ML19225B722
| ML19225B722 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/14/1979 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225B724 | List: |
| References | |
| NUDOCS 7907250571 | |
| Download: ML19225B722 (19) | |
Text
.
!(pn rec,o, UNITED STATES NUCLEAR REGULATORY COMVlSSION
')#(
g E
WASHINGTON, D. C. 20555 I /c o
/
VIRGINIA ELECTRIC AND PO ER C0ffANY DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO.1 FACILITY OPERATING LICENSE License No. NPF-4 f.mendment No.11 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications f pr amendment to the furth Anna Power Station, Unit No. I license, NPF-4, by Virginia Electric and Power Company (licensee), dated August 14, 1978 and August 31, 1978, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The f acility will operate in conformity with the license, as amended, the provisions of the Act, and the regulat.ons of the Comission:
C.
There is reasonable assurance (i) tnat 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 Comission's regulations; D.
The issuance of this amendment wi!1 not be inimical to the comon 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 $1 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended b, page changes to Appendices A & B as indicated in the attachment to this license amendment.
(2 ) Technical Specifications The Technical Specifications contained in ppendices A and B, as revised through Amendment No.11, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications.
.e 7907250777 452 Wm
. 3.
The license is further amended by adding condition 2.D(3)o. to read as f ollows:
- 2. D (3 )o. The provisions of Sprc1fication 4.0.4 are not applicable to the performance cf surveillance activities associated with the diesel geceratcr battery technical specification (4.6.1.1.3) until the completion of the initial surveillance interval associated with that specification.
4.
This license amendrent is effective as of thc date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION arr b ef L1ght Water Reactors Branch tb. 3 Division of Project Management Date of Issuance:
JUN 14 DT
Enclosure:
Revised pages tc Appendices A & B Technical Specifications 452 PM M8
ATTACHMENT TO LICENSE AMENDMENT NO.11 FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by Amendment number and contain vertienllines indicating the area of change. The corresponding overleaf pages are also provided to maintain document compl.eteness.
Pages 3/4 8-3a (was 3/4 8-4) 3/4 8-4 (added) 3/4 8-5 6-2 6-3 6-5 6-6 6-8 I
e i
4 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Verifying the fuel transfer pump can be started and transfers 3.
fuel from the storage system to the day tank.
Verifying the diesel starts from ambient condition and 4.
accelerates to at least 900 rpm in 1 10 seconds.
Verifying the generator is synchronized, loaded to 3,1375 5.
kw, and operates for > 60 minutes, and Verifying the diesel generator is aligned to provide standby 6.
power to the associated emergency busses.
At least once per 92 days by verifying that a sample of diesel b.
fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.
At least once per 18 months during shutdown by:
c.
Subjecting the diesel to an inspection in accordance with 1.
procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, Verifying the generator capability to reject a load of > 610 2.
kw without tripping, Simulating a loss of of fsite power in conjunction with a 3.
safety injection test signal, and:
a)
Verifying de-energization of the emergency busses and load shedding from the emergency busses.
Verifying the diesel starts from ambient condition on b) the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected emergency loads through the timers and operates for 3,5 minutes while its generator is loaded with the emergency loads.
452 200 NORTH ANNA - UNIT 1 3/4 8-3 m
_E_LECTRICAL POWER SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)
Verifying that all diesel generator trips, except c) engine overspeed, generator differential and breaker overcurrent are automatically bypassed upon loss of voltage on the emergency bus and/or safety injection actuation signal.
Verifying the diesel generator operates for > 60 minutes 4.
while loaded to 1 2750 kw.
Verifying that the auto-connet.ted loads to each diesel 5.
generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3000 kw.
Verifying that the load sequencing times are within the 6.
tolerances shown in Table 4.8-1.
Each diesel generator 125-volt battery bank and charger shall 4.8.1.1.3 be demonstrated OPERABLE:
At least once per 7 days by verifying that:
a.
The electrolyte level of each pilot cell is between the 1.
minimum and maximum level indication marks, The pilot cell specific gravity, corrected to 77 F and 2.
full electrolyte level, is t 1.200, 3.
