ML20065M075

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Rev 3 to CNEI-0400-24, Catawba Unit 1 Cycle 8 Colr
ML20065M075
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 04/14/1994
From: Clark R, Hager N, St Clair R
DUKE POWER CO.
To:
Shared Package
ML20065M071 List:
References
CNEI-0400-24, CNEI-0400-24-R03, CNEI-400-24, CNEI-400-24-R3, NUDOCS 9404220226
Download: ML20065M075 (19)
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CMFI44)-24 Page 1 of 154 Rev.3

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Catawba Unit 1 Cycle 8 Core Operating Limits Report April 1994 Duke Power Company DATE PREPARED BY:

-M.'M db (le, 4 - / L/ '?'l

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d-Y~lV-W CHECKED BY:

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APPROVED BY:

/C/Ebtad-V-/V-7V

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QA CONDITION I NOTE i

This document does not contain information that affects the results and conclusions presented in the CIC8 Reload Report, Safety Analysis.

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Catawba' 1 Cycle 8 Core Operating Limits Report CNElem0-24 Page 2 of 154 Rev.3 l

INSERTION SHEET Remove EE pages 1-15, rev. 2 pages 1-14,15 A,158, 15C,15D,15E rev. 3 1

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Catawha 1 Cycle 8 Core Operating 1.imits Report CNEI4M00-24 Page 3 of 154 Rev.3 REVISION LOG Revision Effective Date Comment Original Issue 8 September 1992 CIC7 COLR Revision 1 10 October 1992 ClC7 COLR rev.

Revision 2 1 December 1993 CIC8 COLR Revision 3 14 April 1994 CIC8 COLR rev.

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1 Catawba 1 Cycle 8 Core Operating Limits Report CNE14)400-24 Page 4 of 154 Rev.3 1.0 Core Operating Limits Report This Core Op.: rating Limits Report (COLR) for Catawba Unit 1, Cycle 8 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.

The Technical Specifications affected by this report are listed below:

2.2.1 Reactor Trip System Instrumentation Setpoints 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.2.5 Borated Water Source - Shutdown 3/4.1.2.6 Borated Water Source - Operating 3/4.1.3.5 Shutdown Rod insertion Limit 3/4.1.3.6 Control Rod Insertion Limit 3/4.2.1 Axial Flux Diffemnce 3/4.2.2 Ileat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3/4.3.3.11 Baron Dilution Mitigation System 3/4.5.1 Accumulators 3/4.5.4 Refueling Water Storage Tank 3/4.9.2 Instrumentation 4

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Catawha I Cycle H Core Operating 1 imits Report CNEl.0400 24 Page 5 of 154 Rev.3 4

1.1 Operating 1.imits

'Ihe cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using NRC-approved' methodologies specified in Technical Specification 6.9.1.9.

l-2.0 Reactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.1 Overtemperature AT Setpoint Parameter Values Parameter Value i

Overtemperature AT reactor trip setpoint K = 1.1954 i

Overtemperature AT reactor trip heatup setpoint K = 0.03371/oF 2

penalty coefficient Overtemperature AT reactor trip depressurization K = 0.001529/ psi 3

setpoint penalty coefficient Measured reactor vessel ATlead/ lag time t = 12 sec.,

i constants 1 = 3 sec.

2 Measured ATlag time constant T = 0 sec.

3 Measured reactor vessel average temperature T = 22 sec.,

4 lead / lag time constants is = 4 sec.

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. Measured reactor vessel average temperature lag T = 0sec, 3

time constant f (AI) " positive" breakpoint

= 8.0% Al i

f,(A1) " negative" breakpoint

= -42.0% Al f (AI) " positive" slope

= 1.640% ATg % Al i

f (Al) " negative" slope

= 3.672% ATg % Al l

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Catawha 1 Cycle 8 Core Operating Limits Report CNEl-04CD-24 Page 6 of 154 Rev.3 2.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K = 1.0855 4

Overpower AT reactor trip heatup setpoint penalty 1( = 0.001262/oF coefficient (for T > 590.8 aF)

Overpower AT reactor trip heatup setpoint penalty K = 0.0/aF 6

coefficient (for Ts 590.8 aF)

Measured reactor vessel AT lead / lag time t = 12 sec.,

i constants 1 = 3 sec.

2 Measured ATlag time constant T = 0 sec.

3 Measured reactor vessel average temperature lag 1 = 0sec.

6 time constant Measured reactor vessel average temperature rate-t, = 10 sec.

