ML20049J239
| ML20049J239 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/10/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20049J208 | List: |
| References | |
| EPIP-100-C3-01, EPIP-100-C3-1, NUDOCS 8203120294 | |
| Download: ML20049J239 (6) | |
Text
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EPIP h
100 - Station Group Director's Cuties l
t 100-1 Supervision of Emergencies, Drills and Exercises (Primary Responsibility - Station Director)
Bev.1 5/81 100-C1 Station Director - Checklist of Initial GSEP Responsibilities Bew 1 1 /81 100-C2 Operations Director - Checklist of Initial GSEP l
Responsibilities Rev.1 1 /81 f
100-C3 Technical Director - Checklist of Initial GSEP Responsibilities Rev. 2 2/82 l
100-C4 Maintenance Director - Checklist of Initial GSEP Responsibilities Rev.1 3/81 100-CS Stores tirector - Checklist of Initial GSEP Responsibilities Rev.1 7/81 l
100-C6 Administrative Director - Checklist of Initial GSEP Responsibilities Rev. 2 1 0/81 100-C7 Security Director - Checklist of Initial GSEP Responsibilities aer.1 1 /81
~100-C8 Rad / Chem Director - Checklist of Initial GSEP Responsibilities Rev.1 1 /81 100-C9 Emergency Reports Checklist (Primary Responsibility - Operations Director)
Bev.1 3/81 100-C10' Beoord Of GSEP Activitise Eer. O 1 /81 100411 Environs Director - Checklist of Initial GSEP Re y=4h414 ties Rev. O 7/81 i
I FEB 101982 1 8203120294 825305
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EPIP 100-C3 i
TECHNICAL DIRECTOR Revision 2 i
(Checklist of Initial GSEP Responsibilities)
February 1982 NOTE i
This checklist is provided solely for the convenience of the Technical Director.
It is not necessary to f
follow this checklist step by step.
Its completion is not required and l
its use is detennined by the Technical Director.
l I.
Commence long tenn assessment of the GSEP condition.
A.
Core Parameters (Time) l 1.
Reactor Power 2.
Reactor Water Level 3.
Reactor Pressure t
4.
Core Flow l
S.
Core dP 6.
Recire. Loop A Flow i
7.
Recirc. Loop A Temp.
8.
Recire. Loop B Flow i
9.
Recirc. Loop B Temp.
1 B.
Containment Parameters (Time)'
lf i
1.
Drywell Pressure 2.
Torus Pressure 3.
Torus Level 4.
Torus Temperature 5.
Containment Isol.
i 6.
Containment Activity
'j 7.
Containment Rad. Level-l I
i APPROVED FEi 10'82 1 of 5 0.0.S.R
l t
i l
EPIP 100-C3 Revision 2 i
C.
Estimate Containment Activity (Use Item 8.7. and attached Figure 1) 1 Emergency Core Cooling System and Inventory Make-Up /
0.
Capability 1.
High Pressure Coolant Injection
[
2.
Low Pressure Coolant Injection j
3.
Core Spray 4.
Automatic Depressurization System 5.
Isolation Condenser 6.
Feedwater/ Condensate System 7.
Standby Coolant Supply System f
8.
Diesel Generators E.
Release Rate Infonnation (Time) l[
1.
Coolant Activity 2.
Containment Activity 3.
Radiation Monitor Readings a.
b.
c.
d.
i e.
4.
Wind Speed l
t l
5.
Wind Direction r
6.
150 ft 35 ft Temp. Difference i
F.
Toxic Gas 1.
Type APPROVED 2 of 5 FB IOM o.o.s.a.
ll M
EPIP 100-C3 Revision 2 2.
Source 3.
Location 4.
Quantity 5.
Hazards G.
Fire, Explosion, etc.
1.
Location 2.
Safety Related Tech. Spec. Related or Reliability Related equipment involved.
H.
Other II. Identify critical data points and control parameters that the Operations Department should monitor.
III. Note assistance requested by the Operations Director.
.g e
e e g
t APPROVED 3 of 5 fB 1012 0.0.SR.
- - - - - + - -
-w-r-'-
V--
j EPIP 100-C3 Revision 2 l
i IV. Note assistance requested by the Rad./ Chem. Director.
l I
t I
V. Request emergency assistance as necessary from General Electric in j
accordance with the Emergency Support Program, j
VI. Identify special procedures needed to effect recovery.
L t
VII. Record subsequent GSEP-related activities on Record of GSEP Activities, EPIP 100-C10.
t i
I I
l i
6 l
l c
i E
f i
i f
I I
o APPROVED i
FB 10*82
.l 4 of s D.O.S.R.
r
\\
EPlP 100-C1 Rcvisics 2 FIGURE I CORE DAMAGE ASSISS E (DNPS.UNIIS 2 and 3) i I
l J
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l
' --- ) nx
- _ ;..;q :y'. f.--R.-g y
l r
w_w
- _:apw@w a cr wg= m+_,;=%; =__w; M_
=2;= :
rL ; h = =- w
?-_
\\
_g=---k_,;_=_ma #-
4 i
_,__-.=_--^=2 4..=.i+-- -: -:-_ _ _ :_._ =- ; _, ; -:
.T3 L- _; ;;.
2===
.y -
t g
n, x_ = __2__-1-n = =_ =- =- +W=E.+ +t=;=K==pa = _ i-a=_ _.id-:+= = E-
n
t
\\
b 8
/
~
C 2
i u
1r
- -L.--
..; :-e --, a q., ;r. T-7. E---g j
T.-
7
_x.,
g -
_ _y_,__,____.
- _... - g _ -; _,,_.: ;
y 3
g=_- z = y m __=_r= - e== 7 -==r==_-
=w m-
= = = - = = = -
[i s
.a c
g
=
L _ p: _ - _:ns _ '__.-
_ ; :: _: - - _ r= _
\\
e r-
'm_.__._
_ _ _ _.. aE y~
j M
3 s.u i
7
[
10;
- ({. k. -
- e.-
, t..: c. P 1 3 + g -;.2.~.2;i.-2 -5 g
a-7 q __.. _ _ _
- x.. r ;-
e
- m-=+7-we =m---w ea m 1 m_
,.e a
i 4.&
~
. _ _... f.
t
- _.. - - _ 88' - - *-_ _W M'
^
M-p]
-m.s
_ _sr x j at st.
[
a s s k = _= A-A -n5 & M h = n i e n =- a _=,=- W m I
i b
i 8
APPROVEDp.0 4
5 7..t35 1g x
+ s
- r 4 103
- * * *10 FB 10'82 Radiation I, aver in con +=$,---tatad/hr)
D.O.S.R.
3,,, g,,,,,,,,,,,
u,,,,,1,1,7 1,,,1, 1, e,,,,,,,,,
following releases in which the ratio of the "% noble gases re-leased frca the core" to the "% iodines released frca the cere" is equal to 4.
Curve @ represents estimated activity levels in the cent =4"=-a_t following releases in which the above mentioned ratio is equal to ena(1).
Specifically, the following ycints are plotted on the. curves.
Point 1 100% noble gases released, 25% of iodines released i
Point 2 10% nchie gases released, 10% of icdines released
{
Point 3 -
0.2% nchla-gases released,0.2% of icdines released Total coolant act.dvity(I + Noble gases) is 18 curies.
If air-borne is the cont =%mant, -Jie radiatica level would be 0.02 Rad /hr; icoo Tow-to pict en this graph.
l 5 of 5 (final) i
~
-,i
.