ML20069P821
| ML20069P821 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 06/20/1994 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20069P812 | List: |
| References | |
| MCEI-0400-47, MCEI-0400-47-R01, MCEI-400-47, MCEI-400-47-R1, NUDOCS 9406270134 | |
| Download: ML20069P821 (14) | |
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DOCUMENT CONTROL NO.
MCEI-0400-47 REVISION NO.
0001 PAGE NO.
1 OF 153 TITLE MCGUIRE UNIT 2 CYCLE 9 CORE OPERATING LIMITS REPORT SIGNOFF DATE Gho/9V PREPARED BY
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MCEl-060047 Page 2 of 153 1
Revision 1 McGuire Nuclear Station COLR McGuire Unit 2 Cycle 9 Core Operating Limits Report June 1994 Revision 1 Duke Power Company NOTE j
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 M2C9 Reload Safety Evaluation (calculation file: MCC-1552.08-00-0210)
L MCEl-(M00-47 Page 3 of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report REVISION LOG Revision Effective Date Effective Paces OriginalIssue August 25,1993 Pages 6,8,9,12,13,15-153 Revision 1 June 20,1994 Pages 1-3,3A,4,5,5A,5B, 7,7A,10,11,14,14A I
l j
MCEl-0100-47 Page 4 of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report, (COLR), for McGuire, Unit 2, Cycle 9 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
The Technical Specifications affected by this report are listed below:
2.2.1 Reactor Trip System Instrumentation Setpoints 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.2.5 Borated Water Source - Shutdown 3/4.1.2.6 Borated Water Source - Operating 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insert on Limit i
3/4.2.1 Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3/4.5.1.1 Accumulators 3/4.5.5 Refueling Water Storage Tank 1
i MCEI-0400-47 Page 5 of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 1.1 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 6.9.1.9.
t t
2.0 Reactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.1 Overtemperature AT Setpoint Parameter Values 1
Parameter Value Overtemperature AT reactor trip setpoint K1 s 1.1988 Overtemperature AT reactor trip heatup K2 = 0.03354/0F setpoint penalty coefficient K = 0.001522/ psi Overtemperature AT reactor trip 3
depressurization setpoint penalty coefficient I
T 2 8 sec.
Measured reactor vessel AT lead / lag time i
t s 3 sec.
constants 2
t s 2 sec.
Measured ATlag time constant 3
Measured reactor vessel average temperature T4 2 28 sec.
t s 4 sec.
lead / lag time constants 5
Measure reactor vessel average temperature T6 s 2 sec.
i lag time constant f (AI) " positive" breakpoint
= 12.0 %Al i
f (AI) " negative" breakpoint
= -44.0 %Al i
f (AI) " positive" slope
= 1.619 %ATg %AI i
f (AI) " negative" slope
= 3.436 %ATg %AI i
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MCEI-0400-47 Page SA of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 2.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4 s 1.0851 Overpower AT reactor trip heatup setpoint K6 = 0.001207/0F penalty coefficient Measured reactor vessel ATlead/ lag time T 2 8 sec.
1 T s 3 sec.
constants 2
1 s 2 sec.
Measured ATlag time constant 3
Measure reactor vessel average temperature 1 s 2 sec.
6 lag time constant Measure reactor vessel average temperature T 2 5 sec.
7 rate-lag time constant 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" slope
= 7.0 %ATg %AI 2
)
1 1
MCEI-0400-47 Page 5B of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 3.0 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 3.0.1 The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the limits shown in Figure 1. The BOC, ARO, HZP MTC shall be less positive than 0.7 x 10E-04 AK/K/ F.
The EOC, ARO, RTP MTC shall be less negative than -4.1 x 10E-04 AK/K/ F.
j 3.0.2 The MTC Surveillance Limitis:
The 300 PPM ARO, RTP MTC should be less negative than or equal to -3.2 x 10E-04 AK/K/ F.
Where: BOC stands for Beginning of Cycle EOC stands for End of Cycle ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power RTP stands for Rated Thermal Power F
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MCEI-0400-47 l
Page 7 of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 3.1 Borated Water Source - Shutdown (Specification 3/4.1.2.5) 3.1.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 5 & 6:
Earameter Limit Boric Acid Storage System minimum contained 6,132 gallons borated water volume for LCO 3.1.2.5a Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.5a Boric Acid Storage System minimum water volume 585 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 26,000 gr.11ons borated water volume for LCO 3.1.2.5b Refueling Water Storage Tank minimum boron 2,175 ppm concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,175 ppm i
MCEI-04CD-47 Page 7A of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report l
3.2 Ilorated Water Source - Operating (Specification 3/4.1.2.6) 3.2.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, & 4:
Parameter Lunit Boric Acid Storage System minimum contained 20,453 gallons borated water volume for LCO 3.1.2.6a Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.6a Boric Acid Storage System minimum water volume 9,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 372,100 gallons barated water volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum boron 2,175 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank maximum boron 2,275 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,175 ppm 3.3 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 3.3.1 The shutdown rods shall be withdrawn to at least 222 steps.
3.4 Control Rod Insertion Limits (Specification 3'/4.1.3.6) 3.4.1 The control rod banks shall be limited to physical insertion as shown in Figure 2.
