ML20053A263
| ML20053A263 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/11/1982 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20053A183 | List: |
| References | |
| EP-5-1, NUDOCS 8205250152 | |
| Download: ML20053A263 (10) | |
Text
q 5
EP-5-1 Fort Calhoun Station Unit No. 1
()
EMERGENCY PROCEDURE EP-5 Loss of Coolant Accident (PPLS Unblocked)
A.
PURPOSE To describe the operator action in the event of a Loss of Coolant Accident.
This procedure describes operator action in the event of a Loss of Coolant Accident with PPLS unblocked (normal operating condition).
NOTE 1:
If the loss of coolant is within the capacity of the available charging pumps, follow EP-28 (Reactor Coolant Leak).
NOTE 2:
If the loss of coolant is within the capacity of the available charging pumps, follow EP-28 (Reactor Coolant Leak).
NOTE 3:
If the offsite power low signal is received when a PPLS/
SIAS signal is in, the 4160V buses will load shed and resequence the safeguards loads or the diesels.
B.
SYMPTOMS 1.
Any one or more of the following alarms may be present a.
Pressurizer level low or low-low with no corresponding decrease in TAV.
NOTE:
This does not include transient drop in TAV due to plant trip.
b.
Containment sump level high.
c.
Containment high pressure and reactor trip.
d.
Containment isolation.
e.
Pressurizer low-low pressure followed by SIAS actuation.
f.
Thermal margin / low pressure channel trip.
g.
Containment and/or auxiliary building stack monitor alarms.
h.
Containment and/or auxiliary building area radiation monitor alarms.
i.
Containment high humidity.
j.
VCT decreasing.
g1 L1362 R17 5-11-82 8205250152 820517 PDR ADOCK 05000285 P
~~~
.. ~
EP-5-2 B.
SYMPTOMS (Continued)
..y 1.
k.
High temperature on pressurizer relief lines.
1.
Red indicating lights on PORV actuation supervisory circuit.
m.
High quench tank temperature and/or level.
n.
RC-141/PCV-102-1 and/or RC-142/PCV-102-2 alarms.
2.
Any one or more of the following indications may be present:
a.
Leakage exceeds the capacity of the Chemical and Volume Control System.
b.
Letdown flow goes to minimum.
NOTE:
Many of the above symptoms could result from an uncontrolled heat extraction or from a malfunction of the CVCS system.
Therefore, careful analysi.
is required in order to determine the cause of these alarms.
C.
IMMEDIATE ACTION
("?).
1.
Depress the manual reactor trip push button. Ensure that all regulating and shutdown CEA's have been fully inserted and that reactor power is decreasing.
2.
Ensure turbine has tripped and all stop and intercept valves closed.
3.
Ensure generator breaks have tripped.
4.
If Reactor Coolant pressure is equal to or less than 1600 psia and Containment pressure is greater than or equal to 5 psig coincidentally, actuate the engineered safeguards system, if not already actuated, using both Master Emergency Switches on AI-30A/B.
5.
Upon reactor trip and initiation of HPI, trip all operating reactor coolant pumps.
6.
Insure PORV's are closed and RC-141/PCV-102-1 and RC-142/PCV-102-2 alarms are not actuated; if not isolate via motor operated isolation.
7.
If component cooling pump discharge pressure is greater than 133 psig or the component cooling motor amps are less than 300 amps, restore component cooling water flow to the reactor coolant pumps by placing HCV-438A, 438B, 438C and 438D control switches in the " Pull to Override" position.
- q l
I R17 5-11-82 Nt%Y 111982
EP-5-3 D.
FOLLOW-UP ACTION 1.
Ensure containment isolation has taken place by verifying that containment isolation valves have gone to their accident positions.
2.
Ensure safety injection flow is being delivered to the reactor core by verifying high and low pressure safety injection header flows.
3.
Ensure containment spray flow exists and that the recirculation fans are in operation with CCW supplied to the coils.
CAUTION:
If the offsite power low signal is received when a PPLS/SIAS signal is in, the 4160V buses will load shed and resequence the safeguards loads or the diesels.
CAUTION:
Indicated water level relative to actual water level may be in error due to the effects of varying fluid pressure and flashing of reference leg to steam on the water level measurements.
