ML20098B085
| ML20098B085 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/30/1995 |
| From: | Clark R DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20098B081 | List: |
| References | |
| CNEI-0400-24, CNEI-0400-24-R08, CNEI-400-24, CNEI-400-24-R8, NUDOCS 9510020134 | |
| Download: ML20098B085 (20) | |
Text
.
CNEI-0400 24 Page 1 of 20 Revision 8 Catawba Unit 1 Cycle 9 Core Operating Limits Report September 1995 Duke Power Company Date Prepared By:
AmgAAy 9/n/qr-rY Checked By:
2 (p p /ff~
Checked By:
k k) 9 /f4/s(
Approved By:
[f/MM S/r //ff QA Condition 1 1
The contents of this document have been reviewed to verify that no material herein either directly or indirectly changes the results and conclusions presented in the 10CFR50.59 Catawba 1 Cycle 9 Reload Safety Evaluation (CNC-1552.08-00-0236).
I 9510020134 950930 PDR ADOCK 05000413 P.
,PDR
Oct:wb31 Cycle 9 Ccre Oper ting Limits Report CNEI-0400-24 Page 2 of 20 Revision 8 INSERTION SHEET FOR IGVISION 8 9
Remove Insert Pages 1-19, rev 6-7 Pages 1-20, rev 8
~
Cattwba 1 Cycle 9 Ccre Operating Limits Report CNEI-0400-24 Page 3 of 20 Revision 8 REVISION LOG Revision Effective Date Comment Original Issue September 8,1992 CIC07 COLR Revision 1 October 10,1992 CIC07 COLR rev 1 Revision 2 December 1,1993 CIC08 COLR Revision 3 April 14,1994 CIC08 COLR rev 1 Revision 4 October 24,1994 C1C08 COLR rev 2 Revision 5 November 30,1994 C1C08 COLR rev 3 Revision 6 February 15,1995 C1C09 COLR Revision 7 April 12,1995 ClC09 COLR rev 1 Revision 8 September 28,1995 C1C09 COLR rev 2 1
i
~
Cct:wbn 1 Cycle 9 Cere Operzting Limits R: port CNEl-0400-24 Page 4 of 20 Revision 8 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) 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:
Tech Spec COLR COLR Section Technical Specifications Section Pace 2.2.1 Reactor Trip System Instrumentation Setpoints 2.0 5
3/4.1.1.3
. Moderator Temperature Coefficient 3.0 7
3/4.1.2.5 Borated Water Source - Shutdown 3.1 9
3/4.1.2.6 Borated Water Source - Operating 3.2 10 3/4.1.3.5 Shutdown Rod Insertion Limit 3.3 10 3/4.1.3.6 Control Rod Insertion Limit 3.4 10 3/4.2.1 Axial Flux Difference 3.5' 10 3/4.2.2 Heat Flux Hot Channel Factor 3.6 13 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3.7 16 3/4.3.3.11 Boron Dilution Mitigation System 3.8 18 3/4.5.1 Accumulators 3.9 18 3/4.5.4 Refueling Water Storage Tank 3.10 18 3/4.9.1 Refueling Operations - Boron Concentration 3.11 19 3/4.9.2 Instrumentation 3.12 19 3/4.9.12 Refueling Operations - Spent Fuel Pool Boron 3.13 19 Concentration 4.7.13.3 Standby Makeup Pump Water Supply - Boron 3.14 20 4
Cct:wba 1 Cycle 9 Ccre Op:r: ting Limits Report CNEl-0400-24 Page 5 of 20 Revision 8
~
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.
2.0 Reactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.0.1 Overtemperature AT Setpoint Parameter Values Parameter Value K = 1.1954 Overtemperature AT reactor trip setpoint i
K = 0.03371/0F Overtemperature AT reactor trip heatup 2
setpoint penalty coefficient K = 0.001529/ psi Overtemperature AT reactor trip 3
depressurization setpoint penalty coefficient t = 8 sec.
Measured reactor vessel AT lead / lag time i
1 = 3 sec.
constants 2
T = 0 sec.
Measured AT lag time constant 3
Measured reactor vessel average temperature T4 = 22 sec.
lead / lag time constants T = 4 sec.
