ML20117H549

Rev 0 to Toed Davis-Besse Unit 1 Cycle 11 Colr

ML20117H549
Person / Time
Site:	Davis Besse
Issue date:	05/22/1996
From:	CENTERIOR ENERGY
To:
Shared Package
ML20117H538	List: ML20117H535 ML20117H549 ML20117H571
References
NUDOCS 9605280250
Download: ML20117H549 (24)

Text

1

%. ' Enclosure 1 4

COLR f

Page 1 of 24 1

I Revision.0 i

l l

l I

i

(

' TOLEDO EDISON COMPANY DAVIS-BESSE UNIT'l

~

CYCLE 11 CORE OPERATING LIMITS REPORT I

i-l 1

L LIST OF EFFECTIVE PAGES Page C-1.through C-24 Rev. O

!~

l l-9605280250 960322 PDR ADOCK 05000346 P

PDR C-1

._m

~ -_.

l e

l COLR Page 2 of 24 Revision 0 l

4 Technical Specification /COLR Cross-Reference l

Technical Specification COLR Figure / Table 3.1.3.6 Figure la Regulating Group Position and Alarm Setpoints, O to 300 3.1.3.8 110 EFPD, Four RC Pumps

{

l 3.1.3.6 Figure Ib Regulating Group Position and Alarm Setpoints, 300 110 3.1.3.8 to 610 110 EFPD, Four RC 4

Pumps l

3.1.3.6 Figure 1c Regulating Group Position and Alarm Setpoints, after 610 3.1.3.8 110 EFPD, Four RC Pumps 3.1.3.6 Figure 1d Regulating Group Position and Alarm Setpoints, O to 300 110 3.1.3.8 EFPD, Three RC Pumps 3.1.3.6 Figure le Regulating Group Position and Alarm Setpoints, 300 110 3.1.3.8 to 610 110 EFPD, Three RC Pumps l

3.1.3.6 Figure if Regulating Group Position l

l and Alarm Setpoints, after 610 l

3.1.3.8 110 EFPD, Three RC Pumps 3.1.3.7 Figure 2 Control Rod Core Locations and Group Assignments I

3.1.3.9 Figure 3 APSR Position Alarm Setpoints 3.2.1 Figure 4a AXIAL POWER IMBALANCE Alarm Setpoints, 0 EFPD to 300 i10 EFPD, Four RC Pumps l'

3.2.1 Figure 4b AXIAL POWER IMBALANCE Alarm Setpoints, 300 110 EFPD to 610 110 EFPD, Four RC Pumps 4

C-2

COLR j.

Page 3 of 24 Revision 0 l

3.2.1 Figure 4c AXIAL POWER IMBALANCE L

Alarm Setpoints, after 610 110 l

EFPD, Four RC Pumps 3.2.1 Figure 4d AXIAL POWER IMBALANCE Alarm Setpoints, 0 EFPD to 300 i

110 EFPD, Three RC Pumps 3.2.1 Figure 4e AXIAE, POWER IMBALANCE Alarm Setpoints, 300 *10 to 610 t10 EFPD, Three RC Pumps 3.2.1 Figure 4f AXIAL POWER IMBALANCE Alarm Setpoints, after 610 110 EFPD, Three RC Pumps 2.1.2 Figure 5 AXIAL POWER IMBALANCE Protective Limits 2.2.1 Figure 6 Flux - A Flux / Flow (or Power /

Imbalance / Flow) Trip Setpoints 3.2.4 Table 1 QUADRANT POWER TILT Limits 3.1.1.3c Table 2 Negative Moderator Temperature Coefficient Limit B2.1 Table 3 Power to Melt Limits 3.2.2 Table 4 Nuclear Heat Flux Hot Channel Factor - Fg 3.2.3 Table 5 Nuclear Enthalpy

'se Eot Channel Factor -

AH 3.2.3 Figure 7 Allowable Radial Peak for F AH l

l l

C-3

COLR Page 4 of 24 Revision 0 TOLEDO EDISON DAVIS-BESSE UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 11 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7.

The core operating limits have been developed using the methodology provided in reference 2.0 (1).

