ML20140E039
| ML20140E039 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/09/1997 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20140E037 | List: |
| References | |
| CNEI-0400-25, CNEI-0400-25-R10, CNEI-400-25, CNEI-400-25-R10, NUDOCS 9704250039 | |
| Download: ML20140E039 (28) | |
Text
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s CNEI-0400-25 Page 1 of 22 Revision 10 Catawba Unit 2 Cycle 9 Core Operating Limits Report April 1997 Duke Power Company Date Prepared By:
g [ hg
- /./'p/f7 Checked By:
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ff[ h ( gf j f t//f/99 f
Approved By:
[7/M f[#/fj i
i QA Condition 1 The contents of this document have been reviewed to verify that no material herein either direedy or indirectly changes the results and conclusions presented in the 10CFR50.59 Catawba 2 Cycle 8 Rele ad i
Safety Evaluation.
ADOCK 05000414 [;;
9704250039 970416 PDR P
PDR 1
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Cttawba 2 Cycle 9 OIre Operating Limits Report CNEI-0400-25 t
Page 3 of 22 Revision 10 7
l INSERTION SHEET FOR REVISION 10
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Pages 1,3,4,6,10,11 Pages 1,3,4,6,10,11
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-o Cctawba 2 Cycle 9 Core Opercting Limits Report CNEI-0400-25 Page 4 of 22 Revision 10 REVISION LOG Revision Effective Date Comment OriginalIssue February 1993 C2C06 COLR Revision 1 April 1994 C2C06 COLR rev 1 Revision 2 May 1994 C2C07 COLR Revision 3 October 1994 C2C07 COLR rev 1 Revision 4 April 1995 C2C07 COLR rev 2 Revision 5 September 1995 C2C07 COLR rev 3 Revision 6 October 1995 C2C08 COLR Revision 7 September 1996 C2C08 COLR rev 1 Revision 8 March 1997 C2C08 COLR rev 2 Revision 9 March 1997 C2C09 COLR Revision 10 April 1997 C2C09 COLR rev 1 e__
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Cctawba 2 Cycle 9 Ccre Opercting Limits R: port CNEI-0400-25 i
Page 6 of 22 i
Revision 10 1.1 Operating Limits i
l 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.
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2.0 Reactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.0.1 Over temperature AT Setpoint Parameter Values Parameter Value Over temperature AT reactor trip setpoint K = 1.1953 i
Over temperature AT reactor trip heatup K = 0.03163/0F 2
setpoint penalty coefficient Over temperature AT reactor trip K3 = 0.001414/ psi depressurization 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.
4 lead / lag time constants t = 4 sec.
5 Measure reactor vessel average temperature T = 0 sec.
6 lag time constant f (AI) " positive" breakpoint
= 3.0 %AI i
i f (AI) " negative" breakpoint
= -39.9 %Al i
i f (AI) " positive" slope
= 1.525 %ATg %AI i
f (AI) " negative" slope
= 3.910 %ATg %AI i
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Cctawba 2 Cycle 9 Cors Operating Limits Report CNEI-0400-25 Page 10 of 22 Revision 10 3.1 Borated 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 and 6:
Parameter Limit Boric Acid Storage System minimum boron 7,275 ppm concentration for LCO 3.1.2.5 Boric Acid Storage System minimum contained 12,000 gallons water volume for LCO 3.1.2.5a Boric Acid Storage System minimum water 585 gallons volume required to maintain SDM at 7,275 ppm Refueling Water Storage Tank minimum boron 2,875 ppm concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum contained 45,000 gallons borated water volume for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,875 ppm l
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Cctawba 2 Cycle 9 Cere Operating Limits Report CNEI-0400-25 Page 11 of 22 Revision 10 3.2 Borated Water Source - Operating (Specification N4.1.2.6) 3.2.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, and 4:
Parameter Limit
)
Boric Acid Storage System minimum boron 7,275 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 9,851 gallons volume required to maintain SDM at 7,275 ppm Refueling Water Storage Tank minimum boron 2,875 ppm j
concentration for LCO 3.1.2.6b 1
Refueling Water Storage Tank minimum contained 98,607 gallons borated water volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,875 ppm 33 Shutdown Rod Insertion Limit (Specification 3/4.13.5) 33.1 The shutdown rods shall be withdrawn to at least 222 steps.
