ML20203A404
| ML20203A404 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/22/1998 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20203A401 | List: |
| References | |
| CNEI-0400-24, CNEI-0400-24-R14, CNEI-400-24, CNEI-400-24-R14, NUDOCS 9902090354 | |
| Download: ML20203A404 (24) | |
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CNEI-0400-24 !
Page 1 of 24 Revision 14 Catawba Unit 1 Cycle 11 Core Operating Limits Report Revision 14 December 1998 Duke Power Company j i
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Date Prepared By: C /s f M M /> -r8-7/
/00 f '
Checked By: / 2.// r,/r/
,Ed., /[ /kA/p[
Checked By: l\///h a u lA/ai/tt j
Approved By: [d7M / 2./2.2/fp QA Condition 1 The contents of this document have been reviewed to verify that no material herein either directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 Catawba 1 Cycle 11 Reload Safety Evaluation.
9902090354 990128 PDR ADOCK 05000413 i P PDR L
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CNEI-0400-24 l
' Prge 2 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 14 Revision 14 of the Catawba Unit 1 COLR updates this report to be compliant with the Improved Technical Specifications (ITS). This revision should be implemented concurrently with the release ofITS.
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CNEI-0400-24 Page 3 of 24 Revision 14 Catawha 1 Cycle 11 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR f
OriginalIssue September 8,1992 N/A CIC07 COLR j Revision 1 October 10,1992 N/A CIC07 COLR rev 1 Revision 2 December 1,1993 N/A CIC08 COLR Revision 3 April 14,1994 N/A C1C08 COLR rev 1 1
Revision 4 October 24,1994 N/A CIC08 COLR rev 2 l l
Revision 5 November 30,1994 N/A CIC08 COLR rev 3 Revision 6 February 15,1995 N/A CIC09 COLR Revision 7 April 12,1995 N/A C1C09 COLR rev 1 i i
Revision 8 September 28,1995 N/A CIC09 COLR rev 2 l l Revision 9 August 2,1996 N/A CIC10 COLR 1
l Revision 10 May 28,1997 N/A CIC10 COLR rev 1 l l !
! Revision 11 July 1997 N/A ,
CIC10 COLR rev 2 Revision 12 November 1997 N/A CICI1 COLR Revision 13 August 1998 N/A CICI1 COLR rev 1 Revision 14 December 1998 1-24 CICI1 COLR rev 2 l
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CNEI-0400-24 Page 4 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report INSERTION SHEET FOR REVISION 14 Remove pages Insert Rev.14 pages Pages 1-21 Pages 1-24 l
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CNEl-0400-24 Pcge 5 of 24 Revision 14 Catawba 1 Cycle 11 Com Operating Limits Repod l 1.0 Com Operating Limits Repod This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of the Technical Specification.
The Technical Specifications that reference this report are listed below:
COLR TS Section Technical Specifications Section Egge 3.1.1 Shutdown Margin 2.1 6 3.1.3 Moderator Temperature Coefficient 2.2 6 3.1.4 Shutdown Margin 2.1 6 3.1.5 Shutdown Margin 2.1 6 3.1.5 Shutdown Bank Insenion Limit 2.3 7 3.1.6 Shutdown Margin 2.1 6 3.1.6 Control Bank Insertion Limit 2.4 7 3.2.1 Heat Flux Hot Channel Factor 2.5 10 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 2.6 15 3.2.3 Axial Flux Difference 2.7 16 3.3.1 Reactor Trip System Instrumentation Setpoint 2.8 18 p 3.3.9 Boron Dilution Mitigation System 2.9 20 h 3.5.1 3.5.4 Accumulators Refueling Water Storage Tank 2.10 2.11 20 20 3.7.15 Spent Fuel Pool Boron Concentration 2.12 21 3.9.1 Refueling Operations - Boron Concentration 2.13 21 i 3.9.2 Refueling Operations -Instrumentation 2.14 21 !
