ML20196G058
| ML20196G058 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/06/1998 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20196G051 | List: |
| References | |
| MCEI-0400-06-R17, MCEI-0400-46-01, MCEI-400-46-1, MCEI-400-6-R17, NUDOCS 9812070230 | |
| Download: ML20196G058 (44) | |
Text
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Page I cf 22 Revision 17 McGuire Unit 1 Cycle 13 Core Operating Limits Report Revision 17 November 1998 Calculation Number: MCC-1553.05-00-0274, Rev. 2 Duke Power Company i
Date
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Prepared By:
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Checked By:
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Approved By:
/2f/(fe/ -
/fd/fr QA Condition 1 1
NOTE 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 MlCl3 Reload Safety Evaluation (calculation file: MCC-1552.08-004284).
9812070230 981123 PDR ADOCK 05000369 i
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MCEI-0400-46 Page 2 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report i
IMPLEMENTATION INSTRUCTIONS FOR REVISION 17 I
Revision 17 of the McGuire Unit 1 COLR updates this mport to be compliant with th i
i Improved Technical Specifications (ITS). This revision should be implemented concurrently with this micase ofITS.
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Page 3 Cf 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report
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j REVISION LOG I
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i Revision Efffective Date Effective Panes COLR OriginalIssue May 24,1993 N/A M1C09 Revision 1 May 27,1993 N/A MIC09, Rev. I Revision 2 Febmary 24,1994 N/A M1C09, Rev. 2
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t Revision 3 June 20,1994 N/A M1C09, Rev. 3 Revision 4 September 13,1994 N/A MIC10 i
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Revision 5 October 18,1994 N/A MICIO, Rev. I i
l Revision 6 -
October 24,1994 N/A MICIO, Rev. 2 i
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Revision 7 June 26,1995 N/A M1CIO, Rev. 3 Revision 8 November 28,1995 N/A MIC10, Rev. 4 Revision 9 December 14,1995 N/A MICI1 i
Revision 10 Mamh 11,1996 N/A MIC11, Rev.1 l
Revision 11 June 24,1996 N/A MICil, Rev. 2
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Revision 12 Febmary 13,1997 N/A MIC12 i
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Revision 13 June 13,1997 N/A MICl2, Rev. I l
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Revision 14 July 08,1997 N/A MIC12, Rev. 2 Revision 15 Mamh 12,1998 N/A MIC12, Rev. 3 Revision 16 May 27,1998 1-21 MICl3 Revision 17 November 6,1998 1-22 M1C13, Rev 2*
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MCEI-0400-46 Page 4 cf 22 4
Revision 17 McGuire I Cycle 13 Core Operating Limits Report INSERTION SHEET FOR REVISION 17 Remove pages Insert Rev.17 pages Pages 1-21 Pages 1-22 w.
a
MCEI-0400-46 I
Page 5 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report
' Core Operating Limits Report
' 1.0 -
i This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of the Technical Specification Limiting Conditions for Operation (LCO))
l from Section 5.6.5.
t i
The Technical Specifications that reference this report are listed below:
Technical Specifications Section Page l.1 Requirements for Operational Mode 6 2.1 5
3.1.1 Shutdown Margin 2.2 6
)
3.1.3 ModeratorTemperature Coefficient 2.3 6
i 3.1.5 Shutdown BankInsertion Limit 2.4 6
3.1.6 Control BankInsertion Limit 2.5 6
3.2.1 Heat Flux Hot Channel Factor 2.6 9
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 2.7 14 3.2.3 Axial Flux Difference 2.8 15 t
3.3.1 Reactor Trip System Instrumentation Setpoint 2.9 17 3.5.1 Accumulators 2.10 19 3.5.4 Refueling Water Storage Tank 2.11 19 3.7.14 Spent Fuel Pool Boron Concentration 2.12 20 3.9.1 Refueling Operations - Boron Concentration 2.13 20 The Selected Licensee Commitments that reference this report are listed below:
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SLC Section Selected License Commitment Section Page
{
16-15.3.1.2.5 Borated Water Source-Shutdown 2.14 21
)
16-15.3.1.2.6 Borated Water Source-Operating 2.15 22 2.0 Operating Limits 1
The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in i
the following subsections. These limits have been developed using NRC approved methodologies specified in Technical Specification 5.6.5.
