ML20196G076
| ML20196G076 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 11/06/1998 |
| From: | Houston J DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20196G051 | List: |
| References | |
| MCEI-0400-47, MCEI-0400-47-R15, MCEI-400-47, MCEI-400-47-R15, NUDOCS 9812070234 | |
| Download: ML20196G076 (22) | |
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~ MCEI-0400-47~
- Page 1 of 22 Revision 15 McGuire Unit 2 Cycle 12 .
i Core Operating Limits Report Revision 15 November 1998 -
Calculation Number: MCC-1553.05-00-0252, Rev. 2 Duke Power Company Date Prepared By:
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{[6/6ik Checked By: dyd <_ (t(c.FtB Checked By: _1/L u
/df /( fc, /tj U l Approved By: fM&d v/4/rp QA Condition 1 i
NOTE I 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 M2Cl2 Reload Safety Evaluation (calculation file: MCC-1552.08-00-0279).
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l McGuire 2 Cycle 12 Core Operating Limits Report .
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l IMPLEMENTATION INSTRUCTIONS FOR REVISION 15 Revision 15 of the McGuin: Unit 2 COLR updates this report to be compliant with the -
Improved Technical Specifications (ITS). This revision should be implemented concurrently with this release of ITS.
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l McGuire 2 Cycle 12 Core Operating Limits Report , j I
. i REVISION LOG l
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Revision Effective Date Effective Paces COLR Revisions 0-2 Superseded N/A M2C09 i-Revisions 3-6 Superseded N/A M2C10 i
Revisions 7-12 Superseded N/A M2C11 !
Revision 13 October 23,1997 5-8 and 12-21 M2C12 Revision 14 November 24,1997 1-4,9,10 and 11 M2C12 - rev.1 i Revision 15 November 6,1998 1-22 M2C12 rev. 2 3
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., Page 4 cf 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report ,
i INSERTION SHEET FOR REVISION 15 !i i
Remove pages Insert Rev.15 pages . !
Pages 1-21 Pages 1-22 ;
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McGuire 2 Cycle 12 Core Operatir.g Limits Report j 1.0 ' Core Operating Limits Report This Core Operating Limits Repon (COLR) has been prepared in accordance with the requirements of the Technical Specification Limiting Conditions for Operation (LCO) ,
4 from Section 5.6.5. I l
The Technical Specifications that reference this repon are listed below:
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l Technical Speci6 cations Section Page I 1.1 Requirements for Operational Mode 6 2.1 5 j 3.1.1 Shutdown Margin 2.2 6 ;
3.1.3 Moderator Temperature Coefficient 2.3 6 .
~3.1.5 Shutdown BankInsertion Limit 2.4 6 i 3.1.6 Control Bank Insertion Limit 2.5 6 i 3.2.1 Heat Flux Hot Channel Factor 2.6 9 -;
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 2.7 141 3.2.3 Axial Flux Difference 2.8 15 3.3.1 Reactor Trip System Instrumentation Setpoint 2.9 17 i 3.5.1 Accumulators 2.10 19 !
3.5.4 Refueling Water Storage Tank 2.11 19 ;
l 3.7.14 Spent Fuel Pool Boron Concentration 1.12' 20 3.9.1 Refueling Operations - Boron Concentration 2.13 20 !
The Selected Licensee Commitments that reference this report are listed below:
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 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 L
methodologies specified in Technical Specification 5.6.5.
l 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 kert must be less than, or equal to 0.95.
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McGuire 2 Cycle 12 Core Operating Limits Report l
2.2 - Shutdown Margin - SDM (LCO 3.1.1) l 2.2.1 Shutdown margin shall be greater than 1.3% AK/K in modes 14.
l 2.2.2. Shutdown margin shall be greater than or equal to 1.0% AK/K in mode 5. . ;
i 2.3 Moderator Temperature Coefficient - MTC (LCO 3.1.3) ,
2.3.1 The Moderator Temperature Coefficient (MTC) LCO Limits are:
1 The MTC shall be less positive than the upper limits shown in Figum 1. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/ F.
i The EOC, ARO, RTP MTC shall be less negative than the -4.lE-04 AK/K/"F lower MTC limit. .
l 2.3.2 The'300 ppm MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC should be less negative than or equal to -3.2E-04 AK/K/ F. ,
2.3.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC should be less negative than or equal to
-3.85E-04 AK/K/'F. l Where: BOC = Beginning of Cycle -
EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Thermal Power RTP = Rated Thermal Power PPM = Parts per million (Boron) 2.4 Shutdown Bank Insertion Limit (LCO 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 226 steps.