The Selected Licensee Commitments that reference this report are listed below:
SLC Section Selected License Commitment Section Eagg 16.7-9.3 Standby Makeup Pump Water Supply 2.17 24 16.9-11 Borated Water Source-Shutdown 2.15 22 16.9-12 Borated Water Source-Operating 2.16 23 ,
i 2.0 Operating Limits l 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 j methodologies specified in Technical Specification 5.6.5. l 1 i i
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l CNEI-0400-24 Prge 6 of 24 Revision 14
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Catawba 1 Cycle 11 Core Operating Limits Report l
2.1 Shutdown Martin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6) 2.1.1 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2 with Keff < l.0 and in modes 3 and 4.
2.1.2 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.0% AK/K in mode 5.
2.1.3 For TS 3.1.4, shutdown margin shall be greater than or eq%i to 1.3% AK/K in mode 1 and mode 2. j 2.1.4 For TS 3.1.5, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 1 and mode 2 with any control bank not fully inserted. ,
2.1.5 For TS 3.1.6, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 1 and mode 2 with Keff 21.0. ,
2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The Moderator Temperature Coefficient (MTC) Limits are: ;
O The MTC shall be less positive than the upper limits shown in Figure 1. The i BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/'F. l The EOC, ARO, RTP MTC shall be less negative than the -4.1E-04 AK/K/ F lower MTC limit. !
I 2.2.2 The 300 ppm MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.2E-04 AK/K/ F.
2.2.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-3.85E-04 AK/K/ F.
Where: BOC = Beginning of Cycle ,
l EOC = End of Cycle !
ARO = All Rods Out i HZP = Hot Zero Thermal Power O RTP = Rated Thermal Power PPM = Parts per million (Boron) l
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Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report 2.3 Shutdown Bank Insertion Limit (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to at least 226 steps.
I 2.4 Control Bank Insertion Limits (TS 3.1.6) 2.4.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 2.
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CNEI-0400-24 Pige 8 of 24 Revision 14 q Catawba 1 Cycle 11 Com Operating Limits Report l
O Figum 1 Moderator Temperature Coemcient Upper Limit Versus Power Level 1.0 ;
0.9 -- i E Unacceptable Operation E 0.8 --
E 8 0.7 U 1 E 0.6 --
m E o 0.5 -- !
Eg i E y 0.4 -- Acceptable Operation '
H ct gO 0.3 --
C') E 0.2 --
v 1 2 0.1 --
1 0.0 l l l l l l l 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit 1 ROD manual for details. -
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I CNEI-0400-24 Pzge 9 of 24 Revision 14 Catawba 1 Cycle 11 Com Operating Limits Report
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Figum 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power r%11y Withdrawn (29.5 %,231) (80.0 %,231)
(Maximum = 231) N 31 __________ __________________ ________
220 -- \ tvilywithdrawn (Minimum = 226) 200 --
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(Control Bank B) l 5 180 --
gg ,_ (100 %,161) h
[.140 -- i I
05 (Control Bank C) j 120 --
m j
'5 100 -- I c >
. 80 --
q (Control Bank D)
) .$ 60 --
3 M 40 --(0*' 47) i 1
20 --
FullyInserted =
(30%,0) 0 '
. l l l l l \l l 0 10 20 30 40 50 60 70 80 90 100 l Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawallimits.
Refer to the Unit 1 ROD manual for details.
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CNEI-0400-24 '
Pege 10 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report 2.5 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) !
2.5.1 Fo(X,Y,Z) steady-state limits are defined by the following relationships:
Ff *K(Z)/P for P > 0.5 Ff *K(Z)/0.5 for P s 0.5 ;
4 j wkm, P = (Thermal Power)/(Rated Power) ,
Note: The measured Fn(X,Y,Z) shall be increased by 3% to account for ;
manufacturing tolerances and 5% to account for measurement uncenainty l
when comparing against the limits. The manufacturing tolerance and measurement uncenainty are implicitly included in the Fo surveillance limits i as defined in COLR Sections 2.5.5 and 2.5.6. ,
t 2.5.2 Ff = 2.50 x K(BU) l
-i 2.5.3 K(Z) is the normahzed FQ(X,Y,Z) as a function of core height for MkBW fuel and is provided in Figure 3.
