ML20203A410
| ML20203A410 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/22/1998 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20203A401 | List: |
| References | |
| CNEI-0400-25, CNEI-0400-25-R16, CNEI-400-25, CNEI-400-25-R16, NUDOCS 9902090355 | |
| Download: ML20203A410 (24) | |
Text
I CNEI-0400-25 Page 1 of 24 Revision 16 Catawba Unit 2 Cycle 10 Core Operating Limits Report Revision 16 December 1998 Duke Power Company Date Prepared By: OMI/
/p d-78 f69f Checked By:
(?L & AntA it./n(/rs' O
Checked By:
//
/.tja.t /n a
y-i Approved By:
MM
/2/J.2/fr QA Condition 1 The contents of this document have been reviewed to verify that to material herein either directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 Catawba 2 Cycle 10 Reload Safety Evaluation.
9902090355 990128 P
PDR ADOCK 05000413 P
PDR 1
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CNEI4400-25 Page 2 of 24 Revision 16 l
Catawba 2 Cycle 10 Com Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 16 Revision 16 of the Catawba Unit 2 COLR updates this report to be compliant with the Improved Technical Specifications (ITS). This revision should be implenwnted concurrently with the release ofITS.
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CNEI-0400-25 Pege 3 of 24 Revision 16 OU Catawba 2 Cycle 10 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR OriginalIssue February 1993 N/A C2C06 COLR Revision 1 April 1994 N/A C2C06 COLR rev 1 Revision 2 May 1994 N/A C2C07 COLR Revision 3 October 1994 N/A C2C07 COLR rev 1 Revision 4 April 1995 N/A C2C07 COLR rev 2 Revision 5 September 1995 N/A C2C07 COLR rev 3 Revision 6 October 1995 N/A C2C08 COLR Revision 7 September 1996 N/A C2C08 COLR rev 1
[
Revision 8 March 1997 N/A C2C08 COLR rev 2 Revision 9 March 1997 N/A C2C09 COLR Revision 10 April 1997 N/A C2C09 COLR rev 1 Revision 11 June 1997 N/A C2C09 COLR rev 2 Revision 12 July 1997 N/A C2C09 COLR rev 3 Revision 13 August 1997 N/A C2C09 COLR rev 4 Revision 14 August 1998 N/A C2C10 COLR Revision 15 October 1998 N/A C2C10 COLR rev 1 Revision 16 December 1998 1-24 C2C10 COLR rev 2 l
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CNEI-0400-25 Page 4 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report I
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INSERTION SHEET FOR REVISION 16 1
Remove pages Insert Rev.16 pages 1
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Pages 1-22 Pages 1-24 i
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1 CNEI-0400-25 Page 5 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report 1.0 Core Operating Limits Report 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 Eage 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 Insertion Lirrit 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 AxialFlux Difference 2.7 16 3.3.1 Reactor Trip System Instrumentation Setpoint 2.8 18 O
3.3.9 Boron Dilution Mitigation System 2.9 20 3.5.1 Accumulators 2.10 20 3.5.4 Refueling Water Storage Tank 2.11 20 3.7.15 Spent Fuel Pool Boron Concentration 2.12 21 3.9.1 Refueling Operations - Boron Concentration 2.13 21 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 Ea&G 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
- 2.0 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 5.6.5.
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CNEl-0400-25 P:ge 6 of 24 Revision 16 l
l Catawba 2 Cycle 10 Core Operating Limits Report 2.1 Shutdown Margin - 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 i
mode 2 with Keff < 1.0 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 equal to 1.3% AK/K in mode 1 and mode 2.
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 Temperatum Coefficient - MTC (TS 3.1.3) 2.2.1 The Moderator Temperature Coefficient (MTC) Limits are:
q U
The MTC shall be less positive than the upper 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 the -4.1E-04 AK/K/ F lower MTC limit.
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:
l The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equan..
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-3.85E-04 AK/K/'F.
I Where:
BOC = Beginning of Cycle l-EOC = End of Cycle ARO = All Rods Out l
HZP = Hot Zero Thermal Power l
RTP = Rated Thermal Power PPM = Parts per million (Boron)
CNEI-0400-25 Page 7 of 24 Revision 16 Catawba 2 Cycle 10 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.
2.4 Control Bank Insedion 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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. -. - ~ ~ -. -.