2.1 Requirements for Operational Mode 6 The following condition is required for operational mode 6.
2.1.1 The Reactivity Condition requirement for operational mode 6 is that kerrmust be less than, or equal to 0.95.
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MCEl-040046 i
Page 6 cf 22 Revision 17 McGuire I Cycle 13 Core Operating Limits Report i
2.2
, Shutdown Margin -SDM (LCO 3.1.1) 2.2.1 Shutdown margin shall be greater than 1.3% AK/K in modes 1-4.
2.2.2 Shutdown margin shall be greater than or equal to 1.0% AK/K in mode E i
2.3 Moderator Temperature CoefTicient - MTC (LCO 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) ILO Limits are:
l 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.
l The EOC, ARO, RTP MTC shall be less negative than the -4.lE-04 AK/K/ Flower MTC i
limit.
l 2.3.2 The 300 ppm MTC Surveillance Limit is:
i The measured 300 PPM ARO, equilibrium RTP MTC should be less negative than or l
equal to -3.2E-04 AK/K/ F.
l 1
s 2.3.3 The 60 PPM MTC Surveillance Limit is:
t The 60 PPM ARO, equilibrium RTP MTC should be less negative than or equal to
-3.85E-04 AK/K/*F.
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Where:
. BOC = Beginning of Cycle EOC = End of Cycle ARO = All Rods Out HZP = Hot Zem Thermal Power RTP = Rated Thermal Power i
PPM = Parts per million (Bomn) 2.4 Shntdown Bank Insertion Limit (LCO 3.L5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps.
2.5 Control Bank Insertion Limits (LCO 3.1.6) i i
2.5.1 Control banks shall be within the LCO insertion, sequence, and overlap limits shown in Figure 2.
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MCEI-040046 Page 7 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report l
i Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 i
0.9 --
g
- c 0.8 --
Unacceptable Operation 0.7 2
0.6 --
5g E o 0.5 --
E E E$ g '0.4 --
Acceptable Operation et gC 0.3 --
0.2 --
T E
0.1 --
0.0 O
10 20 30 40 50 60 70 80 90 100 1
Percent of Rated Thermal Power i
NOTE: Compliance with Technical Specification LCO 3.1.3 may requi;e rod withdrawal limits. Refer to OP/1/A/6100/22 Unit 1 Data Book for details, l
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l MCEI4400-46 Pcge 8 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report l
Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power l
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i (Fully Withdrawn min - 222, max - 231) 240 (216%,231) l 220 g
(80.0 %,231)
,p t
j 200 l
180 Bank B 160 (100%.161) l Rod j (0%,163)j i
140 insertion Position 120
/
Bank C l
(Steps Withdrawn) l
/
B0 60
'/
Bank D 40 j (0%,47) l 20 j~
(30% 0) j 0
O 10 20 30 40 50 60 70 80 90 100 (Fullyinserted)
Relative Power (Percent)
?
NOTE: Compliance with Technical Specification LCO 3.1.3 may require rod withdrawal limits. Refer to OP/1/A/6100/22 Unit i Data Book for details.
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i MCEI-0400-46 Page 9 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report i
2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (LCO 3.2.1) 2.6.1 Fn(X,Y,Z) steady-state limits are defined by the following relationships:
F
- K(Z)/P for P > 0.5 Q
1 F
- K(Z)/0.5 for P s 0.5 q
i
- whem, P = (Thermal Power)/(Rated Power) j
- Note:
The measund 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 ILO limit.
The manufacturing tolerance and measurement uncertainty are implicitly included in the Fq surveillance limits as defined in Sections 2.6.5 and 2.6.6.