3.4 Control Rod Insertion Limits (Specification 3/4.13.6) 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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CNEI-0400-25 Page1of R Revision 9
'V Catawba Unit 2 Cycle 9 i
Core Operating Limits Report March 1997 l
Duke Power Company 1
Date O
Prepared By:
ggMg 3/cg/fj Checked By:
p// //
3/:u/97 3fA7[77 Checked By:
(
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v Approved By:
f[J/ ((g,fu 3[7[F 7 I
i i
QA Condition 1 The contents of this document have been reviewed to verify that no material herein either directly or indirectly changes the results and conclusions presented in the 10CFR50.59 Catawba 2 Cycle 8 Reload Safety Evaluation.
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Cetawb3 2 Cycle 9 Cere Operating Limits Report CNEI-0400-25 Page 2 of 22 Revision 9 O
IMPLEMENTATION INSTRUCTION FOR REVISION 9 Revision 9 to the Catawba Unit 2 COLR contains limits specific to the Catawba 2 Cycle 9 Core and may become effective any time during NO-MODE between Cycles 8 and 9. This revision shall become effective prior to entering MODE 6 which stans Cycle 9.
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t Cetswba 2 Cycle 9 Ccre Operating Limits R: port CNEI-0400-25 i
Page 3 of 22
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Al'.Pages Pages 1-22, rev 9 l
Appendix A, Allpages Appendix A, Pages 1 - 269 4
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E Cct:wba 2 Cycle 9 Ccre Operating Limits Report CNEI-0400-25 Page 4 of 22 Revision 9 O
REVISION IPG Revision Effective Date Comment f
OriginalIssue February 1993 C2C06 COLR Revision 1 April 1994 C2C06 COLR rev 1 Revision 2 May 1994 C2C07 COLR Revision 3 October 1994 C2C07 COLR rev 1 Revision 4 April 1995 C2C07 COLR rev 2 Revision 5 September 1995 C2C07 COLR rev 3 Revision 6 October 1995 C2C08 COLR Revision 7 September 1996 C2C08 COLR rev 1 Revision 8 March 1997 C2C08 COLR rev 2 Revision 9 March 1997 C2C09 COLR i
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Catawba 2 Cycle 9 Ccre Operating Limits R: port CNEI-0400-25 Page 5 of 22 Revision 9 OV 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) 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:
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i Tech Spec COLR COLR Section Technical Specifications Section Eage 2.2.1 Reactor Trip System Instrumentation Setpoints 2.0 6
3/4.1.1.3 Moderator Temperature Coefficient 3.0 8
i
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3/4.1.2.5 Borated Water Source - Shutdown 3.1 10 3/4.1.2.6 Borated Water Source - Operating 3.2 11 1
3/4.1.3.5 Shutdown Rod Insertion Limit 3.3 11 3/4.1.3.6 Control Rod Insertion Limit 3.4 11 3/4.2.1 Axial Flux Difference 3.5 11 O'
3/4.2.2 Heat Flux Hot Channel Factor 3.6 14 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3.7 18 3/4.3.3.11 Boron Dilution Mitigation System 3.8 20 l
3/4.5.1 Accumulators 3.9 20 l
3/4.5.4 Refueling Water Storage Tank 3.10 20 i
3/4.9.1-Refueling Operations - Boron Concentration 3.11 21 i
3/4.9.2 Instrumentation 3.12 21 1
3/4.9.12 Refueling Operations - Spent Fuel Pool Boron 3.13 21 Concentration 4.7.13.3 Standby Makeup Pump Water Supply - Boron 3.14 22 Concentration I
i N
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Cet:wbi 2 Cycle 9 Ccre Opercting Limits Report CNEI-0400-25 Page 6 of 22 Revision 9 O
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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 methodo!.ogies specified in Technical Specification 6.9.1.9.