I CNEI-0400-25 Page 8 of 24 Revision 16
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Catawba 2 Cycle 10 Core Operating Limits Report Figure 1 Moderator Temperature Coemclent Upper Limit Versus Power Level 1.0 0.9 --
Unacceptable Operation e
E 0.8 --
E 8
0.7 0
2 0.6 --
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1 2A 0.5 --
E 3 l g 0.4 --
Acceptable Operation H *!
gC 0.3 --
(O 0.2 --
u) 3 E
0.1 --
0.0 0
10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power I
NOTE: Compliance with Technical Specificati9n 3.1.3 may require rod withdrawal limits.
Refer to the Unit 2 ROD manual for details.
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CNEI-0400-25 Pige 9 of 24 Revision 16 Q
Catawba 2 Cycle l'J Core Operating Limits Report O
Figure 2 Contml Bank Insertion Limits Versus Percent Rated Thermal Power i
Fully Withdrawn (29.5 %.231)
(Maximum = 231) 'N (80.0 %.231) 231 220 --
\\ Pullywithdrawn 200 --
(Minimum = 226) 180 --
' 160 --(o%.163)
E g.140 --
G (Control Bank C) j 120 --
c
'E 100 --
A O
80 --
(Control Bank D) an 3
a: 4_30 %.47) 20 --
Fullyinserted\\l I
(30%. o) 0 l
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0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power i
NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit 2 ROD manual for details.
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I CNEI-0400-25 Page 10 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report l
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:
F* *K(Z)/P for P > 0.5 g
F" *K(Z)/0.5 for P s 0.5 g
I
- where, P = (ThermalPower)/(Rated Power)
Note: The measured Fo(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the Fo surveillance limits as defined in COLR Sections 2.5.5 and 2.5.6.
2.5.2 F" = 2.50 x K(BU)
O 2.5.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height for MkBW fuel and is provided in Figure 3.
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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 Surveillance l
Requirements of Technical Specification 3.2.1 1
Fn(X,Y,Z)
- M (X,Y,Z) 2.5.5 ((n(X,Y,Z)]oP =
o
. g where:
[Ff(X,Y,Z)]oP = Cycle dependent maximum allowable design peaking factor that ensures that to the Fn(X,Y,Z) LOCA limit is not exceeded for I
operation within the AFD, RIL, and QIrTR limits.
Fj(X,Y,Z)OP ncludes allowances for calculational and i
e measurenent uncertainties.
-g..
,,=~
_ _ _ _. ~. _ ~
CNEl-0400-25 Page 11 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report F[(X,Y,Z) = Design power distribution for F. F[(X,Y,Z) is provided in q
Table 1, Appendix A, for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial stanup operation.
M (X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in n
the transient power distribution. M (X,Y,Z) is provided in q
Table 1 Appendix A for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial 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 ratio of 1.02. (TILT = 1.035)
NOTE:
F'(X,Y,Z)# is the parameter identified as F"(X,Y,Z) in DPC-NE-2011PA.
g o
O F"(X,Y,Z)
- M (X,Y,Z) 2.5.6 [Fq'(X,Y,Z)]aPs q
c
=
UMT
- MT * 'I'IL'I' where:
[F'(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that q
- ensures that the Fq(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPRT limits. [F'(X,Y,Z)]RPS jncludes allowances for calculational and q
measurement uncertainties.
Fq"(X,Y,Z) = Design power distributions for Fn. 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.
l M (X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z from c
the transient power distribution. M (X,Y,Z) calculations c
parallel the M (X,Y,Z) calculations described in DPC-NE-n 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 a.
CNEI-0400-25 Page 12 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report normal operating conditions and in Table 4, Appendix A for power escalation testing during initial startup operations.
UMT = Measurement Uncertainty (UMT = 1.05) i 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: [ Fj (X,Y,Z)]"" is the parameter identified as Ff" (X,Y,Z) in DPC-NE-2011PA, except that M (X,Y,Z) is replaced by Mc(X,Y,Z).
n 2.5.7 KSLOPE = 0.0725 where:
KSLOPE = the adjustment to the K value from OTAT trip setpoint required to 1
compensate for each 1% that F[(X,Y,Z) exceeds Fj(X,Y,Z)"".
