ML20098B164

Cycle 7,Core Operating Limits Rept,Sept 1995,QA Condition 1

ML20098B164
Person / Time
Site:	Catawba
Issue date:	09/27/1995
From:	Clark R DUKE POWER CO.
To:
Shared Package
ML20098B161	List: ML20098B159 ML20098B164
References
ONEI-0400-25, ONEI-0400-25-R05, ONEI-400-25, ONEI-400-25-R5, NUDOCS 9510020300
Download: ML20098B164 (20)

Text

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CNEI-0400-25 Page 1 of 20 Rev.5 A

Catawba Unit 2 Cycle 7 Core Operating Limits Report September 1995 l

Duke Power Company DATE PREPARED BY:

)) w A D E A '.

9 [ 1 6 / 95 -

CHECKED BY:

[//

4,/9f 9

CHECKED BY:

do-

!O C /U /W w

I 1

U APPROVED BY:

/7 M 7/2.7/9.s~

QA CONDITION 1 NOTE This document does not contain information that affects the results and conclusions presented in the C2C7 Reload Report, Safety Analysis.

9510020300 950928 f'

PDR ADOCK 05000414 P.

PDR

Cet;wb3 2 Cycl 3 7 Cere Oper: ting Limits R1 port CNEI-0400-25 Page 2 of 20 Rev.5 INSERTION SHEET Remove Insert pages 1-19, rev 2-4 pages 1-20, rev 5 i

l t

Catawb2 2 Cycle 7 Cere Operating Limits Report CNEl-0400-25 Page 3 of 20 Rev.5 i

REVISION LOG Revision Effective Date Comment OriginalIssue 15 February 1993 C2C6 COLR

}

Revision 1 -

14 April 1994 C2C6 COLR ret 1-Revision 2 19 May 1994 C2C7 COLR Revision 3 24 October 1994 C2C7 COLR rev 1 Revision 4 12 April 1995 C2C7 COLR rev 2 Revision 5 28 September 1995 C2C7 COLR rev 3 i

9 i

d 9

Cctawb3 2 Cycl 3 7 Cere Operitirg Limits R: port CNEl-0400-25

' Page 4 of 20 Rev.5 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) for Catawba Unit 2,.. Cycle 7 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 Instnimentation 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 i

3/4.1.3.6' Control Rod Insertion Limit

'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 3/4.3.3.11 Boron Dilution Mitigation System 3/4.5.1 Accumulators 3/4.5.4-Refueling Water Storage Tank 4.7.13.3 Standby Makeup Pump Water Supply - Boron Concentration.

3/4.9.1 Refueling Operations - Boron Concentration 3/4.9.2 Instrumentation 3/4.9.12 Refueling Operations - Spent Fuel Pool Boron Concentration j

i 4

b h

~

Cctawb: 2 Cycle 7 Core Op;r-ti;g Limits Riport CNEI-0400-25 Page 5 of 20

/*

Rev.5 1.1 Operating Limits The 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.

2.0 Reactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K = 1.1953 i

Overtemperature AT reactor trip heatup setpoint K = 0.03163/oF 2

penalty coefficient Overtemperature AT reactor trip depressurization K = 0.001414/ psi 3

setpoint penalty coefficient Measured reactor vessel AT lead / lag time t = 8 sec.

i constants T = 3 sec.

2 Measured AT lag time constant T = 0 sec.

)

3 Measured reactor vessel average temperature T = 22 sec.

i 4

lead / lag time constants ts = 4 sec.

j Measured reactor vessel average temperature lag T = 0 sec.

6 time constant i

f (AI) " positive" breakpoint

= 3.0% AI i

f (AI) " negative" breakpoint

= -39.9% Al i

f (AI) " positive" slope

= 1.525% AT/ % AI i

f (AI) " negative" slope

= 3.910% ATg % Al i

Catawb2 2 Cycis 7 Csre Operr. ting Limits R: port CNEl-0400-25 Page 6 of 20 Rev.5 i

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2.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K = 1.0819 4

Overpower AT reactor trip heatup setpoint penalty K = 0.001291/oF 6

coefficient (for T > 590.8 0F)

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

coefficient (for T < 590.8 oF) l Measured reactor vessel AT lead / lag time t = 8 sec.

i constants T = 3 sec.

2

~

Measured AT lag time constant T = 0 sec.

3 Measured reactor vessel average tempet ature lag T = 0 sec.

6 i

time constant Measured reactor vessel average temperature rate-T = 10 sec.

