ML20235T642
| ML20235T642 | |
| Person / Time | |
|---|---|
| Site: | Byron, Zion, 05000000 |
| Issue date: | 12/31/1987 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-871231, NUDOCS 8903080397 | |
| Download: ML20235T642 (24) | |
Text
_ _ __ _ . - - - - - - - . - - - - - - - __ - .- -
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/~} . BYRON REVISION llB i/
m DECEMBER 1987 i ODCM TABLE OF CONTENTS FOR BYRON SECTION 8.0 PAGE 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENT RADIOLOGICAL MONITORING 8.1-1 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 Monitors 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 Allocation of Effluents from Common Release Points 8.1-6 8.1.7 Symbols Used in Section'8.1 8.1-7 8.1.8 Constants Used in Section 8.1 8.1-8
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(_/ 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 8.2-3 8.2.4 Station Blowdown Monitor 8.2-4 8.2.5 Reactor Containment Fan Cooler (RCFC),
Essential Service Water Outlet Line, Fire and Oil Sump, and Condensate Polishing High and Low Conductivity Sumps Monitors 8.2-5 8.2.6 Administrative and Procedural Controls for Radwaste Discharges 8.2-6 8.2.7 Determination of Initial Dilution Steam Flow Rates 8.2-6 8.2.8 Allocation of Effluents from Common Release -
Points 8.2-7 8.2.9 Symbols Used in Section 8.2 8.2-7 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 O
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REVISION 11A DECEMBER 1987 GENERIC ODCM REVISION INDEX REVISION REVISION PAGE NUMBER PAGE NUMBER i 11 2.2-1 11 11 11 2.2-2 11 111 11 2.2-3 11 iv 11 2.2-4 11 v 11A- 2.2-5 11 vi 11 2.2-6 11 2.2-7 11 Section 1.0 2.2-8 11 2.2-9 11 1.0-1 11 2.3-1 11 1.0-2 11A 2.3-2 11 1.0-2a 11A 2.3-3 11 1.0-3 11 2.3-4 11 F1.0-1 11A 2.3-5 11 2.3-6 11 Section 2.0 2.3-7 11 2.3-8 11 2.1-1 11 2.3-9 11 2.1-2 11 2.3-10 11 2.1-3 11 2.3-11 11 9 2.1-4 2.1-5 2.1-6 11 11 11 2.3-12 T2.3-1 (2 Sh.)
11 11 2.1-7 11 Section 3.0 2.1-8 11 2.1-9 11A 3.1-1 11 2.1-10 11 3.1-2 11 2.1-11 11 3.1-3 11 2.1-12 11 3.1-4 11 2.1-13 11 3.2-1 11 2.1-14 11 3.2-2 11 2.1-15 11 3.2-3 11 2.1-16 11 3.2-4 11 2.1-17 11 3.2-5 11 2.1-18 11A 3.2-6 11 c.1-19 11 3.2-7 11 2.1-20 11A 3.2-8 11 2.1-20a 11A 3.2-9 11 2.1-21 11 3.2-10 11 2.1-22 11 3.2-11 11 2.1-23 11 3.3-1 11 2.1-24 11 3.3-2 11 2.1-25 11 9
n 0 REVISION 11A DECEMBER 1987 j' ')
GENERIC ODCM REVISION INDEX (Cont'd) 0%.</. ,
REVISION REVISION
-PAGE NUMBER PAGE NUMBER 3.3-3 11 T7.1-3' 11A 3.3-4 11 T7.1-4 11 3.3-5 11 T7.1-5 11 3.3-6 11 T7.1-6 11 3.3-7. 11 T7.1-7 11
'3.4-1 11 T7.1-8 11 T7.1-9 11 Section 4.0 T7.1-10 11 T7.1-11 (2 Sh.) 11 4.1-1 11 T7.1-12 11 4.1-2 11 T7.1-13 11 t 4.1-3 11 T7.1-14 ( 2 Sh . ) 11 4.2-1 11 T7.1-15 11A 4.2-2 11 F7.1-1 11 4.3-1 11 F7.1-2 11 4 4.3-2 11 F7.1-3 11 F7.1-4 11 Section 5.0 F7.1-5 11 F7.1-6 11
.5.1-1 11 F7.1-7 11 1/,'l. 5.1-2 11 F7.1-8 11
\- l T5.1-1 11 T5.1-2 11 5.2-1 11 5.2-2 11 T5.2-1 11 5.3-1 11 T5.3-1 11 5.4-1 11 T5.4-1 11 Section 6.0 6.0-1 11 l 6.0-2 11 6.0-3 11 Section 7.0 7.0-1 11
- 7.1-1 11 i T7.1-1 11A l
T7.1-E-7 (3 Sh.) 11 T7.1-E-9 (3 Sh. ) 11A T7.1-E-10 (3 Sh.) 11 T7.1-E-11 (3 Sh.) 11 g-')s
(_ , T7.1-E-14 ( 3 Sh. ) 11
, T7.1-2 (2 Sh.) 11 l
l 1
, REVISION llA DECEMBER 1987 7~5 ODCM LIST OF TABLES 1
)
