ML20205T109
| ML20205T109 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 03/12/1999 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20205T107 | List: |
| References | |
| MCEI-0400-47, MCEI-0400-47-R16, MCEI-400-47, MCEI-400-47-R16, NUDOCS 9904270148 | |
| Download: ML20205T109 (23) | |
Text
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MCEl-0400-47 Page 1 of 23 Revision 16 McGuire Unit 2 Cycle 13 Core Operating Limits Report Revision 16 March 1999 Calculation Number: MCC-1553.05-00-0298 Duke Power Company l
Date Prepared By:
T)ds /" M 3//t /99
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Checked By:
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3 /12 / 9 9 Approved By:
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.34z//'y 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 McGuire 2 Cycle 13 Reload Safety Evaluation (Calculation File: MCC-1552.08-00-0294.)
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'l MCEI-0400-47 Page 2 of 23 Revision 16 McGuire 2 Cycle 13 Cort Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 16 Revision 16 of the McGuire Unit 2 COLR contains limits specific to the McGuire Unit 2 Cycle 13 Core design. This revision shall be implemented after no mode is reached r.nd prior to the start of fuel loading in the McGuire Unit 2 EOC-12 outage.
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Page 3 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report REVLSION LOG Revision Effective Date Effective Panes COLR Revisions 0-2 Superseded N/A M2C09 Revisions 3-6 Superseded N/A M2C10 Revisions 7-12 Superseded N/A M2C11 Revision 13-15 Superseded N/A M2C12 Revision 16 March 12,1999 1 23 M2C13
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MCEI-0400-47 Pege 4 cf 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report INSERTION SHEET FOR REVISION 16 Remove pages Insert Rev.16 pages Pages 1-22 Pages 1-23
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'd MCEl-0400-47 Page 5 cf 23 Revision 16 McGuire 2 Cycle 13 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 Limiting Conditions for Operation (LCO) from Section 5.6.5.
The Technical Specifications that reference this report are listed below:
TS Section Technical Specifications Section Eage 1.1 Requirements for Operational Mode 6 2.1 5
3.1.1 Shutdown Margin (Additional Entry points 2.2 6
from TS 3.1.4, TS 3.1.5 and TS 3.1.6) 3.1.3 ModeratorTemperature Coefficient 2.3 6
3.1.5 Shutdown Bank Insenion Limit 2.4 7
3.1.6 Control Bank Insertion Limit 2.5 7
3.2.1 Heat Flux Hot Channel Factor 2.6 10 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 2.7 15 3.2.3 Axial Flux Difference 2.8 16 3.3.1 Reactor Trip System Instrumentation Setpoint 2.9 18 3.5.1 Accumulators 2.10 20 3.5.4 Refueling Water Storage Tank 2.11 20 3.7.14 Spent Fuel Pool Boron Concentration 2.12 21 3.9.1 Refueling Operations - Boron Concentration 2.13 21 The Selected Licensee Conunitments that reference this report are listed below:
SLC Section Selected License Commitment Section Eage 16.15-3.1.2.5 Borated Water Source-Shutdown 2.14 22
- 16.15-3.1.2.6 Borated Water Source-Operating 2.15 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.
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 kerr must be less than, or equal to 0.95.
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MCEI-0400-47 ~
Page 6 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report i
2.2 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, and TS 3.1.6) 2.2.1 For TS 3.1.1, SDM shall be 21.3% AK/K in mode 2 with k-eff < 1.0 and in modes 3 and 4.
2.2.2 For TS 3.1.1, SDM shall be 21.0% AK/K in mode 5.
2.2.3 For TS 3.1.4, SDM shall be 21.3% AK/K in modes 1 and 2 2.2.4 For TS 3.1.5, SDM shall be 21.3% AK/K in mode 1 and mode 2 with any control bank not fullyinserted.
2.2.5 For TS 3.1.6, SDM shall be 21.3% AK/K in mode 1 and mode 2 with K-eff 21.0.
2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:
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.