I 2.5 Control Bank Insertion Limits (LCO 3.1.6)
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2.5.1 Control banks shall be within the LCO insertion, sequence, and overlap limits shown in Figure 2.
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- Page 7 of 22 Revision 15 1 McGuire 2 Cycle 12 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level ,
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j Unacceptable Operation
. "O 0.8 - !
l 0.7 U
E 0.6 --
2 6 Cl 0.5 --
E lg4 ' 0.4 -- Acceptable Operation H C2 w O 0.3 --
2
$ 0.2 -- 1 1
g 0.1 - -
0.0 l 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 LCO 3.1.3 may require rod withdrawal limits. Refer to OP/2/A/6100/22 Unit 2 Data Book for details.
- IRadkO400-47 i Pege 8 of 22 l, Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report Figure 2 l Control Bank Insertion Limits Versus Percent Rated Thermal Power (Fully Withdrawn min - 226, max - 231) 240 - ' '
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....,. (29.6 %,231) .T (80.0 %,231) 220 ,
200 ,
180 ,
' 8*'* 8 ,
' :100%.161)
Rod 160 i (3,,g) ,
/- ,
7 Insertion 140 ,- ,
Position ,
120 -
Bank C -
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l Withdrawn) 100 ,.
80
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60 ,
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' Bank D 40 ,
20 / (30%,o) 0 :
O 10 20 30 40 50 60 70 80 90 100 (FullyInserfed) Relative Power (Percent) l l
NOTE: Compliance with Technical Specification LCO 3.1.3 may require rod withdrawal limits. Refer to OP/2/A/6100/22 Unit 2 Data Book for details. .
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- . . Page 9cf 22 Revision 15 McGuin 2 Cycle 12 Com Operating Limits Report i.
l 2.6 Heat Mux Hot Channel Factor - FQ(X,Y,Z) (LCO 3.2.1)'
2.6.1 Fo(X,Y,Z) steady-state limits are defined by the following relationships: .
i F *K(Z)/P for P > 0.5
, Q.
F *K(Z)/0.5 for P s 0.5
'Q j- .
where, P = (Thermal Power)/(Rated Power)
Note: The measured Fo(X,Y,Z) shall be increased by 3% to account for j manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limit. The manufacturing tolerance and
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l L measurement uncertainty are implicitly included in the Fo surveillance limits. l as defined in Sections 2.6.5 and 2.6.6. !
P 2.6.2 F = 2.50 x K(BU) 9 ;
A 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height for MkBW fuel and is provided in Figure 3.
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. 1 i
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification LCO 3.2.1:
L 2.6.5 h(X,Y,Z)OP = (X,Y,Z) x MQ(X,Y,Z)/(UMT x MT x TILT) q where:
' h(X,Y,Z)OP = cycle dependent maximum allowable design peaking factor which I
q l ensures that the FQ(X,Y,Z) limit will be preserved for operation I
MCEI-0400-47
, Fage 10 of 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report within the LCO limits. h(X,Y,Z)OP includes allowances for q
calculational and measuremet t uncenainties. I F9(X,Y,Z) = design power distribution for FQ. F (X,Y,Z)is provided in Table 1, -
Appendix A, for nonnal operating conditions and in Table 2, Appendix A for power escalation testing during initial stanup operation. l MQ(X,Y,Z) = margin remaining in core location X,Y,Z to the LOCA limit in the 1
) transient power distribution. MQ(X,Y,Z) is provided in Table 1, I i
Appendix A for normal operating conditions and in Table 2 Appendix A for power escalation testing during initial startup operation.
UMT = Total Peak Measurement Uncenainty, = 1.05.
I MT= Engineering Hot Channel Factor, = 1.03.
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TILT = Peaking penalty that accounts for allowable quadrant powe.r tilt ratio of 1.02.
(TILT = 1.035)
NOTE: F (X,Y,Z)OP s ithe parameteridentified as (X,Y,Z) in DPC-NE-2011PA.
q 2.6.6 h(X,Y,Z)RPS q = F (X,Y,Z) x (M (X,Y,Z)/(UMT C x MT x TILT))
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F (X,Y,Z)RPS = cycle dependent maximum allowable design peaking factor 9
which ensures that the centerline fuel melt (CFM) limit will be preserved for operation within the LCO hmits. h(X,Y,Z)RPS q
includes allowances for calculational and measurement uncenainties.
