ML20148E673

From kanterella
Jump to navigation Jump to search
Rev 2 to RXE-96-001, CPSES Unit 2 Cycle 3 Colr
ML20148E673
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 05/31/1997
From: Bosma J, Choe W, Maier S
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20148E657 List:
References
RXE-96-001, RXE-96-001-R02, RXE-96-1, RXE-96-1-R2, NUDOCS 9706030216
Download: ML20148E673 (13)
v • d • e


Text

'

l RXE-96-001, Rev. 2 )

CPSES UNIT 2 CYCLE 3 CORE OPERATING LIMITS REPORT May 1997 a

Prepared: Date: .

2S!i7 -

7 John T. Bosma Reactor Physics Approved:

  • Date E/A7/Y7 Stephen M. Maier Reactor Physics Supervisor Approved: Date: ) i Mh.e o. oe Safety alysis Manager l

l l

9706030216 970527 I PDR ADOCK 05000446 (

P PDR e

l

i l

DISCIAIMER

)

i The information contained in this report was prepared for the specific requirement of Texas Utilities Electric Company (TUEC),

and may not be appropriate for use in situations other than those for which it was specifically prepared. TUEC PROVIDES NO WARRANTY HEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING

BUT NOT I.IMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICUIAR PURPOSE.

By making this report available, TUEC does not authorize its use I I

by others, and any such use is forbidden except with the prior '

written approval of TUEC. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers.of warranties provided herein. In no event shall TUEC have any liability for any incidental or consequential i duages of any type in connection with the use, authorized or unauthorized, of this report or of the information in it.  !

11

COLR for CPIES Unit 2 Cycle 3 l

TABLE OF CONTENTS DISCIAIMER

................................................. il TABLE OF CONTENTS l

, ...........................n ............. iii LIST OF FIOURES iy i

, SECTION 1.0 CORE OPERATING LIMITS REPORT .......................... 1

, 2.0 OPERATING LIMITS ....... .............................. 2 1

2.1 MODERATOR TEMPERATURE COEFFICIENT 1

................ 2  ;

2.2 I SHUTDOWN ROD INSERTION LIl8IT ..................... 3 2

2.3 CONTROL ROD INSERTION LIMITS ..................... 3 2.4 AXIAL FLUX DIFFERENCE ............................ 3 i 2.5 HEAT FLUX HOT CHANNEL FACTOR l

..................... 4 l

2.6 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

, ......... 5 2.7 SHUTDOWN MARGIN .................................. 5 J

i

-1 2

1 a

9

'd d

4 iii 3

COLR fer CPSES Unit 2 Cycle 3 LIST OF FIGURES FIGURE PAGE 1

ROD BANK INSERTION LIMITS VERSUS THERMAL POWER ..... 6 2

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER ............................. 7 3

K(Z) - NORMALIZED Fg(Z) A8 A FUNCTION OF CORE HEIGHT

........................................ 8 4

W(Z) AS A FUNCTION OF CORE HEIGHT -

(10000 MWD /MTU - EOL) ............................... 9 iv

, . j COLR for CPSES Unit 2 Cycle 3

. l 1.0 CORE OPERATING LIMITS REPORT i i

This Core Operating Limits Report (COLR) for CPSES UNIT 2 CYCLE 3 has been prepared to satisfy the requirements of Technical.

l Specification'6.9.1.6.

The Technical specifications affected by this report are listed a below:

I l

3/4.1.1.1 Shutdown Margin - T m Greater Than 200'F  !

3/4.1.1.2 Shutdown Margin - Ty Less Than or Equal to 200"F I 3/4.1.1.3 Moderator Temperature Coefficient 3 /4 .1. 2 . 2 Flow Paths - Operating

, 3/4.1.2.4 Charging Pumps - Operating 3/4.1.2.6 Borated Water Sources - Operating 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits h

3/4.2.1 Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 9

W 4

4 1

COLR fcr CPSES Unit 2 Cyclo 3 I 2.0 OPERATING LIMITS The cycle-specific parameter ?.imits for the specifications listed i i

in Section 1.0 are presented in the following subsections. These f t

limits have'been developed using the NRC-approved methodologies ,

specified in Technical Specification 6.9.1.6b, Items 5, 6, 7, 8, !