The pilot cell voltage is 1 2.08 volts, and 4.
The overall battery voltage is t 125 volts, At least once per 92 days by verifying that:
b.
The voltage of each connected cell is 1 2.08 volts under 1.
float charge and h6s not decreased more than 0.05 volts from the value observed during the previous test, The specific gravity, corrected to 77 F and full electro-2.
1.200 and has not lyte level, nf each connected cell is t decreased more than 0.08 from the value observed during the previous test, and 11 Amendment No.
NORTH ANNA - UNIT 1 3/4 8-3a A 5 7' 2 0T ~
1,
ELECTRICAL POWER SYSTEMS SURVEILLANCE F EQUIREMENTS (Continued) 3.
The electrolyte level of each connected cell is between the minimum and maximum level indication marks.
At least once per 18 months, by verifying that:
c.
The cells, cell plates and battery racks show no visual indication of physical damage or abnonnal deterioration.
The cell-to-cell and terminal connections are clean, 2.
tight and coated with anti-corrosion material.
The resistance of each cell-to-cell and tenninal 3.
connection is < 0.01 ohms.
The battery charger will supply at least 10 amperes at 4.
125 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
At least once per 60 months, during shutdown, by verifying that d.
the battery capacity is at least 80% of the manufacturer's rating when subjected to a perfomance discharge test.
NORTH ANNA - UNIT 1 3/4 8-4 Amendment No. 11
~bf 4 $7.- M
ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
One Circuit between the offsite transmission network and the a.
onsite Class lE distribution system, and b.
One diecel generator with:
1.
A day tank containing a minimum volume of 750 gallons of
- fuel, 2.
A fuel storage system containing a minimum volume of 45,000 gallons of fuel, and 3.
A fuel transfer pump.
APPLICABILITY _: MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required A.C. electrical power sources are restored to CPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance 4.8.1.1.1, 4.8.1.1.2 (except for requirement 4.8.1.1.2a.5),
Requirements of and 4.8.1.1.3 11 NORTH ANNA - UNIT 1 3/4 8-5 Amendment No.
k' 2 J
ELECTRICAL POWER SYSTEMS 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. electrical busses shall be OPERABLE and energized with tie breakers open 5etween redundant busses:
4160 volt Emergency Bus # lH 4160 volt Emergency Bus #
IJ 480 volt Emergency Bus # 1H, 1H1 480 volt Emergency Bus # IJ, 1J1 120 volt A.C. Vital Bus # 1-I 120 volt A.C. Vital Dus # l-II 120 volt A.C. Vital Bus # l-III 120 volt A.C. Vital Bus # l-IV APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With less than the above complement of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.2.1 The specified A.C. busses shall be determined OPERABLE with tie breakers open between redundant busses at least once per 7 days by verifying correct breaker alignment and indicated power availability.
NORTH ANNA - UNIT 1 3/4 8-6 452 20Y:
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITi 6.1.1 The Station Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during 'is absence.
n 6.2 ORGANIZATION OFFSITE The offsite organization for facility management and technical 6.2.1 support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
Eacn on duty shift shall be composed of at least the minimum a.
stift crew composition shown in Table 6.2-1.
k; least one licensed Operator shall be in the control room b.
wqen fuel is in the reactor.
At least two licensed Operators shall be present in the c.
controi room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fue' is in the reactor.
All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
A Fire Brigade of at least 5 members shall be maintained onsite f.
at all times.
The Fire Brigade shall not include the minimum shift crew shown in Table 6.2-1 or any personnel required for other essential functions during a fire emergency.
NORTH ANNA - UNIT 1 6-1 Amendment No. 3 452.