5 Measure reactor vessel average temperature T6 = 0 sec.
lag time constant f (AI) " positive" breakpoint
= 8.0 %AI i
f (AI) " negative" breakpoint
= -42.0 %Al i
f (AI) " positive" slope
= 1.640 %ATo/ %Al i
f (AI) " negative" slope
= 3.672 %ATo/ %Al i
Cat;wb21 Cycle 9 Ogre Operati:g Limits Rrp:rt _
CNEI-0400-24 Page 6 of 20 Revision 8 2.0.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4 = 1.0855 K = 0.001262/0F Overpower AT reactor trip heatup setpoint 6
penalty coefficient (for T > 590.8 F)
Overpower AT reactor trip heatup setpoint K6 = 0.0/0F penalty coefficient (for T $ 590.8 *F)
Measured reactor vessel AT lead / lag time t = 8 sec.
i T = 3 sec.
constants 2
t = 0 sec.
Measured AT lag time constant 3
T = 0 sec.
Measure reactor vessel average temperature 6
~ lag time constant T = 10 sec.
. Measure reactor vessel average temperature 7
rate-lag time constant f (AI)" Positive" breakpoint
= 35.0 %Al 2
f(AI) " negative" breakpoint
= -35.0 %Al 2
f (AI) " positive" slope
= 7.0 %ATo/ %AI 2
f (AI) " negative" slope
= 7.0 %ATo/ %Al 2
Cct:wba 1 Cycle 9 Cere Oper: ting Limits Rep:rt CNEI-0400-24 Page 7 of 20 Revision 8 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 0.7E-04 AK/K/*F.
The EOC, ARO, RTP MTC shall be less negative than -4.1E-04 AK/K/ F.
3.0.2 The MTC Surveillance Limit is:
The 300 PPM /ARO/ RTP MTC should be less negative than or equst to -3.2E-04 AK/K/ F.
where.
BOC = Beginning of Cycle EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Thermal Power RTP = Rated Thermal Power 4
i
~
Citawb31 Cycle 9 Cora Operating Limits Rep:rt CNEl-0400-24 Page 8 of 20 Revision 8 Figure 1 Moderator Temperature Coefficient Versus Power Level 1.0 0.9 -
0.8 -
Unacceptable Operation 0.7 k( 0.6 -
E
%0.5-~~
Acceptable Operation 5
0.4 -
0.3 -
0.2 -
0.1 -
0.0 l
l l
l l
l l
0 10 20 30 40 50 60 70 80 90 100 l
Percent of Rated Thermal Power 4
b 1
4
Cet.wbs 1 Cycis 9 Core Operzting Limits Rep:rt CNEI-0400-24 Page 9 of 20 Revision 8 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 and 6:
Parameter Limit i
Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.5a Boric Acid Storage System minimum contained 12,000 gallons water volume for LCO 3.1.2.5a Boric Acid Storage System minimum water 585 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron 2,475 ppm concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum contained 45,000 gallons borated water volume for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,475 ppm 4
Cctawba 1 Cycle 9 Core Operating Limits Rep:;rt CNEI-0400-24 Page 10 of 20 Revision 8
)
3.2 Horated Water Source - Operating (Specification 3/4.1.2.6) 3.2.1 Volum( ud boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, and 4:
i Parameter Limit Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.6a Boric Acid Storage System minimum contained 22,000 gallons water volume for LCO 3.1.2.6a Boric Acid Storage System minimum water 9,851 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron 2,475 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank minimum contained 98,607 gallons borated water volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,475 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.
Cctiwba 1 Cycle 9 Cere Op: rating Limits Report CNEI-0400-24 Page 11 of 20 Revision 8 Figure 2 Control Rod Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (29.I %,230)
(Maximum = 230)\\ (79.6%,230) 230 220 --
3 Fully Withdrawn 200 -
(Minimum = 222) 180 -
BANK B e
(100 %, 161) g 160 --(0%,163) iG g,140 - -
3E BANK C 120 --
e S
[100--
8 E 80 --
BANK D j
60 - -
7 x
40 --(0%,47) 20 --
Fully Inserted (30%,0) 0 0
10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power k
1 0
Cctawbs 1 Cycle 9 Ccre Operating Limits Rtport CNEI-0400-24 Page 12 of 20 Revision 8 Figure 3 Axial Flux Difference Limits Versus Percent of Rated Thermal Power l( 18,100)l l(+10,100)l (Unacceptable Operation l 90
.80 --
l Unacceptable Operatiq ti 8
70 --
l Acceptable Operatiod 60 --
C 3
cll!