Reference:
Technical Data Book - Steam Generator Level Correction Curves, III.3.a. through III.3.g.
4.
Start auxiliary feedwater pump (s) and feed steam generators via emergency feedwater nozzles as required to restore and maintain y
level.
NOTE:
'This step should be accomplished within 15 minutes of the accident and must be accomplished within 30 minutes.
5.
Implement the Emergency Plan. Refer to EPIP-OSC-1 for emergency classification and to EPIP-OSC-2 for the method of implementing the Emergency Plan.
6.
Monitor reactor coolant system parameters to verify natural circula-tion.
This circulation can be verified by the following:
i CAUTION:
Following a reactor trip and reactor coolant pump coastdown, will initially increase.
When natural circulation begins, H
T will still increase slightly, then peak.
As natural g
circulation flow rate becomes greater, T will decrease y
to a nominal T f r c rresponding decay heat.
H Core exit thermocouple temperatures are stable and at least a.
50*F below the saturation temperature for the existing RCS pressure as indicated on subcooled margin meters, b.
Core exit thermocouples and RCS hot leg temperatures reading approximately the same.
c.
At AT across the core of not greater than 50 F: yet representa-tive to the decay heat power level.
Immediately after a 100%
power trip it is anticipated to be <20 F.
R17 5-11-82 NtAY 111982 l
t
(
. ~,.,.
v~
EP-5-4 D.
FOLLOW-UP ACTION (Continued)
.,3ki CAUTION:
Indicated water level relative to actual water level may be in error due to the effects of varying fluid pressure and flashing of reference leg to steam on the water level measurements.
Reference:
Technical Data Book - Pressurizer Level Correction, (III.1.b. - III.I.e.) and Steam Generator Level Correction Curves, (III.3.a - III.3.g).
7.
Observe available indications to avoid a saturated steam / water system on the primary side.
This will eliminate voiding in the core area.
Use RCS hot leg temperature, RCS cold leg temperature, core exit thermocouples and primary system pressure to maintain the RCS at least 50 F below the saturation temperature for a given system pressure (see the attached saturation curve).
Other indications of system voiding are as follows:
a.
Increasing core AT; b.
erratic steam generator d/p;
'1 c.
erratic RCP motor current; and
~
d.
RCP vibration.
NOTE:
PRESSURIZER PRESSURE CONTROL USING HEATERS The pressurizer proportional heaters and one group (75 kw) from each bank of back-up heaters are available approximately 50 sec.
after 480 volt load shed has occurred.
To use any of the back-up heater g.oups the control switch must be placed in the reset position thei to the required operating position. This provides an additiona 300 kw heating power.
Use of heaters is limited by diesel genirator loading.
8.
When pressurizer level indication has returned to above the heater cutoff level, and pressurizer pressure is at a value corresponding to 50 F subcooling, terminate the emergency boration and proceed to EP-35 to terminate safety injection.
The emergency boration should be shut-down after 30 minutes to prevent boron stratification in the core.
9.
During the INJECTION PHASE Ensure balanced HPSI flow to each loop (HPSI maximum design flow a.
rate is 400 gpm/ pump).
When HPSI loop valves are throttled, the primary system pressure may be reduced.
Observe system pressure dur,ing valve repositioning in relation to maintaining system U
?
pressure above saturation pressure.
Centinued operation of the
.;f HPSI system should not present an overpressurization problem as k
long as the RCS temperature is greater than 360 F.
If the 100 F/hr cooldown rate curve is violated, RQS pressure shall be decreased NtAY l 11982 to bring the pressure within the cooldown curve limits.
J R17 5-11-82
.~.
EP-5-5 D.
FOLLOW-UP ACTION (Continued)
Da#
9.
b.
Ensure balanced LPSI flow to each loop (LPSI maximum design flow rate is 2600 gpm/ pump).
c.
Ensure balanced containment spray flow to each spray header (containment spray maximum design flow rate l
is 2600 gpm/ pump).
NOTE:
Spray flow may be terminated per EP-35 after containment pressure is less than 3 psig.
Continued spray flow may result in damage to reactor coolant pumps.
CAUTION:
Refer to Step 6 of FOLLOW-UP ACTION.
d.
Monitor charcoal filter temperature on the Containment Air Filtering and Cooling Units.