2.0 Reactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.0.1 Over temperature AT Setpoint Parameter Values Parameter Value Over temperature AT reactor trip setpoint K = 1.1954 i
Over temperature AT reactor trip heatup K = 0.03164/0F 2
setpoint penalty coefficient Over temperature AT reactor trip K = 0.001414/ psi 3
depressurization setpoint penalty coefficient i
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, 4
lead / lag time constants T = 4 sec.
5 Measure reactor vessel average temperature t = 0 sec.
l 6
lag time constant f (AI) " positive" breakpoint
= 3.0 %AI i
f (AI) " negative" breakpoint
= -39.9 %AI i
f (AI) " positive" slope
= 1.525 %ATc/ %Al i
f (AI) " negative" slope
= 3.910 %ATo/ %AI
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Cctanha 2 Cycle 9 Cere Operating Limits Report CNEI-0400-25 Page 7 of 22 Revision 9 2.0.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint
. K4 = 1.0819 Overpower AT reactor trip heatup setpoint K = 0.001291FF 6
penalty coefficient (for T > T")
Overpower AT reactor trip heatup setpoint K = 0.0FF 6
penalty coefficient (for T s T")
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 Measure reactor vessel average temperature 5 = 0 sec.
6 lag time constant
/h Q
Measure reactor vessel average temperature T = 10 sec.
7 rate-lag time constant f (AI) " Positive" breakpoint
= 35.0 %AI 2
f (AI) " negative" breakpoint
= -35.0 %AI 2
f (AI) " Positive" slope
= 7.0 %ATg %AI 2
f (AI) " negative" slope
= 7.0 %ATg %AI 2
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Cet:wbs 2 Cycle 9 Ccre Opere. ting Limits R: port CNEI-0400-25 Page 8 of 22 Revision 9 OG 3.0 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 3.0.1 The Moderator Temperature Coefficient (MTC) LCO Limits are:
The MTC shall be less positive than the limits shown in Figure 1. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/ F.
The EOC, ARO, RTP MTC shall be less negative than -4.lE-04 AK/K/ F.
3.0.2 The MTC Surveillance Limit is:
The 300 PPM /ARO/ RTP MTC shall be less negative than or equal to -3.2E-04 AK/K/ F.
where:
BOC = Beginning of Cycle EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Thermal Power RTP = Rated Thermal Power O
~ Citawba 2 Cycle 9 Core Operzting Limits R: port CNEI-0400-25 i
Page 9 of 22 4
Revision 9 i!O j
Figure 1 4
i Moderator Temperature Coefficient Versus Power Level i
1.0
}
0.9 -
0.8 -~
Unacceptable Operation i
n
)
0.7 0.6 --
}
E I
h0.5--
Acceptable Operation 5
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!n
,4 -..
o o
0.3 -
\\
f 0.2 -
1 i
0.1 -
0.0 l
l l
l l
l l
c 0
10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power i
1 l
l 2
a i
)
h, i
Catawba 2 Cycle 9 Cere Oper ting Limits Report CNEI-0400-25 Page 10 of 22 Revision 9 O
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 and 6:
Parameter Limit Boric Acid Storage System minimum boron 7,275 ppm concentration for LCO 3.1.2.5a Boric Acid Storage System minimum contained 12,000 gallons water volume for LCO 3.1.2.5a Boric Acid Storage System minimum water 585 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron 2,875 ppm concentration for LCO 3.1.2.5b f)
Refueling Water Storage Tenk minimum contained 45,000 gallons U
borated water volume for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,475 ppm e
Catawba 2 Cycle 9 Ccre Operating Limits Report CNEI-0400-25 Page 11 of 22 Revision 9 0
3.2 Borsted Water Source - Operating (Specification N4.1.2.6) 3.2.1. Volume and boron concentrations for the Boric Acid Storage Lystem and the Refueling Water Storage Tank (RWST) during modes 1,2,3, and 4:
Parameter Limil Boric Acid Storage System minimum boron 7,275 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 9,851 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron 2,875 ppm concentration for LCO 3.1.2.6b C-).