2.5.4 K(BU) is the normahzed FQ(X,Y,Z) as a function of burnup for MkBW fuel and is provided in Figure 4.
The following parameters are required for core monitoring per the Surveillarse Requirements of Technical Specification 3.2.1:
F" 2.5.5 [F'(X,Y,Z)]*
q = o(X,Y,Z)
- M o(X,Y,Z)
UMT
[Ff(X,Y,Z)]* = Cycle dependent maximum allowable design peaking factor that
- - ensures that the F q (X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
1 Fj(X,Y,Z)OP ncludes i allowances for calculational and - -
measurement uncertainties.
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Revision 14
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Catawba 1 Cycle 11 Cost Operating Limits Report j j
F[(X,Y,Z) = Design power distribution for Fq. Ff(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 operation. l M n(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in !
the transient power distribution. Mq(X,Y,Z) is provided in Table 1, Appendix A for normal operating conditions and in i Table 2, Appendix A for power escalation testing during initial l startup operation.
UMT = Total Peak Measurement Uncertainty. (UMT = 1.05)
MT = Engineering Hot Channel Factor. (MT = 1.03)
, TILT = Peaking penalty that accounts for allowable quadrant power tilt L ratio of 1.02. (TILT = 1.035)
- NOTE
- F,'(X,Y,Z)" is the parameter identified as oF"(X,Y,Z) in DPC-NE-2011PA.
l I$(X,Y,Z)
- Mc(X,Y,Z) 2.5.6 [En(X,Y,Z)]RPs =
UMT
- TILT l
l where:
[Eq(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that i ensures that the Fn(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPRT limits. [Eq(X,Y,Z))RPS jnCludes allowances for Calculational and measurement uncertainties.
1 F$(X,Y,Z) = Design power distributions for Fn. Fn(X,Y,Z) is provided in Table 1, Appendix A for normal operating conditions and in i Table 2, Appendix A for power escalation testing during initial l
startup operations.
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- 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
!p parallel the M9(X,Y,Z) calculations described in DPC-NE-V 201 IPA, except that the LOCA limit is replaced with the CFM limit. Mc(X,Y,Z) is provided in Table 3, Appendix A for y
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CNEI-0400-24 l Page 12 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report normal operating conditions and in Table 4, Appendix A for power escalation testing during initial startup operations.
UMT = Measurement Uncenainty (UMT = 1.05)
MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty that accounts for alloweble quadrant power tilt ratio of 1.02. (TILT = 1.035)
NOTE: [ Ff (X,Y,Z)]"" is the parameter identified as F["(X,Y,Z) in DPC-NE-2011PA, except that Mo(X,Y,Z) is replaced by Mc(X,Y,Z).
2.5.7 KSLOPE = 0.0725 where:
KSLOPE = the adjustment to the K1 value from OTAT trip setpoint required to compensate for each 1% that F[(X,Y,Z) exceeds Fj(X,Y,Z)"".
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CNEI4400-24 Page 13 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report O
Figure 3 K(Z), Normalized Fn(X,Y,Z) as a Function of Core Height for MkBW Fuel 1.2 (0.0,1.00) (12.0,1.0) 0.8 --
h0.6--
0.4 --
0.2 --
0.0 l l l l 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
I CNEI-0400-24 Page 14 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report l
l Figure 4 K(BU), Normalized Fn(X,Y,Z) as a Function of Burnup for MkBW Fuel 1.2 i
(0.0,1.00) ( .0,1.W)
(45.0, 0.98) 0.8 -
(60.0,0.792)
S 6 0.6 --
w 0.4 -
1 0.2 -- t I
0.0 , l l :
0.0 10.0 20.0 30.0 40.0 50.0 60.0 I
- I Bumup(GWD/MTU) I I
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(~'N Catawba 1 Cycle 11 Core Operating Limits Report 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2) ,
i The FAH steady-state limits referred to in Technical Specification 3.2.2 is defined by the following relationship.
2.6.1 (FA(X,Y)]"= MARP (X,Y)
- 1.0 + RRH * (1.0 - P) where:
[Fh(X,Y)]" is defined as the steady-state, maximum allowed radial peak.
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MARP(X,Y) = Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(X,Y) radial peaking limits are provided in Table 7, Appendix A.
