Text

Bass:Use of Incore Detector Sys to Monitor DNB-LCO on Calvert Cliffs Units 1 & 2, Nonproprietary Version
	ML19320B121
Person / Time
Site:	Calvert Cliffs
Issue date:	11/30/1979
From:	; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	;
Shared Package
ML19289B046	List: ML19320B114; ML19320B121; ML19320B132; ML19320B136; ML19320B139; ML19320B145; ML19320B150;
References
	CEN-119(B)-NP, NUDOCS 8007090332
	Download: ML19320B121 (21)
	v • d • e

.

CEN 119 (B) NP 4

BASSS l

USE of the INCORE DETECTOR SYSTEM to MONITOR the DNB-LCO on CALVERT CLIFFS UNIT 1 and UNIT 2 I

I NOVEMBER,1979

~

1 l

1 3lE POWER 8007000 3 3 (

miiiiiil SYSTEMS COMBUSTION ENGINEERING. INC.

LEGAL NOTICE THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED BY COMBUSTION ENGINEERING, INC. NEITHER COMBUSTION ENGINEERING NOR ANY PERSON ACTING ON ITS BEHALF:

A.

MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED INCLUDING THE WARRANTIES OF FITNESS FOR A PARTICULAR PURPOSE OR MERCHANTABILITY, WITH RESPECT TO THE ACCURACY, COMPLETENESS, OR USEFULNESS OF THE INFORMATION CONTAINED IN THIS REPORT, OR THAT THE USE OF ANY INFORMATION, APPARATUS, METHdD, OR PROCESS DISCLOSED IN THIS REPORT MAY NOT INFRlNGE PRIVATELY OWNED RIGHTS;OR B. ASSUMES ANY LIABILITIES WITH RESPECT TO THE USE OF, OR FOR DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION, APPARATUS, METHOD OR PROCESS DISCLOSED IN THIS REPORT.

es e

ABSTRACT The Better Axial Shape Selection System (BASSS) uses the in-ccre detector system to monitor the Departure from Nucleate Boiling-Limiting Condition for Operation (DNB-LCO).

An algorithm is used to determine allowable power level as a function of rod insertion, core average axial shape index, and total integrated radial peaking factor.

The computer code PSINCA has been developed to evaluate this algorithm.

A summary of this code is included.

The implementation of this system for Calvert Cliffs Unit 1 and Unit 2 is also described.

e e

i

TABLE OF CONTENTS Section Title Page No.

1.0 Introduction 1-2.0 Definition of Terms 2.

3.0 Functional Requirements of System 3.

4.0 Functional Description of PSINCA 5.

5.0 Technical Specification Changes 9-6.0 References 15.

Table LIST OF TABLES Page No.

1 BASSS Coefficients for Calvert Cliffs 16.

I Cycle 4 Figure LIST OF FIGURES Pace No.

1 Flow Diagram for PSINCA 17.

2 Octant Representation of Distribution 19.-

of Incore Detectors 3

Octant Coupling Mechanism 20.

4 Power Alarm Limits vs IASI 21.

11

1.0 Introduction The purpose of the Better Axial Shape Selection System (BASSS) is to wse the in-core detector system to monitor the Departure from Nucleate Boiling-Limiting Condition for Operation (DNB-LCO).

This document defines the algorithm which is used to determine allowable power level

~

I as a function of rod insertion, core average axial shape index, and I

total integrated radial peaking factor.

The computer code pSINCA has been developed to evaluate this algorithm.

A summary of what this code does is incladed in this document.

Certain Technical Specification

]

changes required for implementatior, of this system for Calvert Cliffs Unit 1 and Unit 2 are also outlined in this report.

i I

I l

)

l.

- - - - - - - - - - -l

2.0 Definition of Terms Name Meaning ARO All Rods Out BASSS Better Axial Shape Selection System BLIM Alarm Limit Power at which DNB-LC0 is reached C

Lead CEA group insertion (% inserted)

CEA Control Element Assembly DNB-LCO Departure from Nucleate Boiling - Limiting Condi tion for Operation FT R

Total Integrated Radial Peaking Factor (AR0)

IASI Core Average Axial Shape Index O

2

3.0 Functional Requirements of System The Better Axial Sh we Selection System's (BASSS) function is to mor.itor CEA position and core average axial shape index (IASI) and provide an alarm on power when the DflB-LC0 is exceeded.