Douse the filters with containment spray water as required by opening HCV-864 and/or HCV-865 to prevent filter temperature exceeding 500*F.
NOTE:
When containment air temperature approaches normal, maintain charcoal temperature below 360*F to prevent re-release of contaminates already absorbed on the charcoal.
Yh e.
Ensure control room vill remain tenable by:
1 4
- checking all access doors closed.
1
- ensure that the control room ventilation system is in the filtered air makeup mode by.nlacing the mode switch on the protection if a positive pressure does not exist.
f.
Monitor both engineered safeguards pump room sumps for in-dicaton of excessive leakage.
Check local radiation levels before entering pump rooms.
1 l
g.
Ensure that the Recirculation Actuation Signal (RAS) triggers when the STLS trips on low SIRWT level.
10.
Just after "RECIRC. ACTUATION" Verify that HCV-383-3 and 4 have opened and that HCV-383-1 a.
and 2 have closed to maintain minimum SIRWT inventory.
b.
Verify that the LPSI pumps have stopped.
I NOTE: The low pressure safety injection pump (s) may be restarted by operation of override switches at AI-30A/B if increased safety injectlan flow is l
desired or when necessary to pressureize low pres-Y sure safety injection header to obtain RCS sample.
l R17 5-11-82 AfAY 111982 g,
EP-5-6 D.
FOLLOW-UP ACTON (Continued)
~
10.
c.
Ensure balanced HPSI flow to each loop.
NOTE:
If desired, cooled containment cump water may be diverted to the suction of the HPSI pumps from the shutdown cooling heat exchangers by opening HCV-349 and HCV-350.
d.
Ensure maximum achievable component cooling water flow to the shutdown cooling heat exchangers.
NOTE:
It may be necessary to reduce component cooling water flow to containment recirculation fans.
DO NOT secure CCW flow to the reactor coolant pumps (if in operation).
e.
Ensure that HCV-385 and HCV-386 have closed.
CAUTION: This secure pump mini-recirc capability (i.e.
dead head protection) is eliminated.
f.
Ensure balanced containment spray flow.
g.
Check shut LCV-218-3 (SIRWT to charging pumps suction valve) to ensure minimum SIRWT inventory is maintained.
NOTE:
Shutdown boric acid pumps and charging pumps when concentrated boric acid tank inventory has been exhausted.
h.
Monitor both engineered safeguards pump room sumps for indication of excessive leakage.
Check local radiation levels before entering room.
i.
Once containment pressure has been reduced to below 3 psig, the containment spray system can be utilized to augment safety injection flow to the core if desired.
Refer to EP-35 prior to resetting any pumps or repositioning any valves.
l l
NOTE 1:
Access to manual valves SI-173 a.nd 174 will be re-l quired to align discharge of shutdown cooling heat l
exchangers to LPSI header via HCV-341.
Check l
local radiation levels before entering room.
NOTE 2:
Do not dead head containment spray pumps during this transfer.
j.
General Note:
(1)
If a LPSI pump is manually started l
(control switch in red flag) the load shed for that motor is disabled.
j
?!
1b
(
E..
R17 5-11-82 NiAY 111982
.~
EP-5-7 D.
FOLLOW-UP ACTION (Continued) swv
~~
10.
k.
Obtain a Reactor Coolant System sample when radiation levels permit and analyze for boron concentration.
Repeat every hour until boron concentration is stable and then once per shift.
(See NOTES on the following page)
NOTE 1:
This analysis will show the rate at which the containment sump suction concentration is de-creasing after concentrated boric acid tanks are empty. This could be an indication of boron precipitation in the core.
NOTE 2:
To obtain this sample it will be necessary to initiate flow through the LPSI header by re-starting a LPSI pump. A pressurized sample can then be obtained in the primary sample room.
1.
If required monitor containment hydrogen concentration with containment hydrogen analyzers VA-81A and VA-81B per OI-VA-6-2-1.
11.
During LONG TERM COOLING PHASE
{}
Procedure to flush and align ECCS to accomplish Reactor Coolant System hot leg suction and simultaneous hot and cold leg injec-tion utilizing pressurizer auxiliary spray is provided in EP-5B.
12.
To reset or shutdown any safeguards equipment, refer to EP-35.