Jag time constant f (AI) " positive" breakpoint

= 35.0% Al 2

f (AI) " negative" breakpoint

= -35.0% Al 2

f (AI) " Positive" slope

= 7.0% ATd % Al 2

I f (A1) " negative" slope

= 7.0% ATd % Al 2

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P Catawba 1 Cycle 8 Core Operating 1,imits Report CNEl-0400-24 Page 7 of 154 Rev.3 3.0 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 3.0.1 The Moderator Temperature Coefficient (MTC) Limits are:

The MTC shall be less positive than the limits shown in Figure 1. The BOC, ARO, 1-lZP MTC shall be less positive that 0.7

  • 10-4 AK/K/'F.

The EOC, ARO, RTP MTC shall be less negative that -4.l* 10 4 AK/K/'F.

3.0.2 For the MTC Surveillance Limit:

The 300 PPM /ARO/RTP MTC should be less negative than or equal to -3.2

  • 10-4 AK/K/'F.

Where:

BOC stands for Beginning of Cycle EOC stands for End of Cycle ARO stands for All Rods Out 11ZP stands for llot Zero (Thermal) Power RTP stands for Rated Thermal Power 4

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9 Catawba 1 Cycle H Core Operating Limits Report CNEl-0400-24 Page 8 of 154 Rev.3 1

0.9 -

o,g.

Unacceptable Operation C

07 0

0.6 -

.5g 0.5 -

E y'0'4~

Acceptable Operation g 0.3 -

0.2 -

0.1 0

l l

l 0

10 20 30 40 50 60 70 80 90

.100 Percent of Rated Thermal Power i

Figure 1

.i Moderator Temperature Coefficient Versus Percent of Rated Thermal Power br

Cntawba 1 Cycle 8 Core Operating Limits Report CNE14)400-24 Page 9 of 154 Rev.3 3.1 llornted Water Source - Shutdown (Specification 3/4.1.2.5) 3.1.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 5 & 6:

Parameter Limit Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.5a Boric Acid Storage System minimum contained 2,000 gallons water volume for LCO 3.1.2.5a Boric Acid Storage System minimum water volume 585 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron 2,175 ppm concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum contained 45,000 gallons water volume for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,175 ppm e

Catawba 1 Cycle 8 Core Operating Limits Report CNEl-N00-24 Page 10 of 154 Rev.3 3.2 llorated Water Source - Operating (Specification 3/4.1.2.6) 3.2.1 Volume and baron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, & 4:

Parameter Limit Boric Acid Storage System minimum baron 7,000 ppm concentration for LCO 3.1.2.6a Boric Acid Storage System minimum contained 22,000 gallons water volume for LCO 3.1.2.6a Boric Acid Storage System minimum water volume 9,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum baron 2,175 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank minimum contained 363,513 gallons water volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,175 ppm 3.3 Shntdown Rod Insertion Limit (Specification 3/4.1.3.5) 3.3.1 The shutdown rods shall be withdrawn to at least 222 steps.

o 3.4 Control Rod Insertion Limits (Specification 3/4.1.3.6) 3.4.1 The control rod banks shall be limited to physical insertion as shown in Figure 2.

3.5 Axial Flux Difference (Specification 3/4.2.1) 3.5.1 The Axial Flux' Difference (AFD) Limits are provided in Figure 3.

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Catawba I Cycle H Core Operating Limits Report CNIII (M(M)-24 Page 11 of 154 Rev.3 Fully Withdrawn (29,1 %,230)

(Maximum m 230)\\

(79.6%,230)

,,0 m

Fully Withdrawn 200 --

(Minimum = 222)

II ANK 11 180 --

g (100 %,161) j160--(0%,163)

G g,140--

Dj llANK C 7 120 --

e

]100--

l 1,e 80 --

IIA N K D E

60 --

40 -. (0%,47) l 20 --

Fuuy Inwne(A -

(30%,0) 0

)

0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power

)

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Figure '

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Control Rod llank Insertion Limits Versus Percent of Rated Thennal Power

Catawlia 1 Cycle H Core Operating Limits Report CNE14ME24 Page 12 of 154 Rev.3

(.20,100)

(+ 10,100) nacceptable Opetateau g,,

~~

Unacceptable Operatum 70 --

Acceptable Operation

(,0 --

50 --

dll 636,50)

(+21,50)