9, 10, 11, 12, 13, 14, 15, 16, 17, and 19. I These limits have been determined such that all applicable limits of the safety analysis are met. I i

2.1 Moderator Temperature coefficient (Specification 3/4.1.1.3) ,

2.1.1 The Moderator Temperature-Coefficient (MTC) limits are:

The BOL/ARO/HZP-MTC shall be less positive than f

+5 pcm/ F.  !

The EOL/ARO/RTP-MTC shall be less negative than t

-40 pcm/'F. .

i 2.1.2 The MTC surveillance limit is: $

The 300 ppm /ARO/RTP-MTC should be less negative  !

than or equal to -31 pcm/ F. i where: BOL stands for Beginning of Cycle Life ,

ARO stands for All R ws Out i i

HZP stands for Hot Zero THERMAL POWER e EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2

1 l

l i

l

l ' COLR fcr CPSES Unit 2 Cycle 3 I i [

l l

2.2 shutdown Rad Insertion Limit (Specification 3/4.1.3.5) l 2.2.1 The shutdown rods shall be fully withdrawn.

l. Fully f

! withdrawn shall be the condition where shutdown l

rods are at a position within the interval of 222 1

and 231 steps withdrawn, inclusive. i 4

2.3. Control Rod Insertion Limits (Specification 3/4.1.3.6) j 2.3.1  !

1 The control banks shall be limited in physical  ;

i insertion as shown in Figure 1.

2.4 Axial Plux Difference (Specification 3/4.2.1) t r

2.4.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +5%, -12%.

l

-lRev.2 l 2.4.2 The AFD Acceptable Operation Limits are provided I

in Figure 2.

l t

I l

l l

\

l l

i.

I i ,

1 i i I

~

COLR far CPCE3 Unit 2 Cyclo 3 2.5 Heat Flux Hot channel Factor (Specification 3/4.2.2) l F,"

F,(Z) s [K(Z)] for P > 0.5

, P F,(Z) s 0.5

[K(Z)] for P s 0.5 where: P= THERMAL POWER RATED THERMAL POWER 2.5.1 Fg " = 2.40 1 lRev.

2.5.2 K(Z) is provided in Figure 3.

2.5.3 Maximum elevation dependent W(Z) values are given in Figurc 4 valid for a burnup Rev. 2 range of 10000 MND/MTU through EOL.

l 2.5.4 A constant 2% decrease in F, margin allowance shall be used to increase Fg(Z) C for compliance with the 4.2.2.2.f Surveillance Requirement for i all cycle burnups. l 1

l i

t 4

l r

. . . _ . . _ . . . . . _ __ . . . m ._m.. . _ ___. . __ _ _ _._ _ _ _ _ _ _ . . . _ . . _ . _ _ _ . . . . _ _ . . _ .

. j COLR for CPSES Unit 2 Cycle 3 2.6 Nuclear Enthal'w Rise Hot Chann=1 Factor .

(Specification.3/4.2.3)

{

F" , s F" , [1 + PF , (1-P)]

where: P= TimDRAL POWER RATED THERMAL POWER 2.6.1 F", = 1.55 2.6.2 PF. = 0.3 J

i 2.7 Shutdown Marain 2.7.1 Shutdown Marain - T_ Greater Than 2 0 0*F -

(Specifications 3/4.i.1.1, 3/4.1.2.2, 3 /4 .'1. 2 . 4 , and 3/4.1.2.6)

The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k in MODES 1, 2, 3, and 4.

2.7.2 Shutdown Maruin - T_ Less Than or Eaual to 200*F (Specification 3/4.1.1.2) i l

The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k in MODE 5.

I

! 1 l

5 l

l

- ., i

COLR fer CPSES UNIT 2 CYCLE 3 FIGURE 1 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240

' i ,

t i

I 220 j

' (17.1,222) ' (73.1,222) j p  !