D D 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 stanup operation.
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M C(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 MQ (X,Y,Z) calculations described in DPC-NE-2011PA, except that the LOCA limit is replaced with the CFM limit. MC (X,Y,Z) is
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provided in Table 3, Appendix A for normal operating conditions and in Table 4, 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 = Factor to account for a peaking increase due to the allowed quadrant power tilt ratio of 1.02. (TILT = 1.035).
NOTE:qh(X,Y,Z)RPS is the parameteridentified (X,Y,Z)inas [q 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 K1 value from OTAT trip setpoint required to compensate for each 1% that F (X,Y,Z) exceeds h(X,Y,Z)RPS, q
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l McGuire 2 Cycle 12 Core Operating Limits Report Figure 3 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for MkBW Fuel L
l l 1.00 :: :
0.90 -_ (0.0,1.0) (12.0.1.0) 0.80 --
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=0 .50 --
$ 0.40 --
C Z 0.30 --
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0 00 l : : l : :'
! 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft.)
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. Page 13 of 22 Rsvision 15 McGuire 2 Cycle 12 Core Operating Limits Report l
Figure 4 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for MkBW Fuel .
l 1.000 :: : _
0.900 -- (0,1.0) (30.0,1.0) (45.0,0.98)
! 0.800 -- i (60.0,0.792)
$ 0.700 --
6 g 0.600 --
) 0.500 --
1 g 0.400 --
- $ 0.300 --
0.200 --
- 0.100 --
0.000 l l l l l :"
0 10 20 30 40 50 60 Burnup (GWD/MTU) l l
h P
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, Page 14 of 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report l -
l- 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (LCO 3.2.2) t I
l The FAH steady-state limits referred to in Technical Specification LCO 3.2.2 is defined by l the following relationship.
2.7.1 F (X,Y)LCO = MARP (X,Y) x [1.0 + (1/RRH) x (1.0 - P)] -
j wh re:
L F (X,Y)LCO 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. l MARP(X,Y) radial peaking limits are provided in Table 7, Appendix A. >
- - Thermal Power I p , RatedThermalPower l
1 RRH = -3.34 when 0.0 < P s 1.0, and l RRH = Thermal Power reduction required to compensate for each 1% that the !
- measured radial peak,F (X,Y), exceeds the limit.
The following parameters are required for core monitoring per the Surveillance requirements l of Technical Specification LCO 3.2.2. lt 2.7.2 F (X,Y)SURV = F (X,Y) x MAH(X,Y)/(UMR x TILT) where:
1 FAH(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. F (X,Y)SURV includes
, allowances for calculational and measurement uncertainty.
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Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report D D Fg(X,Y) = the design power distribution for FAH.FAH(X,Y)is provided in Table 5, Appendix A for normal operation and in Table 6, 1 Appendix A for power escalation testing during initial startup operation. .
l i MAH(X,Y) = the margin remaining in core location X,Y relative to the -
Operational DNB limits in the transient power distribution.
l 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.
i 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 parameteridentified as F AX (X,Y) in DPC-NE-2011PA.
2.7.3 RRH = 3.34 when 0.0 < P $ 1.0, where:
RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, Fh (X,Y) exceeds its limit. l 2.7.4 TRH = 0.04 where:
TRH = Reduction in OTAT K} setpoint required to compensate for each 1% that the measured radial peak, Fh (X,Y), exceeds the limit.
l 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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, Pcg316 of 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power vs. Axial Flux Difference Limits ,
- 00 110 -
l (-1s.100)l
- 00 (+10.100) l Unacceptable operadonl N~~
80 "
l 70 --
l Unacceptable operation l l Acceptable operation l g.,
T 50 --
l (+21.50)l g l (.36.50)l ,,
1E g 30 --
g 20 --
10 --
l : : 0 : : :
-50 -40 30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta I)
NOTE: Compliance with Technical Specification LCO 3.2.1 may require more restrictive AFD limits. Refer to OP/2/A/6100/22 Unit 2 Data Book for details.
Page 17 of 22 Revision 15 McGuire 2 Cycle 12 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 .
Parameter Value Overtemperature AT reactor trip setpoint K1 s 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.0334/0F penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/ psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator ti n 8 sec.
for AT.