NUMBER TITTE PAGE 2.3-1 Numerical Models for Computing Radiation Dose for Uranium Fuel Cycle Operations 2.3-13 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 7.1-1 Dose Commitme'nt Factors 7.1-2 7.1-E-7 Inhalation Dose Factors for Adults 7.1-3 7.1-E-9 Inhalation Dose Factors for Children 7.1-Sa l 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 -
Infants and Child 7.1-17 l
[.,') 7.1-4 Stable Element Transfer Data 7.1-18 k/ 7.1-5 Atmospheric Stability Classes 7.1-19 7.1-6 Wind Sensor Treshold 7.1-20 7.1-7 Vertical Dispersion Parameters 7.1-21 7.1-8 Wind Speed and Wind Direction Classes 7.1-22 ;
7.1-9 Airborne Isotope Data 7.1-23 l 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 7.1-11 Listing of Radiological Decay Constants 7.1-25 7.1-12 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data 7.1-27 7.1-13 Dose Factors For Exposure to a Semi-Infinite Cloud of Noble Gases 7.1-28 7.1-14 External Dose Factors for Standing on Contaminated Ground 7.1-29 7.1-15 Sector Code Definitions 7.1-31 l I 7.2 Lists of Tables for Section 7.2 will be found preceding the site-specific data for Dresden, Quad-Cities, La Salle, Zion, Byron, and Braidwood Stations 8.0 Lists of Tables for Section 8.0 will be found preceding the site-specific
,e 3 data for Dresden, Quad-Cities, La Salle, Zion, Byron and Braidwood
() Stations v
F 4 . .
- REVISION llA j DECEMBER 1987 l' h .
'(bone, liver, total body, thyroid, kidney, lung,.and-
[M ,
GI-LLI) are computed from individual nuclide contributions.
in each of the sectors. ' Searching over sector and organ, the largest organ dose is compared to the 10 CFR 50, Appendix Icdesign objectives. ,
To identify.whether an adult or an infant is the critical receptor.(the one receiving the larger dose), this. dose l calculation is performed for both adults and infants at the following times after station startup: (1) during the earliest 10 CFR 50, Appendix-I offsite organ dose evaluation in,which sufficient data is available.to identify
~
the critical receptor, and (2)' once per calendar year thereafter.using the previous year's data. At other times, this dose calculation'is performed monthly only for the critical receptor.
- As necessary, the release rates of these nuclides'are l converted to dose-rates for comparison to the limits i of 10 CFR'20. For this purpose, the dose rate to the infant is~ considered limiting at three stations (Dresden, l La Salle, and Quad Cities). At Braidwood, Byron, and Zion, it is the child. ;
j (2) Noble Gases l Exposure to the beta and gamma radiations of the noble i gases will result in a'whole body and skin dose. The maximum whole body and skin doses for each offsite sector are determined from the individual nuclide contributions and the maximum dose values are compared to the 10 CFR 50, Appendix I design objectives. This calculation is performed monthly. As necessary, the noble gas release rates are converted to dose rates for comparison to the
.- limits of 10 CFR 20.
1.0-2 l
l j
REVISION llA
- DECEMBER 1987
. i
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Liquid Releases For liquid releases it is assumed that liquid effluents ,
discharged into a river undergo mixing prior to consumption O
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t r pa .
r ed n y B cn w
.L * .
- d e rl e o o t d A N * .