The following cycle-specific core operating limits, Protective Limit and Flux -/A Flux / Flow Reactor Protection System Setpoints are included in this report:

1)

Regulating Group Position Alarm Setpoints (insertion limits) and Xenon reactivity

" power level cutoff" 2)

Rod program group positions (Control Rod Core locations and group assignments)

3) Axial Power Shaping Rod Alarm Setpoints (insertion lindts)

4) AXIAL POWER IMBALANCE Alarm Setpoints

5) AXIAL POWER IMBALANCE Protec.ive Limits 6)

Flux-A Flux / Flow (or Power / Imbalance / Flow) Trip Setpoints 7)

QUADRANT POWER TILT limits

8) Negative Moderator Temperature Coefficient limit

9) Nuclear Heat Flux Hot Channel Factor, F and g

10) Nuclear Enthalpy Rise Hot Channel Factor, F AH 2.0 References (1)

BAW-10179P-A, Revision 1, " Safety Criteria and Methodology of Acceptable Cycle Reload Analysis."

C-4

COLR Page 5 of 24 Revision 0 Figure la RegulatinD Group Position Alarm Setpoints 0 to 300110 EFPD, Four RC Pumps-Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power I.evel f

Cutoff = 100%

r u

90.

l s

Unacceptable j

80 Operation

/

j l

' Operation Restricted 70

^

i o

a.

60 1

m

Shutdown

/

g j

Mamin 5

50 Limit f

jz; r

40

/

t

(

j j

Acceptable Operation 3

30 i

/'-

5

\\

/ "

?'

o.

20 e

r l

/

n.

10

~

s 0'.f 0

25 50 75 100 125 150 175 200 225 250 275 300 Rod index (% Withdrawn) 0 75 100 l

I I

Group 5 0

25 75 100 l

I Group 6 0

25 100 l

l l

Group 7 Note 1: A Rod Group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these setpoints.

C-5

COLR Page 6 of 24 e

Revision 0 FiDure Ib Regulating Group Position Alarm Setpoints 300110 to 610110 EFPD, Four RC Pumps-Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level

~

f Cutoff = 1(0%

I j

I Unacceptable

[

90 j

Operatiori

/

80 j

s i

^

70 Operation 60 Ftstrictea g

Shutdown

/

f 3

f 50 M*'9 "

m Umit

s 40

/

Acceptable 3

30 f, -"

Operation s

S 20 g

/

n.

10 j

0' 0

25 50 75 100 125 150 175 200 225 250 275 300 Rod index (% Withdrawn) 0 75 100 I

I Group 5 3

5 75 1 X)

Group 6 0

5 1 X)

Group 7 Note 1: A Rod Group overlap of 2515% between sequential withdrawn groups 5 and 6 and 6 and 7, shall be maintained.

Note 2 Instrument error is accounted for in these setpoints.

C-6

COLR Page 7 of 24 Revision 0 4

Figure Ic Regulating Group Position Alarm Setpoints After 610110 EFPD Four RC Pumps-l Davis-Besse 1, Cycle 11 1

This Figure is referred to by Technical j.

Specifications 3.1.3.6 and 3.1.3.8 110 100 Power Level

/ /

-~

Cutoff = 1 C0%

/

/

' [

90 Unacceptable

/

/

80 Onemtion

/

/

i e

r

~

.r i

70

/

' Operation 2

Shddown

/

te strMe 60

^

j Margin l

ymit N

/

s '

5 50 i

iE

./

O 40 1,

j Acceptable

}

y.d7 Operation 30 r

y 7

e.

20 l

l

. /

a 10 0"

0 25 50 75 100 125 150 175 200 225 250 275 300 Rod index (% Withdrawn) 0 75 100 l

I I

Group 5 3

25 75 1 30 Group 6 0

25 1 X) l Group 7 Note 1: A Rod Group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be m6dained.

Note 2: Instrumerd error is accounted for in these setpoints.

C-7

COLR Page 8 of 24 e

Revision 0 Figure ld Regulating Group Position Alarm Setpoints 0 to 300110 EFPD, Three RC Pumps-Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 90 80 ::: Power Level i

5: Crdoff = 75% :: : Unacceptable

/

[

Owat ce l

60 7

h

Shutdown Operation 50

Margin f

Restrictej Limit w

i 40

/

i f

~

"~

3 30

(

/

x 5

j Acceptable E

20 j -V Operation i

n.