Refueling Water Storage Tank minimum contained 98,607 gallons borated watet volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,475 ppm 3.3 Shutdown Rod Insertion Limit (Specificadon N4.1.3.5) 3.3.1 The shutdown rods shall be withdrawn to at least 222 steps.
3.4 Control Rod Insertion Limits (Specification N4.1.3.6) 3.4.1 The control rod banks shall be limited to physical insertion as shown in Figure 2.
3.5 Axial Flux Diff'erence (Specification N4.2.1) 3.5.1 The Axial Flux Difference (AFD) Limits are provided in Figure 3.
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Cctawba 2 Cycle 9 Ccre Operating Limits R: port CNEI-0400-25 Page 12 of 22 Revision 9
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l Figure 2 Control Rod Bank Insertion Limits Versus Percent Rated Thermal Power i
Fully Withdrawn l
(29.5 %,231)
(Maximum = 231) %
(80.0%,231) 231 220 --
Fully Withdrawn l
200 --
(Minimum-222)
(Control Bank B) g 180 --
(
160 --(0%,163) g 140 --
g (Control Bank C) j 120 --
c j 100 --
c 80 --
(Control Bank D) 3 60 --
G 2"
40 --(0** *)
20 --
FullyInserted (30%,0) 0 l
l l
l l
l l
l 0
10 20 30 40 50 60 70 80 90 100 Percent of Rated ThermalPower NOTE: Compliance with Technical Specincation 3.1.1.3 may require rod withdrawal limits. Refer to the Unit 2 ROD manual for details.
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Cctawba 2 Cycle 9 Ccre Oper: ting Limits R: port CNEI-0400-25 Page 13 of 22 Revision 9
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Figure 3 Axial Flux Difference Limits Versus Percent of Rated Thermal Power 4
( 20,100)
(+10,100)
'~
Unacceptable Operation Unacceptable Operation 90 -
t 80 --
in 4
S 70 --
1[.
Acceptable Operation 60 --
E 50 --
E
(-36, 50)
(+21,50) j 40 --
30 --
[
20 --
10 --
l l
l l
0 l
l l
l
-50
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (% Delta I)
NOTE: Compliance with Technical Specification 3.2.2 may require a reduction in the COLR AFD limits. Refer to the Unit 2 ROD manual for operating AFD limits.
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I Cctawba 2 Cycle 9 Ccre Oper: ting Lhnits R: port CNEI-0400-25 Page 14 of 22 i
Revision 9 3.6 Heat Flux Hot Channel Factor, FQ(X,Y,Z) (Specification 3/4.2.2) 1 3.6.1 F"" = 2.50 x K(BU) for MkBW Fuel q
Fq"" = 2.32 x K(BU) for PGE MkBW Fuel
[
c i
3.6.2 K(Z) and K(BU) are provided in Figure 4 and Figure 5, respectively, for MkBW i
fuel and POE MkBW fuel.
)
The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.2:
I FS(X,Y,Z)
- Mo(X,Y,Z) i i
3.6.3 [Fq'(X,Y,Z)]oP =
where:
j f
[Ff' (X,Y,Z)]oP = Cycle dependent maximum allowable design peaking factor which ensures that the Fq(X,Y,Z) limit will be pmserved for operation within the LCO limits. [Fq'(X,Y,Z)]oP includes
)
allowances for calculational and measurement uncenainties.
Fn(X,Y,Z) = Design power distribution for Fq. Fn(X,Y,Z)is provided in Table 1, Appendix A, for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operations.
Mo(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. M (X,Y,Z)is provided in Table g
1, Appendix A for normal operating conditions and in Table 2, Appen.iix A for power escalation testing during initial startup operidons.
UMT = Measurement Uncertainty (UMT = 1.05)
MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)
NOTE: [Fq'(X,Y,Z)]oP is the parameter identified as Fo"(X,Y,Z) in DPC-NE-2011PA.
Cctawba 2 Cycle 9 Ccre Operzting Limits R: port CNEI-0400-25 Page 15 of 22 Revision 9 Ov
[Eq(X,Y,Z)]RPS = F$(X,Y,Z)
- Mc(X,Y,Z) 3.6.4 where:
j
[Eq(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor which ensures that the centerline fuel melt limit will be preserved for operation within the LCO limits. [Eq(X,Y,Z)]RPS jnCludes allowances for calculational and measurement uncertainties, i
F$(X,Y,Z) = Design power distributions for Fq. Fq(X,Y,Z)is provided in Table 1, Appendix A for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operations.