- l l
! )
0'
- yi R17 5-11-82 E
(h f
l k1AY 1 l 1982
.a EP-5-8 E.
DISCUSSION
($h The major objective for a loss of coolant accident is to minimize the release of radioactivity to the environment.
To achieve this it is important to:
1.
Ensure the contaimnent is properly isolated. This ensures that any radioactivity which has been released to the containment structure will not be released to the environment.
2.
Ensure cooling water is being supplied to the reactor core.
Adequate cooling water delivered to the reactor core will prevent further degradation of the fuel and prevent the release of more fission product radioactivity to the con-tainment structure.
3.
Ensure that containment spray flow exists and that the recir-i culation fan coolers are in operation with an adequate supply of cooling water.
This will ensure that the containment structure wll be depressurized.
If there is leakage from the containment, depressurization will reduce the amount of radio-activity release to the environment.
4 Ensure the steam generators are available to remove decay heat.
In the case of a small break, extensive core damage can result if auxiliary feedwater flow to both steam generators is not established within 30 minutes.
(p NOTE:
Main feedwater flow is automatically terminated by CIAS.
5.
Th+: automatic response of the Emergency Core Cooling System (ECCS) is considered to be questionable for long term core cooling for large Reactor Coolant System (RCS) cold leg breaks.
Large RCS cold leg breaks present a potential problem because core cooling is accomplished by continuous boil-off, a condition which eventually could cause the buildup of solids in the reactor vessel.
For hot leg breaks, ECCS flow delivered to the cold leg nozzles will travel down the annulus, through the core, and out the break.
This establishes a flushing path through the reactor vessel, precluding the accumulation of solids in the core region.
However, for cold leg breaks the core consumes only enough in-jected fluids to match decay heat by boil-off; the excess in-jectiion flow spills out the break. Therefore, while the ECCS M~ ' <
provides sufficient injection flow to the core for residual heat removal, the ECCS may not provide adequate flow through the core.
The objective for long term cooling is to establish flow through N
the core and ultimately achieve a sub-cooled core, independent of break size and break location.
Interim realignment procedures will be provided later which utilize existing hardware and exten-sive operator action to:
7.]
R17 5-11-82 MAY 1-1 1982
- - ~ ::
- - ~ - -
EP-5-9 DISCUSSION (Continued)
E.
~.
5.
(Continued) i a.
Transfer ECCS pump suction back to SIRWT for a brief period of time to purge radioactive fluid to reduce operator exposure and to flush pumps with clean water.
NOTE:
This will require overriding motor operated valves HCV-383-1, 2, 3 and 4.
b.
Utilize a back-up hot leg injection scheme by utilizing the charging system.
Flow path would be from the high pressure safety injection pumps; through the charging pump to the high pressure safety injection pump cross-connect (check valve SI-163 internals have been removed);
into the charging header; through the auxiliary pres-surizer spray valve HCV-240; into the pressurizer; and down the pressurizer surge line into the RCS hot Icg.
It is anticipated that such a POST-LOCA realignment would not be necessary until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident under the most adverse conditions.
1 Reference EP-5B for long term cooling alignment.
i l
l
~
R17 5-11-82 1 982 At4Y 1 1
.- T : = -
- r ::-
EP 10 9
Miii=Is M1".':M.-E ~;GE"2:=i =f9=#f # T 1 =E== M is?"=i P ?_ 6:3 "i=M==Erf==irF 7 h@ 4 f'~ ~=. ~I:__b._~~_2 ~ ~. zr -. *^'~ ~~ ~1 - * -.i =.=n== =.-* : m?: ^5b.k
_g_
- i= 5 "'~
_ -. =- i ~~$-
- - r'= ^ = 5 =._ _ h n_..__.
~
t
=~
^
=.
r g_
_y
, ~ - '...
I~
--jc; r -
._..._2m=------..
.._a__
.=_--___1_...
__ __... _ _. _ _ _ __.....___.._.;:=- _.---1 t.= =:. = - t :
=:-
_z: --
c- :-_ t = =_ =;. =..y_u =__= t==_ _ ;. _..~. g - r = t :. :_:.. u_:.u :. =-
. o.=_,.==:3, (a._<-}
t - : -- = [.;=__~ r. }._.=_=.