10 2"7

~

0' O

25 50 75 100 125 150 175 200 225 250 275 300 Rod index (% Withdrawn) 0 75 100 I

I I

Group 5 3

25 75 1 30 Group 6 0

5 1 X)

Group 7 Note 1: A Rod Group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these setpoints.

C-8

i COLR e

Page 9 of 24 Revision 0 Figure le Regulating Group Position Alarm Setpoints 300110 to 610110 EFPD, Three RC Pumps -

Davis-Besse 1 Cycle 11 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8

)

110 100 90 80 ;;: Power Level n

C Acf = 75%

Unacceptable i

70 operation

[

2 60 f

s 5

50 Operation ig Shutdown

,2 ggg l

o Margin.

/

40 f

mit 2

30 i

\\

g n

/

n e

9

/1 Acceptable E.

20 jL P Operation u

g s

a 10 s-0" 0

25 50 75 100 125 150 175 200 225 250 275 300 Rod index (% Withdrawn) 0 75 100 I

I I

Group 5 3

5 75 1 X)

Group 6 0

25 1 X) j Group 7 Note 1: A Rod Group overiap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be mairdained.

d Note 2; instrument error is accounted for in these setpoints.

l C-9

COLR Page 10 of 24 Revision 0 q

}

Figure if Regulating Group Postion Alarm Setpoints After 610110 EFPD,Three RC Pumps -

Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 I

110 100 t

i 90 80 ;;: Power Level

=

O doff = 75%

/

/

70 g

Unacceptable-f g

1 5

Operation

/

/

2 60

/

/

g j

5 50

/

Operation Shutdown Margin

/

Rm;trictecLL 40 Umit m

W'-

s

~

1 d'

A 30

\\

1 1g i

f.,-

Acceptable E

i s

20 3#

Operation s^~'

n.

10 f

.nnn"s 0"

0 25 50 75 100 125 150 175 200 225 250 275 300 Rod index (% Withdrawn) 0 75 100 l

l Group 5

)

25 75 1M Group 6 0

25 1E I

Group 7 Note 1: A Rod Group overlap of 2515% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these setpoints.

C-10

COLR Page 11 of 24 Revision 0 Figure 2 Control Rod Core Locations and Group Assignments DaWs-Besse 1, Cycle 11 This Figure is referred to by Technical Specifications 3.1.3.7 N

X l

A B

4 6

4 C

2 5

5 2

D 7

8 7

8 7

E 2

5 5

2 F

4 8

6 3

6 8

4 G

5 1

1 5

H 6

7 3

4 3

7 6

w y

K 5

1 1

5-L 4

8 6

3 6

8 4

M 2

5 5

2 N

7 8

7 8

7 0

2 5

5 2

P 4

6 4

R I

Z 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 Group No. of Rods Function X

Group Number 1

4 Safety

^2 8

Safey 3

4 Safety 4

9 Safety 5

12 Control 6

8 Conhol 7

8 Control

)

8

_Q_

APSRs

]

Total 61 C-11

COLR

)

Page 12 of 24 Revision 0 Figure 3 APSR Position Alarm Setpoints This Figure is teferred to by Technical Specification 3.1.3.S Before APSR Pull- 0 EFPD to 610 +/- 10 EFPD, Three or Four RC pumos operation

• Lower Setpoint: 0%WD Upper Setpoint: 100 %WD After APSR Pull - 610 +/- 10 EFPD to End-of-Cycle Three or Four RC pumps operallon'

~

Insertion Prohibited per Tech Spec 3.1.3.9

• Power restricted to 77% for 3 pump operation C-12

COLR Page 13 of 24 Revision 0 Figure 4a AXIAL POWER IMBALANCE Alarm Setpoints 0 to 300110 EFPD, Four RC Pumps-Dans-Besse 1. Cycle 11 This Figure is referred to by Technical Specification 3.2.1 i10 RESTRICTED j'

/

iOO g

~_IREGION f

4 1

i i

I 1

[

f 90 a

n

[

/

\\

/

t j

50 i

/

j I

I,

-70 i

f I

I

/

RESTRICTED.--

k-

-60 REGION s

s

-J J

}

l

\\

b 50 h

i,

'i

[

g 40-t

=s j'

E 30

'l i

i i,

ti n.