Mc(X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. Mc(X,Y,Z) calculations parallel the M (X,Y,Z) calculations described in DPC-NE-2011PA, i
n except that the LOCA limit is replaced with the CFM limit.
O.
Mc(X,Y,Z)is provided in Table 3, Appendix A for normal operating conditions and in Table 4, Appendix A for power escalation testing during initial startup operations.
UMT = Measurement Uncertainty (UMT = 1.05)
MT = Engineering Hot Channel Factor (MT = 1.03) -
]
TILT = Peaking penalty that accounts for allowable quadrant power tilt j
ratio of 1.02. (TILT = 1.035)
NOTE: [En(X,Y,Z)]RPS is the parameter identified as F7(X,Y,Z) in DPC-NE-201 IPA, except that M (X,Y,Z) is replaced by Mc(X,Y,Z).
n
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KSLOPE = Adjustment to the K value from OTAT required to compensate for 3.6.5 1
each 1% that [Eq(X,Y,Z)]RPs CxCecds its limit. (KSLOPE = 0.0725)
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Cctawha 2 Cycle 9 Ccre Oper: ting Limits Report CNEI4)400-25 Page 16 of 22 Revision 9 l
Figure 4 K(Z), Normalized Fo(X,Y,Z) as a Function of Core Height for MkBW Fuel MkBW Fuel an] PGE MkBW Fuel l.2 (0.0,1.00)
(12.0,1.00)
(8.0,1.00)
( Efx1)
(12.0.0.91) 0.8 --
(PGE fuel) h0.6--
0.4 --
0 0.2 --
0.0 l
l l
l l
0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft) i O
i 1,
Octawba 2 Cycle 9 Ccre Oper:> ting Limits Report CNEl-0400-25 Page 17 of 22 Revision 9 O
Figure 5 K(BU), Normalized Fo(X,Y,Z) as a Function of Burnup for MkBW Fuel and PGE MkBW Fuel 1.2 (0.0,1.00)
(47.5,1.0) 1.0 (60.0,0.868)
(47.0, O.1.0)
PGE fuel 0.8 --
(60.0,0.825)
PGE fuel 1
0.6 --
'l K(BU) 0.4 --
0.2 --
i 1
0.0 l
l l
l O.0 10.0 20.0 30.0 40.0 50.0 60.0 Burnup (GWD/MTU)
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C:.tawba 2 Cycle 9 Cere Oper: ting Limits R: port CNEI-0400-25 Page 18 of 22 Revision 9
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3.7 Nuclear Enthalpy Rise Hot Channel Factor, FAH(X,Y,Z) (Specification 3/4.2.3)
The following parameters are required for the LCO requirements of T.S. 3/4.2.3.
3.7.1 [Fh(X,Y)]" = MARP (X,Y)
- 1.0 + RRll * (1.0 - P) where:
MARP(X,Y) = Cycle specific operating limit Maximum Allowable Radial Peaks.
MARP(X,Y) limits for blanket and non-blanket fuel are provided in Table 7, Appendix A.
Thermal Power p " Rated Thermal Power i
RRH = (Defined in section 3.7.3) l OV The following parameters are required for core monitoring per the Surveillance requirements of T.S. 3/4.2.3.
[Fh(X,Y)]SURV = Fh(X,Y)xM3nG,0 3.7.2 UMRxTILT where:
[Emi(X,Y)]SURV = Cycle dependent maximum allowable design peaking factor which ensures that the FAH(X,Y) limit will be preserved for operation within the LCO limits. [Egi(X,Y)]suRv includes allowances for calculational and measurement uncertainty.