- d B s d a a w d
C A d i u i
- l c o I
G i .i o e o o
- r . a l T o c n i rre o s cr b E R r
~ r r l r yon t n ie R O y y y h
o i k a h o p a t p r C h n h v T B e g i e T T T W S c r re t
- - e o cc a r n w
- - eo s s
- 7 .
e e l h g e l r e a . r td n L r cs of n i A u b u r ra T s a s u ie ti o t
a NY o t o s it d f p EA n n p n e p o ri e u u l
p MW o .o x o g e
x E x cC t yt c NH i i E i E u l r r OT t t t a
v ec d ed p ha i RA a a .d y u n e r r ha m tt c IP l l n l e e t u o ns V a a k - u a k t f d u m h Q c o mg o f o l a a o ro u t s t s
N E
h n .hn i l
r h. i : e r l a i a id s n
~
' MG 1 M ". L P G P W F W I n ~i di e
- - - - - - da ew t
- - - l i, s e mo i rl s
" R s he o ol o O n cl d f o p T = tn d , t l rf m P n t o t t l ea , e o a .l a s l E l u l r u u hS r pd c i f e CE - nrh R
f I oC I n d A
l e AP d
A d t
,L e
a ve sm ir
'n o
- A- s w o o nf n n ,
s on h or or i e e i e td ; t p y
_ u E d as n a B
, i D l e a l e I ssl s ur g ur t L S eec e cD r ca a C nt u s l o l U S i aN at ar y A dl a cot N L our G ca l l O C a k I ice e ed c ep e D cih l 8 se i se e A itt b l os t oc w R drO o l du i de aa N A r r d RP5 c
~ 0s 0 e
-- - 2i y
5l a
m r
- Rt l Rc o
~ e F n e Fi f E n Ca k Cti r
> s , SE A D r
o d
i u 0 n f i l 0r e
p L O b 1 c q 1i L M r t o E i i re s ee s R A L hh l
- oh o A FT M Tt
- A t
" h s.
i
~
. REVISION llA DECEMBER 1987 7-~s vf Gamma Whole Body Dose (mrad /yr per
\- Constant, Vent Release pCi/sec)
The constant V i multiplied by the attenuation !
afforded by 5 cm of tissue; used to evaluate whole body dese. (See Subsection 3.3.1.2; also, see Tables 7.2-8 or 7.2-11.)
G Gamma Whole Body Dose (mrad /yr per 1
Constant, Ground Level Release pCi/sec)
The constant G 1 multiplied by the attenuation 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.)
2.1.1.1.3 Skin Dose Calculations p_
The skin dose to individuals in unrestricted areas due to noble (s ) gas released in gaseous effluents from each reactor shall be calculated when necessary by the following expression:
(X/Q)g A'g
-0 + +
Dg = 3.17 x 10 1.0 L g (X/0) s Aks+ (X/Q)y A'gy 1
- )
(0. 7) (1.11) (S g Als + Yi A gy +G 1 Agg) (2.Sa)
~
\
( D s
Skin Dose (mrem)
The dose to the skin due to beta and ganma l l s s emissions from noble gases.
l l 1.0 Shielding Attenuation and occupancy Factor The shielding attenuation and occupancy factor for protection against beta radiation.
(~'N
. ('l ~
2.1-9 i
h -- ..-_-m._m_ _. ..
p.. .. . .
, . . . e.
'-4.
REVISIOil llA,,
' DECEMBER 1987:
(pCi/kg);
Cf Pasture Grass Concentration The concentration of radionuclides i in pasture grass (calculated ~using Equation 2.12 for Cp with ff = 1; other parameters,; including f a for use in Equation 2.15, are given-in-Tables 7.7-.' and 7.1-3).
" s C Stored Feed (pCi/kg).
Concentration The concentration of. radionuclides.i' in stored-feed (calculated using Equation 2.12 for C1 with ff = 1; other parameters,. including f,.for
. use in Equation 2.15, are given in Tables 7.1-2 and 7.1-3).
Wf Feed Consumption (kg/ day)
The amount of feed consumed by the' animal each day. See-Tables 7.1-2 and 7.1-3.
t M
Milk Transport Time (hr)
.The average time from the production
+
of milk to.its consumption. See Tables 7.1-2 and 7.1-3.
Meat Concentration (pCi/kg)
- Cf The concentration of radionuclides i in meat.
C[ = F 7 Cf Wf exp (- A f3 t ) (2.16) n -
[' u .l ~
2.1-18
.4
= _ _ _ _ _ ____- - __- ______ _ _-____- -- -_______-_ _2_-___-________-_____-___ --____-_-______-__-__-____--_______-_____.
4- . REVISION.llA DECEMBER 1987
) (D/Q) s See Table 7.2-6 or 7.2-9.
I (D/Q)y See Table 7.2-6 or 7.2-9.
i (D/Q)g See Table 7.2-6 or 7.2-9.
