ML20059M780
| ML20059M780 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/15/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059M774 | List: |
| References | |
| NUDOCS 9311190315 | |
| Download: ML20059M780 (16) | |
Text
_ - - _ - _
_(( )
'o, UNITED STATES NUCLEAR REGULATORY COMMISSION g
3
.E WASHINGTON, D. C. 20555
\\..../
l.
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the l
licensee) dated April 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, ti.s license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No, DPR-39 is hereby amended to read as follows:
9311190315 931115 PDR ADOCK 05000295 p
w
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B,-as revised throuch Amendment No.
150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and is to be implemented within 30 days of the date of its issuance.
FOR TH7 NUCLEAR REGULATORY COMMISSION
+ %24. f.
W James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 15, 1993 e
I i
l
.1
L
>3 RICg,
'o UNITED STATES
-[ " '
~,,
NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D. C. 20$55
- e j COMMONWEALTH EDISON COMPANY QOCKET NO. 50-30_4 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENS_E Amendment No. 138 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated April 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the rmvisions of the Act, and the rules and regulations of the C omission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this ar~ ndment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this ar.dment is in accordance with 10 CFR Part 51 of the Commissiun's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
~
1 t '
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 138, are hereby incorporated in the license. The licensee shall operate the facility in accordance with l
the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and is to be implemented within 30 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
f.hw James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 15, 1993 i
i J
9
t ATTACHMENT TO LICENSE AMENDMENTS t
AMENDMENT NO.150 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO.138 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS, 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 10a 10a 10b 10b 10c 10c 10d 10d 22 22 32 32 130a 130a 131b 131b 135 135 136 136 144 144 l
i i
L NOTE 1: Overtemperature ai (sheet 1 of 2)
(1 + T4ST (1 + tjST f
3 ai
! 1 AT Kj - K2 T - T' l +K3 (P - P') - fj (61) o (1 + tS )
kl + T2SJ k
/
S Where:
1 + T45 = lead-lag compensator on measured AT 1 + 155 t4, 15
- Time constants utilized in the lead-lag controller for AT, 14 = 8 seconds, t5 - 3 seconds
- Indicated AT at RATED THERMAL POWER ATO Ki
- 1.36 K
- 0.0180/*F 2
1 + t;S
- The function generated by the lead-lag controller for T dynamic compensation avg 1 + t25 ti, x2
- Time constants utilized in the lead-lag controller for Tavg T1 - 33 seconds, T2 - 4 seconds T
= Average temperature, "F 10a Amendment Nos. 150 and 138
NOTE 1: Overtemperature 87 (sheet 2 of 2)
T'
- 1 562.2'F (Nominal T at RATED THERMAL P0HER) avg K
- 0.000935 3
P
= Pressurizer pressure, psig P'
- 2235 psig (Nominal RCS operating pressure)
S
= Laplace transform operator, S-1 and f (aI) is a function of the indicated difference between top and bottom detectors of the power range i
nuclear ton chamber; with gains to be selected based on measured instrument response during plant startup tests such that:
(1) for qt - gb between -50 percent and +8.0 percent f,(aI) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL P0HER in percent of RATED THERMAL POWER).
(11) for each percent that the magnitude of (qt - gb) exceeds -50 percent, the AT trip setpoint shall be automatically reduced by 0.0 percent of its value at RATED THERMAL POWER.
(111) for each percent that the magnitude of (qt - qb) exceeds +8.0 percent, the AT trip setpoint shall be automatically reduced by 1.66 percent of its value at RATED THERMAL POWER.
10b Amendment Nos. 150 and 138
~ n. u.
NOTE 2: Overpower AT (sheet 1 of 2) fl + t ST f1 5 Y
r 3
3 AT
.s aT K, - K, T - K.
l T - T"
- f (AI) o 3
(1 + t,5)
(1 + T 5)
(
)
3 Where:
1+TS4 lead-lag compensator on measured AT
=
1+tSs I
- Time constants utilized in the lead-lag controller for AT, t4 - 8 seconds, 23 - 3 seconds.
T4, x3 i
Indicated AT at RATED THERMAL POWER AT
=
O 1.C9 K
=
4 K
0.020/-F for increasing average temperature and 0 for decreasing average temperature
=
3 f
Tb 3
The function generated by the lead-lag controller for T dynamic compensation
=
avg I+T53 y
Tine constants utilized in the lead-lag controller for Tavg' T3 = 10 seconds.