2.3.2 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 EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Power RTP = Rated Thermal Power PPM = Parts per million (Boron)
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MCEI-0400-47 Page 7 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 2.4 Shutdown Bank Insertion Limit (l'S 3.1.5) 2.4.1 Each stutdown bank shall be withdrawn to at least 226 steps.
2.5 Control Bank Insertion Limits (TS 3.1.6) 2.5.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 2.
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f-MCEI-0400-47 Pag 3 8 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 --
g Unacceptable Operation
- U 0.8 --
0.7 E
0.6 --
5y 2A 0.5 --
E 3
$ g 0.4 --
Acceptable Operation E
at gC 0.3 --
0.:, --
12 0.1 --
0.0 l
1 l
l l
l l
l 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 OP/2/A/6100/22 Unit 2 Data Book for details.
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MCEI-040047 Pag 3 9 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report
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Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231)
(29.6%,231) P T,
~,Ni(80.0%,231)F
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~
2 s'
l s'
y f'
Fully Withdrawn e'
180 z'
l Control Bank B e'
h(0%,163)j
,e '
5 160 -
}140 s
Control Bank C a 120 e
s i 100 e'
f I
/
k
/
/
Control Bank D
~ 60 z'
f
)
E s
s b (0**47)!
40 -
,/
-- l Fully inserted k 20
. (30%,0) i f
0 0
10 20 30 40 50 60 70 80 90 100 Percent of Reted Hermal Power NOTE: Compliance with Technical Specification 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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MCEl-040047 Page 10 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor - F (X,Y,Z) (TS 3.2.1) n 2.6.1 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
- where, P = (Thermal Power)/(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 LCO limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the Fo surveillance limits as defined in COLR Sections 2.6.5 and 2.6.6.
2.6.2 Ff = 2.50 x K(BU) 2.6.3 K(Z) is the normalized F (X,Y,Z) as a function of core height for MkBW fuel and q
is provided in Figure 3.
2.6.4 K(BU) is the normalized F (X,Y,Z) as a function of bumup for MkBW fuel and is n
provided in Figure 4.
The following parameten are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
Fn(X,Y,Z)
- M (X,Y,Z) 2.6.5 F'(X,Y,Z)oP =
o q
where:
4 Fj (X,Y,Z)oP = ' Cycle dependent maximum allowable design peaking factor j
that ensures that the F (X,Y,Z) LOCA limit will be preserved n
for operation within the LCO limits. Fj(X,Y,Z)OP includes allowances for calculation and measurement uncertainties.
MCEI4400-47 Page 11 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report Ff(X,Y,Z) = Design power distribution for F. Ff(X,Y,Z) is provided in n
Table 1, Appendix A, for normal operating conditions, in Table 2, Appendix A for power escalation testing during initial stanup operation and in Table 3, Appendix A for the EOC power coastdown.
M (X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in n
the transient power distribution. M (X,YJ.)is provided in o
Table 1, Appendix A for normal operating conditions,in Table 2, Appendix A for power escalation testing during initial stanup operation and in Table 3, Appendix A for the EOC power coastdown.
UMT = Total Peak Measurement Uncenainty. (UMT = 1.05)
MT = Engineering Hot Channel Factor. (MT = 1.03)
TILT = Peaking penalty that accounts for the peaking increase from an 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.
a q
F$(X,Y,Z)
- Mc(X,Y,Z)
Fq'(X,Y,Z) PS R
2.6.6
=
UMT
- TILT where:
F'(X,Y,Z)RPS =
Cycle dependent maximum allowable design peaking factor q
that ensures that the Fo(X,Y,Z) Centerline Fuel Melt (CFM) limit will be preserved for operation within the LCO limits.
Eq(X,Y,Z)RPS includes allowances for Calculation and measurement uncenainties.
Fn(X,Y,Z) = Design power distributions for Fn. Fn(X,Y,Z) is provided in Table 1 Appendix A for normal operating conditions,in Table 2 Appendix A for power escalation testing during initial stanup operations and in Table 3, Appendix A for the EOC power coastdown.