2.1.2.1.2 Organ Dose Due to Inhalation, Food Pathways, and Ground Exposure, Calendar Year Limit 6 +
3.17 x 10
-8 x 10 p a
DFA lja (x/Q), Als + (*/0)v ^$v + (*/0)g^$g i
365 d ija U f p Cf+U C
+U[f y Cf+U[Cf -
+
i .
i 24 x 0.7 t r DFG g C $15 mrem (2.17) i
/h
(_,) 2.1.2.1.3 Organ Dose Due to Inhalation, Food Pathways, and Ground
! Exposure, Projections
)
I The projected dose to any organ of a member of the public shall be calculated by use of the formula of Equation 2.11. In this calculation,A{s'Aky, andA{g are taken as projected accumulative reledses, adjusted to account for radiodecay in transit, during the period of projection.
l 2.1.2.2 10 CFR 20 Release Rate Limit The maximum dose rate to any organ from all radionuclides, radioactive materials in particulate form, and radionuclides l
l other thaa noble gases with half-lives greater than 8 days shall be limited to the value given by the equation which follows. For purposes of demonstrating compliance with the Technical Specifications of Dresden, La Salle and Quad Cities, l
(
OI ,
2.1-20 +
p -
REVISION llA DECEMBER 1987 I -
V- .
the dose rate to the infant from the inhalation pathway shall be considered limiting. For demonstrating compliance with the Technical Specifications of Braidwood, Byron, and
~
Zion, the dose rate to the child from the inhalation pathway shall be considered limiting.
o 4
2 (3 *
(J 2.1-20a I 4 T
- REVISION 11A DECEMBER 1987
'i /T ,
\- /
TABLE 7.1-1 COSE COMMITMENT FACTORS PATHWAY INFANT CHILD' ADULT Inhalation Table 7.1-E-10 Table 7.1-E-9 Table 7.1-E-7 Ingestion Table 7.1-E-14 Not Required Table 7.1-E-ll The following tables are from Tables E-7, E-9, E-10, E-ll, and l !
t E-14 of Appendix E of Reference 6.5. Each table contains seven organ-dose factors for=73 radionuclides. For radionuclides not found in these tables dose factors will be derived from 'ICRP 2 (1959) or NUREG-0172 (Reference 6.10).
C l
1 u V s c
- b;
\ ,/ <
7.1-2 i
_________'_______.__ _ _ _ _ __ __ _i
l
[
L,, . REVISION llA DECEMBER-1987 TABLE 7.1-E-9
- 3 i I *
\. v /
- INHALATION DOSE FACTORS FOR CHILDREN (mrem per pCi Inhaled)
NUCLIDE 80NE liver T.RODY THYROID KIDNEY LUNG GI-LLI-H 3 NO DATA 3.04E-07 3.04E.07 3.046-07 3.04E-07. 3.04E-07 1.04E-07 C 14 9.70E-06 1.62E-06 f.82E-06 1 22E-06 1.82E-06 1.82E-06 1.82E-06 N A 24 4.35E-06 4.35 -06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06
.................................. ....c._- ................................
P 32 .7.04E-04 1.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.31F-08 6.57E-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19F-06 NN 56 NU DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 53 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 57 5.59E-06 9.04E-06 4.51E-06 NO DATA' NO DATA 3.43C-04 1.91E ................................. ...................................__....
