, 0.0021 hr i
Yy = 0.7 kg/m 2 t, = 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> t
h = 0 for pasture grass (milk pathway) t h = 2160 hr (stored feed and milk pathway) f f
= 1.0 May-October l
fg = 0.0 November-April f
g = 0.5 K = 0.5 May-October K = 0.0 November-April O *The r factor provides for the non-deposition on grass of the organic forms of iodine.
7.1-17 i
l l
REVISION 2 AUGUST 1980 TABLE 7.1-4 STABLE ELEMENT TRANSFER DTTA*
Fp FM(Cow)
Element Meat (d/kg), Milk (d/1)
H 1.2E-02 1.0E-02 :
C 3.1E-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 3.0E-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 8.0F-03 1.4E-02 Zn 3.0E-02 3.9E-02 Rb 3.1E-02 3.0E-02 Sr 6.0E-04 8.0E-04 i Y 4.6E-03 1.0E-05 Zr 3.4E-02 5.0E-06 Nb 2.8E-01 2.5E-03 Mo 8.0E-03 7.5E-03 p
d Tc Ru 4.0E-01 4.0E-01 2.5E-02 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 l- La 2.0E-04 5.0E-06
( Ce 1.2E-03 1.0E-04 Pr 4.7E-03 5.0E-06 Nd 3.3E-03 5.0E-06 W 1.3E-03 5.0E-04 Np 2.0E-04 5.0E-06 Br 2.9E-03** 1.4E-02***
- 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 to Man Via the Forage-Cow-Milk Pathway From Radionuclides Released to the Biosphere," UCRL-51939.
C4 7.1-18 l
f
,_ _- _ .- _ _ ~ _ _ __ .. -- - - . . - -
O O O i
i I
TABLE 7.1-5 1
ATMOSPHERIC STABILITY CLASSES
+
PASQUILL U TEMPERATURE CHANGE STABILITY O' WITH HEIGHT DESCRIPTION CLASS (SEE NOTE, BELOW) (*C/100 m)
Extremely A >22.5* <1.9
- Unstable Moderately B 17. 5
- to 22.5 * -1.9 to -1.7 Unstable i
y Slightly C 12.5* to 17.5* -1.7 to -1.5 ,
i -
Unstable
) Y*
$ Neutral D 7.5* to 12.5* -1.5 to -0.5 Slightly E 3.8
- to 7.5 0 -0.5 to 1.5 Stable Moderately F 2 . l
- to 3 .8 o 1.5 to 4.0 Stable i
Extremely G 0* to 2.lo >4.0 ,
Stable '
c
' a -
CH i mm-dH ,
O NOTE: 0 is the standard deviation of horizontal wind direction fluctuation over a HZ pSriodoe15minutesto1 hour. $w o
_ - _ _ _ , . . = - . . . . - . . . - . . . _ - - - - . - - . _ - - - - . - . . _ . . . - . . . . - . .
REVISION 2 AUGUST 1980
\
] l O '
l l TABLE 7.1-6 4
WIND SENSOR THRESHOLD ANEMOMETER VANE LOCATION WIND SPEED (mph) WIND DIRECTION (mph)
Dresden O.8 09 j Quad Cities 0. 6 0.8 Zion 0.5 0.7 LaSalle 05 0.7 Braidwood 0.8 0.8
! Byron O.8 O.8 l Carroll County 05 07
( ,
l 4
i
!O 4
1 7.1-20
REVISION 2 AUGUST 1980 TABLE 7.1-7
("'/)
u.
HORIZONTAL AND VERTICAL DISPERSION PARAMETERS
- Horizontal Dispersion Parameters, o , meters **
o y = aR R = downwind range, meters
- STABILITY l
CLASS 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 0.9031 F 0.0722 0.9031 G 0.0481 0.9031 O Vertical Dispersion Parameters' z, meters **
a z = aR +C STABILITY 100 < R < 1000 R> 1000 i 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 l
l
- From Reference 6.21.
f_s
- Values of o y and a z are also limited to a maximum of 1000 meters.
7.1-21
REVISION 2 AUGUST 1980 TABLE 7.1-8 O
i WIND SPEED AND WIND DIRECTION CLASSES Wind Direction Classes WIND DIRECTION CLASS (DEG) N WIND DIRFCTION GT 348.75 AND LE 11.25 l 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 AU9 LE 78.75 WIND DIRECTION CLASS (DEG E WIND DIRECTION GT 70.75 AND LE 101.25 WIND DIRECTION CLASS (DEG) ESE WIND DIRECTION GT 101.25 AND LE 123 75 WIND DIRECTION CLASS (DEG) SE WIND DIRECTION GT 123 75 AND LE 146.25 WIND DIRECTION CLASS (DEG) SSE WIND DIRECTION GT 146.25 AND 1.E 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 l WIND DIRECTION CLASS (DEG) SW WIND DIRECTION GT 213 75 AND LE 236.25 l WIND DIRECTION CLASS (DEG) WSW WIND DIRECTION GT 236.25 AND LE 258.75 l WIND DIRECTION CLASS (DEG) W WIND DIRECTION GT 255.75 AND LL 281.25 l WIND DIRECTION CLASS (DEG) WNW WIND DIRECTION GT 281.25 AND LE 303 75 WIND DIRECTIO!4 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 O l Wind Speed Classes WIND SPEED CLASS (MPH) 1 WlHD SPEED GE 0.0 AND LT ST*
WIND SPEED CLASS (MPH) 2 WIND SPEED GE ST AND LE 3.5 WIND SPEED CLASS (MPH) 3 WIND SPEED GT 35 AND LE 75 WIND SPEED CLASS (MPH) 4 WIND SPEED GT 75 AND LE 12 5 WIND SPEED CLASS (MPH) 5 WIND SPEED tit 12.5 AND LE 18.5 WIND SPEED CLASS (MPH) 6 WIND SPEED GT 18.5 AND LE 24.5 WIND SPEED CLASS (MPH) 7 WIND SPEED GT 24.5 AND LE 31 5 WIND SPEED CLASS (MPH) 8 WIND SPEED GT 31 5 AND LE 38.5
, WIND SPEED CLASS (ni II) 9 WIND SPEED GT 38.5 AND LE 46.5 l WIND SPEED CLASS (MPH) 10 WIND SPEED GT 46.5 AND LE 99 8 i l l
- ST: Speed Threshold Value 7.1-22 l
1 -
f) !3 IO G' V \.)
TABLE 7.1-9 AIRBORNE ISOTOPE DATA 0 o Tissue Energy **
Isotope Decay
- Average Energy
- Linear Energy Linear Constant Per Disintegration Absorption Attenuation Absorption Coeff.
(1/hr) (Mev/ dis) in air in air Ki A
i Eg EB (1 eter) (1/ meter) = u - ua Kr-83m 3 79E-1 2 58E-3 3.82E-2 37 37 0 4.87 Fx-85 7 38E-6 2c23E-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 i
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 "K~-90 r 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 0.093 0.51 0 533 Xe-133 5 51E , 4.60E-2 1 35E-1 0.0066 0.028 3 24 0.0566 Xe-1335 1.32E-2 4.1CF-2 1 90E-1 0.0076 0.03 2 95 0.0674 Xc-135 7.63E-2 2.48E-1 3 17E-1 0.0036 0.015 3.17 0.0305
. Xe-135m 2.66E+0 4.31E-1 9 58E-2 0.0038 0.012 2.16 0.0326 ,,
C C1 Xe-137 1.09E+1 1.82E-1 ' 78
. 0.0035 0.016 3 57 0.0293 85 mm Xe-138 2 93E+0 1.13 6.32E-1 0.0035 0.0075 1.14 0.0301 [$
Ar-41 3 79E-1 1.28 4.64E-1 0.0034 0.0072 1.12 0.030 kN
- Computed from data in Reference 6.8
- The Academic Constants Press( Table XXII) .t) were obtained from Radiation Dosimetry, Vol. I, Attix and Roesch, editors,1958, oother values from Radiological Health Handbook, Revised Eiition, January 1970.
i REVISION 2 AUGUST 1980 O
TABLE 7.1-10 MAXIMUM PERMISSIBLE CONCENTRATION OF D_ISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE MPC(uCi/ml)#
l Kr 85 m 2E-4 85 SE-4 87 4E-5 88 9E-5 Ar 41 7E-5 Xe 131 m 7E-4 133 m SE-4 133 6E-4 135 m 2E-4 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 /Pt = 1.0.
l 7.1-24 1
I
REVISION 2 AUGUST 1980 TABLE 7.1-11 7- LISTING OF RADIOLOGICAL DECAY CONSTANTS (fi) A U
DECAY CONSTANT ISOTOPE Ai(hrs-1)*
H-3 6.40E-6 C-14 1 38E-8 Na-2h 4.52E-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-50 4.08E-4 Co-60 1 50E-5 Ni-63 8.23E-7 N1-65 2.75E-1 cu-64 5.46E-2 zn-65 1.18E-4 Zn-69 7.29E-1 Br-8,3 2 90E-1 Br-M 1 31E+O r~s Br-85 1.45 E+1 k ,)
m Rb-86 1.55E-3 Rb-88 2 34E20 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 l Y-91M 8.36E-1 l 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 l
7.1-25
REVISION 3 NOVEMBER 1901 TABLE 7.1-11 (Cont'd) l
['a DECAY ISOTOPE CONSTAN{)*
A g (hrs-l Ru-106 Ag-110M 7.84E 1.15E- k 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 1.66E+0 Te-132 8.86E-3 I-130 5 61E-2 I-131 3 59E-3 I-132 3 01E-1 I-133 3.33E-2 I-134 7.90E-1 I-135 1.05E-1 Cs-134 3.83E-5 Cs-136 2.20E-3 Cs-137 2.62E-6 Cs-138 1.29E+0
- C,x) Ba-139 5 03E-1 Ba-140 2.26E-3 Ba-141 2.28E+0 4
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 Nd-147 2.61E-3 W-187 2 90E-2 i Np-239 1.23E-2 Sb-124 6.94E-4
- Ai= Radiological Decay Constant Ti = Radiological Half-life Ai= (693 / Tifrom Reference 6.8)
A For unlisted nuclides, see References 6.8 and 6.9.
p .
U 7.1-26
REVISION 3 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 I
H 9.0E-01 C 4.c2+03 Na 1.0E+02 P 1.0E+05 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E403 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E401 Y 2.5E+01 S Zr 3.3E400 Nb 3.0E404 Mo 1.0E401 Tc 1.5E401 Ru 1.0E401 Rh 1.0EMI Te 4.0E402 I 1.5E401 Cs 2.0E403
- Ba 4.0E400 La 2.5E+01
! Ce 1.0E+00
, Pr 2.5E401 Nd 2.SE+01 W l.2E403 Np 1.0E401 Ag 2. 3 E400 *
- Table A-lc of Reference 6.5.
- S. E. Thompson, " Concentration Factors of Chemical EleDt:nts
- in Edible Aquatic Organisms," UCRL-50564, Revision 1, 1972.
l
'O 7.1-27 l
O O O TABLE 7.1-13 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- i BETA AIR BETA SKIN CAMMA AIR CAMMA WHOLE DOSE FACTOR DOSE FACTOR DOSE FACTOR BODY DOSE FACTOR
! L 51 X i i Xi NUCLIDE (mrad /yr per 1rCi/m ) 3 (mrem /yr per uC1/m3 ) (mrad /yr per pCi/m 3) (mrem /yr per UCi/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 i
Kr-85 1.95E+03 1.34E+03 1.72E+01 1.61E+01
,4 Kr-87 1.03E+04 9.73E+03 6.17E+03 5.92E+03 i Kr-88 2.93E+03 2.37E+03 1.52E+04 1.47E+04 Co 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 1.11E+03 4.76E+02 1.56E+02 9.15E+01 e
Xe-133m 1.48E+03 9.94E+02 3.27E+02 2.51E+02 l
Xe-133 1.05E+03 3.06E+02 3.53E+02 2.94E+02 Xe-135m 7.39E+02 7.11E+02 3.36E+03 3.12E+03
. Xe-135 2.46E+03 1.86E+03 1.92E+03 1.81E+03 '
Xe-137 1.27E+04 1.22E+04 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 gg Gr-999*** 4.00E+03 4.00E+03 6.37E+03 3.43E+03 h I
- From Table B-1 of Ref ence 6.5.