2 D!i
T N G ED NS NRIE C
EE T
I 1
E V N
r I
NR I
u R G E 4n S
EN P
U 2n E
i rt a..a s
- i N
.s S
L RO R RN N
OI R
AT
,A OA O E
TCR I
O T
TET IG Ct O TA U4 C
C L P
A E
HP D
EC AN Rf OCU R
wt RI U TA E
ES O NP S M DR
,C r
T O
P o
R Y
p R
p O
M S
E I
- au T
SV S
T I
,s SM R la T
,f, N
Y E
E c
P L
SH U e
E D A S n
CS N C h
E E
I C c
T NI e
V NH T
R I
C R
E S
T d
E ET MH5 n
P T I a
U E
C L
S T
I t
SAS n
YEY e
$HH m
P egan T
a NE M
EC DNS y
NAE it C
E NI l
5 T
4 NT ic EV 0
I R
a l
R N I
E F
&i EA S T
A r
4S P
M o
NY R U
R0N L
f EP lO S
E Di P P E
iI n
sL0 G
CT o
A UA i
E$4
- N 0R R.
t R R0 T
a A 0E E
N T
E P
l M 1. O WC R0N E SN is E
C i
P P
E n
C P
AT DL I
GU E
a 0
s O4 NR NAM g
VP 0 T
0 r
C1 EO E I O
RE
=
T TP G
E U
e
=
I UAI S RAN t
D0 M
EMA s
i 0
P M
f R&
U R
S f
P ORN O
S I
O SA I m
1 VET a
T R LA r
2 g
C E
R o
N U
r 6
P E
P ENS UNP D0N l
S O
n e
N1 O o
r T
i u
E I
c E
CT t
g T
E UA e
i N
R T
I DR R
to F
T ROE O N Pr A
t E RP TOY e
DM E
PPO AIT r
L N U U
T C A O S
NCRI Fi 0
I UU ta e
Y C 4
l3 D
DC T
G R
r wE OE o
N O
S p
F F I
O r
R T AT P
o C
S$ A C
Y R
r S
f E
o P
A O
N ie N
ROGY RG -
d R
OI NT A N n
T I
E iO T
o C
N' EbS C
I p
LI s
UIDA A CAV e
E RIOR URR R
S E
DRT &
NT P
P U
D 0 h @a:o:"
3- )
w ge 3t3 hiw 5
2OD 2
8
>33 Ce csp 4LN N &O
se i
4 E
T
'0 S
3 E 4 F E n
ty EC 0 0 O E
P L
t Ry 0
O y
Ig R
SI t
E E L f
CE 4 E R
Rl Fg T
I 1 A R i fTR 0TS a
$gP AC l
R bmE 1AE gU C R C IU g uA EoE V
I g
S LO R Qu tRC I
I TV T
u E E O N 0C4 RS R A u R L sYG EtR 0 R 1
1 I E T T P4E 1
M T G A 4 iTN U1S 4E 0q
=
RLE S
I M
O t
P O i
R i
=
E
=
A 0
SO C 4S A
N P M 0
A I
=
O
=e 0
G I
L L =
L
$O =
=
=
=
=
E F
I F
A N
T S
=
==
=
==
S G
C T R R
2
=
RI R Y NO iO n
S O R E S RS d
=
0 Y S
IV an Y
3 T
MI E
4 l
H I S V
yP V
l U
E R
R 4
EL S
RH Ru R
1E 1
0A t
E E
ET t
T P GP 4Cl U A f
n P
s a
1 1C P L H
$ U U
t U
u$
i 1my S
SC 7 $
=
1C H
U 4HR E
E R
=
E$
=
P a
U S
n
=
n
=
A
=
h t
r oN R
E G
A l
N A
n R
N o
R O O
T I
A i
t E
M a
C A
a LC R 4
E RI U E 0
LR n
P f
AO a
DN f
CS g
F O
A If F
r RV A
T O
S TR T
CE S
y tP t
LU h
a 1S a
=
=
F T
NE 2
C E
2 DN A
6 N
N e
E I4 TE r
N1 u
G R N Rt ig I
A F
A T PM E
EL RE AE U
C 1
t U
1 P
L N O 1
R M
A O 4 &M lS F
C 0
F tI 1
Y O V
A Y T C A
R T
A E H
S E
i T CP
~
SA E U MS G
?