CD 58 NO DATA 4.79E-07 8.55E-07 NO DATt NO DATA 2.99E-04 9.29E-06 CD 60 NO DATA 3.55E-06 6.12 E-0 6 NO DATA NO DATA 1.91E-03 2.60E-05 NI 61 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06
~
'41 65 8.08E-10 7.99E-11 4.44E-11 NO DATA NU DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2 59E-06 9.92E-06 IN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06
,-~s IN 69 1.81E-11 2.61E-11 2.410-12 NO DATA 1.58E-11 3.84E-07 2.75E-06
/ \ HR 85 NO DATA NO DATA 1. 2 6E -0 7 NO DATA NO DATA NO DATA LT E-24
\ ,j/s JR 84 NO DATA NU DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 et 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 Mn 86 NO DATA 5.36E-05 3.09E-05 NO CATA NO DATA NO DATA 2.16E-06 RP 88 NO DATA 1.52E-0T 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09
- RB 89 NO DATA 9. 3 3E-08 7.8JE-08 NO DATA NO DATA NO DATA 5.11E-10 54 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 5R 90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SP 91 3.2 8 E- 0 9 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05. 4.70E-05 SR 92 3 54E-09 M0 DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 1 11E-06 NO DATA 2.94E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 917 1.17E-10 NO DATA 4. 9 8 E -12 NO DATA NO DATA 7.60F-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 l Y 92 5.50E-09 NO DATA 1. 5 7 E-10 NO DATA NO DATA 6.46E-C6 6.46E-05
]:
v i
! \
-- /
7.1-Sa l
l
_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _________________________j
REVISION llA
, DECEMBER 1987
.m g
y TABLE 7.1-E-9 (Cont'd)
L; aVCLIDE BONE LIVER T.dOCY THYROID K!DNEY LONG GI-LLI Y 93 5.04E-08 NO DATA 1.3UE-09 NO DATA NO DATA 2.01E-05 1.05E-04 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.616-05 6.03E-04 1.65E-05 2R 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 N8 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO Daft 1.06E-07 3.66E-05 3.42E-05 TC 99F 4.81E-13 9.410-13 1.56E-11 40 DATA 1.37E-11 2.57E-07 1.30E-06 TC101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41F-09 RU103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RU105 4.13E-10 NU DATA 1.5CE-10 NO DATA 3.63E-1C 4.30E-06 2.69E-05 RU106 3.68E-05 NO DATA 4. 5 7E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG110* 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74L-06 1.48E-03 2.71E-05 TE1254 1.82E-06 6.29E-07 2.4 7E-0 7 5.205-07 NC DATA 1.29E-04 9 13E-06 TE127M 6.72E-06 2.31E-06 8. l oE-0 7 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.57E-10 1. 6 F E -10 5.30E-10 1.91E-09 2.71F-06 1.52E-05 1E12?P 5.19E-C6 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94L-11 7.93E-07 6.89E-06 TE131F 1.63E-08 1.60E-08 1.37E-08 2.64E-08 1.06E-07 5.56E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.78E-12 4.59t-12 1.59E-11 5.55E-07 3.60E-07
._____. ____...__. __.._____.. .._______...__.._________ .......___.o_......
s TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79L-07 1.02E-04 3.72E-05
! 130 2.21E-06 4.435-06 2 28E-06 4.99E-04 6.61L-06 NO DATA 1.38E-06
[s ,/}
t I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.136-05 NO DATA 7.68E-07 1 132 5.72E-07 1.10E-06 5. 0 TE-01 5.23E-05 1.69E-06 NO DATA S.65E-07 1 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 1 134 3.17E-07 5.84E-07 2.6?E-07 1.37E-05 8.92E-07 NO DATA 2.5BE-07 1 135 1.33E-06 2.16E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 CS134 1.76E-04 2.74E-04 6. 0 7 E -0 5 to DATA 8.93E-05 3.27E-05 1.04E-06
< CS136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.935-06 1.13E-06
! CS137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 l CS138 1.71E-07 2.27E-07 1. 5 0E-0 7 NO DATA 1.68E-07 1.84E-08 7.29E-08 l HA139 4.98E-10 2.66F-13 1.45E-11 NO DATA 2.33E-13 1 56E-06 1.56E-05 i
l i
.p
- V l
7.1- 5b ,
e f
t
- i. . .,
'1
- .y
~
REVISION llA 4
DECEMBER 1987:
i TABLE. 7.1-E-9 (cont ' d)
--[v - a
.l LIVER T.00DY. THYR 010 KIDNEY LUNG GI-LLI
'NUCLIDE 80NE
.--......-- .-----.......---- ..... -----...------------. 5.71E-09 4.71E-04 2 75E-05 DA140 2.00E-05 1.75E-08 1.17E-0 6 . NO D AT A .
BA141' 5.29E-11 2.95E-14 1. 72 F-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 84142 -1.35E-11' 9.73E-15 7.54E-13 NO CATA 7.87E-15 .4.44E-07. 7.41E-10 LA140 'l.14E-07 6.08E-08 2. 04 E-0 8 : NO DATA NO DATA 4.94E-05 6.10E-05' LA142 ~3.50E-10 4 1.11E-13. 3.49E-11 .NO DATA NO DATA 2.35E-06 2.05E-05 5.28E-Oo- 7. 8 3E-0 7 NO DATA 2.31E-06 ,1.47E 1.53E-05 CE141 1 06E-05 9.89E-08 S.37E-Od 7. 7 7E -09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE143 3.23E-03 1.05E CE144 1 83E-03 5.72E-04 .9.77E-05 NO DATA 3.17E-04 4.99E-06 1.50E-06 2.47E-07. NO DATA- 8.11t-07-' 1.17E-04 2.63E-05 PR14) 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07. 5.32E-08 PR144 8.87E-05; 2.22F Nji47 '2.92E-06 2.36E-06 1. 84E-0 7 .NO DATA 1.30E-06 W 187 4.41E-09 2 61E-09 1.17F-09 NO CATA NC UATA 1.11E-05' 2.46E-05 NP239 1.26E-07' 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05. 1.73E I 5e A.