3.1 Power The BASSS algorithm calculates a power alarm limit (BLIft) from knowledge of CEA position (C), total integrated radial peaking factor (FR ) and

~ T core average axial shape index (I,ASI).

The calculated power limit is then compared to the measured power level of the reactor.

An alarm is actuated if the measured power level exceeds the calculated limit.

For this comparison, the measured power level is assumed to have an uncertainty of 2%.

Updates on measured power level are available at two-minute intervals.

3.2 CEA Position The CEA positien input to the algorithm is that of the control rod of CEA Bank 5 with the greatest insertion including the measurement uncertainty of that position.

The BASSS is valid for CEA insertions of Bank 5 from "all rods out"'(AR0) to 55% inserted.

Operation with insertions greater than 55%

of Bank 5 will require monitoring the DflB-LC0 with the ex-core DflB axial flux offset control limits.

3.3

_ Core Average Axial Shape Index The core average axial shape index (IASI) is calculated by the online computer code PSIf1CA using the ii. svie aetector signals as described in Section 4.2.1.

Updates of the in'-core detector signals are available at thirty-second intervals.

Operability of the in-core detectors is established in accordance with the in-core detector Technical Specification (Section 3.3.3.2).

Uncertainties and biases on IAST are included either in the determination of the coefficients for the BASSS algorithm or in PSIflCA.

3.4 Total Integrated Radial Peaking Factor The total integrated radial peaking factor (FgT) input to the BASSS algorithm is the higher of the total integrated radial peaking factor Technical Specification's limit (Section 3.2.3) or the measured value of FR.

Updates T

~

on measured values of FRT are available at intervals specified in surveillance requirements of the FRT Technical Specification (Section 4.2.3.2).

The uncer-tainty on FRT is included in the determination cf the coefficients for the BASSS algorithm.

3.5 Uncertainties All applicable uncertainties and biases are included in either the BASSS algorithm or the PSINCA code with the exception of the measurement un-certainty on CEA position. The measurement uncertainty on CEA position is applied to the input value of CEA position used in the BASSS algorithm.

The other applicable uncertainties are:

1) Temperature measurement 2)

Flow measurement

3) Power measurement

4) Pressure measurement 5)

Integrated Radial Peaking Factor measurement

6) Axial Shape Index measurement

4.0 Functional Description of pSINCA 4.1 Introduction The computer code PSINCA has been developed to perform two tasks using the online computer.

The first task is the calculation of the core average axial shape index based on the incore detector signals and the insertion of the first regulating bank. The second task is the evaluation of the allowable power level of the core based on the core average axial shape index, the amount of insertion of the first regulating bank, and the total integrated radial peaking factor. The allowable power level is calculated at two minute intervals.

4.2 PSINCA Figure 1 displays a flow diagram of the computer code PSINCA. The following sections describe the algorithms used to calculate IASI and BLIM.

4 e,

4.2.1 Core Average Axial Shape Index Calculation The core average axial shape index (IASTI is calculated usino the incore detector signals and the signal to power coefficients which are also used by If4CA (Reference 1). PSIliCA performs this calculation by first i

folding the entire core's complement of detectors into one octant.

Figure 2 displays an octant representation of the distribution of incore detectors in the Calvert Cliffs Unit 1 and Unit 2 reactors.

Each of the nonredundant locations is coupled to its nearest redundantly instrumented neighbor as shown in Figure 3.

If a nonredundant detector fails, PSINCA can provide a replacement signal for this detector using the signal from the nearest redundantly instrumented neighbor and the appropriate coupling coefficient. This technique is analogous to that.used in INCA. PSIrlCA will abort only if a non-redundant detector and the entire set of redundant detectors which supply its replacement signal fail at a given level.

In this situation, t.he DMB-LC0 will be monitored with the ex-core DiiB Axial Flux Offset control Limits.

Only instrumented assemblies are used to calculate the core average axial shape index. A bias exists between the actual core average axial shape index and the shape,index calculated by PSINCA. This bias is identified for each reload cycle using the computer code ROCS (Reference 2).