1 3
10c Amendment Nos. 150 and 138
. ~.. _
NOTE 2: Overpower AT (sheet 2 of 2)
K
= 0.002117/*F for T>T" and K6 - O for T.<T" 6
T
= Average temperature, *F T"
= Indicated T at RATED THERMAL POWER (calibration temperature for AT instrumentation, 1 562.2*F) avg S
- Laplace transform operator, S-f (AI)
= 0 for all AI 2
t i
l 10d Amendment Nos. 150 and 138
..~m
.i,.._,......_;...
indicated by difference between top and bottom The overpower AT reactor trip prevents power power range nuclear detectors, the reactor trip density anywhere in a core from exceeding 118% of limit is automatically reduced. (6) design power density, as described in Sactions 7.2.3 and 14.1.2 of the FSAR and includes corrections for axial power distribution, change in density and heat capacity of water with temperature, and dynamic compensation for piping delays from a core to the loop temperature detectors.
The overtemperature AT and overpower AT reactor trip functions include lag compensation on measured AT and measured T constants have been accounke0.
These lag time for in the safety analysis and provide allowance for RTD response characteristics.
The low flow reactor trip protects core against DNB in the event of a loss of one or two reactor coolant pumps.
The undervoltage reactor trip protects a core against DNB in the event of a loss of two or more reactor coolant pumps. (7)
The low frequency reactor coolant pump trip also protects against a decrease in flow by tripping a reactor before the low flow trip power is reached.
(3)
FSAR Section 14.1.2 (6) FSAR Section 7.2.2-(7)
FSAR Section 14.1.6 22 Amendment Nos 150 and 138
ELEM1131ES SETPOINT P-6 10-10,,,,N P-7 10% Rated Neutron Flux and Pressure Equivalent to 10% of Rated Turbine load P-8 28% of Rated Power (4 loops) for Unit 1 at startup f rom refueling outage 21R12 and Unit 2 at startup from refueling outage Z2R12.*+
60% of Rated Power (4 loops) for Unit 2 until startup from refuel'ng outage Z2R12. p
- P-10 10% of Rated Neutron Flux"
+ If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the Cold Shutduwn condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
+4 Setpoints are i established tolerances for instrument channel and setpoint errors as specified in " Zion NS$$ Setpoint Evaluation.
Protection System Channels, Eagle 21 Version", Revision 1, April 1992 for Westinghouse source range and intermediate range neutron flux channels. For channels other than the Westinghouse source and intermadiate rance neutron flux channels, setpoints are established tolerances for instrument channel and setpoint errors as specified in " Zion NSSS Setpoint Evaluation, Protection System Channels, Eagle 21 Version", Revision 2 March 1993. The instruments shall not be set to exceed a Limiting Safety System Setting.
+++ For channel test, calibration or maintenance, the minimum number of OPERABLE channels may be reduced by one but to not less than one, and the minimum degree of redundancy may be reduced by one but to not less than zero, for a maximum of two hours. For Automatic Reactor Trip Logic and Reactor Trip Breakers, the allowable outage time is a maximum of eight hours.
When block conditions exist, maintain normal operation.
' Maintain Hot Shutdown' means maintain or proceed to Hot Shutdown within four hours if the unacceptable condition arises during power operation.
Verify shutdown margin isinediately and comply with Section 3.2.1.A B.
When blocked conditions exist, maintain normal operation.
- During Modes 3, 4 or 5 and with the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal, the following applies: With the number of OPERABLE channels one less than the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERADLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
N Ouring Modes 1 or 2 with one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and maintain or proceed to Hot Shutdown within four hours if the unacceptable condition arises during power operation. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance and testing to restore the breaker to OPERABLE status, MS Setpoints are e established tolerances for instrument channel and setpoint errors as specified in " Channel Accuracles Overall Channel Accuracles and Setpoint Tolerances for W NES Process I and C Reactor Protection and Control Systems" August 30, 1971 - CEW-652. The instruments shall not be set to exceed a Limiting Safety System Setting.