7 l

lag time constant f (AI) " Positive" breakpoint '

= 35.0% AI 2

f (AI) " negative" breakpoint

= -35.0% Al 2

f (AI) " Positive" slope

= 7.0% ATg % AI 2

f (AI) " negative" slope

= 7.0% ATg % Al 2

1 1

4 e

Cctawba 2 Cycle 7 Cere Oper:ti;g Limits Report CNEI-0400-25 Page 7 of 20 Rev.f

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'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 _ he limits shown in Figure 1. The BOC, t

ARO, HZP MTC shall be less positive than 0.7

• 104 AK/K/ F.

1

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

3.0.2 For the MTC Surveillance Limit:

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

• 104

. AK/KrF.

Where:

BOC stands for Beginning of Cycle EOC stands for End of Cycle ARO stands for All Rods Out HZP stands for Hot Zero (Thermal) Power RTP stands for Rated Thermal Power i

l i

.e

- =. - _,

4 i

Cctawb3 2 Cycle 7 Core Operating Limits Report CNEI-0400-25

~

Page 8 of 20 Rev.5 5

t Figure 1 Moderator Temperature Coefficient Versus Percent of Rated Thermal Power l

e 0.9 -

r 0.8 Unacceptable Operation i

J m" 0.7 M

D.6 -

5

>0

.5 g 0.5 3

4 e 0.4 --.

Acceptable Operation

.t o

1 g0.3--.

i f

l 0.2 -

)

1 O. ! -

l 4

0 l

i 0

10 20 30 40 50 60 70 80 90 100 l

1 l

Percent of Rated Thermal Power 4

l 1

J 1

i l

4

~

Cctawb: 2 Cycle 7 Ccre Oper; ting Limits Report CNEI-0400-25 Page 9 of 20 Rev.5 3.1 Borated Water Source - Shutdown (Specification 3/4.1.2.5) l 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 12,000 gallons water votame for LCO 3.1.2.5a l

Boric Acid Storage System minimum water volume 585 gallons required to maintain SDM at 7,000 ppm l

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 1

[

Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,175 ppm l

l l

CNEl.0400-25 l

Cctawb2 2 Cycle 7 Core Operating Limits R: port Page 10 of 20 Rev. 5 l

l 3.2 Borated Water Source - Operating (Specification 3/4.1.2.6) 3.2.1 Volume and boron concentrations for the Boric Acid Storage System and the I

Refueling Water Storage Tank (RWST) during modes 1,2,3, & 4:

Parameter Limit Boric Acid Storage System minimum boron 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 l

Boric Acid Storage System minimum water volume 9,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron 2,175 ppra j

j 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 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 3.3.1 The shutdown rods shall be withdrawn to at least 222 steps.

l l

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 L The Axial Flux Difference (AFD) Limits are provided in Figure 3.

Ccts.wb32 Cycl 3 7 Cera Oper ting Limits R: port CNEI-0400-25 Page 11 of 20

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Rev.5 Figure 2 Control Rod Bank Insertion Limits Versus Percent of Rated Thermal Power Fully Withdrawn (29.1 %,230)

(Maximum = 230)\\

(79.6%,230) 230 220 -r-------

Fully Withdrawn 200 --

(Minimum = 222)

^

180 --

7 (100 %, 161)

] 160 --(0%,163)

G g,140 --

BANK C 7 120 --

8

[100-8E 80 --

BANK D g

f 60 -

40

.(0%,47) 20 --

Fully inserted (30%,0) 0 0

10 20 30 40 50 60 70 80 90 100 4

Percent of Rated Thermal Power 4

2 1

a

Cett.wb3 2 Cycla 7 Cera Operating Limhs Rrport CNEI.0400-25 Page 12 of 20 Rev,5 I

1 Figure 3 I

Percent of Rated Thermal Power Versus Axial Flux Difference Limits I

I l

\\

l

( 17,100)

(+10,100) l l

Unacceptable Operation

~~

Unacceptable Operation 70 --

Acceptable Operation 60 --

50 --

l

( 36.50)

(+21,50) l 30 --

20 10 --

i l

l l

l l

l l

l l

^

-50

-40

-30 20 10 0

10 20 30 40 50 Aslal Flus Difference (% Delta I) 1 l

)

)

I l

- Cctawb;,2 Cycle 7 Cdre Operatirg Limits Report

- CNEl-0400-25 Page 13 of 20 -

Rev.5 3.6 Heat Flux Hot Channel Factor, Fq(X,Y,Z) (Specification 3/4.2.2) 3.6.1 F