M M
t O
YR 4
4 O
t R
ES G R R
R R
OR T
f O
NO O
0 OR GO 0N I S f S i$
T T I f
I A
i R O R
Y N
A T
I A AT NS hO T
L i
A L
f L A T
E Nv iT A V l
V tl V T
It tI O
eO9 R
1 R
lR IX E C4F IR NA R R HR sHR E
$SE R E E
E0A AE RE O
P T P l1 U
U A
U NO ANO A O OC&
V PO S
O CL U
C 0
t L
t O
0 L
S S
s e
S P
2OUHI >6_>
8 Cz U "
w a3 2O" [ "e
%+ U N 3
l 3
,'i
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
APPLICABLE!"bES LICENSE CATEGORY 1, 2, 3 & 4 5&6 SOL 1
1*
OL 2
1 Non-Licensed 2
1 l
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.
- Shift crew composition (including an individual qualified in radiation protection procedures) may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided inrnediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
NORTH ANNA - UNIT 1 6-4 452 gbar
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS Each member of the facility staff shall meet or exceed the minimum 6.3.1 for comparable positions, except for qualifications of ANSI N18.1 -1971 the qualifica-the Supervisor-Health Physics who shall meet or exce.
tions of Regulatory Guide 1.8, September 1975.
6.4 TRAINING The Station Manager shall assure that retraining and replacement training programs for the facility staff are maintained and that such 6.4.1 programs meet or exceed the requirements and recommendations of Se and App'ndix "A" of 10 CFR Part 55.
These programs of ANSI N18.1-1971 shall be directed by the Director-Production Training and Safety.
A trzining program for the Fire Brigade shall be maintained under the direction of the Fire Marshal and shall meet or exceed the requirements 6.4.2 of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions and drills which shall be held at least once per 92 days.
6.5 REVIEW AND AUDIT STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (S
_6.5.1 FUNCTI0t{
The SNSOC shall function to advise the Station Manager 6.5.1.1 on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The SNSOC shall be composed of the:
Station Manager Chairman:
Superintendent - Operations Vice-Chairman:
Superintendent - Maintenance Superintendent - Technical Services Member:
Member:
ALTERNATES All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis; however, no more than 6.5.1.3 alternate shall participate as a voting member in SNSOC activities at any one time.
6-5 Amendment No. 3, i
t:0RTH ANNA - UNIT 1 1tT1 95 2.
.3ssesf
ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chaiman or his designated alterr. ate.
QUORUM 6.5.1.5 A quorum of the SNSOC shall consist of the Chairman or Vice-Chairman and two members including alternates.
RESPONSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:
Review of 1) all procedures required by Specification 6.8.1 and a.
changes thereto, 2) any other proposed procedures or changes thereto as determined by the Station Manager to affet nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to Appendix "A" Technical c.
Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence to the Director, Nuclear Operations and to the Chaiman of the System Nuclear Safety and Operating Comittee.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written nctification to the f.
Commission.
Review of facility operations to detect potential nuclear g.
safety hazards.
Amendment No.
11 6-6 NORTH ANNA - UNIT 1 452 2W
ADMINISTRATIVE CONTROLS h.
Perfonnance of special reviews, investigations or analyses and reports thereon as requested by the Chairmn of the Station Nuclear Safety and Operating Comittee.
i.
Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Chairman of the station Nuclear Safety and Operating Comittee.
j.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety and Operating Comittee.
AUTHORITY 6.5.1.7 The SNS0C shall:
Reconinend to the Station Manager written approval or disapproval a.
of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Director, c.
Nuclear Operations and the Chairman of the System Nuclear Safety and Operating Comittee of disagreement between the SNSOC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Director, Nuclear Operations and Chainnan of the System Nuclear Safety and Operating Comittee.
6.5.2 SYSTEM NUCLEAR SAFETY AND OPERATING COMMITTEE (SyNS0C)
FUNCTION 6.5.2.1 The SyNS0C shall function to provide independent review and audit of designated activities in the areas of:
NORTH ANNA - UNIT 1 6-7
~
452 2H
ADMINISTRATIVE CONTROLS a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control f.
Radiological safety g.
Mechanical and electrical engineering h.
Quality assurance practices i.