2.6.2 F
= 2.50 x K(BU)
Q 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height for MkBW fuel and is provide:iin Figure 3.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup for MkBW fuel and is provided in Figure 4.
l The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification LCO 3.2.1:
F (X,Y,Z)OP = F (X,Y,Z) x Mg(X,Y,Z)/(UMT x MT x TILT)
2.6.5 where
F (X,Y,Z)OP =
cycle dependent maximum allowable design peaking factor which ensures that the FQ(X,Y,Z) limit will be preserved for operation I:
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_ _ _ _ _ _ _ _ - - - - - - - - - - - - - -- q MCEI4400-46 Page 10 of 22 Revision 17 McGuire 1 Cyc!e 13 Core Operating Limits Report within the LCOlimits, h(X,Y,Z)OP q
includes allowances for calculational and measurement uncenainties.
(X,Y,Z) = design power distribution for FQ. F (X,Y,Z) is provided in Table 1, 9
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Appendix A, for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operation.
MQ(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 Table 2, Appendix A for power escalation testing during initial stanup operation.
UMT = Total Peak Measurement Uncenainty, = 1.05.
MT=
Engineering Hot Channel Factor, = 1.03.
TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02.
(TILT = 1.035)
NOTE: h(X,Y,Z)OP q
is the parameteridentified as (X,Y,Z) in DPC-NE-2011PA.
q h(X,Y,Z)RPS =
2.6.6 (X,Y,Z) x (M (X,Y,Z)/(UMT x MT x TILT))
q C
where:
h(X,Y,Z)RPS =
q cycle dependent maximum allowable design peaking factor which ensures that the centerline fuel melt (CFM) limit will be preserved for operation within the LCO limits. h(X,Y,Z)RPS q
includes allowances for calculational and measurement uncertainties.
F (X,Y,Z) = design power distributions for FQ. F (X,Y,Z)is provided in Table 1, 9
9 Appendix A for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial stadup operation.
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Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report M (X,Y,Z) = margin remaining to the CFM limit in com location X,Y,Z from the C
transient power distribution. M (X,Y,Z) calculations parallel the C
M (X,Y,Z) calculations described in DPC-NE-201 IPA, except that Q
the LOCA limit is replaced with the CFM limit. M (X,Y,Z) is C
provided in Table 3, Appendix A for normal operating conditions and in Table 4, Appendix A for power escalation testing during initial startup operation.
UMT = Total Peak Measurement Uncertainty, = 1.05.
MT=
Engineering Hot Channel Factor, = 1.03.
TILT = Factor to account for a peaking increase due to'the allowed quadrant po tilt ratio of 1.02. (TILT = 1.035).
NOTE: k('X,Y,Z)RPS g
is the parameteridentified as q (X,Y,Z) in DPC-NE-2011PA, except that MQ(X,Y,Z) is replaced by MC(X,Y,Z).
2.6.7 KSLOPE = 0.0725 KSLOPE is the adjustment to the K value from OTAT trip setpoint mquired to 1
compensate for each 1% that Ff (X,Y,Z) exceeds q(X,Y,Z)RPS,
_ = = -..
MCEI-0400-46 Page 12 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report Figure 3 q
K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for MkBW Fuel d
1.00 ::
0.90 - (0010)
(12.0,1.0) 0.80 --
,_., 0.70 --
ti W 0.60 --
1
,3
.50'--
0 a
@ 0.40 --
C Z ' O.30 --.
0.20 --
0.10 --
i O.00 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft.)
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MCEIh6 Page 13 of 22 l
Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report Figure 4 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for MkBW Fuel 1.000 ::
0.900 -- (0,1.0)
(30.0,1.0)
(45.0.0.98) 0.800 --
I
$ 0.700 --
(60.0.0.792)
B g 0.600 --
0 500 --
g 0.400 --
$ 0.300 --
l t
0.200 --
l 0.100 --
+
0.000 0
10 20 30 40 50 60 Burnup (GWD/MTU)
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Page 14 of 22 Revision 17 l
McGuire 1 Cycle 13 Core Operating Limits Report 2.7 ? Nuclear Enthalpy Rise Hot Channel Factor - F t
AH(X,Y) (LCO 3.2.2)
'The Fyg steady-state limits referred to in Technical Specification L the following relationship.