- 2.88E+02 = 2.88 x 10
- Parameters to assess a " gross" noble gas release, E 0.8 MeV, Eg ~ 0.56 MeV.
I
1 REVISION 2 AUGUST 1980 l
[ 8
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O O n O O O C O h 3 Wold NI DNINIVW3B NOllovud 'P d O' FIGURE 7.1-1 PLUME DEPLETION EFFECT FOR GROUND-LEVEL RELEASES (ALL ATMOSPHERIC STABILITY CLASSES)
(FROM FIGURE 2 0F REFERENCE 6.4)
O O O l i 1.0 a=
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REVISION 2 AUGUST 1980 104
/"N,
(.) _
104 \ '
m
- x t
t 5 %
e T t E h
- A Ks ti
=
i 8 10-5 p \
s
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l \ \
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'v' y \ %
10-6 a
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10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
FIGURE 7.1-5 RELATIVE DEPOSITION FOR GROUND-LEVEL RELEASES n (ALL ATMOSPHERIC STABILITY CLASSES)
() (FROM FIGURE 6 0F REFERENCE 6.4)
REVISION 2 10-3 AUGUST 1980 O
UNSTABLE (A,L,C) 10-4 s*C 8
g I
/ N '% . .
- - w -
g [ \\ NEUTRAL s / NN z
r
/NEU IRAL (D) s qsgN h 10-5
/ Q STABLE m
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y 7.w xs w / / AN % A
$ / / \ t o 2 / / N %
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STABLE (E,F,G) x" 3 a" i i f I r
)
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l l
10'7 1 0.1 1.0 10.0 100.0 200.0 l PLUME TRAVEL DISTAf4CE (KILOMLTERS) l FIGURE 7.1-6 RELATIVE DEPOSITION FOR 30m RELEASES
, (^S (LETTERS DEN 0TE PASQUILL STABILITY CLASS)
\s.) (FROM FIGURE 7 0F REFERENCE 6.4) 1
REVISION 2 AUGUST 1980 g
..__- .~._Z. 3
~
% UNSTABLE (A,B,C)
[ \ l 1
/ A s l 10-6
/
( h NEUTRAL (D) 4 l l g
y I j
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lE / \ ^ w '
UNSTABLE
'E / \ %
NEUTRAL N m 3 f 's b 10-6 y , .
, r-r us I s 2
O l ~
(
l /
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.,10-7 STABLE (E,F,G) u l '
o u . ------ ,
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10-8 i l 0.1 1.0 10.0' 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) l FIGURE 7.1-7 RELATIVE DEPOSITION FOR 60m RELEASES pb. (LETTERS DEN 0TE PASQUILL STABILITY CLASS) l (FROM FIGURE 8 0F REFERENCE 6.4) l
REVISION 2 AG 0 104 y
__ UNSTABLE (A,B.C)
/
f ) A N
\ ss 10-5 j p - h x
y f EUTRAL (D) % \g '
E / / N
' s
= / / N s .
E / / N NT '
Q f %
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NO DEPLETION
- 10-7 ;
f o 1 1
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FIGURE 7.1-3 i
RELATIVE DEPOSITION FOR 100n RELEASES
( (LETTERS DEN 0TE PASQUILL STABILITY CLASS)
(FROM FIGURE 9 0F REFERENCE 6.4)
BYRON REVISION 5 FEBRUARY 1983 LIST OF TABLES FOR SECTION 7.2 O :
NUMBER TITLE PAGE 7.2-1 Aquatic Environmental Dose Parameters 7.2-1 7.2-2 Annual Design Objectives Set By 10 CFR 50, Appendix I, for Each Reactor 7.2-2 7.2-3 Station Characteristics 7.2-3 7.2-4 Critical Ranges 7.2-4 7.2-5 Terrain Correction Factors (h ) 7.2-5
- 7.2-6 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary 7.2-6 7.2-7 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles 7.2-8 7.2-8 Maximum Offsite Finite Plume Gamma Dose Factors for Selected Nuclides 7.2-9 i
I i
7.2-1
4 BYRON REVISION 5 FEBRUARY 1983 LIST OF FIGURES FOR SECTION 7.2 i
NUMBER TITLE 7.2-1 Restricted Area Boundary O -
i i
t 7.2-11
BYRON REVISION 5
, FEBRUARY 1983 TABLE 7.2-1 AQUATIC ENVIRONMENTAL DOSE PARAMETERS l PARAMETER BYRON U", water usage, liters /hr 0.042 f -3 U , fish consumption, kg/hr 2.4 x 10 1/M", 1/M f 1 F", cfs 5.2 x 10 4*
3 F f , cfs 4.7 x 10 t f , hr** 24
, t", hr*** 120 By Regulatory Guide 1.109, Revision 1, October 1977, Table A-1, Column 2 for freshwater fish. See Table 7.1-12.
F t, cfs 5 F", cfe 1/M[ Not Applicable. No outdoor tanks t"'
o hr F without overflow pipes connected to other storage tanks.
V, gal to, hr
- 4 F" = sum of average Mississippi Rjver flow of 4.7 x 10 cfs plus the Rock River 5.0 x 10 cfs at como, Illinois, 45 miles downstregm. The average flow of the Rock River is 4.7 x 10 cfs at the site.
- t f (hr) = 24 hr (all stations) for the fish ingestion pathway
- t" (hr) = 120 hr (distance to Mississippi River is approx-imately 120 miles; flow rate of 1 mph assumed) 7.2-1 l
.a
BYRON REVISION 5 FEBRUARY 1983 TABLE 7.2-2 O ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, APPENDIX I, FOR EACH REACTOR TYPE OF DOSE ANNUAL DESIGN OBJECTIVES i
Airborne Releases Gamma Air Dose 10 mrad Beta Air Deee 20 mrad Whole Body Dose 5 mrem Skin Dose 15 mrem Infant Thyroid Dese 15 nrem Liquid Releases Whole Body Dose 3 mrem Thyroid Dose 10 mrem Bone Dose 10 mrem Skin Dose 10 mrem l
o 2.2-2
-BYRON REVISION 5 FEBRUARY 1983 TABLE 7.2-3 STATION CHARACTERISTICS STATION: Byron LOCATION: 3.7 miles SSW of Byron, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT (NA) i
- 1) Release Height = m 2) Diameter = m
- 3) Exit Speed -1
= ms 4) Heat Content = KCal s-1 I
CEARACTERISTICS OF VENT STACK RELEASE POINT
- 1) Release Height = 60.96 m 2) Diameter = 6.28 m
- 3) Exit Speed = 15.34 -l l
ms 1
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
- 2) Building Factor (D) = 60.6 m 1
i METEOROLOGICAL DATA A 250 ft. Tower is located 1036 m SW of elevated release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA)
Vent 250 ft 250 - 30'ft Ground 30 ft
) 250 - 30 ft 7.2-3
- , - , . . -r. . . - - -
- r. y _ _ , . - _ - _ - . . _ - - - - .
BYRON REVISION 5 FEBRUARY 1983 TABLE 7. 2-4 CRITICAL RANGES RESTRICTED AREA NEAREST ** NEAREST DAIRY FARM BOUNDARY
- RESIDE!ff RANGE ***
DIRECTION (m) (m) (m)
N 1875 7240 ----I NNE 1829 2880 --- i NC 1585 1920 3058 ENE 1234 2080 2414 E 1227 1920 3862 ESE 991 2560 4989 SE 1006 2080 4828 SSE 800 1280 6437 S 945 1720 3701 SSW 975 960 3219 SW 1067 1280 --- t WSW 1212 2720 3219 W 1189 3040 4023 WNW 1227 3360 4989 NW 1128 1280 2253 l NNW 1044 1920 --- i
- FSAR Tible 2.1-la (Amendment 39, September 1982);
ER Table 2.1-1 (Amendment 1, July 1981) .
- Hazleton Environmental Sciences, Survey, December 27, 1982.
- * *Within 5 miles , ER Table 2.1-16 (Amendment 2, September 1981) .
t Default range equal to 5 miles.
7.2-4
BYRON REVISION 5 FEBRUARY 1983 TABLE 7.2-5 TERRAIN CORRECTION FACTORS (h t )*
(ht = 0 to Stated Range, Then ht = Given Value)
RANGE h t
DIRECTION (miles) (meters)
N 0.0 NNE 0.0 NE 0.0 ENE 0.0 E '9.0 3.0 l ESE 0.0 1
SE 5.0 11.0 3
SSB 4.2 9.0 S 4.4 9.0 SSW 0.0 SW 5.0 9.0 WSW 6.5 12.0 W 7.6 14.0 WNW 0.0
( NW 7.3 9.0 NNW 9.7 6.0 l
i
- Within 10 miles i
7.2-5 1
+
t TAGLE '.2-6 X/O AND D/O MAXIMA AT OR BEYOND 7HE UNRESTRICTED AREA BOUNDARY OOWNWIND ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE [.ROUND LEVEL RELEASE DIRECTION RADIUS X/Q RA01US D/Q RADIUS X/Q D/Q RADIUS X/O 0/0 (METERS) (SEC/M**3) (METERS) (t/M.*2) (METERS) (SEC/M**3) (1/M**2) (METERS) (SEC/M**3) (t/M**2)
N 1875. 9.557-08 1875. 9.680-10 1875. 2.102-07 1.666-09 1875. 1.007-06 4.937-09 NNE 1829. 1.083-07 1829. 1.048-09 1829. 1.683-07 1.582-09 1829. S.936-07 4.682-09 NE 1585. 9.628-08 1585. 1.062-09 1585. 1.648-07 1.5G2-09 1585. 9.067-07 4.912-09
%J ENE 1609. 9.103-08 1234. 1.305-09 1234. 1.741-07 1.768-09 1234. 1.130-06 6.280-09 DO
- E 1400. 1.OG7-07 1227 1.787-09 1227. 2.204-07 2.143-09 1227. 1.436-06 7.005-09 "4 ESE 1400. 1.066-07 991 991
?.J f3 SE 1500, 9.378-08 1006.
2.199-09 1.846-09 991.
1006.
2.591-07 3.791-07 2.748-09 2.589-09 1006.