PSINCA evaluates IASI in the following manner:

l.

All instrument signals are converted to equivalen powers over the length of the detector segment.

2.

The full complement of powers is averaged into one set of octant powers.

3.

A replacement power is substituted for any missing nonredundant powers.

4.

All instrument powers are averaged at each of 4 detector levels (P1,'P2,P3,P4). _

'~'

7 5.

Using burnup-dependent axial coefficients from It1CA (Cl, C2, C3, C4), IASI is calculated frcm the following relation:

.(

where BIAS accounts for the difference between the core average axial shape index and the PSINCA calculated index using only instrumented assembly I

)

powers.

f.

4.2.2 Allowable Power Level Calculation The algorithm used by PSINCA to calculate the allowable power level (BLIM) uses the core average axial shape index, the amount of insertion of the first regulating bank, and the associated total integrated radial peaking factor.

t i

PSINCA calculates BLIM in the followinn manner:

/

s

~

This section describes C-E proprietary methods used in calculating BLIM.

e I _. _.

4.3 Example of PSINCA Monitering System A sample calculation based on input data from the Calvert Cliffs Unit 1 Cycle 4 setpoint evaluation provides an example of the coefficients for the BASSS algorithm. These values are listed in Table 1.

Using these values in the BASSS algorithm defined above, power alarm limits have been calculated for the following rod configurations:

1.

AR0 2.

Bank 5 Inserted 15%

3.

Bank 5 Inserted 25%

The results of this calculation are displayed in Figure 4 which shows an improved operating margin relative to the present ex-core DNB-LCO.

9._,

5.0 Technical Specification Changes In order to implement the BASSS on Calvert Cliffs Unit 1 and Unit 2, several modifications to Technical Specifications are required.

These modifications are identified in the following five pages (pp 3/41-27, 3/4 2-9, 2-10, 2-13, 3/4 2-14 of the Calvert Cliffs Technical Specifications for Unit 1 and Unit 2) with parentheses.

1 I

e

_ 8 o-i i.

.4 l

t g

{

.e.

. l 9

.g~

4 I.

,i

.3

....l..

.)..

.. I

. o, N

l-

..". j :: ;

,n i.

p

.e :

. l.:

p-.:;c.

r :

1 i

l"!.

..I alU.

i '

' '1 "

"* 7

...t T.

l

... j :i

- t'....

I..

.t.

o

.r *

". ?"

r*1 "..

o v

g.

.l;'

t l'.'

't i

m 1 *:].

...J.

1 m

. :b:

+* :-."

"h.. n i. '

t l::

"t.

".,.."t' 1'

. I: t..

...I'."

6.i

-*:i."

+ - * * - -

.t i;.

I. t -

i

^

...l....

C o-j

.p;

. r **

o nl*rp' - i.' :l.. ::1,lL.;

5 l ".,

yW

-oo l:

ij.

j!

3

.i,.

t.

p" t.: :;

e p-

q:u* :.:.!".l,...'..

i.:

2.p..:.

n

.] :

5. :

1~

m n

7 ;.

u a..c.

.2 i.

a:

... ;c :!

.: 1. :..

- a.

t

. os

_ mg N

o

j.,.

.. I p" o

n

n !"..

T-l:n.

4 w

r., ".

l..

i::

l-a --

r

- p 8"

_J z 2.:["

. ji{(.

ay:.

L ;(uop;asul %09 @ g enoJD 0)

-oy,- og gg y

ma

p.. \\,.

~j-N O<

.i. :

1. i. :.

" 8,f r. =

o_

_ oa q::j :..

c

.6

.. n

_J z_

W n:..u.:..

i.... :)..

..u.

- a.a a 2 a:

.,:li.

i i..i

i. ;:

2 p

~

.oo

,e il.

< es

-..i : e..

v m i..

., i.;,,l.e..~.:

s qu c..

i.i. l.c.. p. ".

.. n..

al.

.q; i,i

i..

I p:

t m:

.: p i.: k:n..H "h.

i t-..r;.. ":

a. O a

r i

3..:-!.

mi t

on :w

. c.. l :c:..

m 2

a:-

m N

oy r- ~:t- ;l:::.