= 2.32 '

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

43.6.3 L K(Z) is provided in Figure 5 for OFA fuel.

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

Fh(X,Y,Z)

• Mn(X,Y,Z) 3.6N '. [F (X,Y,Z)]OP =

n

' where:

[F (X,Y,Z)]OP cycle dependent. maximu't allowable design

=

n

_ peaking factor which ensums ihat the F (X,Y,Z) q limit will be preserved for operation within the LCO limits. [Fj(X,Y,Z)]OP includes allowances for, calculational and measurement uncertainties.

l D

l n

the design power distribution l'or Fq. F (X,Y,Z)

F (X,Y,Z)

=

q is provided in Table 1, Appendix A for normal operation and Table 2, Appendix A for power escalation testing during initial startup.

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

=

n the LOCA limit in the transient power distribution. M (X,Y,Z) is provided in Table 1, 9

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

UMT Measurement Uncertainty, = 1.05.

=

Engineering Hot Channel Factor, = 1.03.

MT

=-

Peaking penalty that accounts for allowable TILT.

=

quadrant power tilt ratio of 1.02, = 1.035.

NOTE: [Fh(X,Y,Z)]OP is the pemeter identified as F(X,Y,Z) in DPC-NE-2011PA.

q

+

Ct.t wba 2 Cycle 7 Cers Operating Limits Rrport CNEI-0400-25 Page 14 of 20

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Rev.5 Fh(X,Y,Z)

• Mc(X,Y,Z) 3.6.5 [F (X,Y,Z)]RPS =

n cycle dependent maximum allowable design where:

[F (X,Y,7)]RPS

=

9 peaking factor which ensures that the centerline fuel melt limit will be preserved 'for all operation. [F (X,Y,Z)]RPS includes allowances 9

for calculational and measurement uncerta'inties.

I o

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

F (X,Y,Z)

=

q q

l is provided in Table 1, Appendix A for normal-i operation and Table 2, Appendix A for power escalation testing during initial startup.

1 the margin remaining to the CFM limit in core j

M (X,Y,Z)

=

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

M (X,Y,Z) calculations described in DPC-NE-n i

201 IPA, except that the LOCA limit is replaced j

with the CFM limit. M (X,Y,Z) is provided in c

Table 3, Appendix A for normal uperation and i

Table 4, Appendix A for power escalation testing during initial startup.

Measurement Uncertainty, = 1.05.

j UMT

=

Engineering Hot Channel Factor, = 1.03.

MT

=

Peaking penalty that accounts for allowable TILT

=

quadrant power tilt ratio of 1.02, = 1.035.

i.

I MAX (X,Y,Z) in L

NOTE: [F (X,Y,Z)]RPS is similar to the parameter identified as F l

9 9

DPC-NE-201 IPA except that Mc(X,Y,Z) replaces Mg(X,Y,Z).

i KSLOPE = adjustment to the K value from OTAT required to compensate for 3.6.6 i

each 1% that [F (X,Y,Z)]RPS exceeds it limit, = 0.0725

]

n

.~ _

Cct:wb 2 Cycla 7 Cere Oper: ting Limits R: port CNEI-0400-25 Page 15 of 20 Rev. 5 -

Figure 4 K(Z), Normalized F (X,Y,Z) as a Function of Core Height for MkBW Fuel Q

J r

1.2 (0.0,1.00)

(8.0,1.00) 1 (10.8,0.94)

O.8 E 0.6 (12.0.0.647) x 0.4 0.2 j

0 1

0 1

2 3

4 5

6 7

8 9

10 11 12 Core Height (ft)

n.

Ce1:wbz 2 Cycle 7 Core OpIr ting Limits R: port CNEI-0400-25 Page 16 of 20

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Rev.5 Figure 5 K(Z), Normalized F (X,Y,Z) as a Function of Core Height for OFA Fuel Q

1.2 (0.0,1.00)

(6.0,1,00) 1 (10.8,0.94) 0.8 0.6 (12.0.0.647) f 0.4 0.2 0

1 i.,

O I

2 3

4 5

6 7

8 9

10 11 12 Core IIcight (ft) i 4

i

}

E

^

CNEI-0100-25 Cctawha 2 Cycle 7 Cere Oper:thg Limits RJport Page 17 of 20 Rev.5 3.7 ' Nuclear Enthalpy Rise Hot Channd Factor, FAH(X,Y,Z)(Specification 3/4.2.3) i The following parameters are required for the LCO Requirements of T.S. 3/4.2.3:

1 3.7.1 - [Fh(X,Y)]* = MARP (X,Y) *,1.0 + RRH * (1.0 - P),

where:. MARP(X,Y) = Catawba 2 Cycle 7 Operating Limit Maximum Allowable Radial Peaks. (MARP(X,Y)) is provided in Table 7, Appendix A' for non-axial blanket fuel and in Table 8, Appendix A for axial blanket fuel.