TABLE 3.1-1 (Continued)
Reactor Protection System - Limiting Operation Conditions and Setpoints 32 Amendment Mos. 150 and 138
1.
2.
3.
4 5.
6.
Actuation Channel No. of Minimum Minimum Operator Action
- Distription (Per Unit)
No. of Channels Operable Degree of if Column 3 or 4 Qanngela La Tri p..
Channels +++
Redundanev+++
cannot be met +
$_e.1P_03.nh V.
Auxil l ary Fegdwater 1.
Manual 1/ pump 1/ pump 1/ pump 0
Maintain Hot Shutdown"*
N.A.
2.
Automatic 2
1 2
1 Maintain Hot Shutdown"*
N.A.
3.
Steam Generator '(5/G)
Water Level low-low -
I.
Start Motor 3 per S/G 2 per S/G 2 per S/G 1 per S/G Maintain Hot Shutdown"*
10% Narrow Driven Pumps any.1/4 5/G Range *+
- II.' Start Turbine 3 per 5/G 2 per 5/G 2 per S/G 1 per S/G Maintain Hot Shutdown ***
10% Narrow Driven Pumps any 2/4 5/G Range ++
4.
Undervoltage-RCP 4-1/ bus 2
3 1
Maintain Hot Shutdown"*
75% RCP, Bus busses Start Turbine Voltage Drivea Pump 5.
5.1. Start Motor and Turbine Driven Pumps 2
1 2.
1 Maintain Hot Shutdown"*
N.A.
6.
Station Blackout 3-1/ bus 2
.2 1
Maintain Hot Shutdown **'*
Time Start Motor and Turbine Dependent Driven Pump on Voltage
- 7.
Secondary Undervoltage 2/ bus 2
2 0
N.A.
3846 2% volts for 5 5% min.
with inherent time delay of 8 12 sec.*
VI.
Siggm__Generalgr Qverfill Protection 1.
Steam Generator (5/G)
Water Level Hi-Hi 3 per S/G 2 Per S/G 2 Per 5/G 1 Per S/G Maintain Hot Shutdown"*
70% Narrow Range.+
SEE F00fNOTES ON PAGE 131b.
ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING CONDITIONS F0E OPERATION AND SETPOINTS Table 3.4-1 (Continued) 130a Amendment Nos.150 and 138
p If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the COLD SHUTDOWN condition within an
+
additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Setpoints are established tolerances for instrument channel and setpoint errors as specified'in " Zion NSSS
++
Setpoint Evaluation, Protection System Channels, Eagle 21 Version", Revision 2, March 1993.
The instruments shall not be set to exceed a Limiting Safety System Setting.
This channel may be placed in the bypass mode during periods of active testing during safeguards equipment
+++
testing as specified in Section 4.4.2.
Setpoints are i established tolerances for instrument channel and setpoint errors as specified in " Channel Accuracles, Overall Channel Accuracles and Setpoint Tolerarices for H NES Process I and C Reactor Protection and Control Systems" August 30, 1971 - CEH-2652.
The instruments shall not be set to exceed a Limiting Safety System Setting.
Requires simultaneous. actuation of two switches.
' Maintain Hot Shutdown' means maintain or be in HOT SHUTDOWN within four hours if the unacceptable condition arises during power operation.
ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING CONDITIONS FOR OPERATION AND SETPOINTS (Footnotes to Table)
TABLE 3.4-1 (Continued) 131b Amendment Nos. ~ 150 and 138-
ACTUATION CHANNEL CHANNEL CHANNEL GLARNELDJSCRIPTION
_Q1EG_
CALJBRATISN FUNCTIONAL TEST IV.
SIEARLUiE_Il0_1.ATLQN A
1.
Manual Actuation N.A.
N.A.
R 2.
Automatic Actuation N.A.
N.A.
M 3.
High-High Containment Pressure See Item II Above 4.
High Steam Line Flow in Coincidence with Low-Low Tavg or Low Steam Pressure See Item I Above V.
AtJ1LLIARY FEEDWATER 1.
Manual N.A.
N.A.
R 2.
Automatic N.A.
N.A.
M 3.
R Q
Hater Level Low-Low 4.
Undervoltage - RCP Busses N.A.
R R
5.
Safety Injection See Item I on Page 134 6.
Station Blackout N.A.
R R
7.