_.. }=_ _ _=... _._.=._ =. r : _
. *.._ _ r :r 1_
. _.. =_
=. : - = ~ _ __ _ _ i _. :nr : : __
y._,
n =_= =_= y s = ;= = _ s = =t,. _.~ = = =~-_.-. _ _ _=== c ;. i_ r-- -J.
.. _ _.j=_.====== ar 21 :
- c=j 4.___.._....__.___...
.. _. _..__. =i. =
L
._...~~__;.
- t. := =r_ = 4 = = r- - -?._
7_..c - ;=:: r 7 - 7 _. _= 2
~ :- :- - -- 1,;== =~,..
L=-
n __
~
=._._:==t._.
_ _ t-
-- t = =:- _ - t =
.t= =
=-=~~t t
J L--4
. =.-- : t =. _ _g - : =._ _=___.- - - - - - - -
- _- l.=:
- -,=...._ _ _i.
_;=._=__f._._.__._________I._._,._
.-t r
.=r=__
_ _ _ _ _ = _ _ _.
.;_ ; _ _. _. y _ _ _
__. __ _..._...._ _= =__..-:-.==r_.-._--=____..__._.__t--=---=-l,_v____,,
+
c = _ n_...st = t _ _ _.___ _ - =a=. _ _ _.
_.,..;-_.___,__;=~,=__-=_;=._~_:_.._-;__._3_=.__._..q_
u
._=_=_,:_=:==__=._\\w._._1=._..=__=..a_.._t---..-.= _.=_=__ _._.._ _=.
i m
=
====.i=_.--.--= - =7
._z _ -_ :...... g. _ _ -
F._._. ~._.--.54
=t-
= ---- : t- = t-~.
_.g.
t-- ~
-t-- 2:=g;_._=Ek_ __ _-,._ _ _.. _. _
_.y.___.,_.
_a_._. _ t.__ =_._.j=u_j. - _.i __ __.
=g g. _.__ - g 5.. =.;,,
._ _ _n=_ ; r
-- : =.
r_____
t g._ __.. - - -- - - =_p;=. _=_ _;_=.3. =.__j.._ __ __. _= =.c g - _-- t=_ _ - __.
_=.e_-
4__
___g
_a__.__..
,__x______-- - -
_;_;.;.;p=;u;-_==_.. =; v_,;_ _
_=.
_.7_-.
~ _t
- _,- _-_.-._-.=-- -
r-
==r--a-
._.=--:==t==.
- =-,-==_a=.
y-- -;;-.
- w F=_____,.____.__.B
-t-
+ _. _ _ _. _ _ _. _
_ _. =_._.__t_.__
. _.._1
- =q=
$1;;=; g _ __ _ _ ___ g-t-- ---t - = r t _.. _ _
-_....._-+._._._t:-c_.-__. _4 r = ~--~..
t----L
. r rr
. =._
===,=___..:=___s=__- ;=.: __:1 = =.
_ _. _._; =p- _-
._: =.
x.:. ~
- _ _== -- -
- ===,. t =.:= = :; - -
.r== _
- - = =
=u=--
<=-
==:-- - -
r-== :==_.
e.
--_=..=-_x_===- :4==_~l an p_=-_.__..+,_=_=-_=,__,_-__-_;._.___p=t--
~_
+
c
_r_----
m
-z__,_-_7
-- +
p....
.- _..g; n______-
me
_ _. _ = -,. _ _. = -
... = s o
- u. _.__,:
.._._..m__
_..-=-t-:___r=...___-f_.___,_._..,_._..._i._.a==r=_=_._ ;..=_ =_-l c_
v
[=- _- M.. _. _g _=_: = t_.__ - _. _ ;__7 _.. _ ;; _;_. __;_
=
w
>__.__c
-+
m.;.g._.._..___._..___._=4==r=7_ =.= d.
e....,
.. y _ m..
-=====
__t
- - - = =
==:--------at-==_;t___a____-_m..=.-+---
.._.:=-._.
x3
~== _=s =.:==:.== a
- .n_=
,==_1=-.==.-------=_=z=:_=_.=_.--.___...----:=--===-=
=. - -
==n==.===-:=..
..=e__=._._==__._==...._..__-..