Thermal Power p, Rated Thermal Power RRH is defined in section 3.7.3 The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.3:

[Fh(X,YT]SURV = FE(X,Y)xM,(X,Y) 3.7.2 UMRxTILT where: [Fi(X,Y)]S" =

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

[Fh(X,Y)]5" includes allowances for calculational and measurement uncertainties.

FE(X,Y) = the design power distribution for FAH. FE(X,Y) is provided in Table 5, Appendix A for normal operation and Table 6, Appendix A for power escalation testing during initial startup.

MAH(X,Y)= the margin remaining in core location X,Y to the Operational DNB limit in the transient power distribution. MAH(X,Y) is provided in Table 5, Appendix A for normal operation.and Table 6, Appendix A for powe: escalation testing during initial startup.

UMR = Uncertainty value for measured radial pw.ks, = 1.04.

n b

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio cf 1.02, = 1.035.

2. m

1 Cct;,wba 2 Cycle 7 Core Operating Limits R: port CNEl-0400-25 Page 18 of 20

]

Rev.5

~

j NOTE: [Fh(X,Y)]" is the parameter identified as F7(X,Y) in DPC-NE-2011PA.

3.7.3 RRH = Thermal Power reduction required to compensate for each 1% that FAII(X,Y) exceeds its limit, = 3.34.

TRH = Reduction in OTAT K setpoint required to compensate fdr each 3.7.4 1

1% that FAH(X,Y) exceeds its limit, = 0.04 3.8 Boron Dilution Mitigation System (Specification 3/4.3.3.11) 3.8.1 Reactor Water Makeup Pump flowrate limits:

Anolicable Mod _e Limit Mode 3 or 4 5150 gpm Mode 5 5 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 4

Cold Leg Accumulator maximum boron 2,275 ppm concentration for LCO 3.5.lc Minimum Cold Leg Accumulator boron 1,900 ppm concentration required to ensure post-LOCA l

suberiticality n

l Cr;tawbr 2 Cycle 7 Ccre Oper. ting Limits Report CNEI-0400-25 Page 19 of 20

=Rev.5 3.10 Refdeling 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 Refueling Water Storage Tank maximum boron 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:

Applicable Mode Limits Mode 6

< 70 gpm 3.12 Refueling Operations - Boron Concentration (Specification 3/4.9.1) 3.12.1 Minimum boron concentrations for the filled portions of the Reactor Coolant System and the refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.

Parameter Limit Refueling boron concentration for the filled portions of 2175 ppm the Reactor Coolant System and the refueling canal, for I

LCO 3.9.1.b.

j

Cctawbi2 Cycle 7 Cere Oper1 ting Limits Reprt CNEI-0400-25 Page 20 of 20 Rev.5 3.13 Standby Makeup Pump Water Supply - Boron Concentration (Specification 4.7.13.3) 3.13.1 Minimum boron concentration limit for the spent fuel pool, or a contained borated water volume (meeting additional requirements of surveillance 4.7.13.3.a.2).

Applicable for modes 1,2, and 3.

Parameter Limits Spent fuel pool minimum boron concemration, for surveillance 2175 ppm 4.7.13.3.a.1 Contained borated water volume, for surveillance 4.7.13.3.a.2 2175 ppm 3.14 Refueling Operations - Spent Fuel Pool Boron Concentration (Specification 3/4.9.12) 3.14.1 Minimum boron concentration limits for spent fuel pool. Applicable when fuel is stored in the spent fuel pool.

Pa.rameter Limit Spent fuel pool minimum boron concentration 2,175 ppm for LCO 3.9.12

• - Values provided as Tables in the Appendix to this document were generated in the C2C07 Maneuvering Analysis calculational file (CNC-1553.05-00-0177). The CNS Reactor Engineering Group will control this information via computer file (s) and should be contacted if there is a need to access this information.

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