Secondary Undervoltage M
R R
ENGINEERED SAFEGUARDS SYSTEM TESTING AND CALIBRATION REQUIREMENTS-TABLE 4.4 (Continued)'
135 Amendment Nos. 150 and 138
ACTUATION CHANNEL CHANNEL CHANNEL CHANNELDlSCRI1_T10E
_CliEEK_
CetLIEBA_lLQN f_UNCJT10NAL TESI VI.
SIEAH__GENLR_AIOR RVERFILL PRQTlCJTLQN
~
1.
Steam Generator (S/G) Hater S
R Q
Level Hi-H1 PEBlilSSIXES 1.
P-11 N.A.
N.A.
Q 2.
P-12 N.A.
N.A.
Q ENGINEERED SAFEGUARDS SYSTEM TESTING AND CALIBRATION REQUIREMENTS TABLE 4.4 (Continued) 136 Amendment Nos. 150 and 138
e g
t r
p h
n u p
)
e i
t i
h e
oi d
3 s z
r nt i
o et ie r
( i i
t n
r a
. o h
r t
ni it f
o a i e m n
ic i
w n
f t d
.k e u ah s s
l e
s ei d
o a c s e e a h R et s r
e n n e
a s e
t h b wA r e
uf c n i n
l n
s p e st S b
,r t oi a gl ai s e s r y e
l F e p a
vh y i e v el a sh h e
e v e s e c a s n ol m n s
t t v n gl w f
sd r
e n m e o u t s ni y
e o r a o yl c a s.
d a e n c n ip o w n c l i a vl o
t p h r n e m i
i a Z l h
n e c ab e io r t t h r a
y m t
igt t o r
sh t
pt a nt u e at o e e f h o ni a r s c c s t
u ei c t h e r o a i y e et t w c at rf f at l s wta sf pt g s s h c s a
o a s
e
, r c n u l
y a o t ai s d nf st d l o ai t e yB h l e
m si n ei l
a c n t t
h eh s n o
n w a u e a
,l pt a ni x t t
c e ot i d o s
r r e e s r
al
. gi 1
si r c nt ia el f e e nt, o r h i n n r n e n n c o cb oit ip2 yh u i a t z f o r
(
s wt t o r n y g e o f
ai c a r a e pb i l mg n 8
ig mie n pt a mt l
n t e s t i a a a n o 3
n n ut h r o a al e
o af el mn eii e s a at nt 1
eI r at e i c r p et n it s yb c
s s e a t t w
t e
e o n e
s n s o a e p y r n a a et i s p u d
o d" r
ad ot n
h
. n ei p uh ob h h
u u e m
t t t s c t l f t e o t
e c
t d ie u nt c
rd e
c a a rf nk t s a a
o r, r o n a e e ef ot a v sd u i a a u t o st i e d wh od n e sd o el o e 0
t r s t m si o s e
sl d r a e p r ui n 5
ri o n p u e v pi t g r e a e e e w b t ri 1
e n s i e r r o l
u n r r n rd m o t
s ul w o n c t u r g p oi u ui ei l
e e o p o m e s x s t
p n m t c t m e s sl s n p s m 5
p s e e n a
i o o s n a o n n a a i
a 1 2 s
y r
i e o r c w e o e ni o wl e e e 2
o l l e u e f t u c t T c f
g c" 5 5 N
)
o h h t 4
o s h t n e d a e n e e l
mt t s 7 7 1
r ut a o r y y a
a yh e sh c f a t
t o
e i
t ct s
. n e
n a
et l o n e
t t i t n e, rd n
n n n n u of e u e n si
, c o o o o n t h q f
a e
.ii f
e a n n r n s eF a m
2 i i i ci yT e ad t l e g a r o e e i
v d
t t t t rt r
s n e
o s s a rih l l
a e n
n c c c f n e e ud nil r ot w o l
. o e
. h d d n n u
d 1 f c t
mh wi e e e o o wf m
S S S c o a e c e e a a, x c e -
n e at r ot A
4 y
p sd i r r h ei c r
t u ud ei el c R R R nf l e
t w wf e t s oh e
n cd r o e
A A A i i t d m w et o ot e3 i ah s
o j
S S S l
n e n ni n m a n n
ok v s p p m n.
