ML20236C345
| ML20236C345 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/31/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20236C200 | List: |
| References | |
| NUDOCS 8903220096 | |
| Download: ML20236C345 (15) | |
Text
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.O 00CM-REVISION
'The f0llowing pages are an addendum to the previous Monthly Operating-Report. The prior report contained a.section describing revisions (Revision :
11A) made in the;00CM.
However, the revised pages'were not included'in that report. The ensuing pages are the aforementioned.
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i I
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i 1397t il8903220096' 890307 PDR ADOCK 05000295 0934A' J
PDC R-
REVISION 11A DECEMBER 1987 GENERIC ODCd REVISION Il4DEX 1
REVISION REVISION PAGE NUMBER PAGE NUMBER i
11 2.,2 11 ii 11 2.2-2 11 iii 11 2.2-3 11 iv 11 2.2-4 11 y
11A.
2.2-5 11 i
vi 11 2.2-6 11 l
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 l
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 l
Section 2.0 2.3-7 11 1
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 2.1-4 11 2.3-12 11 1
2.1-5 11 T2.3-1 (2 Sh.)
11 2.1-6 11 l
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 i
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 1
2.1-17 11 3.2-5 11 2.1-18 11A 3.2-6 11 j
2.1-19 11 3.2-7 11 L
2.1-20 11A 3.2-8 11 2.1-20a 11 A 3.2-9 11 2,1-21 11 3.2-10 11 l
2.1-22 11 3.2-11 11 l
2.1-23 11 3.3-1 11 l
2.1-24 11 3.3-2 11 2.1-25 11 i
REVISION 11A DECEMBER' 1987 i
GENERIC 00CM REVISION INDEX (Cont'd)
REVISION REVISION PAGE
_JJUMBER PAGE NUMBER 3.3-3 11 T7.1-3 11A 3.3-4 11 T7.1-4 11 3.3-3 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 i
4.1-1 11 T7.1-12 11 4.1-2 11 T7.1-13 11 4.1-3 11 T7.1-14 (2 Sh.)
11 4.2-1 11 T7. c-15 11A 4.2-2 11 F7.1-1 11 4.3-1 11 F7.1-2 11 4.3-2 11 F7.1-3 11 F7.1-4 11 Se:: tion 5.0 F7.1-5 11 F7.1-6 11 5.1-1 11 F7.1-7 11 5.1-2 11 F7.1-8 11 TS.1-1 11 T5.1-2 11 5.2-1 11 5.2-2 11 i
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 6.0-2 11 6.0-3 11 Section 7.0 7.0-1 11 7.1-1 11 T7.1-1 11A 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 T7.1-E-14 (3 Sh.)
11 T7.1-2 (2 Sn.)
11
. REVISION llA i
DECEMBER 1987 TABLE 7.1-1 DOSE COMMITMENT FACTORS PATHWAY INFANT CHILD ADULT Inhalation Table 7.1-E-10 Table 7.1-E Table 7.1-E-7
. Ingestion Table 7.1-E-14 Not Required Table 7.1-E-11 1
.l The following tables are from Tables E-7, E-9, E-10, E-ll,'and l
E-14 of Appendix E of Reference-6.5.
Each table contains seven organ dose factors for 73 radionuclides.
For radionuclides.not i
found in these tables dose factors will be derived from ICRP 2 (1959) or NUREG-0172 (Reference 6.10).
1 J
f 7.1-2 lj
....x
REVISION llA DECEMBER 1987 TABLE 7.1-E-9 INHALATION DOSE FACTORS FOR CHILDREN
)
1 (mrem per pCi Inhaled) l NUCLIGE BONE LIVER T. BODY THYRO!D K1DNEY LUNG GI.LLI h
J NO DATA 3.C4E-97 3.04E-0T 3.046-07 1.04E-07 3.04E-07 3.04E-07 C 14 9.70E-06 1.82E-06 1.926-06 1.22E-06 1.82E-06 1.82E-06 1.B2E-06 s
NA 24 4.35E-06 4.35306 4.35E-06 4.3SE-06 4.35E-06
- 4. 3 5 t.-0 6 4 35E-06
{
P 32 7.04E-04 3.C95-05 2.670-05 NO CATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17 E -0 8 2.3tr-08 6.57E-09 4.59E-06 2.93E-07 HN $4 NO DATA 1.16E-05 2.57E-06 NO DATA 2.7tE-06 4.26E-04 6.19F-06 MN 56 NU DATA 4.48E-10 8.4 3E-11 NO DA1A 4.52E-10 3.55E-06 3.33E-05 FE 53 1.28E-05 6.00E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 4
FE 57 5.59C-06 9.C4E-06 4.5tE-06 NO DATA 40 DATA 3.43E-04 1.91E-05 j
g CO 58 NO DATA 4.796-07 8.55E-07 NO DAT\\
NC DATA 2.99E-04
'9.29E-06 CO 60 NO DATA 3.55E-06 6.12 E -0 6 NO DATA NO DATA 1.91E-03 2.60E-05 N1 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-lt 4.44E-11 NO DATA NC 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 ZN 65 1.15E-05 3.06E-05
't. 9 0 E -0 5 NO DATA l.93E-05 2.69E-04 4.41E-06 IN 67 1.81E-11 2.btE-1L
- 2. 41 E -12 NO DATA 1.58E-11 3.84E-07 2.75E-06 aR 83 NO 1; A T A NO DATA
- 1. 2 0 E-0 7 NO DATA NO DATA NO DATA LT E !