77 g 3 sec, Time constant utilized in the lag compensator for AT T3 s 2 sec.
Time constants utilized in the lead-lag compensator T4 2 28 sec.
for T '
T5 s 4 sec.
Time constant utilized in the measured T., lag T6 s 2 sec.
compensator fg(AI) " positive" breakpoint = 19.0 %Al f 1(AI)" negative" breakpoir.t = N/A*
f 1(AI) " positive" slope
= 1.769 %ATo/ %Al f 1(AI) " negative" slope = N/A*
The f t(AI) " negative" breakpoint and the f](AI) " negative" slope are not applicable since the fg(AI) function is not required below the ft(AI) " positive" breakpoint of 19.0% AI.
.m. .. _ _ _ _ _ _ _ _
c---- - ^ - - - - - - ~ - - - - - - - - ' ' ^
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McGuire 2 Cycle 12 Core Operating Limits Report a
l 2.9.2 ' , Overpower AT Setpoint Parameter Values I
Parameter Value Overpower AT reactor trip setpoint K4s 1.086359 i Overpower AT reacte trip heatup setpoint K6= 0.001179FF ;
penalty coefficient l l
Time constants utilized in the lead-lag Ti 2 8 sec.
. compensator for AT T2s 3 sec. I Time constant utilized in the lag T3 s 2 sec.
compensator for AT ]
j Time constant utilized in the measured Tavs T6s 2 sec. j lag compensator t
Time constant utilized in the rate-lag T7 2 5 sec.
controller for T.y, '
i f 2(AI) " positive" breakpoint
= 35.0 %Al l
f2(AI) " negative" breakpoint = -35.0 %AI f 2(AI) " Positive" slope = 7.0 %ATo/ %AI f 2(AI) " negative" slope = 7.0 %ATo/ %AI i
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- Revision 15 I
i_ McGuire 2 Cycle 12 Core Operating Limits Report
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'l 2.10~ Accumulators (LCO 3.5.1) i 2.10.1 Boron concentration limits during modes 1 and 2, and mode 3 with RCS pressure l >1000 psi:
Parameter Limit Cold leg Accumulator minimum boron concentration. 2,475 ppm '
Cold leg Accumulator maximum 'ooron concentration. 2,875 ppm l
2.11 Refueling Water Storage Tank - RWST (LCO 3.5.4) i 2.11.1 Boron concentration limits during modes 1,2,3, and 4:
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Parameter Limit Refueling Water Storage Tank minimum boron 2,675 ppm concentration. I Refueling Water Storage Tank maximum boron 2,875 ppm concentration.
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g Page 20 of 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report 2.12 Spint 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 Spent fuel pool minimum boron concentration. 2675 ppm 2.13 Refueling Operations - Boron 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 System, the refueling canal, and the refueling cavity.
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. Page 21 of 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report 2.14 Borated Water Source-Shutdown (SLC 16-15.3.1.2.5) 2.14.1 Volume and boron ccncentrations for the Boric Acid Storage System and the -
Refueling Water Storage Tank (RWST) during modes 5 & 6:
Parameter Limit Boric Acid Storage System minimum contained 8,884 gallons borated water volume 10.0% level Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System minimum water 585 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 43,000 gallons borated water volume 35.0 inches Refueling Water Storage Tank minimum boron 2,675 ppm concentration Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,675 ppm
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MCEI-0400 47 O Page 22 of 22 Revision 15 McGuire 2 Cycle 12 Core Operating Limits Report 2.15 Borated Water Source - Operating (SLC 16-15.3.1.2.6) 2.15.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling -
Water Storage Tank (RWST) during modes 1,2,3, & 4: !
C Parameter Limit ,
Boric Acid Storage System minimum contained 22,520 gallons ,
borated water volume 39.0% level i
Boric Acid Storage System minimum boron 7,000 ppm j concentration Boric Acid Storage System minimum water 11,851 gallons I volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 96,607 gallons !
borated water volume 103.6 inches Refueling Water Storage Tank minimum boron 2,675 ppm concentration Refueling Water Storage Tank maximum boron 2,875 ppm I concentration '
l Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,675 ppm i
i NOTE: Data contained in the Appendix to this document was generated in the McGuire 2 Cycle 12 Maneuvering Analysis calculational file, MCC-1553.05-00-0234. 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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