~

7 a

f 20-j

~

OPERATING PERMISSIBLE i

Ii REGION i

i 10 y

n!

si si j

J I'

E' al

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL POWER IMBALANCE %

LEGEND FULL INCORE

_EXCORE_ _ _

Note 1: Instrument error is accounted for in these se' points C-13

COLR Page 14 of 24 Revision 0 Figure 4b AXIAL POWER IMBALANCE Alarm Setpoints 300110 to 610110 EFPD, Four RC Pumps-Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specification 3.2.1 1

'10 gt a,_g i,__

r e

i i

100

___ RESTRICTED _

r g

/

/

(

l

---REGION V

/

90

/

l s

[

80 I

I I

I f

r s

C 70 s

i i

^

t

/

RESTRICTED.--

2 60 REGION

-~

e a

s 3

i u

Ri 50 g

o I

id a

ba 40 f-

}

l t*

v j'

,+

b----3C l

t

.y 1

i' t

I I

p

-PERMISSIBLE -

1 OPERATING s

s REGION 10

.i af 6

=

J, Ii I I'

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL POWER IMBALANCE %

LEGEND FULL INCORE

_EXCORE_ _ _

Note 1: Instrument error is accounted for in these setpoints C-14

COLR Page 15 of 24 Revision 0 Figure 4c AXIAL POWER IMBALANCE Alarm Setpoints ARer 610.t10 EFPD, Four RC Pumps -

Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specification 3.2.1 i10 Z: RESTRICTED

[

oo g

REGION r

t 1

A o

I

\\

l

/

90

)

f I

as L

s n

n k

[

GO-i f

t a

r i

__.-_* ' -d r

70 i

a n

I E

J RESTRICTED---

l

-60 l

REGION s

-d 3

i i

-50

)

]-

r o

I g

i g.

_40 o,

E. '

I i

i m

1 20 PERMISSIBLE i

I OPERATING REGION g

10 e

s ni al l

50

-40

-30

-20

-10 0

10 20 30 40 50 AXtAL POWER IMBALANCE %

LEGEND FULL INCORE

.E._XCOR,E_ _ _

Note 1: Instruinent erroris accounted for in these setpoints C-15

COLR Page 16 of 24 e

Revision 0 Figure 4d AX1AL POWER IMBALANCE Alarm Setpoints 0 to 300110 EFPD,Three RC Pumps-Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specification 3.2.1 i10 iOO 90

^3 RESTRICTED REGION

/

[

j I

a s

v J'

n

/

/

RESTRICTED.--

k-

- 80 REGION i

=

r r

.g 3

j E.

i 3o F

=

Q l

a e

i i

g 40 5

a 6

i M

e i

o.

i PERMISSIBLE l

I OPERATING I

REGION 10 e

i i

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXtAL POWER IMBALANCE %

LEGEND FULL INCORE

_EXCORE_ _ _

Note 1: Instrument error is accounted for in these setpoints C-16

~

COLR Page 17 of 24 Revision 0 Figure 4e AXIAL POWER IMB'iANCE Alarm Setpoints 300110 to 610110 EFPD, Three RC Pumps -

Davis-Besse 1, Cycle 11 This Figure is referred to by Technical Specification 32.1 l

i10 l

100 l

\\

30 33 RESTRICTED j

j j

t REGION

/

t 70

)

i f

/

\\

^

s j'

=

1 RESTRICTED.--

j k-

- 50 s

REGION r

r 4

=

i i

i ifi.

i

_30 l

?

i n

l h

40 I

g._L 6

30 l

a i

l 20 PERMISSIBLE I

i OPERATING REGION l

l 10 I

i l

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL POWER IMBALANCE %

LEGEND FULL INCORE 4

_EXC_ ORE _ _ _

Note 1: Instrument error is accounted for in these setpoints C-17

COLR Page 18 of 24 Revision 0 Figure 4f AXIAL POWER IMBALANCE Alarm Setpoints ARer 610110 EFPD,Three RC Pumps-Davis-Besse 1. Cycle 11 This Figure is referred to by Technical Specification 3.2.1 i10 100 4

L i

j M

l RESTRICTED j

f g

i

~

REGION

/

-50 j

j r

s J

n

=

[

P

~

RESTRICTED.--

2

/

k'-

" 50 l

REGION I

l h

i J

i E.

j i

i

_so Y

h o

i 40 I

i r

3 i

k i

I n.