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i AH(X,Y)LCO = MARP (X,Y) x [1.0 + (1/RRH) x (1.0 - P)]
2.7.1 F i
i where:
(X,Y)LCO is def'med as the steady-state, maximum allowed radial peak.
b F
MARP(X,Y) = Cycle-specific operating limit Maximum Allowable Radial Peaks.
[
MARP(X,Y) radial peaking limits are provided in Table 7, Appendix A.
p, Thermal Power i
Rated Thermal Power RRH = 3.34 when 0.0 < P s 1.0, and i
2RH = Thermal Power reduction required to compensate for each 1% that the i
measured radial peak,F (X,Y), exceeds the limit.
The following parameters are required for core monitoring per the Surveillance requirem of Technical Specification LCO 3.2.2.
2.7.2 F g(X,Y)SURV = F (X,Y) x My3(X,Y)/(UMR x TILT)
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where:
H(X,Y)SURV =
cycle dependent maximum allowable design peaking factor F
which ensures that the FAH(X,Y) limit will be preserved for operation within the LCO limits. F (X,Y)SURV includes allowances for calculational and measurement uncertainty.
,,m c
=
Page 15 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report k
F (X,Y) =
the design power distribution for FAH.F (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.
MAH(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 testing during initial startup operation.
UMR=
Uncertainty value for measured radial peaks, = 1.04.
TILT =
Factor to account for a peaking increase due to the allowed quadrant tilt ratio of 1.02. (TILT = 1.035).
NOTE: F (X,Y) SURV is the parameter identified as PhAX (X,Y) in DPC-NE-201 IPA.
2.7.3 RRH = 3.34 when 0.0 < P s 1.0, where:
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RRH = Thermal Power reduction required to compensate for each 1% that the
{
measured radial peak, F (X,Y) exceeds its limit.
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2.7.4 TRH = 0.04 where:
l TRH =
Reduction in OTAT K setpoint required to compensate for each 1% that i
1 l
i the measured radial peak, F (X,Y), exceeds the linit.
2.8 Axial Flux DifTerence - AFD (LCO 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.
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Page 16cf 22 R: vision 17 McGuire I Cycle 13 Ctre Operating Limits Report Figure 5 i
Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits lL" 110 --
U l (-18.100)l g
.mm
)
A l
90 --
(+10,100) l Unacceptable operation l 80 --
)
h 70 l Unacceptable operation l 60 --
l' W
l Acceptable operation l 50 --
Ct o
l (-36.50)]
40 l (421.50)l j
30 --
20 --
A 10 --
n
-50
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (% Delta I) l l
NOTE:
Compliance with Technical Specification LCO 3.2.1 may require more restrictive AFD limits. Refer to OP/1/A/6100/22 Unit i Data Book for details.
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Page 17 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (LCO 3.3.1) Table 3.3.1 1 2.9.1 Overtemperature AT Setpoint Parameter Values I
Parameter Value l
Overtemperature AT reactor trip setpoint K s1.1978 1
Ovenemperature AT reactor trip heatup setpoint K2 = 0.0334/0F penalty coefficient s
Ovenemperature AT reactor trip depressurization K3 = 0.001601/ psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator tg 2 8 sec.
forAT T2 s 3 sec.
Time constant utilized in the lag compensator for AT T3 s 2 sec.
Time constants utilized in the lead-lag compensator T 2 28 sec.
4 for T..,
T5 s 4 sec.
)
Time constant utilized in the measured T., lag t6 s 2 sec.
i compensator f (AI) " positive" breakpoint
= 19.0 %AI 1
f (AI) " negative" breakpoint
= N/A*
1 f (AI) " positive" slope
= 1.769 %ATo/ %Al 1
i f (AI)" negative" slope
= N/A*
1 The f (AI)." negative" breakpoint and the fg(AI) " negative" slope are not applicable since the f (Al) t t
function is not required below the f (AI) " positive" breakpoint of 19.0% Al.