=-
. _ _ r._=:__.....c._ =..._- L=._
_. m
..: = _=._..._ _.r. _ _ _ a _ -- - t_==_ _ 2____.___.3,_= _ _ :.....___ __.. _ _ _ __. _ _._ _ _ _.. _ _ ______.___.;_
._=_.1 g=..___..,
2
>= E : +7J T: = s!= =,.__..____._._-__.__D_....I = E:Eiz. i:. -
1----i
m. -- -- - = --r _--- ='---,-
a='=
--i:... _ _ 1 =12 =--
= - -
0 E.
- c. :_ _- _.r =_= _ ; =. _g=_=..g=_4.. =_ ___= =__ ;.=__ =.._x;_. y _- =_ c-.=.= rg__. s. = ___. f. =. _ = _=__=__5_=
= =..._. _- _- -- __-.g..... _.=g!
a
-y
- ;.n.
n
_____._.___..._-_-_-_-____-].
- g...._
- ;,-., ;- -- -- - g -- _
.__.,,_4__,_-t--g_
-._c_
__a____,.___._________
g..._
___u__m._.___._..;_.=_,
m __., 7 p_._
_ =. _. _ ;__3_.._
_._.__7.__._{._ _ _. _
5_.. _. + _ _. _ _ _ _ _ _. _ _ _.. _.. -.. _.._ = rt = = t :- -- _.1.-
M
______p = --~.== _._ ___t = t t___..-.__
b
=. J M
.__..R.__7_._._.__.+'1'%=;..--="t---.i__.....*.%---
=.=.
m
-.=r_=.-==-----
p _.,,
__.. _ _. _ - ~ ~ - *. _ _.
2:- -* '**:
t
._..._______a_:.** *- :-'* '
_ p p
c____.
. ;;=-- - g
--,_..;--_g;----;__.
t___..
=; - - - - - ;
- ._,,..;g.4
:.-=t__....p----
f-=;
r
[_==; g- ---
_.=n._.._.g.__=t==l_.___._.4__..{===:---___._.2__
r := a = =_-
y u.____
= = r_j
- 5
. = =.
- ==.=. _ r_. _ _ ;_ _ __- -! -; _ __=
- r - m =__=_. :._=_=._=__=. __==_ _;_.- _ - r=== r_ =_ g.=. =_ =_.__ _ ___
____t__
,=r.cr---
3 3
__ __.::=*;
___.._c
.--7 p
w s =- i._ _;_= -.__=_== - - - c_- - - - : =- r--: -
3.=:= _===c =: c,.
r=
=
:___._
( _ _ _==_ ______=-=== r== := :=y===-
=t
--=~------.=-__.:=._=.._:.;___;_..-=.l__+_..____.._=_.=:--=.__2=_=.2...._
r___._
- - - - - - =,
t= = :
t t.---
-a___=-.._.;;==---___._=..;-=__==c:...
. = =.;
- .. :=.
1-
~
.=. = = _ m r.
^
.____.t._._..._.__g-.;._______..__y___..n._._r_. _y_._--_-__-,_-._,___-_i..__---.,-_
_---a..
r _.-
g.;_.._..__....____.
_y j
gI h_=.. _.. _ _ _ _.. g = =_ a r = -- 1,==4 r-.. t===i=ri-- i=;:_=. + - _. 1 "_=-N__ _ __ _ _ _.,.._. _. _. ___ _..__ _....
= r= n
=_,
r---- - =.= M===7=== E i!
'=_=......_.._.__..__.._.{=.==.t.=__=.=_.F.=_K_____..=__=.._._._-_.t.-.....2......
-4
=r--_-_..-.=.F...t._._..,......_._._..L._._:=.==1.==..=._=._.p_=_=-
.::. =.. 1,
. _: =.. _=_-
2
_ _=_t- = - -.... ____.=_._=_:_=.
+
3 y
=- :. :::::..: =. =~::L..:=.=~*
= :: = =_f:=:=- g:===;;==:,====== r =-._. _ {=-% __ :
.. _ - - r===:=.:; :~:.. :::p= = = : =._ e-. ~;=..
---r-<
- z
- r. =:. tr - ~~
t===.=._.