F F I i s e r p s i et o mo i e p c i
h i o e r
ai e m
eil gi aid i
b l gl t ol l g r a e ue r e n c r t e ot nb el ab i t rt y u l
n r ig e a ef l t i n
e et ms el 7 f e
) ) )
nt n eib a p wi e a s r n a h
e s t s n t n
f i u pt d T
ei t l
z e s ia a s v h n nh h h u a c r f o
h nh n o e h i t 0 a r 1
2 3 A c i et c T s c at o c T iT i n(
T wA 4 s p
( ( (
4 m
d
,d d
l 4
l e
e n e
f o d
a e
1 o r n
e s t t n r o t
t a
t u a n g e
, se n
a n n S
h ei e g mi a
w o s
et ms d
e n n eD m l
d n o c n m d
s p e e
l i i t e
o y n od o e) s n s o eid z
g gd s et e o r a t eit 1 r a e yh c u
.i n n n yh s r c s rlia d uh t s(
o r
b t i q el el i E eS t y u
s eh t a y t t u v e r el i s
p s
e r s t s i nt d o e a nb t e e nd a oi ri mn n a a et d s ni u ah d o n r et x u ud o el t ol e t
e s a s T
( i a e mc ut q n r ml mof a r e rl h s e h
t t
i a a a e af u a n o
u a u e c o r c
s c ma n e e r r
u nC y t l st n p a i. e e e w.
o rd f
,d t f i
n s n e s o a io t
ci e a nt h nt jt d l r e a mt e a n e s w o a n s el t a a y e ol n t of i af h e rt i uI y ei a
t l i l i nf at a e s u cd e n nt t S f f t nt eb t o o o t c s r
t y nh e i c c y r
ni nf a a r si n a a s ct e eW m n at y a e e
e ai r t s t e e ed k a eh p e
mu e a v
ms ms r e n e a g mR e s r f T e r
ef mf r s o ul n a p o c r n u
r mok a d
u t
e a p e r eid v o c o e a r e e e w r s n c s sd t S S d r t v a e r p r t h e t t o
. i i a y e s i o s et r s
,d p o s t n s e wd s g e sd y et v t nl n e s p n g
n i
y nt e r d o m nS h n o a i
o e e u af y n i n g s
e r o nl e e t e r r
,c n c -
ol i i n e n et a r
l t n mp e s s ot d r t s
e s c e a p e b n o) n n
e w r ig r r e s e a e s e nh n r,i t aii ni o e r o o np ad ed r r e e r e ci e s r e i
t o a sG ul t e t r p r e u rt ud a g p rt m l
e ait l t f c s o y o p t u ia t iE n o o a
eh t t n a m a
,a e.
ct o
al a c e
s t r rt ni o a
e eh n e e d
eit e n e n n a ed C me f s rt oh rd nl f ai f io n el sd n a u o
,t S
.d v e e p d t m n et e
i t n al f n y r, st
,a u
y y c ot a i d a e r c n s t u me a rd ef t t i t
i a vt c e f t o yt e s et r o e yf e c o n ed t i n nt e e s ei s n f s t a ef t t a e f
et io f
n c cd ai a f d nh t e
a e s u p ai sh a t a a e o nd ol a
I t a s v s r yt o s ct t
s ed t s
t s a n c e st l i e p s c ii n e d n a c o s u
r o sf oh r d
a r sd a r r d
a r d i r a sdd a n e o sT p e
,m i a n u u e e o e
e gp r e nt r
i r s at eb i q s v r t s p r o e e r a u sl u y o
e e eI h n o e
mo el rh t
,b el t t t
.t e rt t s e e e e s e e
ot r e ri ai n s n u s u rh s
n rt t nt t a i r n s
F e m o o n yt u w e r e r n t
. s o aT d e i e s n i n c st ig a
,s r u e s gt y e g a a e s b t e
n e v nt it n r mmo nt
.d s
n a S m nd et mir e r y ei a a
e m p
e n r a r o u e ut s a r a e e e et ii pt t i t n m i c a wi u
r o c cf sl e t
el v
e e s s n n u o o o e r o u ed r et rf i if e n n o h e y y o o o r r h al q h e o p o oii h a ah o e s T t s s mc a r p p T pF e T rf o mt cd T f S t C Gi n
a 4
i R
3
-