JR A4 NO DATA NU OATA 1.4HE-07 NO OATA NO DATA NO DATA LT E-24 1
I d3 8 ';
NO DATA NO DATA 6.84E-09 NO DATA NC DATA NO DATA LT E-24 l
NO 86 NO DATA 5.36E-05
- 3. 09E-0 5 NO CATA NO DATA NO DATA 2.16E-06 i
RP 89 NC OA1A 1.52E-07 9.90E-08 NO DATA NO DATS NO CATA 4.66E-09.
RB 89 NO DATA
- 9. 3 3E-08 7.8aE-08 NO.0ATA NO DATA NO DATA 5.11E-10 j
S4 81 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05
)
$R 90 2.73E-02 NO CATA
- 1. 74 E -0 3 NO DATA NC DATA 3.99E-03 9 28E-05 SP 91 3.28E-09 NO CATA L. 24 5 -0 9 NO OATA NO DATA 1 44E-05 4.70E-05 SR 92 3 54E-09 NO DATA 1.42E-to NO DATA NO DATA 6.49E-06 6.55E-05 Y
00 L.112-C6 NO DATA 2.94F-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 91P 1.17E-10 NO DATA
- 4. 9 3 E -12 NO DATA NO DATA 7.60F-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.595-06 No DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-04 NO DATA 1.57E-to NO DATA NO DATA 6.46E-C6 6.4bE-05 7. l. - 5A
v i
REVISION llA DECEMBER 1987 4
TABLE 7.1-3 MISCELLANEOUS DOSE ASSESSMENT FACTORS - INFANT AND CHILD l
PARAMETER AND VALUE BASIS
- i 330 liters /yr A
U
=
1 V
F Ua, U U
= 0 for infant' A
a, a
= 520, 26,.and 330~kg/yr for child A
l
)
R
= 1400 m /yr for infant A
a 3
= 3700 m /yr for child A
l l
r
= 1.0 (iodines)**; 0.2 (others)
B j
l t
= 48 hr (2 days)
B I
M
~
A
= 0.0021 hr B
w i
2 Y
= 0.7 kg/m B
v I
t
= 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> B
e 1
t 0 for pasture grass (milk pathway)
B l
h I
l
= 2160 hr (stored feed and milk pathway)
B l
i 1
f
= 1.0 May-October; 0.0 November-April C
l f
1 f
= 0.5 C
g f
= 1.0 May-October; 0.0 November-April C
a Wf 50 kg/ day D
=
l 175,200 hr (20 years)
E t.
=
D l
- Basis Codes:
A:
Reference 6.5, Table E-5.
B:
Re ference 6. 5.,
Table E-15.
C:
Typical for climate of Illinois and' vicinity.
D:
Reference 6.5, Table E-3.
E:
The parameter t is taken as the midpoint of plant operating life per Reference 6.5, Appendix C, Section 1).
- The r factor provides for the nondeposition on grass of the organic forms of iodine.
l l
7.1-17
REVISION 11A DECEMBER 1907
.)
1 TABLE 7.1-15 SECTOR CODE DEFINITIONS
\\
l SECTOR SECTOR CODE DIRECTION
- i l
A N
l
~B NNE l
+1 C
NE
]
D ENE l
E E
1 F
ESE l
G SE l
H SSE J
S
]
K
- SSW, J
L SW x
wSw N
W l
P WNW i
/
Q
'NN l
l R
NNW I
l l
l l
I l
l i
. See Table ?.1-8 for wind directicns in degrees corresponding
-to each sector.