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. McGuire 1 Cycle 13 Core Operating Limits Report
- 2.9.2, Overpower AT Setpoint Parameter Values Parameter Valut Overpower AT reactor trip setpoint -
K s1.086359 4
Overpower AT reactor trip heatup setpoint K = 0.001179FF 6
penalty coefficient Time constants utilized in the lead-lag T 2 8 sec.
1
~
compensator for AT T s 3 sec.
2 Time constant utilized in the lag 2-
. T s 2 sec.
3 compensator for AT Time constant utilized in the measured Tavs -T s 2 sec.
6 lag bompensator Time constant utilized in the rate-lag T 2 5 sec.
7 controller for T,y,
- f (AI) " positive" breakpoint
= 35.0 %AI 2
f (AI) " negative" breakpoint
= -35.0 %AI 2
f (AI) " Positive" slope
= 7.0 %AT/ %Al 2
f (AI) " negative" slope -
= 7.0 %ATg %AI 2
...~o,..,o Page 19 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report 2.10 ' Accumulators (LCO 3.5.1) 2.*0.1 Boron concentration limits during modes I and 2, and mode 3 with RCS pressure
>1000 psi:
Parameter Limit Cold Leg Accumulator minimum boron concentration.
2,475 ppm Cold leg Accumulator maximum boron concentration.
2,875 ppm 2.11 Refueling Water Storage Tank - RWST (LCO 3.5.4)
~
2.11.1 Boron concentration limits during modes 1,2,3, and 4:
Parameter Limit Refueling Water Storage Tank minimum boron 2,675 ppm concentration.
Refueling Water Storage Tank maximum boron 2,875 ppm i
concentration.
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{
Revision 17
]
McGuire 1 Cycle 13 Core Operating Limits Report 2.12. Spent Fuel Pool Boron Concentration (LCO 3.7.14) 2.12.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter Limit l
Spent fuel pool minimum boron concentration.
2675 ppm 2.13 Refueling Operations - Boren Concentration (LCO 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.
Parameter Limit Minimum Boron concentration of the Reactor Coolant 2675 ppm t
System, the refueling canal, and the refueling cavity.
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--.___..m.-
_. _ -. _.. _. _.. - _. _ = -. -. _.... _
.g.
Page 21 cf 22 Revision 17 McGuire I Cycle 13 Core Operating Limits Report l
2.14 Borated Water Source-Shutdown (SLC 16-15.3.1.2.5) 2.14.1' Volume and boron concentrations for the Boric Acid Storage System and the
[
Refueling Water Storage Tank (RWST) during modes 5 & 6:
i Parameter 1/imit Boric Acid Storage System minimum contained 8,884 gallons borated water volume 10.0% level
)
l Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System minimum water 585 gallons l.
volume required to maintain SDM at 7,000 ppm i
t.
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Refueling Water Storage Tank minimum contained 43,000 gallons l
borated water volume 35.0 inches i
I Refueling Water Storage Tank minimum boron 2,675 ppm concentration y
Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,675 ppm m
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Page 22 of 22 Revision 17 t
l McGuire 1 Cycle 13 Core Operating Limits Report L
l 2.15 Borated Water Source - Operating (SLC 16-15.3.1.2.6) 1 2.15.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling l
Water Storage Tank (RWST) during modes 1, 2, 3, & 4:
I l
Parameter Limit l
l Boric Acid Storage System minimum contained 22,520 gallons borated water volume 39.0% level l
Boric Acid Storage System minimum boron 7,000 ppm concentration l
Boric Acid Storage System minimum water 11,851 gallons volume required to maintain SDM at 7,000 ppm l
i Refueling Water Storage Tank minimum contained 96,607 gallons borated water volume 103.6 inches Refueling Water Storage Tank minimum boron 2,675 ppm l
concentration Refueling Water Storage Tank maximum boron 2,875 ppm concentration Refueling Water Storage Tank minimum water 57,107 gallons J
volume required to maintain SDM at 2,675 ppm NOTE: Data contained in the Appendix to this document was generated in the McGuire 1 Cycle i
13 Maneuvering Analysis calculational file, MCC-1553.05-00-0256. 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 infonnation.
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