Thermal Power p , Rated Thermal Power l
(~]
RRH = Thermal Power reduction required to compensate for each 1% that the V measured radial peak, FA (X,Y), exceeds the limit. (RRH = 3.34) j The following parameters are required for core monitoring per the Surveillance I requirements of Technical Specification 3.2.2.
2.6.2 [Ph(X,Y)]suav = FE(X,Y)x M,(X,Y))
UMRxTILT where:
[ FA (X,Y)]*" = Cycle dependent maxunum allowable design peaking factor that ensares that the F,.,(X,Y) limit is not exceeded for operation within the AFI), RIL, and QPRT limits.
Ph (X,Y)8" includes allowances for calculational and measurement uncertainty. i Fa" (X,Y)= Design power distribution for F,, Fm (X,Y) is provided in
, Table 5, Appendix A for normal operation and in Table 6,
( Appendix A for power escalation testing during initial startup l operation.
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CNEl-0400-24 Page 16 of 24 i Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report M y,(X,Y) = The margin remaining in core location X,Y relative to the Operational DNB limits in the transient power distribution.
MAH(X,Y) is provided in Table 5, Appendix A for normal )
operation and in Table 6, Appendix A for power escalation l testing during initial startup operation.
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). l l
NOTE: [Eu,(X,Y)]suav is the parameter identified as u [F ,(X,Y)]m in DPC-NE-2011PA. l 2.6.3 RRH = 3.34 where:
RRH = Thermal Power reduction required to compensate for each 1% that the i
measured radial peak, F5 (X,Y) exceeds its limit O
V 2.6.4 TRH = 0.04 where:
TRH = Reduction in OTAT K 1setpoint required to compensate for each 1% that the measured radial peak, Fg (X,Y) exceeds its limit.
2.7 Axial Flux Difference- AFD (TS 3.2.3) 2.7.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.
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CNEI4400-24 Page 17 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report J
Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-l8,100) (+10,100)
Unacceptable Operation Unacceptable Operation 90 --
80 --
D 5
E 1G --
3l=
Acceptable Operation 60 --
2 E 50 --
$ (-36,50) (+21,50) 40 --
f 30 --
20 --
10 --
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-50 -40 -30 -20 -10 0 10 .20 30 40 50 Axial Flux Difference (% Delta 1)
NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits.
l Refer to the Unit 1 ROD manual for operational AFD limits.
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1 CNEI-0400-24 l Pege 18 of 24 Revision 14 l Catawba 1 Cycle 11 Core Operating Limits Report l i
2.8 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.8.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K 1= 1.1978 !
Overtemperature AT reactor trip heatup setpoint K2 = 0.03340/0F penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/ psi ;
setpoint penalty coefficient i Time constants utilized in the lead-lag compensator T1 = 8 sec.
for AT T2 = 3 sec. )
Time constant utilized in the lag compensator for AT T3 = 0 sec. .
Time constants utilized in the lead-lag compensator T4 = 22 sec, fort8 T5 = 4 sec.
Time constant utilized in the measured T.,, lag T6 = 0 sec. ,
compensator !
I f;(AI)" positive" breakpoint = 19.0 %AI
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f 1(AI) " negative" breakpoint = N/A*
l f 1(AI) " positive" slope = 1.769 %ATo/ %AI f t(AI)" negative" slope = N/A*
The fg(AI) " negative" breakpoint and the f}(AI) " negative" slope are not applicable since tie 3f (AI) function is not required below the f3(AI) " positive" breakpoint of 19.0% AI.
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CNEI-0400-24 P:ge 19 of 24 Revision 14 q Catawba 1 Cycle 11 Core Operating Limits Report 2.8.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4= 1.0864 l
Overpower AT reactor trip heatup setpoint K6 = 0.001179FF f penalty coef5cient (for T>T")
j j Time constants utilized in the lead-lag t i= 8 sec. j compensator for AT T2= 3 sec. !