Other appropriate fields associated with the unique char-acteristics of the nuclear power plant COMPOSITI0ti 6.5.2.2 The SyNSOC shall be composed of the Chairman and four other members. Membership shall be composed of the Managers of the Power Station Engineering, Fuel Resources and Production Operations Departmeats,
and Execu.ive Manager Licensing and Quality Assurance or qualified designees from these departments and a fif th qualified member selected by the four other members. Members of the SYN 0C shall have an academic degree in an engineering or physcial science field and, in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in Section 6.5.2.1.
ALTERNATE:._
6.5.2.3 All alternate members shall be appointed in writing by the SyNSOC Chaiman to serve on a temporary basis.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as detennined by the SyNS0C Chairman to provide expert advice to the SyNSOC.
11 NORTH AN% - U J l
6 -8 Amendment No.
452 218
ATTACHMENT TO LICErlSE AMENDMEflT NO. 11 FACILITY OPERATING LICENSE NO. NPF-4 DOCKET fl0. 50-338 Replace the following pages of the Appendix "B" Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Pages 5-1 5-2 452 217
5.0 ADMINISTRATIVE CONTROLS Administrative controls established below are deemed edequate to implement the Environmental Technical Specifications which provide continuing protection to the environment.
5.1 Responsibility _
The responsibility for implementing the Environmental Technical Specificaticns is assigned to the Director of Nuclear Operations at the corporate level and to the Station Manager at the station level.
The Superintendent -
Operations shall be responsible for l
ensuring that the station is operated to accordance with the Limiting Conditions of Operation. The Station Supervisor - Health Physics shall be responsible for the radiological environmental surveillance requirements. The Executive Manager of Ensironmental Services shall be responsible for providing services which will fulfill the nonradio-logical environmental surveillance requirement <.
0rganization 5.2 l
The relationship between the Production Operations Department and the Environmental Services Department is shown in Figure 5.2-1.
5.3 Review and Audit Station Nuclear Safety and Operating Committee (SNSOC) 5.3.1 5.3.1.1 Function The SNSOC, as described in Section 6.5.1 of Appendix A of this license, shall function to advise the Station Manager on matters related to the environmental impact of the station. When the SNSOC is exercising its responsibility for non-radiological aspects of the ETS, the Station Biologist or his alternate shall be consulted.
l 5.3.1.2 Responsibility The SNSOC shall be responsible for:
Coordination of the Environmental Technical Specifications with a.
the Safety Technical Specifications (Appendix A) to avoid con-flicts and maintain consistency.
Review of changes to the Environmratal Technical Specifications b.
and the evaluation of the environmental impact of the change.
5-1 fc.S;rts:7 1:n. 11
M KR 452
%f42d
Y RT i'
E EI C
GL N
AA A
NUE E
RR AQC RYC OU M
N OTN SS
&A TIA IS CLR VAM E
R I
EAU R
VGU I NS RUS EYO TI S I QS PT USA D
~
XC U
EI Q -
L S
E TC N
NI O
EV I
DR T
NE HS A
T L I_
N NL AS E
S S
IA EY M
N N
RC HH E
O O
EI R
P f
L DI I
PN R
P TNT T
E UH G
A M NAA A
S SC E
A CT S
E R
R R
N H
I E
N.
I N N
DYE E
C O R 0_
A T
C I LP P
TACEU M
VERO N E DEI SPO RO O P RIWT
, EP E
OSOA RUN GN.
ELA D)~
N I
S RCR T
O T
I A H NR E
I NI DNP T
ERT AT Q
DN J[
I C S
O CEC MC A
E H T IWU U
T NO I
EI VOD D
S ML TT PO O
NA i
R A R
R IR O T P
P RE N
EP E
P 0_
M U
N S
O R
I V
R G
M O
N E
S I
I R
VRO R I T_
EAI Y
P N
T U
O S
}
i I
RL EA GU R
AO E
N L
GL AR A
SGO ANS I OI MEE VLT l C ROA eI ERR Ef POE V0V UEP IRR S T 0_
Y TIE T
E M
UVS I
S l
Cl RL EE f
i EA 0
Ns X
GU l I OI E
AQ uT Ic To N
P A
BO W
i[-
d ]:
d.
vE s
ALw N m n