3.5 Axial Flux Difference (Specification 3/4.2.1) 3.5.1 The Axial Flux Difference (AFD) Limits are provided in Figure 3.
MCEl-0600-47 Page 10 of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 3.6 Heat Flux Hot Channel Factor, FQ(X,Y,Z) (Specification 3/4.2.2)
[q
= 2.32 3.6.1 i
3.6.2 K(Z) is provided in Figure 4 for Mark-BW fuel.
3.6.3 K(Z) is provided in Figure 5 for OFA fuel.
The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.2:
D 3.6.4 [h(X,Y,Z))OP = F (X,Y,Z) x Mg(X,Y,Z)/(UMT x MT x TILT) q q
where [h(X Y.Z)]OP = cycle dependent maximum allowable design peaking factor which q
ensures that the FQ(X,Y,Z) limit will be preserved for operation within the LCO limits [h(X.Y.Z)]OP. [h(X.Y.Z)]OP includes q
q allowances for calculational and measurement uncertainties.
F (X,Y,Z) =
the design power distribution for F. F (X,Y,Z)is provided in Q
q q
Table 1 for normal operating conditions and in Table 2 for power escalation during startup operations.
MQ(X,Y,Z) =
the margin remaining in core location X,Y,Z to the LOCA limit in f
the transient power distribution. MQ(X,Y,Z)is provided in Table 1 for normal operating conditions and in Table 2 for power escalation during startup operations.
UMT=
Measurement Uncertainty (UMT = 1.05).
MT=
Engineering Hot Channel Factor (MT = 1.03).'
s TILT =
Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)
[h(X,Y,Z)]OP is the parameter identified as (X,Y,Z) in DPC-NE-2011PA.
NOTE:
q
~
MCEl-0400-47 Page !! of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report l
[h(X,Y,Z)]RPS = [q(X,Y,Z) x (M (X,Y,Z)/(UMT x MT x TILT))
3.6.5 q
C where i/q'(X,Y.Z)lRPS = cycle dependent maximum allowable design peaking factor whic ensures that the centerline fuel melt limit will be preserved for operation within the LCO limits. [Fj(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.
the design power distributions for F. [q(X,Y,Z) is provided F (X,Y,Z) =
Q Table 1 for normal operating conditions and in Table 2 for power escalation during startup operations.
M (X,Y,Z) = the margin remaining to the CFM limit in core location X,Y,Z C
from the transient power distribution. M (X,Y,Z) calculations C
parallel the M (X,Y,Z) calculations described in DPC-NE-Q 201 IPA, except that the LOCA limit is replaced with the CFM limit. M (X,Y,Z)is provided in Table 3 for normal operating C
conditions and in Table 4 for power escalation during startup operations.
UMT=
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: th(X,Y,Z)]RPS is the parameter identified as [q q
(X,Y,Z) in DPC-NE-2011PA.
3.6.6 KSLOPE = 0.0725 where KSLOPE =
Adjustment to the K value from OTAT required to compensate 1
for each 1% that [ q(X,Y,Z)]RPS exceeds its limit.
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MCEl-0400-47
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Page 14 of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 3.7 Nuclear Enthalpy Rise Hot Channel Factor, FAH(X,Y,Z) (Specification 3/4.2.3)
[FAH(X,Y)]LCO = M ARP (X,Y) x [1.0 + (1/RRH) x (1.0 - P)]
j i
3.7.1 McGuire 2 Cycle 9 Operating Limit Maximum Allowable Radial Peaks, (MARP(X,Y)), are provided in Table 7.
The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.3:
L D
[FAH(X,Y)]SURV = p H(X,Y) x MAH(X,Y)/(UMR x TILT),
as identified in DPC-NE-2011PA.
where UMR=
Uncertainty value for measured radial peaks, (UMR = 1.04).
TILT =
Factor to account for a peaking increase due to an allowable quadrant tilt ratio of = 1.02 (TILT = 1.035).
D D
3.7.2 FAH(X,Y) = the design power distribution for FAH.FAH(X,Y)is provided in Table 5 for normal operating conditions and in Table 6 for power escalation during startup operations..
3.7.3 MAH(X,Y) = the margin remaining in core location X,Y to the DNB limit from the transient power distribution. MAH(X,Y)is provided in Table 5 for normal operating conditions and in Table 6 for power escalation during startup operations..
3.7.4 RRH = 3.34 when 0.0 < P s 1.0, where RRH = Thermal Power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit.
Thermal Power P=
Rated Thermal Power 3.7.5 TRH = 0.04 where TRH = Reduction in OTAT K setpoint required to compensate for each 1% that 1
FAH(X,Y) exceeds its limit.
MCEl-0400-47 e
Page 14A of 153 Revision 1 McGuire 2 Cycle 9 Core Operating Limits Report 3.8 Accumulators (Specification 3/4.5.1.1) 3.8.1 Boron concentration limits during modes 1,2, & 3:
)
Parameter Limit Cold l_eg Accumulator minimum boron concentration for 2,000 ppm l
LCO 3.5.1.1c Cold Leg Accumulator maximum boron concentration for 2,275 ppm LCO 3.5.1.1c Minimum Cold Leg Accumulator boron concentration 1,900 ppm required to ensure post-LOCA subcriticality l
r 3.9 Refueling Water Storage Tank (Specification 3/4.5.5) 3.9.1 Boron concentration limits during modes 1,2,3, & 4:
Parameter Limli Refueling Water Storage Tank minimum boron 2,175 ppm concentration for LCO 3.5.5b i
Refueling Water Storage Tank maximum boron 2,275 ppm concentration for LCO 3.5.5b c
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