I 1.1-3L
REVISION 11A DECEMBER 1987 ODCM LIST OF TABLES 1
NUMBER TITLE PAGE 2.3-1 Numerical Models for Computing Radiation Dose for Uranium Fuel Cycle Operations 2.3-13 3
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 CPR 190 5.3-2 5.4-1 Projected Dose At Nearest Community 5.4-2 l
Water System 7.1-1 Dose Commitment 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 I
7.1-E-10 Inhalation Dose Factors for Infants 7.1-6 7.1-E-11 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 -
i Adult
'7.1-15 l
7.1-3 Miscellaneous Dose Assessment Factors -
l Infants and Child 7.1-17 l
7.1-4 Stable Element Transfer Data 7.1-18 7.1-5 Atmospher'ic Stability Classes 7.1-19 7.1-6 Wind Sensor Treshold 7.1-20 f
7.1-7 Vertical Dispersion Parameters 7.1-21 7.1-8 Wind Speed and Wind Direction Classes 7.1-22 7.J-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 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-l Infinite Cloud of Noble Gases, 7.1-28 l
7.1-14 External Dose' Factors for Standing on Contaminated Ground 7.1-29 7.1-15 Sector Code Definitions 7.1-31 l
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 data for Dresden, Quad-Cities, La Salle, ? ion, Byron :. - d Braidwood Stations
v REVISION llA DECEMBER 1987
"(bone, liver, total body, thyroid, kidney, lung, and GI-LLI) a're computed from individual nuclide contributions in each of the sectors.
Searching over sector and organ, the largest organ dose is compared to the 10 CFR 50, Appendix I design objectives, To identify whether an adult or an infant is the critical I
receptor (the one receiving-the larger dose), this dose calculation is performed for both adults and infants at the following times after station startup:
(1) during the earliest 10 CFR 50, Appendix 1 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 converted to dose rates for comparison to the limits of 10 CFR 20.
For this purpose, the dose rate to the infant is considered limiting at three stations (Dresden, La Salle, and Quad Cities).
At Braidwood, Byron, and Zion, it is the child.
( 2 ')
Noble Gases Exposure to the beta and gamma radiations of the noble gases will result in a whole body and skin dose.
The maximum whole body and skin doses for each offsite sector are determined from the individual nuclide contributions 4
and the maximum dose values are compared to the 10 CFR 50, Appendix I design objectives.
This calculation is per formed monthly.
As necessary, the noble gas release rates are converted to dose rates for comparison to the limits of 13 CFR 20, i. C -;:
REVISION.IlA
. DECEMBER'1987 i
i Liquid Releases I
l For liquid releases it is assumed that liquid effluents' discharged into a river undergo mixing prior to consumption I
i l
l l
'l l
l I-l I
1.0-22
s T
C A e
g o^
e c
N L c
y y
c t
y E U e
yl yl y
e a
y f
U C N
ll ll l
N B
l i
Q L ha ha h
h t
A n
t u t u t
n h
t n
E R C e
nn nn n
e c
n e
F h
on on o
h a
o d
W MA MA M
W E
M i
o t
n n
o o
s i
n i
t t
o a
a i
l l
t u
u a
Y E
c c
B l
G C
l n
n n
l n
u a
o o
o a 2
o c
O N L I
t t
t p.
t s
l A
C i
i i C p
i O
a P l t
l l
l t
o l
C D
L e
a a
a e Al a
O a
u u
u a
,C u
n MiT R
c c
c R
0 c
o O E C
l l
l 2,
l i
)
M e
a a
a e
2 a
Z t
s
't C
C s
R C
l a
a F e d
u e
e e
e e
Cl e
n d r l
s s
s l
b s
a ae e
o o
o e
0a o
t R
D D
D R
1 T D
rf n
oa o
e r
t r 0
0 0
0 0
0 0
iy ne Y
R ah 2
5 5
5 2
2 5
l f t O T T
R R
R R
R R
R n
I A M F
F F
F F
F F
d ir L
I C
C C
C C C
C o
(
a U L o
e G
0 0
0 0
0 0
0 w
r y E
1 1
1 1
1 1
1 d
o R
i t r o
pa ed n
in cn w y
l e e o d
t rl d
L o
A N
C d
d d
B s
d a
a w A
I i
i i
u i,
l c o G
T o
o o
e o
o,
r
. a l
R I
r r
r l
n i rr e o
s cr b O
i r
yon t
n i y
y y
o e
R C
h h
h h
k a
h o
p a
t p r
T T
T W
S v
T B
e g i e
c re t
r e
o cc a s
7 eon w s
l h
g e
e e
L r
l r
e a
r t d n
A u
b u
r cs o n i e
f r a t
T s
a s
u i
NY o
t o
s ti o
a EA n
n p
n e
p o
i t d
f p l
MWI o
o x
o g
x p
ri e
u u NI i
i E i e
E x
cC t
yt c
OT t
t t
v e E
u l r r
RA a
a d
a c
d ed p ha i
I P l
l n
l y
u n
e r
r h a n
t t c
M a
a k
u a
k t
f d
u m
e h
e t u o ns l
o h
l a
a o o u
t s
t Q c o f
f h
h.
n r
i r
n i e
e r
r l
a i
a s
mg o E
I M
G I
M M
L
?