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CNEI-0400 25 Page 13 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report Figure 3 K(Z), Normalized Fn(X,Y,Z) as a Function of Core Height for MkBW Fuel 1.2 (0.0,1.00)
(8.0,1.00) 1.0 (12.0,0.95) 0.8 --
h0.6--
0.4 --
0.2 --
i 0.0 l
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0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
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~..--
..._._. -.~.-...- -_.
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CNEl-0400-25 Page 14 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report Figuur 4 K(BU), Normalized F (X,Y,Z) as a Function of Burnup for MkBW Fuel q
1.2 (30.0,1.00)
(
)
1.0 (45.0,0.98) i 0.8 --
(60.0,0.868)
Sg 0.6 --
M 0.4 --
0.2 --
0.0 l
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0.0 10.0 20.0 30.0 40.0 50.0 60.0 Burnup (GWD/MTU) k
CNEl-0400-25 Page 15 of 24 Revision 16 Catawba 2 Cycle 10 Com Operating Limits Report 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)
The FAH steady-state limits referred to in Technical Specification 3.2.2 is def'med by the following relationship.
2.6.1
[Fh(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.
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 RRH = Thermal 1 ower reduction required to compensate for each 1% that the measured radial peak, Fh (X,Y), exceeds the limit. (RRH = 3.34)
The following parametera are required for core monitoring per the Surveillance requirements of Technical Specification 3.2.2.
2.6.2 [Ph(X,Y)]suny Ff,i(X,Y)x M,(X,Y))
=
UMR xTILT where:
[ Ph (X,Y)]'""" = Cycle dependent maximum allowable design peaking factor that ensures that the F,(X,Y) limit is not exceeded for operation within the AFD, RIL, and QPRT limits.
Fh(X,Y)8URV includes allowances for calculational and measurement uncertainty.
Fm (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 operation.
r CNEI-0400-25 Page 16 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report i
M,(X,Y) = The margin remaming 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 testing during initial startup operation.
l UMR = Uncertainty value for measured radid 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).
NOTE: [Fm' (X,Y)]suav is the parameter identified as [F,(X,Y)]m in DPC-NE-2011PA.
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2.6.3 RRH = 3.34 where:
RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, F," (X,Y) exceeds its limit.
i 2.6.4 TRH = 0.04 where:
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TRH =
Reduction in OTAT K setpoint required to compensate for each 1% that 1
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the measured radial peak, FAH (X,Y) exceeds its limit.
2.7 Axial Flux Difference-AFD (TS 3.2.3) 2.7.1 The Axial Flux DifTerence (AFD) Limits are provided in Figure 5.
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CNEI-0400-25 i
Page 17 of 24 Revision 16 Catawba 2 Cycle 10 Com Operating Limits Report l
Figum 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-20,100)
(+10,100)
~
Unacceptable Operation Unacceptable Operation 90 --
l 80 --
70 --
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[
~ Acceptable Operation 60 --
T 50 --
h
(-36,50)
(+21,50) 40 --
30 --
20 --
10 --
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0 l
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-50
-40
-30
-20
-10 0
10 20 30 40 50 AxialFlux Difference (% Delta 1) 1 NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits.
Refer to the Unit 2 ROD manual for operational AFD limits.
CNEI-0400-25 Page 18 of 24 Revision 16 1
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\\O Catawba 2 Cycle 10 Core Operating Limits Report 2.8 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 l
2.8.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K1 = 1.1953 Overtemperature AT reactor trip heatup setpoint K2 = 0.03163/0F penalty coefficient Overteniperature AT reactor trip depressurization K3 = 0.001414/ psi setpoint penalty coefficient Tirre constants utilized in the lead-lag compensator ij = 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.
for T,
T5 = 4 sec.
Time constant utilized in the measured T.,, lag t6 = 0 sec.
compensator f (AI) " positive" breakpoint
= 3.0 %AI t
f (AI)" negative" breakpoint
= -39.9 %AI 1
f (AI)" positive" slope
= 1.525 %ATo/ %AI 1
f (AI) " negative" slope
= 3.910 %ATo/ %AI 1
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CNEI-0400-25 Page 19 of 24 Revision 16 Catawba 2 Cycle 10 Core Operating Limits Report i.
2.8.2 Overpower AT Setpoint Parameter Values Parameter Value l
Overpower AT reactor trip setpoint K4 = 1.0819 Overpower AT reactor trip heatup setpoint K6 = 0.001291FF penalty coefficient (for T>T")
Time constants utihzed in the lead-lag T = 8 sec.
i compensator for AT T = 3 sec.