[i 40 --

30 --

20 --

10 --

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f 1

t I

t i

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4 4

5 5

54

-40

-30 20

-10 0

10 20 30 40 50 Atialhus Difference (% Delta 1)

Figure 3 Percent of Rated Thermal Power Versus Axial Flux Difference Limits

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Catawba 1 Cycle 8 Core Operating 1.imits Report CNEl.0M24 Page 13 of 154 Rev.3 3.6 Ileat Flux IInt Channel Factor, F (X,Y,Z)(Specification 3/4.2.2)

Q 3.6.1 IJtTP = 2.32, for all OFA fuel and the Mark-IlW fuel with predicted EOC peak pin g

burnups < 45 GWD/MTU.

I[ = 2.2505, for Mark-BW fuel with predicted EOC peak pin burnups > 45 GWD/MTU. For CIC08, applies to quarter core locations H-10, F-08, F-12, D 10, and D-12.

3.6.2 K(Z) is provided in Figure 4 for Mark-BW fuel.

3.6.3 K(Z) is provideil in Figure 5 for OFA fuel.

The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.2:

[I (X,Y,Z)]OP = h(X,Y,Z)

  • M (X,Y,Z)

P b

g 3.6.4 g

where:

IIE(X,Y,Z)]OP cycle dependent maximum allowable design

=

q peaking factor which ensures that the F (X,Y,Z) q limit will be preserved for operation within the LCO limits. [Fj(X,Y,Z)]m' includes allowances for calculational and measurement uncertainties.

the design power distribution for Fg. Ph(X,Y,Z)

PhX,Y,Z)

=

is provided in Table 1 for normal operation and

,{

Table 2 for power escalation testing during initial j

startup.

M (X,Y,Z) the margin remaining in core location X,Y,Z to n

=

the LOCA limit in the transient power distribution. M (X,Y,Z) is provided in Table 1 g

for normal operation and Table 2 for power escalation testing during initial startup.

Measurement Uncertainty, = 1.05.

UMT

=

Engineering Hot Channel Factor, = 1.03.

MT

=

.j Peaking penalty that accounts for allowable j

TILT

=

quadrant power tilt ratio of 1.02, = 1.035.

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Catawba 1 Cycle 8 Core Operating Limits Report CNE14M00 24 Page 14 of 154 Rev.3 NOTE: [Ff(X,Y,Z)l0P is the parameter identified as ! q (X,Y,Z) in DPC-NE-2011PA.

F (X,Y,Z)

  • Mc(X,Y,Z) 0 L

3.6.5 [F (x,y,z))RPS "

Q UMT

  • TILT

((q(X,Y,Z)]RPS cycle dependent maximum _ allowable design where:

=

peaking factor which ensures that the centerline fuel melt limit will be preserved for all operation.

((g(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.

D the design power distributions for F. F (X,Y,Z)

F (X,Y,Z)

=

9 g is provided in Table 1 for nonnal operation and Table 2 for power escalation testing during initial startup.

M (X,Y,Z) the margin remaining to the CFM limit in core c

=

location X,Y,Z from the transient power distribution. M (X,Y,Z) calculations parallel the c

M (X,Y,Z) calculations described in DPC-NE-n 201 IPA, except that the LOCA limit is replaced with the CFM limit. M (X,Y,Z) is provided in c

Table 3 for normal operation and Table 4 for power escalation testing during initial startup.

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UMT Measurement Uncertainty, = 1.05.

j

=

Engineering Ilot Channel Factor, = 1.03.

MT

=

Peaking penalty that accounts for allowable 1

TILT

=

quadrant power tilt ratio of 1.02, = 1.035.

NOTE: ((q(X,Y,Z)lRPS is similar to the parameter '.dentified as E (X,Y,Z) in g

DPC-NE-2011PA except that M (X,Y,Z) replaces Mg(X,Y,Z).