50 --
. l( 36,50)l l(+21.50)l B
40 --
c3 30 --
20 - -
10 --
l l
l l
^
l l
l l
50
-40 30 20
-10 0
10 20 30 40 50 Axial Ilux Difference (% Delta I; i
1 i
Cctiwbs 1 Cycle 9 Ccre Operating Limits Report CNEI-0400-24 Page 13 of 20 Revision 8
)
3.6 Heat Flux Hot Channel Factar, FQ(X,Y,Z) (Specification 3/4.2.2) 3.6.1 Ff = 2.32 3.6.2 K(Z) is provided in Figure 4 for MkBW fuel.
The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.2:
[En(X,Y,Z)]OP =, $(X,Y,Z)
- Mo(X,Y,Z)
F 3.6.3 where:
[Fh(X,Y,Z)]OP = Cycle dependent maximum allowable design peaking factor which ensures that the Fo(X,Y,Z) limit will be preserved for operation within the LCO limits [Fh(X,Y,Z)]OP. [Fh(X,Y,Z)]OP includes allowances for calculational and measurement uncertainties.
Fh(X,Y,Z) = Design power distribution for Fo. Fh(X,Y,Z)is provided in Table 1, Appendix A, for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operations.
l Mo(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit m
)
the transient power distribution. M (X,Y,Z) is provided in Table g
1, Appendix A for nomial operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operations.
UMT = Measurement Uncertainty (UMT = 1.05)
MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty that accounts for allowable quadrant power tilt j
ratio of 1.02. (TILT = 1.035)
NOTE: [Fh(X,Y,Z)]or is the parameter identified as Fh"(X,Y,Z) in DPC-NE-2011PA.
L Catzwba 1 Cycle 9 Core Optreting Limits Report CNEI-0400-24 Page 14 of 20 Revision 8
[Fh(X,Y,Z)]RPS = F$(X,Y,Z)
- Mc(X,Y,Z) 3.6.4 k
where:
[Fh(X,Y,Z)]RPs = Cycle dependent maximum allowable design peakin'g factor which ensures that the centerline fuel melt limit will be preserved-for operation within the LCO limits. [Fh(X,Y,Z)]RPs includes allowances for calculational and measurement uncertainties.-
F$(X,Y,Z) = Design power distributions for Fo. F$(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.
Mc(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 M (X,Y,Z) calculations described in DPC-NE-201 IPA, n
except that the LOCA limit is replaced with the CFM limit.
Mc(X,Y,Z)is provided in Table 3, Appendix A for normal operating conditions and in Table 4, Appendix A for power escalation testing during initial 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: [Fh(X,Y,7.))RPs is the parameter identified as Fq"(X,Y,Z) in DPC-NE-201 IPA, except that M (X,Y,Z) is replaced by Mc(X,Y,Z).
g
. l KSLOPE = Adjustment to the K value from OTAT required to compensate for 3.6.5 1
each 1% that [Fh(X,Y,Z)]RPs exceeds its limit. (KSLOPE = 0.0725) e y
O Ccttwha 1 Cycl 2 9 C:re Operating Limits Rrp:rt CNEl-0400-24 Page 15 of 20 Revision 8 Figure 4
~ K(Z), Normalized Fo(X,Y,Z) as a Function of Core Height for MkBW Fuel 1.2 (0.0,1.00)
(8.0,1.00) 1.0 (10.8,0.94) 0.8 E 0.6 (12.0,0.647) x 0.4 0.2 0.0 O.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 Core Height (ft)
Cctswbs 1 Cycl: 9 Core Optrating Limits Report CNEI-0400-24 Page 16 of 20 i
Revision 8 J
3.7 Nuclear Enthalpy Rise Hot Channel Factor, FAH(X,Y,Z) (Specification 3/4.2.3)
The following parameters are required for the LCO requirements of T.S. 3/4.2.3.
I 3.7.1
[Fi,(X,Y)]"= MARP (X,Y)
- _l.0 + RRH * (1.0 - P) where:
MARP(X,Y) = Cycle specific Operating Limit Maximum Allowable Radial Peaks.
MARP(X,Y) radial peaking limits, provided in Table 7, Appendix A.
Thermal Power p, Rated Thermal Power J
RRH = Defined in section 3.7.3 The following parameters are required for core monitoring per the Surveillance requirements of T.S. 3/4.2.3.