1 l

20 PERMISSIBLE l

i OPERATING REGION i

10 l

0 I

I i

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXtAL POWER IMBALANCE %

LEGEND FULL INCORE

_EXC_ ORE _ _ _

Note 1: Instrument erroris accounted for in these setpoints C-18

COLR Page 19 of 24 Revision 0 l

Figure 5 AXIAL POWER IMBALANCE Protective Limits l

This Figure is referred to by Technical Specification 2.1.2

% RATED THERMAL POWER

- - 120 i

4 PUhF UMIT I

}

(-50.48,112) 110

- 100 (71.33,100.00 )

3 PUMP LIMIT

(-50.48,89.80)

(55.34,89.80) j 80 (71.33,77.80

(-78.66,72.72

- 70

)

- 60

(-76.66, 50.52;

-- 50

-- 40 30 UNACCEPTABLI UNACCEPTABLE OPERATION ACCEPTABLE OPERATION

-- 20 FOR SPECIFIED RC PUMP COMBINATION

-- 10 l

I I

I I

I I

I I

I I

I I

I I

I 70 50 30 10 0

10 20 30 40 50 60 70 80 AXIAL POWER IMBALANCE, %

Required Measured Reactor Coolant Flow to Ensure Pumos Operatina Flow. com Compliance. aom 4

380,000 389,500 3

283,860 290,957 C-19

i

\\

COLR e

Page 20 of 24 Revision 0 Figure 6 F l ux-- A F l u x/Fl ow (or Power / Imbalance / Flow)

Trip Setpoints This Figure Is referred to by Technical Specification 2.2.I 110 gi,igigi s

litt1ill N

i,___

e

/

4 PUMP

\\

LIMIT 100 r

3 I

T l

\\

90

(

(

L

\\

80

,,q s

/

s T

/

Curve shows trip

\\

• M setpoint for on approximately j

t 25% flow reduction s

for three pump s

eratlon o$83.860gpm).

M M

(

s

'E The actua[ setpoint 3 PUMP

\\

will be calculated l

d by the Reactor EXAMPLE N

M Protection System w

and will be directly I

o proportional to the A

actual flow with three pumps.

UNACCEPTABLE-OPERATION UNACCEPTABLE OPERATION 3g l

1 20 ACCEPTABLE j

OPERATION FOR SPECIFIEO RC PUMP COMBINATION 10 i

i i

l 0

-40

-35

-30

-25

-20

-15

-10

-5 0

5 10 15 20 25 30 35 40 Axial Power Imbalance, %

1 c-20 1

COLR Page 21 of 24 Revision 0 Table 1 OUADRANT POWER TILT Limits This Table is referred to by Technical Specification 3.2.4 Steady-state Steady-state Limit for Limit for QUADRANT POWER TILT THERMAL THERMAL Transient Maximum as measured by:

POWER s 60%

POWER > 60%

Limit Limit

(%)

(%)

(%)

(%)

Symmetrical Incore 6.8 4.1 10.03 20.0 detector system Table ?

Heantive Moderntor Tamnerature coefficient Limit This Table is referred to by Technical Specification 3.1.1.3c Negative Moderator Temperature

-4x10%k/k/F Coefficient Limit (at RATED THERMAL POWER)

Table 3 Power to Melt Limits This Table is referred to by Technical Specification Bases B2.1 l

. l Batch 9E Batch 11c/11A Batch 12B Batch 13A/13B Fuel Assembly Type Mark-B8A Mark-B8B Mark-B10AZL Mark-B10A Minimum linear heat. rate to melt, kW/ft 20.5 22.3 22.3 22.3 1

l C-21

i COLR Page 22 of 24 Revision 0 Table 4 Nuclear Heat Flur Hot channel Factor - P g This Table is referred to by Technical specification 3.2.2 Heat Flur Hot channel Factor Fg Fo shall be limited by the following relationships:

Fo $ LHR"""( Bu ) / [ LHR""

• P }

(for P $ 1.0) l LHR""*'(Bu):

See the Tables below LHR*" = 6.139 kW/f t for Mark-B8A fuel LHR"" = 6.253 kW/f t for Mark-B8B fuel,