2 MCEI-0400-47 Page 12 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report Mc(X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z fmm the transient power distribution. Mc(X,Y,Z) calculations parallel the M (X,Y,Z) calculations described in DPC-NE-n 2011PA, except that the LDCA limit is replaced with the CFM limit. Mc(X,Y,Z)is provided in Table 4, Appendix A for normal operating conditions, in Table 5, Appendix A for power escalation testing during initial startup operations and in Table 6, Appendix A for the EOC power coastdown.
UMT _ = Total Peak Measurement Uncertainty (UMT = 1.05)
'MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty that accounts for the peaking increase for an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)
Fj(X,Y,Z)""is the parameter identified as F" (X,Y,Z)in DPC-NE-201 IPA, NOTE:
a except that M (X,Y,Z) is replaced by Mc(X,Y,Z).
g 2.6.7 KSLOPE = 0.0725 where:
KSLOPE is 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)"".
g 1
L'*
.MCEl-0400-47 Page 13 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report Figure 3 K(Z), Normalized F (X,Y,Z) as a Function of Core Height for MkBW Fuel n
i 1.2 i
(0.0,1.00)
(12.0,1.0)
J 1.0 0.8 -
0.6 -
0.4 --
f 0.2 -
l 0.0 l
l l
0.0 2.0 4.0 6.0 8.0 10.0 12.0 I
Core Height (ft)
p MCEl-0400-47 PJge 14 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report Figure 4 K(BU), Normalized F (X,Y,Z) as a Function of Burnup for MkBW Fuel.
n 1.2 1
i (0,0,1.00)
(30.0,1.00)
(45.0,0.98) 4 0.8 --
(60.0.0.792) s 8 0.6 --
M 0.4 -
0.2 --
0.0 l
l l
l l
0.0 10.0 20.0 30.0 40.0 50.0 60.0 Burnup (GWD/MTU)
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MCEI-0400-47 Page 15 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 2.7 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 defined by the following relationship.
1 2.7.1 Ph(X,Y)" = MARP (X,Y)
- 1.0 + RRH * (1.0 - P)_
where:
FA(X,Y)" is defined a' the steady-state, maximum allowed radial peak.
FA(X,Y)" includes allowances for calculation and measurement J
uncertainty.
MARP(X,Y) =
Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(X,Y) radial peaking limits are provided in Table 10, Appendix A.
Thermal Power p_
Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, F5 (X,Y), exceeds the limit.
RRH = 3.34 (0.0 < P s; 1.0)
The following parameters are required for core monitoring per the Surveillanco requirements of Technical Specification 3.2.2.
F G,D Wang,D 2.7.2 FA (X,Y)sURv 3g
=
UMR xTILT where:
Ph (X,Y)*"" =
Cycle dependent maximum allowable design peaking factor that ensures that the F $,Y) limit will be preserved for 33 operation within the LCO limits. Eh (X,Y)SURV includes allowances for calculation and measurement uncertainty.
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.1" MCEI-0400-47 Pcge 16 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report F$n (X,Y) = Design radial power distribution for F,, F$u (X,Y) is provided in Table 7, Appendix A for normal operation, in Table 8, Appendix A for power escalation testing during initial startup operation and Table 9, Appendix A for the EOC power coastdown.
M,(X,Y) = The margin remaining in com location X,Y relative to the Operational DNB limits in the transient power distribution.
MAH(X,Y) is provided in Table 7, Appendix A for normal operation, in Table 8, Appendix A for power escalation testing during initial startup operation and in Table 9, Appendix A for the EOC power coastdown.
UMR = Uncertainty value for measured radial peaks,(UMR= 1.04).
TILT = Peaking penalty that accounts for the peaking increase for an allowable quadrant power tilt ratio of 1.02,(TILT = 1.035).
NOTE: fin (X,Y)suav is the parameter identified as Fm(X,Y) MAX in DPC-NE-201 IPA.