Time constant utilized in the lag T3= 0 sec.
compensator for AT t
l Time constant utihzed in the measured Tavs T6 = 0 sec. l l lag compensator s l Time constant utilized in the rate-lag 57= 10 sec.
l controller for T,v, l 1
1 f 2(AI) " Positive" breakpoint
= 35.0 %AI f 2(AI) " negative" breakpoint = -35.0 %AI f2(AI) " Positive" slope = 7.0 %AT/ %AI f 2(AI) " negative" slope = 7.0 %AT/ %AI 1'
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CNEl-0400-24 Page 20 of 24 Revision 14 Catawha 1 Cycle 11 Core Operating Limits Report
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2.9 Boron Dilution Mitigation System (TS 3.3.9) 2.9.1 Reactor Makeup Water Pump flowrate limits:
Applicable Mode Limit Mode 3 s 150 gpm Mode 4 or 5 s 70 gpm 2.10 Accumulators (TS 3.5.1) 2.10.1 Boron concentration limits during modes 1 and 2, and mode 3 with RCS pressure
>1000 psi:
, Parameter Limit
' O Cold Leg Accumulator minimum boron concentration. 2,575 ppm Cold Leg Accumulator maximum boron concentration. 2,975 ppm l
l l 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 1 -
2.11.1 Boron concentration limits during modes 1,2,3, and 4:
Parameter Limil Refueling Water Storage Tank minimum boron 2,775 ppm l concentration.
Refueling Water Storage Tank maximum ix,.on 2.975 ppm concentration.
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CNEI4)400-24 l Pzge 21 of 24 l Revision 14 i
Catawba 1 Cycle 11 Core Operating Limits Report 2.12 Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.12.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel j assemblies are stored in the spent fuel pool.
Parameter Limit i
Spent fuel pool minimum boron concentration. 2,775 ppm t
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2.13 Refueling Operations - Boma Concentration (TS 3.9.1) 2.13.1 Minimum boron concentration limit for the filled portions of tie Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions. The mimmum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the mode 6 reactivity requirement of Keffs 0.95.
Parameter Limit Minimum Boron concentration of the Reactor Coolant 2,775 ppm System, the refueling canal, and the refueling cavity.
t 2.14 Refueling Operations - Instmmentation (TS 3.9.2) 2.14.1 Reactor Makeup Water Pump Flowrate Limit:
Applicable Mode Limit Mode 6 s 70 gpm l
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CNEI-0400-24 Page 22 of 24 Revision 14 p Catawba 1 Cycle 11 Core Operating Limits Report 2.15 Borated Water Source-Shutdown (SLC 16.911) 2.15.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during mode 4 with any RCS cold leg temperature s 285 F, and modes 5 and 6.
Parameter liant Boric Acid Storage System minimum contained 12,000 gallons borated water volume Boric Acid Storage System nunimum boron 7,000 ppm j concentration i Boric Acid Storage System mmimum water volume 585 gallons l required to maintain SDM at 7,000 ppm l , Refueling Water Storage Tank minimum contained 45,000 gallons l C borated water volume l
l Refueling Water Storage Tank minimum boron 2,775 ppm concentration Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,775 ppm I
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CNEl-0400-24 Pzge 23 of 24 Revision 14 Catawba 1 Cycle 11 Core Operating Limits Report -
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2.16 Borated Water Source - Operating (SLC 16.912) I 2.16.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, and mode 4 with all RCS cold leg temperatures > 285 F.
Parameter At Boric Acid Storage System minimum contained 24,000 gallons borated water volume Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System minimum water volume 11,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 98,607 gallons borated water volume Refueling Water Storage Tank minimum boron 2,775 ppm concentration Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,775 ppm 1
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i 2.17 Standby Makeup Pump Water Supply - Bomn Concentration (SLC-16.7-9.3) ;
3 2.17.1 Minimum boron concentration limit for the spent fuel pool. Applicable for modes l 1,2, and 3. ;
f Parameter Linut l
Spent fuel pool muumum boron concentration for 2,775 ppm l l surveillance SLC-16.7-9.3. l t
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l NOTE: Data contained in the Appendix to this document was generated in the Catawba 1 Cycle '
! 11 Maneuvering Analysis calculation file, CNC-1553.05-00-0266. The Plant Nuclear Engineering Section will control this information via computer file (s) and should be l O contacted if there is a need to access this information. !
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