LHR"" = 6.253 kW/f t for Mark-B10AEL fuG1 LHR*" = 6.253 kW/f t for Mark-B10A fuel 1

P = ratio of THERMAL POWER / RATED THERHAL POWER l

Bu = Fuel Burnup (mwd /mtU) 1 i

Batch 9E fMark-BBA) 7 MR^"*' kW / f t(*8 24,500 60,000 Axial senment mwd /mtp mwd /mtU 1

12.8 8.4 2

15.2 9.9 3

15.7 10.5 4

15.8 10.5 5

16.4 10.5 6

17.0 10.5 l

7 16.2 10.0 j

8 13.6 8.4 Batch 11A (Mark-B8B) Y.Mpaum' kW/ f t'*I l

Less than 40,000 47,016 47,557 49,180 55,000 60,000 Arial Senment mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU 1

12.9 12.4 12.4 12.4 10.2 10.0 2

15.3 14.7 14.7 14.6 12.1 11.8 3

16.2 15.6 15.6 15.5 12.8 12.5 4

16.2 15.6 15.6 15.5 12.8 12.5 5

16.2 15.6 15.6 15.5 12.8 12.5 6

16.6 16.0 16.0 15.5 12.8 12.5 1

j 7

16.2 15.6 15.4 14.7 12.2 11.9 8

13.6 13.1 12.9 12.4 10.2 10.0

\\

C-22

COLR Page 23 of 24 Revision 0

\\.

i Table 4 Nuclear Heat Flur Hot Channel Factor - F Batch 11C (Mark-BBB) 7.HRAume kW / f t '3 i

Less than 40,000 47,016 47,557 49,180 55,000 60,000 Arial Semnant mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU 1

12.9 12.4 12.4 12.4 10.2 10.0 r

l 2

15.3 14.7 14.7 14.6 12.1 11.8 l

3 16.2 15.6 15.6 15.5 12.8 12.5 i

4 16.2 15.6 15.6 15.5 12.8 12.5 5

16.2 15.6 15.6 15.5 12.8 12.5 6

16.6 16.0 16.0 15.5 12.8 12.5 7

16.2 15.6 15.4 14.7 12.2 11.9 8

13.6 13.1 12.9 12.4 10.2 10.0 l

i Batch 12B (Mark-B10AEL) T.MRAum' kW/ f t *I I

l Less than 40,000 47,016 47,557 49,180 55,000 60,000 Arial Samaant mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU mwd /mtU 1

12.9 12.4 12.4 12.4 10.2 10.0 2

15.3 14.7 14.7 14.6 12.1 11.8 3

16.2 15.6 15.6 15.5 12.8 12.5 4

16.2 15.6 15.6 15.5 12.8 12.5 5

16.2 15.6 15.6 15.5 12.8 12.5 6

16.6 16.0 16.0 15.5 12.8 12.5 7

16.2 15.6 15.4 14.7 12.2 11.9 8

13.6 13.1 12.9 12.4 10.2 10.0 f HR um, kW / f t "3 A

I Batchen 13 A & B (Mark-B10A1 Less than 20,000 35,000 ArIal Semnane mwd /mtU mwd /mtU 1

13.6 12.9 2

16.0 15.3 3

17.2 16.2 4

17.5 16.2 5

17.5 16.2 6

17.8 16.6 l

7 17.4 16.2 j

8 14.6 13.6

'. ~

Linear interpolation for allowable linear heat rate between specified burnup points is valid for these tables.

4 4

C-23 3

1 4

COLR j

9 Page 24 of 24 Revision 0 i.

i l

Table 5 Nuclear Enthalov Rise Hot Channel Factor - d This Table is referred to by Technical specification 3.2.3 l

Enthalov Rise Hot Channel Factor F5

~

fa $ ARP (1 + 0.3 (1 - P/P.) ]

1 ARP = Allowable Radial Peak, see Figure P = THERMAL POWER / RATED THERMAL POWER and P $ 1.0 1

P, = 1.0 for 4-RCP operation P, = 0.75 for 3-RCP operation i

Figure 7 Allowable Radial Peak for fa 1

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• 112.48":

1.4 l.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak

• Based on an active core height of 140.6 inches. Linear interpolation and extrapolation above 112.48 inches are acceptable. For axial heights <28.12 inches, the value at 28.12 inches will be used.

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C-24