C 3.6.6 KSLOPE = adjustment to the Kj value from OTAT required to compensate for each 1% that [Fh(X,Y,Z)]RPS exceeds it limit, = 0.0725 T

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Calawba 1 Cycle H Core Operating Limits Report CNEl-0400-24 Page 15A of 154 Rev.3 1.2 (0.0,1.00)

(8.0,1.00) 1 (10.8,0.94) 0.8

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E 0.6 (l2.0.0.647)J w

j 0.4

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0.2 O

0 1

2 3

4 5

6 7

8 9

10 11 12 Core lleight (ft)

)

i 1

-f,,

Figure 4

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K(7-), Normalized F (X,Y,Z) as a Function of Core Height for MkBW Fuel Q

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Catawba 1 Cycle 8 Core Operating I.imits Report CNEl.0400-24 Page 15B of 154 Rev.3 1.2 (0.0,1,00)

(6.0,1,00) 1 (l0.8,0.94)

\\

0.8 3 0.6 (12.0.0/4 7)

\\

'l 0.4 i

'l 0.2 0

0 1

2 3

4 5

6 7

8 9

10 11 12 Core lleight (ft)

Figure 5 g

K(Z), Normalized F (X,Y,Z) as a Function of Core Height for OFA Fuel Q

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Catawba 1 Cycle H Core Operating I.imits Report CNEl.0400-24 Py;c 15C of 154 Rev.3 3.7 Nuclear Enthalpy Rise llot Channel Factor, F gg(X,Y,Z)(Specification 3/4.2.3)

A The following parameters are required for the 1 CO Requirements of T.S. 3/4.2.3:

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3.7.1

[ Fin (X, Y)]'" = M ARP (X,Y)

  • 1.0 + RRil * (1.0 - P) l where:

M ARP(X,Y) = Catawba 1 Cycle 8 Operating Limit Maximum Allowable Radial Peaks. (M ARP(X,Y)) is provided in -

Table 7.

i Thermal Power p " Rated Thermal Power RRI-I is defined in section 3.7.3 The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.3:

3.7.2 [ FI,'(X,Y)lSURV = F",(X,Y)x M3n(X,Y' UMR x TILT where: I Fin (X, Y)l"'"" =

cycle dependent maximum allowable design peaking-factor which ensures that the Foll(X,Y) limit will be preserved for operation within the LCO limits.

[ fin (X,Y)l "" includes allowances for calculational SU and measurement uncertainties.

F",(X,Y) = the design power distribution for FAl{. F[n(X,Y) is provided in Table 5 for normal operation and Table t

6 for power escalation testing during initial startup.

i Mali (X,Y) = the margin remaining in core location X,Y to the Operational DNB limit in the ' transient power distribution. Mall (X,Y) is provided in Table 5 fo'r -

normal operation and Table 6 for power escalation testing during initial startup.

UMR = Uncertainty value for measured radial peaks, = 1.04.

TILT = Peaking penalty that accounts for allowable quadrant power till ratio of 1.02 = 1.035.

a.--.

4 Catawba 1 Cycle 8 Core Operating Limits Report CNEI4400-24 Page ISD of 154 Rev.3 NOTE: [ Fin (X,Y)]S'** is the parameter identified as Fy*(X,Y) in DPC-NE-201 I PA.

3.7.3 RRH = Thermal Power reduction required to compensate for each 19o that FAH(X,Y) exceeds its limit, = 3.34.

3.7.4 TRH = Reduction in OTAT K] setpoint required to compensate for each 17e that FAH(X,Y) exceeds its limit, = 0.04 3.8 lloron Dilution Mitigation System (Specification 3/4.3.3.11) 3.8.1 Reactor Water Makeup Pump flowrate limits:

l Applicable Mode Limit Mode 3 or 4 s 150 gpm Mode 5 s 70 gpm 3.9 Accumulators (Specification 3/4.5.1) 3.9.1 Boron concentration limits during modes 1,2 and 3:

Parameter Limits Cold Leg Accumulator minimum boron 2,000 ppm concentration for LCO 3.5.lc

.k Cold Leg Accumulator maximum boron 2,275 ppm

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concentration for LCO 3.5.lc Minimum Cold Leg Accumulator boron 1,900 ppm concentration required to ensure post-LOCA suberiticality 3.10 Refueling Water Storage Tank (Specification 3/4.5.4) 3.10.1 Boron concentration limits during modes 1,2,3 and 4:

Parameter Limits Refueling Water Storage Tank minimum boron 2,175 ppm concentration for LCO 3.5.4b

,4 Catawba 1 Cycle 8 Core Operating 1 imits Report CNEI-04(324 Page 15E of 154 Rev.3 e

Refueling Water Storage Tank maximum baron 2,275 ppm concentration for LCO 3.5.4b 3.11 Instrumentation (Specification 3/4.9.2) 3.11.1 Reactor Makeup Water Pump Flowrate Limit:

Aeolicable Mode Limits Mode 6 s 70 gpm k

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