1.706-06 2.623-06 9.4G2-09 1.030 08 ff 25 SSE 1500. 7.8G9-08 800. 1.558-09 800. 3.376-07 2.176-09 800. 2.622-06 1.146-08 S 1800. 6.347-08 945. 7.539-10 945. 1.775-07 1.377-09 945, 1.390-06 7.506-09 SSW 1609. 5.441-08 975. 8.453-10 975. 1.310-07 1.191-09 975. 9.962-07 5.632-09 SW 1609. 6.179-08 1067 9.762-10 1067. 1.257-07 1.467-09 1067. 8.619-07 5.159-09 WSW 1609. 5.528-08 1212. 7.901-10 1212. 1.244-07 1.310-09 1212. 7.873-07 4.685-09 W 1609. 5.338-08 1185. 7.190-10 1189. 1.310-07 1.173-09 1189. 8.107-07 4.424-09 WNW 1400. 5.222-08 1227. 8.600-10 1227, 1.162-07 1.183-09 1227. 7.074-07 3.598-09 7
NW 1400. 5.652-08 1128, 1.028-09 1928. 1.380-07 1.405-09 1128. c.763-Or 4.804-09 NNW 1400. 8.117-08 1044. 1.591-09 1044 2.769-07 2.540-09 1044 1.492-06 8.173-09 BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 t:1 tIf DO F4 C3 D3 38 h4 PO C)
>< G5
.' H un CD La
BYRON REVISION 5 PEBRUARY 1983
}' TABLE 7.2-6 (Cont'd)
BYRON 1&2 AVERAGE WIND SPEEDS FOR EACH RELEASE MODE DOWtlWIND AVERAGE WIND SPEED (m/sec)
DIRECTION ELEVATED MIXED MODE GROUND LEVEL N 7.6 6.6 4.5 NNE 7.4 6.6 4.7 NE 6.8 6.2 4.6 ENE 6.5 5.8 4.5 E 6.5 5.9 4.5 ESE 6.3 5.7 4.4 SE 6.0 5.4 4.0 SSE t
O S 6.0 5.9 5.2 5.2 3.9 4.1 SSW 6.0 5.4 4.0 J
SW 6.6 6.0 4.6 WSW 6.8 6.2 4.8 W 6.7 5.8 4.1 WNW 7.0 6.1 4.2 1
NW 7.0 6.0 3.9 NNW 7.2 6.2 4.2 7.2-7 i
_ _ _ _ _ _ ______ _ .___ - __ . -__---. .- -._. - _ - -_ _ _ - . = , - . . . - . _ _ . . _ , . _ . _ - _ . . , . _ - _ - _
O J
nV (g~'
- TABLE 7.2-7 D/O AT THE NFARFST MILK CCW AND MEAT ANIMAL LOCATICNS VITHIN 5 MILES DOWNWIND NEAREST MILK COW D/O(1/M**2) NEARTST MEAT ANIMAL D/O(1/M**2)
DIRECTION RADIUS ELEVATED mixed GROUND RAu1US ELEVATED MIXED GGd6NO JMETFRS) RFLE45F RELFASE RELEASE IMETERS) RFLFASE RELEASE RELFASE J
N 8045. 1.085-10 1.639-10 3.852-10 4667, 2.642-10 4.063-10 1.009-09 NNE 8045. 1.142-10 1.545-10 3.500-10 5150, 2.3RO-10 3.257-10 7.717-10 NE 3058. 4.693-10 6.152-10 1.570-09 3701. 3.478-10 4.573-10 1.128-09 ENE 2484. 6.255-10 7.321-10 1.983-09 2575. 5.743-10 6.682-10 1.770-09 E 3A62. 4.274-10 4.455-10 9.650-10 2253. 9.275-10 9.791-10 2.472-09
=J ESE 4989. 2.G99-tO 2.962-10 5.818-10 5150. 2.566-10 2.813-10 5.496-10 08 SE 4828. 2.483-10 2.894-10 6.874-10 2575. 6.402-10 7.350-10 2.051-09 "4
$# SSL 6437. 1.228-10 1.267-10 3.165-10 966. 1.406-09 1.752-09 8.483-09 f$
03 5 3701. 1.632-10 2.121-10 7.181-10 3540. 1.749-10 2.268-10 7.757-10 55 SSW 3219. 2.282-10 2.471-10 7.214-10 2736. 2.867-10 3.113-10 9.581-10 SW 8045. 6.225-11 7.576-11 1.540-10 2414 4.021-10 4.909-10 1.271-09 WSW 3219. 2.591-10 3.434-10 8.670-10 2736. 3.258-10 4.355-10 1.152-09 i W 4023. 1.586-10 2.058-10 5.382-10 1126. 7.610-10 1.269-09 4.854-09 WNW 4989, 1.333-10 1.568-10 3.181-10 1287. 8.151-10 1.106-09 3.317-09 NW 2253. 4.738-40 5.492-10 1.469-09 2414 4.317-10 4.961-10 1.301-09 NNW 8045. 9.382-11 1.156-10 2.351-10 2414, 6.107-10 7.736-10 1.941-09 BYRON SITE METEOROLOGICAL DATA t/74 - 12/76 m
tes i b2
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TABLE 7.2-8 i
8YRON 182
=
MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR kp 83M DOWNWIND RESTRICTED fLEVATED(STACK) RELEASE MIXED MODE (VENT) RELEASE t GROUND LEVEL RELEASE DIRFCTION A9EA BOUND RADIUS S SBAR RADIUS V V8AR RADIUS G j G8AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) ( ME T E RS ) - ( MR AD/ Y R ) /( UCI / S E C ) (METERS) (MRAD /YR)/(UCI/SEC)
{ N 1875. 1875. 1.068 05 9.648-07 1875. 2.360-05 2.131-06 1875, NNE 1829. 1.079-04 9.740-06 1829. 1.192-05 1.076-06 1829. 1.901-05 1.716-06 1829.
NE 1585. 9.390-05 8.479-06
,a 1585. 1.074-05 9.697-07 1585. 1.846-05 1.667-06 1585. -9.516-05 8.593-06 1234 Of
. ENE 1234. 1.132-05 1.022-06 9234. 2.034-05 1.836-06 1234 "4 bJ 1227. 1.229-04 1.110-05
, E 1227. 1.281-05 1.157-06 1227. 2.482-05 2.241-06 1227.
i 1.536-04 1.387-05 d3 ESE 991. 991. 1.432-05 1.~93-06 991. 3.026-05 2.733-06 991 1.894-04 f$
SE 1006. 1006. 1.710-05 GC 1.251-05 1.130-06 1006. 4.172-05 3.767-06 1006. 2.811-04 SSE 800 800. 1.120-05 2.539-05
- 1.011-06 800. 3.735-05 3.372-06 800. 2.846-04 2.570-05 S 945. 945. -8.389-06 7.575-07 945, 2.134-05 1.927-06 945, 1.568-04 1.416-05 SSW 975. 975. 7.085-06 6.397-07 975. 1.572-05 1.420-06 975. 1 124-04 SW 1067. 1067. 8.135-06 7.346-07 1.015-05 1067. 1.503-05 1.357-06 1067 9.529-05 8.605-06 WSW 1212. 1212. 6.862-06 6.196-07 1212. 1.470-05 1.327-06 1212.
W 1189. 1189. 8.648-05 7.809-06 6.732-06 6.079-07 1189. 1.543 05 1.399-06 1189. 9.002-05 8.129-06 WNw 1227, 1227. 4.640-06 $.996-07 1227, 1.360-05 1.228-06 1227. 7.786-05 7.031-06 NW 1128. 1128. 7 413-06 E.694-07 1128.
i NNW 1044, 1044, 1.635-05 1.476-06 1128. 9.772-05 8.824-06 1.074-05 9.694-07 1044. 3.265-05 2.948 06 1044. 1.696-04 1.531-05 8VRON SITE METEOROLOGICAL DATA 1/74 - 12/76 N !xt t9 M tp <
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TABLE 7.2-8 (Cont'd)
BYRON 1&2 MaxfMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FDP KR 85M DOWNWIND RESTRICTED FLEVATED(STACK) RELEASE MIXE0 MODE (VENT) RELEASE GROUND LEVEL RELEASE OfRECTION AREA BOUND RADIUS S SEAR RADIUS V VBAR RADIUS G GRAR (MFTEPS) (MFTERS) (MRAD /YR1/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METFRS) (MRAD /YR)/(UCI/SEC)
N 1875. 1875. 1.731-04 3.137-05 1875. 2.312-04 1.209-04 1875. 6.971-04 3.601-04 NNE 1829. 1829. 1.929-04 1.018-04 1829. 2.179-04 1.143-04 1829. 6.266-04 3.240-04
-J NE 1585 1595. 1.809-04 9.554-05 1585. 2.117-04 1.111-C4 1585. 6.368-04 3.293-04 b5
- ENE 1234 1234 2.207-04 1.168-04 1234. 2.398-04 1.259-04 1234 7.650-04 3.948-04 ><
3 E 1227 1227. 2.297-04 1.214-04 1227, 2.644-04 1227.
pa ESE 991 991. 2.964-04 1.569-04 991. 3.331-04 1.385-04 1.747-04 991.
9.340-04 1.103-03 4.814-04 5.681-04 fl gg .
CD SE 1 COG. 1006. 2.697-04 1.428-04 1006. 3.675-04 1.917-04 1006. 1.569-03 8.060-04 SSE 800. 800. 2.787-04 1.478-04 800. 3.457-04 1.80G-04 800. 1.498-03 7.684-04 S 945. 945. 2.116-04 1.122-04 945. 2.348-04 1.232-04 945, 8.918-04 4.589-04 SSW 975. 975. 1.668-04 8.844-05 975. 1.800-04 9.449-05 975. 6.584-04 3.392-04 SW 1067 1067. 1.795-04 9.508-05 1067. 1.803-04 9.473-05 1067. 5.698-04 2.937-04 WSW 1212. 1212. 1.345-04 7.119-05 1212. 1.579-04 8.276-05 1212. 5.225-04 2.694-04 W 1189 1189. 1.363-04 7.215-05 1189. 1.653-04 8.663-05 1189. 5.437-04 2.803-04 WNW 1227 1227, 1.280-04 6.773-05 1227. 1.442-04 7.557-05 1227. 4.705-04 2.426-04 NV 1128. 1128. 1.468 04 7.76~-05 1128. 1.693-04 8.868-05 1128. 5.778-04 2.977-04 NNW 1044 1044. 2.172-04 1.149-04 1044. 2.891-04 1.509-04 1044. 9.390-04 4.827-04 RYRON SITE METEOROLOGICAL DATA 1/74 - 12/76
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TABLE 7.2-8 (Cont'd)
BYRON 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85 DOWhWIND RESTRICTED FIEVATED(STACK) RELEASF MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASF DIRFCTION 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 1875. 1875. 2.036-06 1.260-06 1875. 2.723-06 1.686-06 1875.
NME 7.846-06 4.857-06 1829. 1829. 2.270-06 1.405-06 1829. 2.598-06 1.608-06 1829. 7.093-06 NE 1585. 1585. 4.390-06
%J 2.140-06 1.325-06 1585. 2.532-06 1.568-06 1585. 7.221-06 4.470-06 e ENE 1234 1234 2.612-06 1.617-06 1234 y hJ 2.865-06 1.773-06 1234. 8.564-06 5.301-06 g E 1227. 7227 2.712-06 1.678-06 1227. 3.151-06 1.951-06 1227 1.050-05 I 6.502-06 ()
ESE 991. 991. 3.523-06 2.181-06 991, 3.971-05 2.458-06 991 1.222-05 7.566 06 1006. 5C h$ SE 1006. 3.204-06 1.983-06 1006. 4.330-06 2.680-06 1006. 1.749-05 1.082-05 i SSE 800. 800. 3.322-06 2.057-06 800. 4.080-06 2.526-06 800. 1.654-05 1.024-05 S 945. 945. 2.530-06 1.566-06 94F. 2.796-06 1.730-06 945. 9.827-06 6.083-06 SSW 975. 975. 1.989-06 1.231-06 975. 2.145-06 1.328-06
' 975. 7.266-06 4.498-06 SW 10G7. 1067. 2.130-06 1.318-06 1067. 2.148-06 1.329-06 1067.
WSW 6.312-06 3.907-06
, 1212. 1212. 1.585-06 9.814-07 1212. 1.860-06 1.151-06 1212. 5.812-06 3.597-06 i
W 1189. 1189. 1.619-06 f.OO2-06 1189. 1.960-06 1.213-06 1189. 6.043-06 3.741-06 WNW 1227. 1227. 1.513-06 9.366-07 1227. 1.708-06 1.057-06 1227.
NW 1128.
5.251-06 3.250-06 1128. 1.733-06 1.073-06 1128. 1.999-06 1.238-06 1128.
NNW 1044. 1044, 6.410-06 3.968-06 2.568-06 f.590-06 1044. 3.374-06 2.089-06 1044 1.032-05 6.390-06 BYRON SITE METEOROLOGICAL DATA f/74 - 12/76 N
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BYRON 182 MAv1 MUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 87 OOWNWINO RESTRICTED ELEVATED (STACK) RELEASE MirFD MODE (VENT) REtEASE GROUND LEVFL RELEASE DIRECTION AREA BOUND RAOIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UOI/SEC) (METERS) (MRAD /YR)/(UCt/SEC)
N 1875. 1875. 5.9G1-04 4.327-04 1875. 7.713-04 5.596-04 1875. 2.020-03 1.459-03 NME 1829. 1829. 6.620-04 4.806-04 1829. 7.4C0-04 5.417-04 1829. 1.807-03 1.305-03
%J NE 1585. 1585. 6.270-04 4.551-04 1585. 7.268-04 5.278-04 1585. s.848-03 1.335-03 08
- 1234 5.640-04 1234 8.465-04 6.151-04 1234, 2.256-03 1.629-03 NC ENE 1234. 7.768-04 3
E ESE 1227.