-r-

~~. -

mM

- oy 3

~ ~ - -

--.r o

7.: : in- : :---

~~-

y1:

na 4

2 C-

i

.;:j ~:

inj.:'

..;;:{ :

4 2

Ou N

~ ;; :.

o_ C*

.a n-4 M7

E]: - huop;osul %09 @ C dnoJ9 0g 0) i

_ gj

_oy $5 N.

g-a: "

..i.:

C H,f Q

Z.

i.I

,o ::. *

.!p

.i., '

m

n"

.m a:

...].i wg cs n,.

n

.a mi m

.l

...s-)

g..

. l:1'.3...

.'. t !..

' l* i. t '.g -

t,. -

u. m

.e,

j....

. vo g..

.....g 3t-l.

o @.

.o-g<

na oa -

- dX

<y

.9 >W y

m::

,l :

-[. 1;;

S gUg tO W

u.

m, t

, z,,j;;

'.j ;g

. :. '... " :....la..

w

.i..

No m

17;t[:-[:

. j:

. Od

_ og Bt *:*

.s-

.;h; L-

_s. c-2

. :.\\.d m_ i

'.';.r n

a

..;W;., ;

w

.)

O Z

J

g W

4,o.:'

c p

.g.

lp....a' (%09 @~..hi'

!h O

z3

i.2

.'i c < z C

_ o T.

OO

- : *2

p oO o3 p o-

~

i h:.

3:::'

s U;. '. 4 '- !L

WW

!L J'l:. '

y dooJD 99'0,1.i ::.

...l:. s:.;

.J.a;-

H >. O c

~

v cJ m

rjn..

........l...s.. :

L:

+

_i.....

m<

w

...n..v..".

..,n..

s. o. g..

.:..i.:.

o-

. o ms c

i..

,.l..

.i.,-

.c<c oo a::

w.

,:,l ;

m a:

Ow m2

(%SB @ g dnoJ9 gg 0)-

..., r..

i,. i:

_W

.:s

j -

g m,

w p-t..

1. w m E __a.

.. t

._..I-..

. o

. W, 03 "

_ o e a

)

N No uopJasul %og @ p dnoJD.

s c.

.i..

.i

(%09 6 g dnoJo oro) +;

].._

g

.l.

3sz.

.i

_ o;

., a $

-m c,

o

(%09 0 9 dnoJD 900) g.

-j;.

iW > o _ -[

l m

g m

kd q

~

E

'O k C b

.. ' '.. UN

_ o*.

m i pn

... j,";f,.. O

m 2 -

Z W U

5-

" Ei

(%9g 6 u!

i, i S*

Z --

g dnoso ot) am_a

- c.n

~-

oo m

- (uop;asu1 %gg @ g dnoJD 00'lly.

"h:* ~.

-3..

,j.-

~

ym 5 - R8

.l

.. l ;., ;.

l.

.t.

.l -

'l. l.

...;r

.1

a:Ia

..i nm-t

. :: ir -

1 p.

i. j.. l

.I

.i l

l...3..

r.

, u._

f m cn cr o o

ggg on R

8 o

o S.

o o

N c

s.

v.

m N.

v c.

o o

o D

O NOl1VN18 WOO dOU DNilS!X3 803 83 mod ~lVWU3H1 a-o 3*18VMO*l*1V 30 NOllOVMd I

CALVERT CLIFFS-UNIT [1,2]

3/4 I 27

-10" L

POWER DISTR 13UTION LIMITS DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1:

a.

Cold leg Temperature

~

b.

Pressuri:er Pressure c.

Reactor Coolant System Total Flow Rate

d. -( AXIAL SHAPE INDEX, Core Power )

APPLICABILITY: MODE 1.

I ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL PCWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REOUIREMENTS 4.2.5.1 Each of the parameters of Table ?.2-1 shall be verified to be 3

within thkir limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its iinit by measurement at least once per 18 months.