G P
W F
W d
s n
i n i di e
da ew t
l e mo i
R i, s rl s
O s
h e o ol o
T t
t n
cl d
f o p
I' n
d n
t o
t t
l rf m
E a
l a
l s
l l
ea
, e o
C f
i f
u l r u
u hS r
pd c
W nrh n
d l e d
d t
e e
oc I
A AP A
A a v sm n I
I
,l e
ir o
s w
o n, o nf n
s ion h
or o
e e
i e r
t p y
E d
t d D
, i as n
a D
l ssl l
e a
l e L
eec s
ur g
ur t
S C
nt u e
cD r
ca a 3
O U
i aN s
l l
N A.
O 1 dl a
at ar y
co l
our G
ca l
I C ice a
t k
A icih e
d c
ep e D
a se t t l
- e i r
e R
drO b
os t
e c w l
d e aa o
l d u i
HP&
N A
r r
d 0 s c o e
2i Sl m
t y
a e
it l
uc r
o E
ri f
r
)e, i m.
n S:
r d
C t.
r A
f o
i t
i i
e D
E *2 b
u 0 n l
0 a p
l f
i iq 1
a 1
c r
o t
c.
s k
A L
ie o
tih oh l
f i n Tt A
I
, I
REVISION llA i
DECEMBER 1987 V[
Gamma Whole Body Dose (mrad /yr per Constant, Vent Release pCi/sec)
The constant V multiplied by the attenuation i
i 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.)
G; Gamma Whole Body Dose (mrad /yr per Constant, Ground Level Release pCi/sec)
The constant G multiplied by the attenuation y
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 The skin dose to individuals in unrestricted areas due to noble gas released in gaseous effluents from each reactor shall be calculated when necessary by the following expression:
-8 g
1 (X/0)s ^'s + (X/Q)y A'
+
(X/Q) g. A 'gg 3.17 x 10 1.0 L
+
D
=
i 1y (0. 7) (1.11) (S Als + Yi iv + Ci ig)
(2.Sa)
A A
1 D
Skin Dose (mrem) g The dose to the skin due to beta and gamma l
emissions from noble gases.
1.0 Shielding Attenuation and Occupancy Factor The shielding attenuation and occupancy factor for protection against beta radiation.
2.1-9
i 1
i REVISION llA
)
DECEMBER 1987 j
I Cf Pasture Grass (pCi/kg)
Concentration The concentration of radionuclides'l i
in pasture grass (calculated using Equation 2.12 for C with fg = 1; other parameters, including f for use a
1 in Equation 2.15, are given in Tables 7.1-2 and 7.1-3).
8 C
Stored Feed (pCi/kg)
Concentration The concentration of radionuclides i in stored feed (calculated using Equation 2.12 for C with fg = 1; i
other parameters, including f f0f a
use in Equation 2.15, are given in Tables 7.1-2 and 7.1-3).
l l
W Feed Consumption (kg/ day) g The amount of feed consumed by the animal each day.
See Tables 7.1-2 and 7.1-3.
t Milk Transport Time (hr)
M The average time from the production of milk to its consumption.
See Tables 7.1-2 and 7.1-3.
l Cf Meat Concentration (pCi/kg)
The concentration of radionuclides i in meat.
e f
C}=Fp i
g exp (-
A C
W g g)
(2.16) t 2.1-18
4 REVISION llA a'
DECEMBER 1987 l
the dose rate to the infant from the inhalation pathway l
sha]1 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.
t f
l 1
i 4
i 2.1-2Ca l
l
r
~
L REVISION 11A DECEMBER 1987 I
{
(D/0) s See Table 7.2-6 or 7.2-9.
l,
(D/0)y See Table 7.2-6 or 7.2-9.
l (D/0)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
i (x/0)gA{g ija X/0)s ^'s + (x/0)y Ajy +
+
-8 x 10 p
DFA 3.17 x 10 a
i Cf+UfCf Cf + U Cf+U f
U f
+
s ija p
y 365 1
C
$15 mrem (2.17) 24 x 0.7 t
, DFGi r
i 2.1.2.1.3 Organ Dose Due to Inhalation, Food Pathways, and Ground Exposure, Projections 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{g, A{y, andA{g are taken as projected accumulative releases, adjusted to account for radiodecay in transit, during the period of projection.
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 other than 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
'"echnical Specifications of Dresden, La Salle and Quad Cities, l
2.1-20