991.
1227.
991.
8.045-04 1.053-03 5.841-04 7.646-04 1227.
991.
9.119-04 1.178-03 6.623-04 8.562-04 1227.
991.
2.713-03 3.265-03 1.958-03 2.357-03 gg ps bJ SE 1006. 1006. 9.613-04 6.980-04 1006. 1.248-03 9.055-04 1006. 4.539-03 3.277-03 SSE 800. 800.
- 005-03
. 7.299-04 800. 1.214-03 8.819-04 800. 4.446-03 3.209-03 S 945. 945. 7.550-04 5.482-04 045, 8.365-04 6.079-04 945. 2.654-03 1.916-03 SSW 975. 975, 5.964-04 4.330-04 975. 6.421-04 4.666-04 975. 1.964-03 1.418-03 SW 1067. 1067. 6.390-04 4.639-04 1067. 6.471-04 4.703-04 1067. 1.696-03 1.225-03 WSW 1212. 1212. 4.785-04 3.474-04 1212. 5.538-04 4.021-04 1212. 1.555-03 1.123-03 W 1189. 1189. 4.779-04 3.469-04 1189. 5.759 04 4.182-04 1189. 1.620-03 1.170-03 WNW 1227. 1227 4.526-04 3.286-04 6227. 5.040-04 3.660-04 1227. 1.388-03 1.002-03 NW 1128. 1128. 5.203-04 3.778-04 1128. 5.944-04 4.316-04 1128. 1.723-03 1.244-03 NNW 1044. 1044. 7.732-04 5.614-04 1044. 9.980-04 7.242-04 1044, 2.811-03 2.029-03 BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 M :s MM DD <
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TABLE 7.2-8 (Cont'd)
BYRON 182 max 1 MUM OFFSITE FINITE PLL*4E GAMMA DOSE FACTORS FOR KR 89 00WNWINO RESTRICTED ELEVATE 0fSTACK) RELEASE _ MIXED MODE (VENT) RELEASE DIRECTION AREA BOUND RADIUS GROUND LEVEL RELEASE S $8AR RADIUS V VBAW RADIUS G IMETcRS) GBAR (MFTERS) (MRAD /YR)/(UCl/SEC) (METERS) (MRAD /vR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC)
N 1875. 1875. A.111-04 3.010-04 1875. 4.0G2-04 NNE 1829. 1829, 2.974-04 1875. 5.990-04 4.364-04 4.422-04 3.237-04 1829. 4.105-04 3.007-04 1829.
%J NE 1585. 1585. 5.406-04 3.939-04 4.341-04 3.178-04 1585. 4.221-04 3.093-04 1585.
e ENE 1234. 1234. 6.185-04 6.219-04 4.532-04 b3 h) 4.529-04 1234 5.854-04 4.292-04 1234. 9.721-04 7.080-04 NC E 1227 1227. 6.462-04 4.731-04 1227.
[, ESE 991. 991. 9.327-04 6.830-04 991.
5.883-04 8.838-04 4.313-04 6.482-04 1227.
991.
1.008-03 t.599-03 7.343-04 N8 4 SE tOO6. 1006. 1.165-03 hk 8.489-04 6.216-04 1006. 8.077-04 5.923-04 1006. 1.616-03 1.177-03 SSE 800. 800. 9.994-04 7.319-04 800, 9.545-04 S 945. 945.
7.001-04 800. 2.238-03 1.630-03 6.409-04 4.693-04 945. 6.336-04 4.646-04 945. 1.433-03 1.043-03 SSW 975. 975. 5.305-04 3.885-04 975. 4.939-04 3.622-04 SW 1067. 1067. 5.759-04 4.217-04 1067.
975. 1.049-03 7.640-04 5.305-04 3.889-04 1067 8.888-04 6.473-04 WSW 1212. 1212. 4.259-04 3.118 I'4 1212. 4.363-04 W 1189. 1189.
3.196-04 1212. 7.908-04 5.759-04 3.744-04 2.742-04 1989. 3.891-04 2.851-04 1189.
WNW 1227 1227. 7.491-04 5.455-04 3.884-04 2.844-04 1227. 3.632-04 2.662-04 1227.
NW 1109, 1128. 5.733-04 4.176-04 4.680-04 3.427-04 1128. 4.492-04 3.292-04 1128.
NNW 1044 1044 7.275-04 8.016-04 5.839-04 5.327-04 1044 7.938-04 5.812-04 1044 1.573-03 1.145-03 BYRON SITE METEOROLJGICAL DATA 1/74 - 12/76 t:1 txt 90 F4 C3 D3
>H l0 0 H: 2:
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TABLE 7.2-8 (Cont'd)
BYRON 1&2 MAvlMUM OFFSTTF FINfTF PLUME GAMMA DOSF FACTORS FOR RR 40 DOWNWIND RESTRICTED ELEVATEO(STACKl RELEASE _HlXED MODE (VENT) RELEASE GRDUND LEVEL RELFASE DIRFCTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METFR9) (MRAD /YRl/(UCf/SFC) (METERS) (MRAD /YRl/(UCT/SFC) (METERS) (MR AD/YR)/f UC1/SEC )
N 1875. 1875. 1.125-05 7.998-06 1875. 7.471-06 5.312-06 1875. 4.324-06 3.054-06 NNE 1829. 1829. 1.194-05 8.491-06 1829. 8.361-06 5.945-06 1829. 5.383-06 3.802-06 NE 1585. 1585. 1.460-05 1.C38-05 1585. 1.163-05 8.268-06 1585.
-J ENE 1234 1234. 3.604-05 2.562-05 1234.
9.069-06 6.405-06 W 2.752-05 1.957-05 1234. 2.745-05 1.938-05 NC bJ E 1227. 1227. 4.020-05 2.857-05 1227.
l 3.091-05 2.190-05 1227. 3.305-05 2.334-05 ]j ESE 991. 991. 8.655-05 6.154-05 991. 6.549-05 4 938-05 991. 7.290-05 i 5.146-05 25 h SE 1006. 1006, 6.896-05 4.903-05 1006. 5.360-05 3.814-05 1006. 6.719-05 4.743-05 SSE 800 800. 1.246-04 8.864-05 800. 9.173-05 6.532-05 800. 1.368-04 9.654-05 S 945. 945. 5.623-05 3.999-05 945. 4.379-05 3.117-05 945. 6.024-05 4.250-05 SSW 975. 975. 4.486-05 3.190-05' 975. 3.367-05 2.396-05 975. 3.851-05 2.717-05 SW 1067. 1067. 4.947-05 3.517-05 1067. 3.940-05 2.800-05 1067 3.895-05 2.749-05 WSW 1212. 1212. 2.878-05 2.046-05 1212, 2.504-05 1.779-05 1212, 2.607-05 1.840-05 W 1189. 1189. 2.728-05 f.939-05 1189. 2.031-05 1.445-05 1189. 1.678-05 1.*84-05 WNW 1227 1227. 2.812-05 1.999-05 1227. 1.958-05 1.393-05 1227. 1.374-05 9.700-06 NW 1128. 1128. 3.999-05 2.844-05 1128, 2.696-05 1.919-05 1128, 1.820-05 1.285-05 NNW 1044. 1044. 7.876-05 5.601-05 1044. 5.964-05 4.241-05 1044 4.889-05 3.450-05 BYRON SITL METEOROLOGICAL OATA 1/74 - 12/76 N
to to so >4 C: CD
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%,l TABLE 7.2-8 (Cont'd)
B Y RO*J 182 MAXIMUM OFFSITF FINITE PLUME GAMMA MOSE FACTORS F00 XE131M 00Welw1ND RESTRICTED ELEVATED (STACK) RELE ASE 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)
N 1875. 1875. 1.246-09 2.765-06 1875. 2.486-05 4.428-06 1875. 1.076-04 1.428-05 NNE 1829. 1829. 1.390-OS 3.085-06 1829. 2.061-05 3.925-06 1829. 9.491-05 1.450-05
,a f.E 1585. 1585. 1.266-05 2.85P-06 1585. 2.015-05 3.825-06 1585. 9.587-05 1.467-05 US
. ENE 1234. 1234. 1.386-05 3.340-06 1234 2.206-05 4.252-06 1234 1.200-04 1.798<05 NC bJ E 1227, 1227. 1.529-05 3.554-06 1227. 2,S69-05 4.907-06 1227 1.516-04 2.245-05 h!
l ESE 991. 991. 1.790-05 4.420-06 991. 3.723-05 6.040-06 991. 1.817-04 2.663-05 25
$( SE 1006. 1006. 1.581-05 3.977-06 1006. 4.314-05 7.345-06 1006. 2.728-04 3.924-05 SSE 800. 800. 1.488-05 3.975-06 800. 3.820-05 6.675-06 800. 2.676-04 3.794-05 5 945. 945. 1.130-05 3.026-06 945. 2.253-05 4.237-06 945. 1.485-04 2.164-05 i SSW 975. 975. 9.262-06 2.415-06 975. 1.677-05 3.205-06 975. 1.069-04 1.573-05 SW 1067. 1067. 1.036-05 2.632-06 1067 1.612-05 3.147-06 1067. 9.124-05 1.352-05
'. S W 1212. 1212. 8.352-06 2.022-06 1212. 1.541-05 2.870-06 1212. 8.326-05 1.237-05 N 1189. 1189. 8.405-06 2.053-06 1189. 1.626-05 3.022-06 1189. 8.6'33-05 1.284-05 WNW 1227. 1227. 8.095-06 1.941-06 1227, 1.428-05 2.642-06 1227. 7.531-05 1.118-05 NW 1128. 1128. 9.101-06 2.208-06 1128. l.697-05 3.117-06 1128. 9.340-05 1.379-05 NNW 1044 1044, 1.327-05 3.248-06 1044 3.270 05 5.644-06 1044. 1.590-04 2.299-05 BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 N
tej tp WH l C3 D3
>s F4 WO H: 2:
00 tu
% % {
d d V}
TABLE 7.2-8 (Cont ',d)
BYRON 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DO"E FACTORS FOR XE133M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRFCTION AREA BOUND RADIUS S 58AR R4.u!US V VBAR RADIUS G GBAR (METERS) (MFTERS) (M24D/YR)/(UCi/SEC) (M1!ERS) (MRAD /YR)/(UCI/SEC) (METER 5) (MRAD /YR)/(UCI/$6C)
N 1875. 1875. 3.363-05 1.394-05 th75. 5.333-05 1.932-05 1875. 1.943-04 6.113-05 NNE 1829. 1829. 3.752-05 1.556-05 1829. 4.741-05 1.800-05 1829. 1.731-04 5.498-05
=a NE 1585. 1525. 3.478-05 1.454-05 1585. 4.620-05 1.750-05 1585. 1.752-04 5.574-05 b3
+ ENE 1234. 1234 4.075-05 1.757-05 1234. 5.142-05 1.967-05 1234. 2.145-04 6.680-05 NC 3 1227. 1227. 4.331-05 1227.
ps E
ESE 991. 991. 5.398-05 1.836-05 2.352-05 991, 5.919-05 7.295-05 2.194-05 2.740-05 1227.
991.