- Fai(X,Y) = Design power distribution for Fui, Fai(X,Y)is provided in Table 5, Appendix A for normal operation and in Table 6, j
Appendix A for power escalation testing during initial startup operations, l
i Cctawba 2 Cycle 9 Core Oper ting Limits Riport CNEI-0400-25 Page 19 of 22 Revision 9 i
- g
, (
i Mon (X,Y) = Margin remaining in core location X,Y mlative to the Operational DNB limit in the transient power distribution.
i Ma (X,Y)is provided in Table 5, Appendix A for normal n
operation and in Table 6, Appendix A for power escalation testing during initial startup operations.
6 UMR = Uncertainty value for measured radial peaks (UMR = 1.04).
TILT = Factor to account for a peaking increase due to the allowed quadrant tilt ratio of 1.02. (TILT = 1.035).
f i
j NOTE: [F' (X,Y)]suav is the parameter identified as [F (X,Y)] MAX in DPC-NE-m a
20llPA.
1 3.7.3 RRH = Thermal Power reduction required to compensate for each 1% that -
Fa(X,Y) exceeds its limit (RRH = 3.34).
3.7,4 TRH = Reduction in OTAT K setpoint required to compensate for each 1% that 1
(
Fa(X,Y) exceeds its limit (TRH = 0.04).
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Cctawba 2 Cycle 9 Core Operating Limits Report CNEI-0400-25 Page 20 of 22 Revision 9 O
3.8 Boron Dilution Mitigation System (Specification 3/4.3.3.11) 3.8.1 Reactor Wat r Makeup Pump flowrate limits:
Acolicable Mode Limi.1 Mode 3 or 4 s 150 gpm Mode 5 s70 gpm 3.9 Accumulators (Specification 3/4.5.1) 3.9.1 Boron concentration limits during modes 1,2, and 3:
Parameter Limil Cold Leg Accumulator minimum boron concentration for 2,675 ppm LCO 3.5.1c Cold Leg Accumulator maximum boron concentration for 3,075 ppm LCO 3.5.1c Minimum Cold leg Accumulator boron concentration 2,567 ppm required to ensure post-LOCA subcriticality 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 Lim!1 Refueling Water Storage Tank minimum boron 2,875 ppm concentration for LCO 3.5.4b Refueling Water Storage Tank maximum boron 3,075 ppm
[
concentration for LCO 3.5.4b
Catawba 2 Cycle 9 Care Oper ting Limits Report CNEI-0400-25 Page 21 of 22 Revision 9 0
.3.11 Refueling Operations - Boron Concentration (Specification 3/4.9.1) 3.11.1 Minimum boron concentration for the filled portions of the Reactor Coolant System and refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.
Parameter kjm_jt Refueling boron concentration for the filled portions of the 2,875 ppm Reactor Coolant System and refueling canal for LCO 3.9.1.b.
4 i
i 3.12 Instrumentation (Specification 3/4.9.2) 3.12.1 Reactor Makeup Water Pump Flowrate Limit:
Anolicable Mode Limit O
V Mode 6 s 70 gpm 3.13 Refueling Operations - Spent Fuel Pool Boron Concentration (Specification 3/4.9.12) 3.13.1 Minimum boron concentration limit for spent fuel pool. Applicable when fuel is stored in the spent fuel pool.
Parameter Limit
~
Spent fuel pool minimum boron concentration 2,875 ppm for LCO 3.9.12 O
Cctawba 2 Cycle 9 Ccre Operating Limits R: port CNEI-0400 Page 22 of 22 Revision 9
'i 3.14 Standby Makeup Pump Water Supply - Boron Concentration (Specification 4.7.13.3) i 3.14.1 Minimum boron concentration limit for the spent fuel pool, or a contained borated i
water volume (meeting additional requirements of surveillance 4.7.13.3.a.2).
l j
~
Applicable for modes 1,2, and 3.
i 4
l Parameter Limil 4
l-Spent fuel pool minimum boron concentration for 2,875 ppm surveillance 4.7.13.3.a.1 Contained borated water volume for surveillance 2,875 ppm 4.7.13.3.a.2 l
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NOTE: ' Data contained in the Appendix of this document was generated in the Catawba 2 Cycle 9 Maneuvering Analysis calculational file, CNC-1553.05-00-0243. The Catawba Nuclear Engineering Section 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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