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Time constant utilized in the lag T = 0 sec.
3 compensator for AT L
Time constant utihzed in the measured T.,,
T6 = 0 sec.
lag compensator Time constant utihzed in the rate-lag T = 10 sec.
7 controller for T.y.
l f (AI) " positive" breakpoint
= 35.0 %AI 2
i 4
l f (AI) " negative" breakpoint
= -35.0 %AI 2
f (AI) " Positive" slope
= 7.0 %ATg %AI 2
i f (AI) " negative" slope
= 7.0 %ATg %AI 2
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CNEI-0400-25 Page 20 of 24 Revision 16 D
Catawba 2 Cycle 10 Com Operating Limits Report 2.9 Boron Dilution Mitigation System (TS 3.3.9) 2.9.1 Reactor Makeup Water Pump flowrate limits:
Applicable Mode Limil Mode 3 s 150 gpm Mode 4 or 5 s 70 gpm I
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 Limil
>O Cold Leg Accumulator muumum boron concentration.
2,500 ppm Cold I2g Accumulator maximum boron concentration.
3,075 ppm 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.11.1 Boron concentration limits during modes 1,2,3, and 4:
Parameter Limit i
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Refueling Water Storage Tank minimum boron 2,700 ppm concentration.
Refueling Water Storage Tank maximum boron 3,075 ppm concentration.
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CNEI-0400-25 P:ge 21 of 24 Revision 16 Catawba 2 Cycle 10 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 assemblies are stored in the spent fuel pool.
Parameter Limil Spent fuel pool mimmum boron concentration.
2,700 ppm 2.13 Refueling Operations - Boron Concentration (TS 3.9.1) 2.13.1 Minimum boron concentration limit for the filled portions of the 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 Keff s 0.95.
Parameter Lim!L Minimum Boron concentration of the Reactor Coolant 2,700 ppm System, the refueling canal, and the refueling cavity.
2.14 Refueling Operations - Instrumentation (TS 3.9.2) 2.14.1 Reactor Makeup Water Pump Flowrate Limit:
Applicable Mode Limil Mode 6 s 70 gpm O
_._m.
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Catawba 2 Cycle 10 Core Operating Limits Report i
l 2.15 Borated Water Source-Shutdown (SLC 16.9-11) 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.
l Parameter Limit Boric Acid Storage System mmimum contamed 12,000 gallons borated water volume
. Boric Acid Storage System mmimum boron 7,000 ppm concentration Boric Acid Storage System minimum water volume 585 gallons I
required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 45,000 gallons l
borated water volume Refueling Wster Storage Tank minimum boron 2,700 ppm concentration l
l Refueling Water Storage Tank mimmum water 3,500 gallons volume required to maintain SDM at 2,700 ppm l
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w-wr-y
CNEI4)400-25 P:ge 23 of 24 Revision 16 z
Catawba 2 Cycle 10 Core Operating Limits Report 2.16 Borated Water Source - Operating (SLC 16.912) 4 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 i
RCS cold leg temperatures > 285 F.
Parameter Limit Boric Acid Storage System minimum contained 24,000 gallons borated water volume i
Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System mmimum water volume 11,851 gallons required to maintain SDM at 7,000 ppm n
Refueling Water Storage Tank minimum contained 98,607 gallons borated water volume Refueling Water Storage Tank minimum boron 2,700 ppm concentration 4
Refueling Water Storage Tank muumum water 57,107 gallons volume required to maintain SDM at 2,700 ppm j
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CNEI-0400-25 l
Page 24 of 24 Revision 16 Catawba 2 Cycle 10 Core Om.dr.i; I.Lmits Report 2.17 Standby Makeup Pump Water Supply - Boron Concentratioa (SLC-16.7-9.3) 2.17.1 Minimum boron concentration ihnit for the spent fuel pool. Applicable for modes 1,2, and 3.
Parameter Limil Spent fuel pool muumum boron concentration for 2,700 ppm surveillance SLC-16.7-9.3.
NOTE: Data contained in the Appendix to this document was generated in the Catawba 2 Cycle 10 Maneuvering Analysis calculation file, CNC-1553.05-00-0291. The Plant 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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