2.676-04 3.175-04 8.228-05 9.660-05 fl 25
-J SE 1006. 1006. 4.861-05 2.135-05 1006. 8.827-05 3.089-05 1006. 4.672-04 1.392-04 SSE 800, 800. 4.869-05 2.190-05 800. 8.037-05 2.871-05 800. 4.516-04 1.323-04 ,
S 945. 945 3.706-05 1.669-05 945. 5.119-05 1.927-05 945. 2.580-04 7.798-05 S%V 975. 975. 2.955-05 1.317-05 975. 3.875-05 1.474-05 975. 1.877-04 5.737-05 SW 1067. 1067. 3.218-05 1.419-05 1067. 3.809-05 1.469-05 1067. 1.613-04 4.964-05 WSW 1212. 1212. 2.468 05 1.066-05 1212, 3.466-05 1.296-05 1212. 1.476-04 4.555-05 W 1189. 1189. 2.505-05 1.086-05 1189. 3.649-05 1.362-05 1189. 1.532-04 4.735-05 WNW 1227. 1227. 2.368-05 1.018-05 1227 3.190-05 1.188-05 1227. 1.334 04 4.114-05 NW 1128. 1128. 2.695-05 1.165-05 1128. 3.763-05 1.394-05 1128. 1.645-04 5.042-05 NNW 1044 1044. 3.966-05 1.722-05 1044. 6.793-05 2.403-05 1044. 2.741-04 8.213-05
, BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 Nw MM tIf 4 WH C 02
>H NO H: 25
>
- Ut W
CD j LJ
n ir
's
'n t
\%
{A
\ %s i
TABLE 7.2-8 (Cont'd) ,
BYRON 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133 00WNWIND RESTRICTED FLEVATED(STACK) RELEASE MIXED MODE (VENT) RELEASE _ GROUND LEVEL RELEASE DIRFcTION AREA BOUND RADIUS S $8AR RADIUS V VBAR R4030S G GBAR iMETERS) (0ETERS) ( MR Af tf R)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (tjt t E RS ) (MRAD /YR)/(UCI/SEC)
N 1875. 1875. 3.840-05 1.340-05 1875. 5.939-05 1.898-05 1875. 2.194-04 6.492-05 NNE 1829. 1829. 4.286-05 1.49G-05 1829. 5.269-05 1.731-05 1829. 1.959-04 5.833-05
=J NE 1585. 1585. 3.988-05 1.400-05 1585. 5.143-05 1.689-05 1585. 1.984-04 5.917-05 b3 EtJE 1234. 1234. 4.709-05 1.686-05 1234. 5.671-05 1.869-05 1234 2.420-04 7.119-05 P4 3 1227, 1227. 1227. 1227.
ps E
ESE 991. 991.
4.980-05 6.263-05 1.744-05 2.259-05 951.
6.529-05 8.019-05 2.111-05 2.611-05 991 3.006-04 3.550-04 8.769-05 1.028-04 fl g
00 SE 1006. 1006, 5.653-05 2.049-05 1006. ? 677-05 3.015-05 1006. 5.192-04 1.482-04 SSE 800. 800. 5.700-05 2.099-05 800. 8.759-05 2.759-05 800. 4.987-04 1.406-04 S 945. 945. 4.348-05 1.603-05 945. 5.614-05 1.829-05 945. 2.878-04 8.294-05 SSW 975. 975. 3.458-05 1.266-05 975. 4.257-05 1.397-05 975. 2.102-04 6.104-05 SW 1067. 1067. 3.747-05 1.362-05 1067. 4.193-05 1.389-05 1067. 1.812-04 5.290-05 WSW 1212. 1212. 2.055-05 1.024-05 1212. 3.836-05 1.248-05 1212. 1.660-04 4.857-05 W 1189. 1169. 2.899-05 1.042-05 1189. 4.030-05 1.309-05 1989. 1.724-04 5.046-05 WNW 1227. 1227. 2.729-05 9.752-06 1227. 3.529-05 1.145-05 1227 1.500 04 4.385-05 NW 1128. 1128. 3.111-05 1.116-05 1128. 4.149-05 1.341-05 1128. 1.84J-04 5.362-05 NNW 1044. 1044. 4.589-05 1.650-05 1044 7.478-05 2.349-05 1044. 3.053-04 8.751-05 BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 MM MM to <C
>$ F4 C: 01 38 H WO
>< 25 Ed Ln W
C0 W
O O C TABLE 7.2-8 (Cont'd)
BYRON 162 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE135M DOWNWIND RESTRICTED ELEVATE 0(STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S S8AR RADIUS V VBAR RADIUS G GBAR (ME7ERS) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UC1/SEC) (METERS) (MRAD /YR)/(UCI/SEC)
N 1875. 1875. 2.796-04 1.722-04 1875. 3.384-04 2.079-04 1875. 8.143-04 4.977-04 NNE 1829. 1829. 3.068-04 1.890-04 1829. 3.264-04 2.007-04 1829. 7.058-04 4.315-04
-J NE 1535. 1585. 2.939-04 1.811-04 1585. 3.169-04 1.949-04 1585. 7.313-04 4.472-04 CO
+ ENE 1234, 1234. 3.759-04 2.318-04 1234. 3.860-04 2.375-04 1234 9.739-04 5.951-04 "4 3
E 1227 1227. 3.865-04 2.382-04 1227 4.000-04 2.460-04 1227. 1.093-03 6.676-04 ps ESE 991. 991. 5.161-04 3.163-04 991. 5.411-04 3.329-04 991. 1.468-03 8.960-04 f$
g5 u) SE 1006. 100G. 4.750-04 2.930-04 1006. 5.507-04 3.383-04 1006. 1.848-03 1.127-03 SSE 800. 800. 5.132-04 3.167-04 800. 5.734-04 3.523-04 800. 2.056-03 1.254-03 S 945. 945. 3.686-03 2.275-04 945, 3.920-04 2.411-04 945. 1.245-03 7.597-04 SSW 975. 975. 2.949-04 1.820-04 975. 3.006-04 1.849-04 975. 9.205-04 5.619-04 SW 1067. 1067. 3.176-04 1.959-04 1067. 3.09G-04 1.905-04 1067. 7.812-04 4.771-04 WSW 1212. 1212. 2.419-04 1.492-04 1212. 2.676-04 1.645-04 1212. 7.102-04 4.338-04 W 1189. 1189. 2.263-04 1.396-04 1189. 2.643-04 1.625-04 1189. 7.371-04 4.502-04 WNW 1227. 1227. 2.227-04 1.373-04 1227. 2.357-04 1.449-04 1227 6.060-04 3.700-04 NW 1128. 1128. 2.585-04 1.594-04 1128. 2.829-04 1.739-04 1128. 7.847-04 4.791-04 NNW 1044 1044, 3.874-04 2.390-04 1044 4.860-04 2.984-04 1044. 1.358-03 8.285-04 BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 N !xf MM CD =0 DO F4 C3 03 58 F4 23 C)
>< 55 Fe Ln W
03 W
n
() O 0
O 0
i TABLE 7.2-8 (Cont'd)
BYRON 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE135 DOWNWIND RESTRICTED FLEVA1FD(STACK) RELEASE MIXED MODE (VENT) RELEASF GROUND LEVEL RELFASE DIRFCTION AREA BOUND RAD]US S 584R RADIUS V VBAR RADIUS G GBAR (METFRS) (METFRS) ( MR AD / Y R ) / ( UC ! / S E C ) (MFTERS) IMRAD/YR)/fuCI/SEC) (METFRS) (MRAD /YR)/(UCI/SEC)
N 1875. 1875. 2.405-04 1.297-04 1875. 3.197-04 f.721-04 1875.
NNE 1829. 1929, 9.558-04 5.129-04 2.681-04 f.446-04 1829. 3.023-04 1.628-04 1829. 8.615-04 4.624-04
-a NE 1585. 1585. 2.515-04 1.356-04 1585. 2.937-04
- 1.582-04 1585. 8.750-04 4.697-04 CU ENE 1234 1234. 3.067-04 1.655-04 1234. 3.321-04 1.789-04 1234 "4 3 1.044-03 5.601-04 E 1227. 1227. 3.190-04 1.721-04 1227. 3.661-04 1.972-04 1227.
ESE 1.277-03 6.849-04 'hf bJ 991. 991. 4.121-04 2.224-04 991. 4.604-04 2.480-04 991. 1.499-03 8.037-04 25 c) SE 1006. 1006. 3.749-04 2.024-04 1006. 5.064-04 2.724-04 1006. 2.135-03 1.144-03 SSE 800. 800. 3.875-04 2.092-04 800. 4.754-04 2.559-04 800. 2.025-03 1.085-03 S 945. 945. 2.948-04 1.591-04 945. 3.243-04 1.747-04 945. 1.208-03 6.479-04 SSW 975. 975. 2.322-04 1.253-04 975. 2.488-04 1.340-04 975. 8.930-04 4,789-04 SW 1067. 1067. 2.495-04 1.347-04 1067 2.492-04 1.343-04 1067. 7.741-04 4,152-04 WSW 1212. 1212. 1.866-04 1.007-04 1212. 2.176-04 1.172-04 1212. 7.108-04 3.813-04 W 1189. 1189. 1.893-04 1.024-04 1189. 2.283-04 1.230-04 1189. 7.393-04 3.t66-04 WNW 1227. 1227. 1.778-04 9.593-05 1227. 1.991-04 1.072-04 1227. 6.410-04 3.43'J-04 NW 1128. 1128, 2.038-04 1.100-04 1128. 2.333-04 1.257-04 1128. 7.849-04 NNW 1044 4.210-04 1044 3.015-04 1.627-04 1044. 3.966-04 1044.
2.134-04 1.270-03 6.806-04 BYRON SITE P'ETEOROLOGICAL DATA 1/74 - 12/76
'O M 2 t9 t4 D2 <0 DO >4 C in l> H Mo H: 2:
>" Ln W
CD t,a#
D
g s q N) %d TABLE 7.2-8 (Cont'd)
BYRON 1&2 MAxfMUM OFFSTTE FINITE PLUME GAMMA DOSE FACTORS FOR XE137 00WNWIND RESTRICTED EtEVATED(STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS 5 5BAR RADIUS V VBAR RADIU5 G GBAR (METERS) (METERS) (MRAD /YR)/(UCi/SEC) (METERS) ( MR AD / YR ) /( UCI / SE C ) (METERS) (MRAD /VR)/(UCI/SEC)
N 1875. 1875. 6.446-05 4.157-05 1875. 6.592-05 4.251-05 1875. 1.103-04 7.093-05 NNE 1829. 1829. 6.951-05 4.483-05 1829. 6.574-05 4.241-05 1829. 9.777-05 6.288-05
=J NE 1585. 1585. 6.795-05 4.382-05 1585. 6.656-05 4.294-05 1585. 1.097-04. 7.055-05 to e ENE 1234 1234 9.459-05 6.101-05 1234 8.954-05 5.779-05 1234, 1.663-04 1.069-04 >4 h3 1227. 1227, 1227.
E 9.821-05 G.335-05 8.967-05 5.787-05 1227. 1.718-04 1.105-04 28
[3 ESE 991. 991. 1.392-04 8.980-05 '991. 1.318-04 8.509-05 991, 2.672-04 1.718-04 hl pa SE 1006. 100G. 1.274-04 8.220-05 1006. 1.220-04 7.974-05 1006. 2.747-04 1.766-04 SSE 800 800. 1.477-04 9.525-05 800. 1.416-04 9.i40-05 800. 3.742-04 2.405-04 5 945. 945. 9.657-05 6.229-05 945. 9.542-05 6.158-05 945, 2.396-04 1.540-04 SSW 975. 975. 7.956-05 5.132-05 975. 7.406-05 4.780-05 975. 1.762-04 1.133-04 SW 10G7. 1067. 8.635-05 5.570-05 1067. 7.944-05 5.126-05 1067. 1.488-04 9.566-05 WSW 1212. 1242. 6.460-05 4.167-05 1212. 6.653-05 4.290-05 1212. 1.335-04 8.585-05 W 1989. 1189. 5.696-05 3.667-05 1189. 6.009-05 3.876-05 1189. 1.295-04 8.323-05 WNW 1227. 1227. 5.870-05 3.786-05 1227. 5.565-05 3.591-05 1227. 9.980-05 6.416-05 NW 1128. 1128. 7.014-05 4.524-05 1128. 6.848-05 4.418-05 1128. 1.380-04 '8.876-05 NNW 1044. 1044 1.081-04 6.974-05 1044 1.210-04 7.804-05 1044. 2.661-04 1.711-04 RYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 Nw MM tD <
NH C U1 H
8 s Ln W
m
(.4
O %
kh (b TABLE 7.2-8 (Cont'd)
BYRON 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE13R DOWNWIND RESTRICIED ELEVATED (STACK) RELEASE _ MIXED MODE (VENT) RELEASE GROUND LE%EL RELEASE FIRECTION AR(i BOUND RADIUS S S8AR RADIUS V VBAR RADIUS G GBAR fMETEkSt (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCf/SEC) (METERS) fMRAD/YR)/(UCf/SEC)
- N 1875. 1875. 6.240-04 4.500-04 1875. 7.439-04 5.360-04 1875. 1.674-03 1.198-03 NNE 1829. 1829. 6.841-04 4.933-04 1929. 7.254-04 5.233-04 1829. 1.453-03 1.040-03
%J NE 1585. 1585. 6.543-04 4.719-04 1585. 7.055-04 5.091-04 1585. 1.503-03 1.076-03 b5 ENt 1234. 1234, 8.415-04 6.071-04 1234 8.093-04 6.278-04 1234 2.004-03 1.434-03 N 3
1227. 1227. 1227.
bJ E
ESE 991. 991.