- =-
a
.____w___=
- _.__...u=--=.._.._-
I:- 4' :.=i :" 7 G n - = -i j n
4
[~2 -- --- = E Ei :--. ===_ =- - += =_C=_is,r -- -
--E==_==a==f.=._-_._-.__.......
n g
_ %. p_
..=t---=1---
_,,. a g:___.__. _=r:=-r= =-~_.==:-- t:- : = n-
__....._g= -= _y ;;;.
- =._ _
- - =.
. = L ~== n ~=
- =:
_y
. _.=.... 3.. g., ;.t. a
_ __ _. _4=a_ _ _=p_-
r==.. =._.=_=_.=g=__=.y_g.;g__;__._7.... -.j __...
_a
= ;;; =__ _ __ _;=_= =:===.;-= = r - =- -
a q
= =_.l
_=
= t =-
t _ __ _m
,m._s F=__= =__ t =-- a. _. _.=._.=_.r_..._ __ _ ;_ _=_ 7. _y== =i.=
=. _ = -- =,. r
=r= =f=. ____w
_-r--
+__
1: =
- :-t=
=.
g
---a g:------ - t===, = =_: = r. u. {==== =_ = _;
t__.
._ ___. A=.= r=._ t =-
r=== =-=r-t
= _. _ _=_,
= r.
4
_ _. _ _ _, _ = =,-._
v
_. _:=:: _
^
,.. _ _ =
g
~~
-_z
..___.__3_____....._.,..
I..._.~~'__==3'=.g.
._.!==._..-'
. __ ~ h--- _...T-Af= -*- "-~r-- i _ :-L... =: ~ =~~t -$ '
53=~?N O- =i
===:== = :=.==;==- -._.
.__=;=:==_\\:,_ _ _ __.= __..-. _.. _g _=. __.;== r g=._=__= ~.. ;.; _g. __y =._ _4 p-- - -.
.__ _.m._._
._._-.. = =.: -==_= = _:=2 v = =_.,. - := = - :====T=====.. = f==_=. =_, ___=_ _==: =-,:=. _=::-x
--- - =.
- _ -- __. :: = ---r=
= --
I
~
t-----==----=
=
- x--t:
.-- =s r_===r = :.= i r_== - - =:== =_ x.===1_., _._. -. __ l = =. _=_. _= =1.. _. h. _. _ _r =
=u _ = =. i_ : _=... =.
=:;
e r - - t== r _ = =r === -t==:== 2==- = :==.
=
r=;==t=n-=r
..c=r
- = _.
1
=
==rc.=:
=- 5:.. : =,===:
r==- _ ;_ =:: = : : t =---. _.. :==== : _===; r===r=== t - =r: : = = = - t =-- - --.. =
1 :== x..
t== - = :== +- :== = --E
= :. === u = = 1==-
~.:.,.
, = =- =.=. _ u = _ = = =4
= n::= =_,m
_. _ =.=. = _-d=n-u = - :.r,N-... r = -- = ;= = =. 3. _== =. = r = - ~
: -l
- ---- = :-== -
r-
=t==.
. = ::::==-
-=.
'= I = M N M ;!4 M :=rEi_rii-~:~4 'E B"E""F-~2TC~+ =f=i E:;"M* W " " 5 "'M 5 E""'rF i -i="F=
m p===
- = e - - - -- --- L = =7- - -
t= - - : _-- _ : = :==;.== =g=: : :- = _2--- - -. : -
,=.=:_=== _
n _,
==2
......:==_r:=:__.
====. _ :. ;=== _::n - - --
--t ws ;gE5i=
=y= :===_hi:= =.-i=_iE ~i===H.=~:i=i:_Er=:i:.; ir.X=li ?. _.r=.=5-in :+- % - ^
f-
!f ~~~~jr== !~~._-~ 9_= ;=$=_'. =I- -_ Inh =~_Mr~=b=== h = =l~ -~. 3 -5'.'. N=:5[= f$i F -
(TN=M
- :_3==_.w==-=5_===:=e: =_=.3,,==. %., =. =...w=.z.:_'.
.5:...._ :;. :- y=
=..p
=1
^
- >==_ r. : := =,
4==. -
_ =
r-
- w= =u, e - :
. : t... -.
.g g # = r w = # = % =
_4_ = 3 _
M"*.:J R17 5-11-82
. r..m.-.A. AL. ( o.:,
s
.. ~.
. _.,