1 CALVERT CLIFFS-UNIT 1,2 3/4 2-13

TABLE 3.2-1 n

((

DNB PARA;lETERS LIMITS p

Uk Four Reactor Three Reactor Two Reactor Two Reactor T

Coolant Pumps Coolant Pumps Coolant Pumps Coolant Pumps

((

Parameter Opera ting Operating Operating-Some Loop Operating-Opposite Loop a

Cold Leg Temperature

< 548"F

a Pressurizer Pressure

> 2225 psia

Reactor Coolant System g

Total flow Rate

> 370,000 gpm.

( AXIAL SHAPE INDEX,

( * * *)

4d Core Power)

.e.

7"

Limit not applicable during either a TilERMAL POWER ramp increase in excess of S% of RATED TilERMAL POWER per minute o" a THERMAL POWER step increase of greater than 10% of RATED TilERMAL POWER.

- These values lef t blank pending NRC approval of ECCS analyses for operation with less than four reactor coolant pumps operating.

(*** The AXIAL SilAPE INDEX, Core Power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertions.of the lead bank of <55% when y

BASSS is operable, or within the limits of FIGURE 3.2-4 for CEA insertions specified by FIGURE 3.1-2. )

d

. {

f

~

, POWER DISTRIBUTION LIMITS TOTALINTEGRATEDRADIAL'PEAKINGFACTOR-Ff_,

LIMITING CONDITION FOR OPERATION T

T 3.2.3 The calculated value of'F, defined as F = F (1+T ), shall be r

r 7

q limited to < l.54.

APPLICABILITY:

MODE 1*.

ACTION:

With FT > 1.54, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

7 a.

Be in at least HOT STANDBY, or (b.

ReducgTHERMALPOWERtobringthecombinationofTHERMALPOWER and Fr to within the limits of Figure 3.2-3, withdraw the full length CEAs to or beyond the Long erm Steady State Insertion 4

Limits of Specification ~3.1.3.6, ar.d insert new value of F) in BASSS; or c.

Reduce THERMAL POWER to bring the combination of THERMAL POWER and F[:. to within the limi s of Figure 3.2-3 and withdraw the full eagth CEAs to or beyond the Long Term Steady State Insertion Limits of 5pecification 3.1.3.6.

The THERMAL POWER limit determined from Figure 3.2-3 shall then be used to estab-lish a revised upper THERMAL POWER level limit on Figure 3.2-4 and subsequent operation shall be maintained within the reduced acceptable operation region of Figure 3.2-4.)

i t

l l

i See Special Test Exfeption 3.10.2.

i CALVERT CLIFFS - UNIT (1,2) 3/4 2-9 i

b e

9 SURVEILLAtlCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

Fr shall be calculated by the expression FT = Fr(1+Tq) and F 4.2.3.2 shall be determined to be within its limit at the fo$ lowing intervals:

a.

Prior to operation about 70 percent of RATED THERMAL POWER after each fuel loading.

b.

At least once per 31 days of accumulated operation in MODE i, and c.

Within four hours if the AZIMUTHAL POWER TILT (T ) is > 0.030.

q 4.2.3.3 Fr shall be determined each time a calculation of F is required by using the in-core detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination.

4.2.3.4 T shall be detennined each time a calculation of F is required andtheva10eofT usedtodetermineF[shallbethemeasuredvalueof T.

q q

CALVERT CLIFFS - UNIT (1,2) 3/4 2-10 l l i

l

t 6.0 References 1.

" INCA, Method of Analyzing In-Core Detector Data in Power Reactors",

s CENPD-145-P, April, 1975 2.

BG&E Application for Cycle 4 Reload, A. E. Lundvall (BG&E) to R. W. Reid (NRC), February 23, 1979 I-l i

1 t

j 4

i I

t E

6 i

e a

f i

< i

- -.,, -.... -... - -. ~ - - - - - -.. -. -.. -,..,--

TABLE 1 Typical BASSS Coefficients for Calvert Cliffs I and II A1 = 99.0 SA1 = -3.1 A2=

.04 SA2 = 0.00 A3=

.00040 SA3 = 0.00 A4=

.00008 SA4 = -3.1 X.", = 9 9. 0 SMj =-0.35 XM2=

.04 SM2 = 0.00 X M3 =

.00040 SM3 = 0.00 XM4=

.00008 SM4 = 1.28 B1 = 99.0 SBj ~= 1.02425 B2 =-0.04000 SB2 = 1.03400 B3 = 0.00040 SB3 = 1.03400 B4 =-0.00008 SB4 = 0.90200 R0 = 2.100 -