8.652-04 1.159-03 6.242-04 8.362-04 991.
8.955-04 1.220-03 6.465-04 8.809-04 1227, 991.
2.238-03 3.025-03 1.601-03 2.163-03 f!
sg h) SE 1006. 1006. 1.067-03 7.703-04 1006. 1.224-03 8.832-04 1006. 3.766-03 2.693-03 SSE 800. 800. 1.155-03 8.336-04 800. 1.288-03 9.298-04 800. 4.217-03 3.014-03 S 945. 945. 8.264-04 5 965-04 945, 8.839-04 6.382-04 945, 2.567-03 1.835-03 SSW 975. 975. 6.624-04 4.782-04 975. 6.789-04 4.903-04 975. 1.901-03 1.359-03 SW 1067. 1067 7.136-04 5.150-04 1067. 7.000-04 5.055-04 1067, 1.613-03 1.154-03 WSW 1212. 1212. 5.430-04 3.917-04 1212. 5.991-04 4.322-04 1212. 1.466-03 1.048-03 W 1189. 1189. 5.063-04 3.653-04 1189. 5.893-04 4.251-04 1189. 1.520-03 1.087-03 WNW 1227. 1227. 4.997-04 3.605-04 1227. 5.270-04 3.802-04 1227. 1.246-03 8.911-04 NW 1128. 1128. 5.810-04 4.192-04 1128. 6.331-04 4.5G8-04 1128, 1.622-03 1.160-03 NNW 1044 1044. 8.715-04 6.290-04 1044 1.077-03 7.764-04 1044, 2.807-03 2.007-03 BYRON S!TE METEOROLOGICAL DATA 1/74 - 12/76 MW til M tp <
21 H C in l> H 20 0 H: 2 Fa Ln W
CD W
O O O 1 .
TABLE 7.2-8 (Cont'd) 8YRON 1&2 Max! MUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR AR di i
DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRFCTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G G8AR 4
. . O (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/lUCI/SEC) (METERS) (MRAD /YR)/fuCI/SEC)
N 1875. 1875. 9 166-04 6.462-04 1875. 1.194-03 8.420-04 1875. 3.209-03 2.262-03 NNE 1829. 1829. 1.019-03 7.187-04 1829. 1.151-03 8.116-04 1829. 2.878-03 2.029-03
- J NE 1585. 1585. 9.617-04 6.780-04 1585. 1.121-03 7.903-04 1585. 2.936-03 2.070-03 08
- ENE 1234. 1234. 1.196-03 8.362-04 -1234. 1.299-03 9.155-04 1234 3.564-03 2.512-03 "4 1227. 1227.
h)
E ESE 991. 991, 1.232-03 1,602-03 8.687-04 1.130-03 1227 991.
1.406-03 1.808-03 9.914-04 1.274-03 1227.
991.
4.311-03 5.133-03 3.039-03 3.619-03
'ff25 La SE 1006. 1006. 1.460-03 1.029-03 1006. 1.929-03 1.360-03 1006. 7.203-03 5.078-03 SSE 800. 800. 1.517-03 1.069-03 800. 1.863-03 1.313-03 800. 6.975-03 4.917-03 5 945. 945. 1.145-03 8.072-04 945. 1.281-03 9.034-04 945. 4.157-03
- 2.930-03 SSW 975. 975. 9.040-04 6.373-04 975. 9.832-04 6.931 04 975. 3.076-03 2.168-03 SW 1067. 1067. 9.698-04 6.837-04 1067. 9.888-04 6.971-04 1067. 2.663-03 1.877-03 WSW 1212. 1212. 7.269-04 5.125-04 1212. 8.472-04 5.973-04 1212. 2.445-03 1.724-03 W 1189. 1189. 7.302-04 5.148-04 1189. 8.847-04 6.237-04 1189. 2.547-03 1.795-03 WNW 1227. 1227. 6.903-04 4.867-04 1227. 7.726-04 5.447-04 1227. 2.190-03 1.544-03 NW 1128. 1928. 7.918-04 5.582-04 1128. 9.099-04 6.415-04 1128, 2.705-03 1.907-03 NNW 1044. 1044. 1.175-03 8.284-04 1044 1.530-03 1.078-03 1044. 4.395-03 3.099-03 BYRON SITE METEOROLOGICAL DATA 1/74 - 12/76 Nw MM O2 <
90 >4 C in
>H D2 O HC 25 Fe Ln W
CD G3
REVISION b rEBRUARY 1983
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BYRON STATION o 1 2 FIGURE 7.2-1 S C ALE IN MILE S
--- EXCLUSION AREA BOUNDARY RESTRICTED AREA B0UNDARY O, ......... RESTRICTED AREA BOUNDARY
4 4
BYRON REVISION 5 FEERUARY 1983 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, l
MODELS FOR SETTING GASEOUS AND LIQUID 1 r
EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENT RADIOLO3ICAL MONITORING TABLE OF CONTENTS PAGE 8.1 GASEOUS RELEASES 8.1-1 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 Containment Purge Effluent Monitors 8.1-4 8.1.5 . Gas Decay Tank Monitors 8.1-5
! 8.1.6 Radwaste Area Vent Exhaust 8.1-6 j 8.1.7 'VR System Arees and Cubicles Ventilation Exhaust 8.1-7
.O 8.1.8 8.1.9 SJAE/ Gland Steam Exhaust Allocation of Effluents from Common 8.1-7 Release Points 8.1-8 7
8.1.10 Symbols Used in Section 8.1 8.1-9 l
8.1.11 Constants Used in Section 8.1 8.1-10 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 Radwaste Effluent Monitor 8.2-2 8.2.4 Component Cooling Water Monitors 8.2-3 8.2.5 Steam Generator Blowdown 8.2-4 8.2.6 Blowdown Filters 8.2-5 8.2.7 Administrative and Procedural Controls
- for Radwaste Discharges 8.2-6 8.2.8 Determination of Initial Dilution Stream Flow Rates 8.2-6 ,
8.2.9 Symbols Used in Section 8.2 8. 2 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1
'8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 lO
- 8-1 l
l
. . - _ . . . _ . _ . . . . . _ _ _ . _ _ . _ . _ . _ . . _ - . . _ _ . ~ . _ _ _ _ _ _ _ _ _ . _ _
BYRON REVISION 5 FEBRUARY 1983 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS ,
MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENP MONITOR ALARM AND TRIP SETPOINPS ,
AND ENVIRONMENTAL RADIOLOGICAL MONITORING LIST OF TABLES NUMBER TITLE PAGE 8.4-1 Radiological Monitoring Program 8.4-2 8.4-2 Radiological Monitoring Program 8.4-5 8.4-3 Practical Lower Limits of Detection (LLD) for Environmental Radiological Monitoring Program 8.4-4 8.4-8 Environmental Radiological Monitoring Scmpling Codes 8.4-9 i
O l
l 5
4 8-11
l BYRON REVISION 5 FEBRUARY 1983 l
8.0 RADIOACTIVE EFFLUElff TREATMElff SYSTEMS ,
MODELS FOR SETTING GASEOUS AND LIQUID EFFLUElff MONITOR ALARM AND TRIP SETPOIlffS ,
l l AND ENVIRONMENTAL RADIOLOGICAL MONITORING LIST OF FIGURES NUMBER TITLE 8.4-1 Fixed Air Sampling Sites 8.4-2 Inner and Outer Ring TLD Locations l
O O 8-111
. . , - - - - . . , ~ . .
._m _ _ _ _ . ... _ _ . .. .
BYRON REVISION 5
, FEBRUARY 1983 2
8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS,
' MODELS FOR SETTING GASEOUS AND LIQUID
_ EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES 8.1.1 System Design
+
1
! 8.1.1.1 Gaseous Radwaste Treatment System ,
l A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system 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 radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
l 8.1.2 Alarm and Trip Setpoints i
i l
Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air 8.1-1
BYRON REVISION 5 FEBRUARY 1983 containing radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded. The set-points are found by solving Equations 2.9 and 2.10 for each class of releases. '
3 For this equation, the radioactivity mixture in the exhaust air is assumed to have the composition of gases listed in Table 3.5-7 of the Environmental Report Operating License Stage. According to Subsection 3.5.3.4 of the report, releases of radionuclides in gaseous effluents were calculated using the FWR-GALE computer program and the parameters listed in Table 3.5-5.
Equation 2.9 is rewritten using the fractional composition of each nuclide, f g , and a total release rate, O , f r station vent t
stack releases (the principal point of release of ventilation exhaust air containing radioactivity) : -
1.11 Q tv ii*f) i
< 500 mrem /yr (8.1) f i
Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides.
Q tv Total Release Rate, Vent Release (pCi/sec)
The release rate for all radionuclides due to a station vent stack release.
Qiy =Q tv fi (8.2)
Equation 8.1 can be solved for Q f r release limit t
determinations. Similarly, Equation 2.10 can be rewritten:
1 (X/Q)v O tv fi **P I- Ai R/3600 uy ) +
1.11 V i
Q tv f i
< 3000 mrem /yr (8.3) 10 ~
8.1-2
i BYRON REVISION 5 FEBRUARY 1983 Equation 8.3 can be solved for Q tv and a corresponding release limit can be determined. The most conservative release
, limit from Equations 8.1 and 8.3 will be used in selecting the appropriate alarm and trip setpoints for a vtat release.
i 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 4.3-3 of the Technical Specifications.
Calibration methods wil1~be consistent with the definitions found in Section 1.0 of the Technical Specifications.
8.1.3 Station Vent Stack Monitor Detectors 1RE-PR028 A, B, and C (air particulate, gas, and 2 channels, respectively) and 2RE-PR028 A, B, and C monitor I
(
station stack effluent from the auxiliary building vent
'O stacks of Units 1 and 2, respectively.
The two wide range monitors are installed on the auxiliary l
' building vent stacks (final release points) , one monitor per stack. The monitor has a range for radioactive gas concentration of 1 x 10-7 pCi/cc to 1 x 10 5 pCi/cc. The monitor includes two isokinetic nozzles, one for normal conditions operating at 2 ft 3/ min and one for high-range conditions operating at 0.06 ft 3/ min; sampling rack; sample conditioner, operating only at high-range conditions to filter out large concentrations of radiciodine and partic-ulates; and the wide-range gas detectors assembly, consisting of three radioactive gas detectors, a low-range detector, a mid-range detector, and a high-range detector.
In addition to the automatic isokinetic sampling system, additional features associated with these monitors include:
O 8.1-3
BYRON REVISION 5 FEBRUARY 1983
- a. automatic grab sampling system,
- s. b. tritium sampling system, and
- c. low /high range gas monitors.
Each monitor system has a microprocessor which utilizes digital processing techniques to analyze data and control monitor functions. Control room readouts include a cathode ray tube display (RM-ll) , a recorder, and an RM-23 remote display module for all monitor parameters.
The monitor panels ~with associated pumps, detectors, and local controls, are located in the auxiliary building on the 477 ft and 463 ft elevations for Units 1 and 2, respec-tively.
A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and f- provides the high voltage for the detector. The power supply k-s unit is located within the monitoring system cabinet. The monitors are powered from local 120-Vac instrumentation buses.
8.1.4 Containment Purge Effluent Monitors Detectors 1RE-PR001 A, B, and C (air parthzulate, gas, and I2 channels, respectively) and 2RE-P. .s, B, and C monitor containment effluent for Units 1 anc~ ospectively.