/ i

/

/ +

  1. I /

200 n ,7

(~~ l 'i BANK B 4

/

ft '

1 l h h(0,187) ,

e 180 ,

f'  !

q u ' '

,cs l 1 \

M . 7 \

sr i

m 160 s 3 (100, 162))'

t

/ i -

, . f r f a s e 140

/ '

a j BANK C l

, st , [

a /

1 i

/

120 f r

, ',- f 2 j ., /,

O /

1

/ )/ '

H 100 f /

tn /

/ ,' f O / r m 1 2./ \

80 }  ;

f,

. f /, , \

-(0,72) '

, / I BANK D 60 ..__._

I a f O /

.! og

/

40 '

~ f J

/

20 , f

/

(21,0) /

l ''# i 0 '

O 10, 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER

, NOTES: 1. Fully withdrawn shall be the condition where control rods are at a position within the interval ~ 222 and 231 steps withdrawn, inclusive.

2. Control Bank A shall be fully withdrawn.

i 6

T

COLR for CPSE2 UNIT 2 CYCLE 3 FIGURE 2 AXIATa FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 , ,  ;

i i I

(-16,90) (9,90)

NO

} \

\

/ \ __

- UNACCEPTABLE - \

UNACCEPTABLE --

CPERATION [ \

OPERATION ~~

1 1 1/ \

l / ... \

/ 1 4 f a p: \

70 / ACCEPTABLR i (

/ OPERATION _l _\ l 0 / \  !

88

/ \1 g ./ Y

/ \

/ \

/ \

/ \

I '

O b

50 ,

~'(-3 4,5 0) f (33,50)-

I O 40

~

0 30 20 i

10 '

l

- 0 1

-40 -30 -20 -10 0 10 20 30 40 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%)

7 I

U

I .

COLR for CPSES UNIT 2 CYCLE 3 FIGURE 3 K(2) - NORMALIEED FQ (2) AS A FUNCTION OF CORE REIGHT j i

1.1 l I l l

( 0 . 0,1, 0 ) ( 6. 0,1. 0) 1 '

O.9 (12.0,0.925)2 l' 1 l

_ 0. 8 0 '

k 0.7 .i a

N'O.6 '

O.5 O.4 5

W 0.3 0.2 0.1 0

'O 1 2 3 4 5 6 7 8 9 10 11 12 go.r'roN CORE HEIGHT (FEET) .f07 Axial . Axial Axial Axial Node K(E) . Node K(5) Node K(E) Node K(E) 1 - 31 1.0000 39 0.9800 47 0.9600 55 0.9400 32 0.9975 40 0.9775 48 0.9575 56 0.9375 33 0.9950 41 0.9750 49 0.9550 57 0.9350 34 0.9925 42 0.9725 50 0.9525 58 0.9325 35 0.9900 43 0.9700 51 0.9500 59 0.9300 j 36 0.9875 44 0.9675 52 0.9475 60 0.9275 1 37 0.9850 ' 45 0.9650 53 0.9450 61 0.9250-38 ~0.9825 46 0.9625 54 0.9425 Core Neight (f t) e (Mode - 1)

  • 0.2 8

I i

e COLR fsr CPSES UNIT 2 CYCLE 3 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (10000 MWD /MTU - EOL) 1.30 I i I i i i

' i 1.25 I I 1.20 i (

Q \  !

~ \ i i

  • g -

E 1.15 N ' i

\ l s%

1.10 \ / \ l

\ -

/ '

\_/

1.05 l i

?

1.00

] 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 BOTTOM CORE HEIGHT (FEET) i TOP  !

1 Axial Axial Axial Axial Nude W(E) Mode W(Z) Node W(E) Node W(1) 1 - 10 --- 21 1.131 32 1.089 43 1.114 11 1.196 22 1.127 33 1.088 44 1.111 4

12 1.190 23 1.124 34 1.089 45 1.105 13 1.183 24 1.121 35 1.093 46 1.098 14 1.176 25 1.118 36 1.099 47 1.091

. 15 1.168 26 1.114 37 1.104 48 1.088 16 1.160 27 1.110 38 1.108 49 1.090

. 17 1.153 28 1.106 39 1.110 50 1.095

, 18 1.146 29 1.101 40 1.112 51 1.102 19 1.141 30 1.097 41 1.114 52 - 61 ---

20 1.136 31 1.092 42 1.115 l

l Core Neight (ft) = (Node - 1)

  • 0.2

' 9 Rev. 2 i l

, --. l

Retrieved from "https://kanterella.com/w/index.php?title=ML20148E673&oldid=2848264"