2.7.3 RRH = 3.34 where:
RRH = Thermal power reduction required to compensate for each 1% that the measured radial peak, F5 (X,Y) exceeds iu; limit.
2.7.4 TRH = 0.04 where:
Reduction in OTAT K setpoint required to compensate for each 1% that TRH =
1 the measured radial peak, FAH (X,Y) exceeds its limit.
2.8 Axial Flux Difference-AFD (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.
l
)
r 0
'se 1."
MCEI4400-47 Pcge 17cf 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
( 18,100)
(+10,100)
Unacceptable Operation Unacceptable Operation 80 --
g Acceptable Operation 70 -
60 --
50 --
g
(-36,50)
(+21,50) h 40 --
a$
30 __
J 20 --
10 --
-4 0 --
l l
l l
50
-40
-30
-20
-10 0
10 20 30 40 50 Axlal Flux Difference (% Delta I)
NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits. Refer to OP/2/A/6100/22 Unit 2 Data Book of more details.
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Page 18 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 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 K = 0.0334FF 2
penalty coefficient Overtemperature AT reactor trip depressurization K = 0.001601/ psi 3
setpoint penalty coefficient Time constants utilized in the lead-lag compensator ti 2 8 sec.
for AT 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 T4 2 28 sec.
for T y, T5 5 4 SCC-Time constant utilized in the measured T., lag t6 s 2 sec.
compensator f (AI) " positive" breakpoint
= 19.0 %Al 1
fg(AI) " negative" breakpoint
= N/A*
f (AI) " positive" slope
= 1.769 %ATo/ %Al 1
f (AI)" negative" slope
= N/A*
t
. The f (AI) " negative" breakpoint and the f (AI) " negative" slope are not applicable since the f (AI) t t
1 function is not required below the fg(AI) " positive" breakpoint of 19.0% AI.
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,O MCEl-040047 P ge 19 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4 s 1.086359 Overpower AT reactor trip heatup setpoint K = 0.001179FF 6
penalty coefficient Time constants utilized in the lead-lag T 2 8 sec.
i compensator for AT T s 3 sec.
2 Time constant utilized in the lag T s 2 sec.
3 compensator for AT Time constant utilized in the measured Tavs T s 2 sec.
6 lag compensator Time constant utilized in the rate-lag T 2 5 sec.
7 controller for T.vg 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" slopc
= 7.0 %ATg %Al 2
'3' MCEI0400-47 P gs 20 cf 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 2.10 Accumulators (TS 3.5.1) 2.10.1 Boron concentration limits during modes I and 2, and mode 3 with RCS pressure
>1000 psi:
Parameter Limit Cold Ixg Accumulator minimum boron concentration.
2,475 ppm
. Cold 12g Accumulator maximum boron concentration.
2,875 ppt i 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 I.imit Refueling Water Storage Tank minimum boron 2,675 ppm concentration.
Refueling Water Storage Tank maximum boron 2,875 ppm concentration.
J u J' MCEI-0400-47 Page 21 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report j
2.12 Spent Fuel Pool Boron Concentration (TS 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.
2,675 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 minimum 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 Limit Minimum Boron concentration of the Reactor Coolant 2,675 ppm System, the refueling canal, and the refueling cavity.
- .D g
MCEI-0400-47 Page 22 of 23 Revision 16 McGuire 2 Cycle 13 Core Operating Limits Report 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 and 6.
{
Parameter Limit Boric Acid Storage System minimum contained 8,884 gallons borated water volume 10% Ixvel
- 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 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 i
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..e, s y MCEI440047 PJge 23 of 23 Revision 16 4
McGuire 2 Cycle 13 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, and mode 4:
Parameter Limit Boric Acid Storage System minimum contained 22,520 gallons borated water volume 39.0% 12 vel 4
Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System minimum water 11,851 gallons 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 2875 ppm concentration (TS 3.5.4)
Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,675 ppm NOTE: Data contained in the Appendix to this document was generated in the McGuire 2 Cycle 13 Maneuvering Analysis calculation file, MCC-1553.05-00-0270. 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.