The monitor has a range of radioactive gas concentration of 10-6 pCi/cc to 10-2 pCi/cc. High radiation is annunciated in the main control room.
Each monitor has a microprocessor which utilizes digital processing techniques to analyze data and control monitor functions. Control room readouts include a cathode ray O
8.1-4
BYRON REVISION 5 FEBRUARY 1983 tube display (RM-ll) , a recorder, and an RM-23 remote display 4
O module for all monitor parameters.
The monitor panels and their associated pumps, detectors, and c
lo'al controls, are located in the auxiliary building on the 451 ft elevation.
A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply i unit is located within the monitoring system cabinet. The monitors are powered from local 120-Vac instrumentation buses.
8.1.5 Gas Decay Tank Monitors Detectors ORE-PR002 A and B (gas channel) monitor the radi-ation level of the gas decay tank discharge to the auxiliary building vent stack. Automatically, on high radiation and/or instrument failure signal from the detectors in the l
gas decay tank discharge, vent valve OGWRCV014 between gas decay tanks OGW0lTA to OGW0lTF closes.
l The monitor has a range for radioactive gas concentration of 10-6 pCi/cc to 10-2 pCi/cc. High radiation is annunciated in the main control room.
The monitor has a microprocessor which utilizes digital processing techniques to analyze data and control monitor functions. Control room readouts include a cathode ray tube display (RM-ll) , a recorder, and RM-23 remote display L module for all monitor parameters. s l
- The monitor panel and associated features, pumps, detectors, l
l and local controls, are located in the auxiliary building on the 396 ft elevation.
O ~
8.1-5
k BYRON REVISION 5 FEBRUARY 1983
() A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply unit is located within the monitoring system cabinet. The monitor is powered from local 120-Vac instrumentation buses.
8.1.6 Radwaste Area Vent Exhaust Detectors ORE-PR026 A, B, and C (air particulate, gas, and I
2 hannels, respectively) monitor the radwaste area vent exhaust. The radwaste area vent exhaust is ducted to the auxiliary building vent stack.
The monitor has a range for radioactive gas of 10-6 pCi/cc
-2 pCi/cc.
to 10 High radiation is annunciated in the main control room.
() The monitor has a microprocessor which utilizes digital processing techniques to analyze data and control monitor l functions. Control room readouts include a cathode ray
. tube display (RM-ll) , a recorder, and an RM-23 remote display module for all monitor parameters.
The monitor panel and associated features, pumps, detectors, and local controls, are located in the auxiliary building on the 426 ft elevation.
A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply unit is located within the monitoring system cabinet. The
! monitor is powered from local 120-Vac instrumentation buses.
l l
8.1-6 1
l BYRON REVISION 5 l FEBRUARY 1983 ,
l 8.1.7 VR System Areas and Cubicles Ventilation Exhaust Detectors ORE-PR040 A, B, and C (air particulate, gas, and I
2 channels, respectively) monitor the ventilation exhaust from the volume reduction equipment areas and cubicles.
The radiation monitor is interlocked with the volume reduction ventilation exhaust fans OVW10C and OVW14C, associated bypass, and filter inlet and outlet dampers. Automatically on high radiation, the bypass dampers close and the fans start to route the exhaust through the filter unit. This system is interconnected with the radwaste building ventilation system.
8.1.8 SJAE/ Gland Steam Exhaust 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 stacks.
Detectors 1RE-PR027 A, B, and C (air particulate, gas, and I
2 hannels, respectively) and 2RE-PR027 A, B, and C monitor the off-gas system exhaust from Units 1 and 2, respectively.
Automatically on high radiation in the off-gas exhaust stream, bypass valves and the off-gas vent filter system 00G015 are energized.
The monitor has a microprocessor which utilizes digital processing techniques to analyze data and control monitor functions. Control room readouts include a cathode ray tube display (RM-ll) , a recorder, and an RM-23 remote display module for all monitor parameters. The monitor has a range for radioactive gas of 10-6 pCi/cc to 10-2 pCi/cc.
8.1-7
BYRON REVISION 5 FEBRUARY 1983 The monitor panel and associated features, pumps, detectors, O and local controls, are located in the auxiliary building on the 401 ft elevation.
A power supply unit furnishes the positive and negative volt-ages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply unit is located within the monitoring system cabinet. The monitor is powered from local 120-Vac instrumentation buses.
- 8.1.9 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation system, and the gas decay tanks are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocat.Lon will normally be made evenly between units.
< O During refueling outages or periods of known major in-plant leakage, the appor-tionment will be adjusted accordingly. The allocations of l effluents will be estimated on a monthly basis.
O j 8.1-8 l
l I . . , ., . _ _ _ . _.,__ _
BYRON REVISION 5 FEBRUARY 1983 8.1.10 Symbols Used in Section 8.1 SYMBOLS NAME UNIT Q tv Total Release Rate, Vent Release (pCi/sec)
V Gamma Whole Body Dose Constant, i
Vent Release (mrad /yr per pCi/sec) f Fractional Radionuclide Composition i
Lg Beta Skin Dose Constant (mrem /yr per pCi/m )
(X/Q) Relative Effluent Concentration, Vent Stack Release (sec/m )
s Ag Radiological Decay Constant (hr~)
R Downward Range (m)
O uy Average Wind Speed, Vent Release (m/sec)
Q gy Release Rate of Nuclide i, Vent Release (pCi/sec) i V Gamma Dose Constant, Vent Stack i
Release (mrad /yr per pCi/sec) l
() 8.1-9
-. ,e. , _. - _ . , , - - - . . - - . , - - - - - . . . - -
BYRON REVISION 5 FEBRUARY 1983 8.1.11 Constants Used in Section 8.1 NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrem / mrad) ,
3600 Conversion Constant (sec/hr) ,
I O i i
8.1-10
BYRON REVISION 5 FEBRUARY 1983 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.
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 concentration limit (Cyg ,) in the discharge line prior to dilution in the initial dilution stream is:
E F
ave +F max lim = MPC C .
(g,4) pr max l
C yg, Limiting Concentration (pCi/ml) in Discharge Line The maximum concentration in the discharge line permitted to be discharged to the initial dilution stream.
() 8.2-1
BYRON REVISION 5 t
FEBRUARY 1983
( MPC Weighted Maximum Permissible (UCi/ml)
Concentration n n
[C
- 1 p [A g MPC = or i n C. n A MC MC i1 1 ( y i (8.5) where:
Cy = UCi/ml of nuclide i; MPC y = maximum permissible concentration ECi/ml of nuclide i; and Ag = pCi of nuclide i released in time t.
F Maximum Flow Rate, Radwaste 3 max (ft /sec)
Discharge Q(/ The maximum flow rate of radwaste from the discharge tank to the initial dilution stream.
F Average Flow Rate Initial ve (ft /sec' Dilution Stream The average flow rate of the initial dilution stream which carries the radionuclides to the unrestricted l area boundary.
Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.
8.2.3 Liquid Radwaste Effluent Monitor Detector ORE-PR001 monitors liquid radwaste effluent and
\
is interlocked with release tank discharge valve OWX353.
8 . 2- 2
BYRON ' REVISION 5 l.
FEBRUARY 1983
[ .The release tank (0WX01T) holds 30,000 gallons and is located in the turbine building on the 401 ft elevation.
On high radiation in the liquid radwaste effluent, the release tank discharge valve is closed automatically. A high radiation level signal initiates automatic closure of the valve located in the component. cooling surge tank vent line~to prevent l gaseous radiation release. '
r I
l The monitor has a range for gamma radiation of 10-6 pCi/cc
- to 10-2 pCi/cc. The monitor panel and associated features are located in the turbine building on the 401 ft elevation.
I The monitor has a microprocessor which utilizes digital j processing techniques to analyze data and control monitor functions. Control room readouts include a cathode ray tube display (RM-ll) , a recorder, and an RM-23 remote display module for all monitor parameters.
A power supply unit furnishes the positive and negative i
voltages for the circuits, relays, and alarm lights and
. provides the high voltage for the' detector. The power supply is located within the monitoring system cabinet. The monitor
- is powered from local 120-Vac instrumentation buses.
8.2.4 Component Cooling Water Monitors Radiation detectors 1RE-PR009, 2RE-PR009, and ORE-PR009 continuously monitor the component cooling system for leakage v2 reactor coolant from the reactor coolant system and/or the residual heat removal system.
Detector 1RE-PR009 is interlocked with the component cooling I surge. tank (lCC0lT ) vent valve ICCRCV017, and detector 2RE-PR009 is interlocked with the component cooling surge tank (2CC0lT )
8.2-3 4
. .. . . . - , - -,..-.m.---.,..---.--..-_.,--...m..-..-..--_m,-.,,_r. y,- -. - -.- , -----,- ,,- - - - , . . - - - - , .- - - - - - . , + - . . - - . - ,
, BYRON REVISION 5
. FEBRUARY 1983
(' '
vent valve 2CCRCV017. Detector ORE-PR009 is interlocked with both vent valves, ICCRCV017 and 2CCRCV017.
The component cooling surge tanks are located next to each other on the 426 ft elevation near the laundry room. They are each capable of holding 2,000 gallons.
The monitor has a range for gamma radiation of 10-6 pei/cc to 10
-2 pCi/cc.
The monitor panels and associated features are located in the auxiliary building on the 364 ft elevation.
The monitor has a microprocessor which utilizes digital proces-sing techniques to analyze data and control monitor functions.
Control room readouts include a cathode ray tube display (RM-ll), a recorder, and an RM-23 remote display module for all monitor parameters.
A power supply unit furnishes the positive and negative O voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply is located within the monitoring system cabinet. The monitor is powered from local 120-Vac instrumentation buses.
8.2.5 Steam Generator Blowdown Detectors 1RE-PR008 and 2RE-PR008 monitor steam generator blowdown for Units 1 and 2, respectively.
Steam generator blowdown sample flow is normally routed through the steam generator blowdown sample panel, OPS 01J, I located on the 426 ft elevation in the chemistry hot lab, I
and on to the radiation monitor. Automatically on high radiation, detector 1RE-PR008 interlocks to close steam generator blowdown sample valves 1PS179A through D to ter-minate sample flow to the sample panel and radiation monitor. '
- i. 8.2-4 l
l
~ '
BYRON REVISION 5 FEBRUARY 1983 A similar interlock exists between detector 2RE-PR008 and CN) valves 2PS179A through D. Sequential isolation of steam generator blowdown can be used to determine which steam i generator may be leaking.
The monitor has a range for gamma radiation of 10 -6 pCi/cc .
-2 pCi/cc.
to 10 The monitor panels and associated features are located in the auxiliary building on the 426 ft elevation.
8.2.6 Blowdown Filters The flow from the blowdown mixed-bed demineralizers is normally sent to the condensate storage tank. Detectors ORE-PR0l6 through 19 are interlocked with the blowdown after-filter
- discharge valves OWX119A through D and blowdown monitor I
tank inlet valves OWX58A through D.
i The two condensate storage tanks are located outside of the plant on the southeast corner. Each tank can hold 500,000 t gallons. The three blowdown monitor tanks (0WX0 2T A, B , and C) are located on the 364 ft elevation. Each tank is capable of holding 20,000 gallons.
1 Automatically on high radiation, the flow from the blowdown mixed-bed demineralizers is redirected to the blowdown monitor tanks.
Mons. tors ORE-PR0l6 and ORE-PR017 are located in the auxiliary building on the 383 ft elevation. Monitors ORE-PR018 and ORE-PR019 are located in the auxiliary building on the 391 ft elevation. All fcur monitors have ranges for gamma radiation of 10 -6 pCi/cc to 10 -2 pCi/cc.
() 8.2-5
BYRON REVISION 5 l- FEBRUARY 1983 4 8.2.7 Administrative and Procedural Controls for Radwaste Discharges F
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 the release tank OWX0lT. On high radiation in the liquid radwaste effluent, the release tank discharge i valve 0WX353 is closed automatically.
l A documented valve checklist is prepared for each batch discharge. The proper valve lineup is made by the operator l and rechecked by the radwaste foreman. The actual dischage is authorized by the shift engineer.