IASI) =-0.05 Rj =.647 IASI2 = 0.00 BIAS =+0.004 IASI3 = 0.20-F

= 1.70 R

e M

6,

5

Figure 1 FLOW DIAGRAM OF PSINCA READ CONTROL R00 POSITIONS READ INSTRUMENT SIGNALS READ SIGNAL TO POWER COEFFICIENTS READ CONTROL R00 DEADBANDlUNCERTAINTY y

CALCULATE AVERAGE REG BANK INSERTION CALCULATE LIMITING CEA INSERTION v

IS AVERAGE YES INSERTION GREATER

+ STOP THAN 55%

NO v

CALCULATE OCTANT-AVERAGFD POWERS v

READ SATELLITE COUPLTNG COEFFICIENTS READ DETECTOR LEVEL BURNUPS READ IASI COEFFICIENTS y

REPLACE MISSING NON-REDUNDANT OCTANT SIGNALS WITH SIGNALS FROM NEARBY REDUNDANT INSTRUMENTED ASSEMBLIES AND APPROPRIATE SATELLITE COUPLING COEFFICIENTS y.

Figure 1 (Cont'd) r ARE REDUNDANT OCTANT YES SIGNALS MISSING STOP NO v

READ BIAS FOR IASI CALCULATION READ COEFFICIENTS FOR BASS ALGORITHM 8_Y CALCULAE IASI v

CALCULATE BLIM i

v STOP

= - - - _

KEY

-OUARTER + 3 1

CORE 7

ID's OF INSTRUMENTS S MBLY IN OCTANT POSITION I

2 20 31 4

5 6

7 3

3 34 26 7

17 39 28 45 13 11 12 27 9

10 3

8 2

6 13 40 32 44 43 14 15 16 17 18 20 8

5 4

15 21 30 25 41 42 3[~ l28 25 26 27 21 22 23 24 g

35 37 10 36 38 29 30 31 32 33 34 35 36 12 33 33 22 24 34 37 38 39 40 41 42 43 16 18 29 45 46 47 48 49 50 51 52 53 23 54 55 56 57 58 59 60 61 62 x

l OCTANT REPRESENTATION OF INCORE DETECTORS Figure GAS & ELE T IC CO.

IN ENTIRE CORE 2

l Calvert arrrs Nuclear Power Plant

KEY QUARTER -+

10 CORE ASSEMBLY 7

+- OCTANT DETECTOR ID NUMBER I

1 2

PROVIDES A SIGNAL 1

2 FOR COUPLING TO NEARBY ASSEMBLY I

3 4

5

/

6 7

3 4

5

s 8

9 10 11 12 13 6

7 8

l

+

l 14

'15 16 17 18 19 20

/

9,/

10 11

/

21 22 23 24 25 26 /

27

,28 12 13

/

14 j 29 30 31 32 33 34 35 36 1 15 16

17

~

+

37 38 39 40 41 42 43 44

- 18 45 1

46 47 48 49 50 51 52 53 54

~

55 56 57 58 59 60 61 62 N

l BALTlMORE GAS & ELECTRIC CO.

NON-REDUNDANT DETECTOR COUPLING PATERN p'9" Colvert Cliffs Nuclear Power Plant 3

t i -

0 l

4 0

\\'\\

\\

\\\\\\

\\

0

) s\\ \\

3 N. \\ K D

\\\\ x

%N N

s 0

2 0

D E

5 T R

K E N S A N B

I 5

0 2

1 0

T

~

U O

0

)

0 u S

.l O(

0S D

A

(

R D

L E

I S

L 5 T A

A R

l

~

K E N S

/'

A N D

B I 1

/

5 0

/

1 e/

0 2

0 0

~

3 0

0 0

0 g

M 0

g 0

0 I

0 L

g 1

1 g

B 1

a

~

9L>mrh6A cm3W >XsE mI?" mm"modoz m<mMg

,iO

~

-rE B nO-D;oOo5 8NoyEmmNC,n"~o<Pmn Z l-o' E=SaE L

.~7

>

ML19320B121

Text

Navigation menu

Search