y 7.1-5c 3
it - '
REVISION.IlA T - -DECEMBER 1987'
+
u: '
.1 TABLE 7.1-3 i MISCELLANEOUS DOSE ASSESSMENT' FACTORS ~- INFANT AND CHILD b
' PARAMETER:AND VALUE BASIS *'
~'
M
~
(U = 33011iters/yr :A
~
'UP , .. U A-a U[ = 0 for infant
- .c =.520, 26, and 330 kg/yr for. child -A l ,
- n. - "
3 R, = 1400 m /yr for infant A c
= 3.700 m3 /yr for child. A -l
-r = 1.0-(iodines)**; 0.2 (others) B
" =.48 hr-(2 days) B i t
M ..
~
kg ' = 0.0021-hr B Y-v
=-.0.7 kg/m 2 .B-t = 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> B -l e
t - = 0; for pasture , grass' (milk pathway) B j h
~
1
= 2160 hr (stored. feed and milk pathway) B ;
f = l.0 May-October; 0.0 November-April- 'C f
I f = 0.5 C.
g
~
f,. =.1.0 May-October 0.0' November-April C y Wf = 50 kg/ day D 1 p tg = 175,200 hr '(20. years) E
- Basis Codes: j A: Reference 6.5,. Table E-5. 3 B: Reference 6.5, Table E-15.
C: Typical for climate of Illinois and vicinity.
D: Reference 6.5, Table E-3.
The parameter t is taken as the midpoint of plant ,
E:
operatinglife~kperReference6.5,'AppendixC, Section 1).
- The r factor provides for-the-nondeposition on grass of the ,
organic' forms of iodine,
- o. ;
, +
7.1-17 bi-__ _ __ ___ _ _ __ _ __ _ _ ___ _ . _ _ . :]
, ,y __
REVISION llA~
- j. ,
DECEMBER 1987
( ; - TABLE 7.1-15
%j SECTO" qODE DEFINITIONS SECTOR SECTOR CODE DIRECTION
(j N W P WNW Q NW R NNW See Table 7.1-8 for wind directions in degrees corresponding to each sector.
,A
%) .
< 7.1-31 d
t4 November 17, 1988 E s Please follow the instructions below for updating your Offsite Dose Calculation Manual'(ODCM). Also, please note that all manual holders do not-receive all annex revisions - only those assigned.
Remove Insert ODCM Revision Index, Pgs 1 & 2.
~
0DCM Rev. Index, Pgs 1-& 2 Rev. 11, 3/85. Rev. 11A, 12/87 Index pg. v., Rev. 11, 3/85 Index pg. v. Rev. 11A,-12/87' Pg. 1.0-2, Rev. 11, 3/85 Pg. 1.0-2 & 1.0-2a, Rev. 11A, 12/87 Pg. 1.0-4, Rev. 11, 3/85 Pg. 1.0-4, Rev. 11A, 12/87 Pg. 2.1-9, Rev. 11, 3/85 Pg. 2.1-9, Rev. 11A. 12/87, Pg. 2.1-18, 2.1-20, Rev. 11 Pg. 2.1-18, 2.1-20-2.1-20a Rev. 11A Pg. 7.1-2, Rev. 11, 3/85 Pg. 7.1-2, Rev. 11A, 12/87 -
Pg. 7.1-5, Rev. 11, 3/85 Pg. 7.1-Sa-c, Rev. 11A, 12/87 Pg. 7.1-17, Rev. 11 Pg. 7.1-17, Rev. 11A Pg. 7.1-31, Rev. 11A,.12/87 ODCM Table of Contents, Byron Sec. 8.0, p. 8-1,-Rev. 11A Contents pg. 8-i, Rev. 118.
Zion, Sec. 8, p. 8.4-2 thru 8.4-6, Sec. 8, p. 8.4-2 thru.8.4-6a, Rev. 11 Rev. 11A.
Please sign, date and return this' control sheet to: "
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1 Name:
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6AsHIhcTOn el oc ac3ss II (,
_ _ - _ _ _