O The system is equipped with a radiation trip point which alarms and initiates automatic valve closure on the radwaste discharge lina to prevent the violation of 10 CFR 20 limits.
8.2.8 Determination of Initial Dilution Stream Flow Rates 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 instrumen-tation will be operated and maintained as prescribed by the Technical Specifications. For those release paths which j do not have installed flow monitoring instrumentation, flow -
l rates will be determined by use of appropriate engineering data such as pump curves, differential pressures, or valve ,
position indication.
l
(::) e.2-e p - - - - -
BYRON REVISION 5 FEBRUARY 1983 1
8.2.9 Symbols Used In Section 8.2 SYMBOL NAME UNIT C yg, Limiting Concentration (VCi/ml) in Discharge Line MPC Weighted Maximum (pCi/ml)
Permissible Concentration Cy Nuclide Concentration (VCi/ml)
MK i Maximum Permissible
, Concentration (pCi/ml)
Ag Nuclide Quantity Released (pCi)
E F ,x Maximum Flow Rate, (ft 3/sec)
Radwaste Discharge yd Average Flow Rate, 3 (ft /sec)
Initial Dilution Stream 8.2-7
BYRON REVISION 5 FEBRUARY 1983 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 1
The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.
O 1
8.3-1
BYRON REVISION 5 FEBRUARY 1983 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs around Byron Station is given in Table 8.4-1 for the preoperational and first 2 years postoperational period. Table 8.4-2 describes the program for subsequent years.
Figure 8.4-1 shows the 8 fixed air sampling sites. Figure 8.4-2 shows the locations of the " inner ring" and " outer ring" TLD's (at an approximate distance of 5 miles from the station).
The TLD's are code numbered as (ollows: XYY-N.
Where:
l X=1 means inner ring, X=2 means outer ring, aad YY-N is an identification' code.
The practical lower limits of detection for this program are given in Table 8.4-3.
O l
l 8.4-1
i 1
l TABLE 8.4-1 l
a 1 RADIOLOGICAL MONITORING PROGRAM i .
- (Preoperational and Two-Year.Postoperational) l i
TYPE'AND FREQUENCY FREQUENCY NONROUTINE SAMPLE MEDIUM OF ANALYSIS
- COLLECTION SITES OF COLLECTING REPORTING LEVELS
- 1. Airborne ,
1
- a. Particulate Gross beta - W. . Byron, Stillman Valley, Cs-134, 10 pCi/m3
~
' i Continuous Filter Sr 89, 90 - Q. comp. Nearsite-East, Paines operation of a. Cs-137, 20 pCi/m Gama Spec. - Q. comp. Point, Nearsite-South, sampler for a Oregon, Mt. Morris, week Leaf River I
- b. Charcoal I-131 Same as for la Continuous 0.9 pCi/m3
.m Cartridge operation of a g p sampler for =
' ro 2 weeks '
i i 2. TLD Gama Same as for la, plus 40 Quarterly None l Radiation other sites distributed i
near the site boundary and at 5 miles (see Figures 8.4-1 and 8.4-2)
Minimum of 2 TLD's per 1 packet
$5 w<
- 3. Surface Water Sr-89, 90 - Q. comp. Woodland Creek, Rock Weekly **
Eh Gamma Spec. - M. comp. River downstream of the k3 Gross beta - W. station, Rock River ,_. m Tritium - Q. comp, upstream of the station , g w_
m <r, ---- ,,,
e
i i
O O O i -TABLE 8.4-1 (Cont'd)
TYPE AND FREQUENCY FREQUENCY NONROUTINE SAMPLE MEDIUM OF ANALYSIS
- COLLECTION SITES OF COLLECTING REPORTING LEVELS
\
l
- 4. Intake / Discharge Gross beta - W. I/D Pipes if pumpihg; if Weekly None pipes Sr-89, 90 - M. comp. not pumping, collect in 4
Tritium - M. comp. Rock River near I/D
- Gama Spec. - M. - comp. structures i
, 5. Precipitation Gama Spec. - Q. comp. Same four sites as Monthly None i' Sr-89, 90 - Q. comp. milk collections Gross beta - M.
Tritium - Q. comp.
! 6. Well Water: Gama Spec. CECO Real Estate Office Quarterly **
m Offsite Sr-89, 90 m
)
. Gross beta ;;j L Tritium @
4
- 7. Well Water: -Gamma Spec. - Q. comp. One onsite well (the Monthly **
Onsite Sr-89, 90 - Q. comp. one chosen for pro-Gross beta - M. viding drinking
- Tritium - Q. comp, water)
I
- 8. Ve5etables Gross beta Farms within 10 miles As available at
$5
-< =
- 9. Cattle Feed Gross beta Same four sites as Quarterly: None Gm and Grass Sr-89, 90 milk collections Grass: Summer $
Gama Spec. Feed: Winter
i TABLE 8.4-1 (Cont'd) i TYPE AND FREQUENCY FREQUENCY NONR00 TIME i
SAMPLE MEDIUM OF ANALYSIS
- COLLECTION SITES OF COLLECTING REPORTING LEVELS i
- 10. Milk Gama Spec. Four nearby dairies or Monthly - Nuclide pCi/l Sr-89, 90 - M. private animals, November to April I-131 (Pasture including the nearest, Weekly - May I 131 3
- Season) if possible to October Cs-134 70 Cs-137 60 Ba/La-140 300
- 11. Sediment, Gross beta Just upstream of Three times a *
- Aquatic Plants Gama Spec. 1/D structure year, if available i
Just downstream of I/D structure i
g
= 12. Fish . Gross beta At discharge surface 8
Three times a year
- l p Gama Spec. water sample site a Sr-89, 90
, If frequency of analysis is not given, it is the same as frequency of collection; W. - Weekly; M. - Monthly; Q. - Quarterly; Comp. - Composite.
- pCi/kg wet weight ** Nuclide pCi/l Nuclide pCi/l 4
! Co-58 3 x 1044 Mn-54 1,000 I-131 2 l
' Zn-65 2 x 10 3 Fe-59 100 Cs-134 30 n :=
Cs-137 2 x 10 .Co-58 600 Cs-137 i Fe-59 1 x 10 44 Co-60 50 90 i 300 Ba/La-140 100 EG Co-60 1 x 10 3 Zn-65 200 M5 '
Cs-134 1 x 10 . -< a w a, CD GJ
[
O O
~
O TABLE 8.4-2 RADIOLOGICAL MONITORING PROGRAM (Third Year and later Operational Program) i NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS
- 1
- 1. Air a. By-01 Byron a. Filter - a. Continuous Cs-134, 10;
- Monitoring By-02(a) Stillman Valley gross beta ** operation of a Cs-137, 20 pCi/m3 i By-03 Nearsite-East sampler for a i By-04 Paines Point week l By-05 Nearsite-South 0.9 pC1/m 3 By-06 Oregon b. Charcoal - b. Continuous By-07(a) Mt. Morris I-131 operation of a cm
- By-08(a) Leaf River sampler for 35
,co 2 weeks E
- c. Sampling c. Weekly Not Applicable ,
Train -
Test and Maintenance
, 2. TLD a. Same as Item 1, Air Gamma Quarterly None
] Monitoring Sites *** Radiation 1
- b. Plus 40 other sites distributed about the M site boundary and at E5 5 miles *** t (minimum of 2 TLD's per packet) y
-c z G*
O O O TABLE 8.4-2 (Cont'd) 1 NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS *
- 3. Fish By-12 Downstream Gama Semi-annual pCi/kg wet weight Isotopic Mn-54 3 x 10 44 Co-58 3 x 10 Zn-65 2 x 10~43 Cs-137 2 x 10 4 Fe-59 1 x 10 4 Co-60 1 x 10 3 Cs-134 1 x 10
- 4. Milk a. Four nearby dairies I-131 " a. Weekly pCi/l or private animals during including the nearest, grazing I 131 3 if possible season, May Cs-134' O
.{ to October Cs 137 b E c'n Ba La-140, 300 $l
' b. Monthly, Same as 4a November to April
- 5. Surface By-09 Woodland Creek Gama Monthly Nuclides pCi/1 Water By-12 Downstream Isotopic analysis of By-13(a) Upstream weekly H-3 000 composites gn-54 20'000 l,
Fe-59 100 l
Co-58 600 Co-60 300 n :x, Zn-65 200 9Q Zr-Nb-95 400 E0; I-131 2 3;2; Cs-134 30 **
l Cs-137 50 G" 1 Ba-La-140 100 8 r
O O O i
l
! TABLE 8.4-2 (Cont'd) 1 NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS *
- 6. Cooling a. Inlet ttt Gross Beta Weekly None Water Sample b. Discharge ttt -
1
- 7. Sediment Downstream site Gama Annual None t
- Isotopic !
i
. 'I 4
?
u 8
a i
I F
- Average concentration over calendar quarter.
I **A gamma isotopic analysis shall be performed whenever the gross beta concentration in a sample exceeds by five times (5x) the average concentration of the preceding calendar quarter for the sample location.
- See Figure 8.4-1. n :o j
.; tSee Figure 8.4-2. 90 I
ttA gama isotopic analysis shall be performed if I-131 from the plant is found above the LLD. EG tttProvided by station personnel. Ql G*
4
_7_ _.m , _ _
BYRON REVISION 5 FEBRUARY 1983 TABLE 8.4-3 (O
(/ PRACTICAL LOWER LIMITS OF DETECTION (LLD)
FOR ENVIRONMENTAL khDIOLOGICAL MONITORING PROGRAM LLD SAMPLE MEDIA ANALYSIS (4.660) UNITS Airborne Gross Beta
- 0.01 pCi/m 3
" Particulate" Gamma Isotopic 0.01 pCi/m 3 Sr-89, 90 0.01 pCi/m 3 Airborne I-131 Iodine-131 0.10 pCi/m Liquids Sr-89 10 pCi/l Sr-90 2 pCi/l I-131 5** pC1/1 Cs-134 10 pCi/l Cs-137 10*** pCi/1 Tritium 0.2 pCi/ml Gross Beta
- 5 pCi/l Gamma Isotopic <20 pCi/1/nuclide Vegetation Gross Beta
- 2 pCi/g wet O- I-131 Sr-89, 90 0.03 1
pCi/g pCi/g wet 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 Sr-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 l
- Referenced to Cs-137.
l **0.5 pCi/1 on milk samples collected during the pasture season.
- 5.0 pCi/1 on milk samples.
t
!O 8.4-8
O O O TABLE 8.4-4 ENVIRONMENTAL RADIOLOGICAL MONITORING SAMPLING CODES SURFACE WELL AQUATIC PLANTS PRECIPITATION, MONITORING SITES AIR TLD WATER WATER FISH AND SEDIMENT MILK FEED, GRASS VEGETABLES By-01 Byron X X By-02 Stillman Valley X X By-03 Nearsite-East X X By-04 Paines Point X X By-05 Nearsite-South X X
'Jy-06 Oregon X X By-07 Mt. Morris X X co By-08 Leaf River X X k* E By-09 Woodland Creek X By-10 Intake Pipe X By-11 Discharge Pipe X By-12 Downstream X X By-12 Downstream (from Oregon Pool of Rock River) X By-13 Upstream X X By-14 CECO Real Estate Office X n :=
90 By-15 Groenhagen/0ltmann Dairy X X ED; By-16 Ashelford Dairy Farm X X h5 By-17 Bosecker/Lingre Dairy Farm X X (;;
- By-18 Onsite Well X 0
t i
O O O !
l TABLE 8.4-4 (Cont'd) l
! SURFACE WELL AQUATIC PLANTS PRECIPITATION, l MONITORING SITES AIR TLD WATER WATER FISH AND SEDIMENT MILK FEED, GRASS VEGETABLES i ,
By-19-1 Oregon Stand X l i
l' By-19-2 Oregon Stand X I
- By-20 Meyers Dairy Farm X X 3
4
=
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,, Point 6
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SCALE
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O FIXE 0 AIR SAMPLING SITES
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.-TLD FIGURE 8.4-2 INNER RING AND OUTER RING TLD LOCATIONS 1
? _ _ _ -____ _ _____ _ _ _ _ _ -