[F[,(X,Y)]SURV = F (X,Y)xM3g(X,Y) 3n 3.7.2 UMRxTILT where:
[ fin (X,Y)]suny = Cycle dependent maximum allowable design peaking factor which ensures that the FAH(X,Y) limit will be preserved for operation within the LCO limits. [ fin (X,Y)]sunv includes allowances for calculational and measurement uncertainty.
F$n(X,Y) = Design power distribution for F n, F$n(X,Y)is provided in 3
Table 5, Appendix A for normal operation and in Table 6, Appendix A for power escalation testing during initial startup operations.
4
l Cat wba 1 Cycle 9 Cere Operating Limits R p rt CNEl-0400-24 Page 17 of 20 Revision 8 Mon (X,Y) = Margin remaining in core location X,Y relative to the
. Operational DNB limit in the transient power distribution.
Ma (X,Y)is provided in Table 5, Appendix A for normal n
operation and in Table 6, Appendix A for power escalation testing during initial startup operations.
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: [ fin (X,Y)]sunv is the parameter identified as [F n(X,Y)]M^x in DPC-NE-3 20llPA.
3.7.3 RRH = Thermal Power reduction required to compensate for each 1% that F n(X,Y) exceeds its limit (RRH = 3.34).
3 TRH = Reduction in OTAT K setpoint required to compensate for each 1% that 3.7.4 1
Fan (X,Y) exceeds its limit (TRH = 0.04).
d
/
a
Ccttwb: 1 Cycle 9 Core Op: rating Limits Report CNEI-0400-24 Page 18 of 20 Revision 8 3.8 Boron Dilution Mitigation System (Specification 3/4.3.3.11) 3.8.1 Reactor Water Makeup Pump flowrate limits:
Apolicable Mode Limit Mode 3 or 4
$ 150 gpm -
Mode 5 5 70 gpm 3.9 Accumulators (Specification 3/4.5.1) 3.9.1 Boron concentration limits during modes 1,2, and 3:
Parameter Limit Cold Leg Accumulator minimum boron concentration for 2,375 ppm LCO 3.5.1c Cold Leg Accumulator maximum boron concentration for 2,575 ppm LCO 3.5.1c Minimum Cold Leg Accumulator boron concentration 2,250 ppm required to ensure post-LOCA suberiticality 3.10 Refueling Water Storage Tank (Specification 3/4.5.4) 3.10.1 Boron concentration limits during modes 1,2,3, and 4:
Parameter Limit j
Refueling Water Storage Tank minimum boron 2,475 ppm j
concentration for LCO 3.5.4b Refueling Water Storage Tank maximum boron 2,575 ppm concentration for LCO 3.5.4b
Cctiwbs 1 Cycle 9 Core Optrating Limits Report CNEI-0400-24 Page 19 of 20 Revision 8
~
3.11 Refueling Operations - Boron Concentration (Specification 3/4.9.1) 3.11.1 Mmmm.a boron concentrations for the filled portions of the Reactor Coolant System and refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.
Parameter Limit Refueling boron concentration for the filled portions of the 2,475 ppm Reactor Coolant System and refueling canal for LCO 3.9.1.b.
3.12 Instrumentation (Specification 3/4.9.2) 3.12.1 Reactor Makeup Water Pump Flowrate Limit:
Applicable Mode Limit Mode 6
< 70 gpm 3.13 Refueling Operations - Spent Fuel Pool Boron Concentration (Specification 3/4.9.12) 3.13.1 Minimum baron concentration limits for spent fuel pool. Applicable when fuel is stored in the spent fuel pool.
Parameter Limit Spent fuel pool minimum boron concentration 2,475 ppm for LCO 3.9.12
Cetawba 1 Cycle 9 Core Operating Limits Report CNEI-0400-24 Page 20 of 20 Revision 8 3.14 Standby Makeup Pump Water Supply - Boron Concentration (Specification 4.7.13.3) 3.14.1 Minimum boron concentration limit for the spent fuel pool, or a contained borated water volume (meeting additional requirements of surveillance 4.7.13,3.a.2).
Applicable for modes 1,2, and 3.
Parameter Limit Spent fuel pool minimum boron concentration for 2,475 ppm surveillance 4.7.13.3.a.1 Contained borated water volume for surveillance 2,475 ppm 4.7.13.3.a.2 4
l NOTE: Data contained in the Appendix of this document was generated in the Catawba 1 Cycle 9 Maneuvering Analysis calculational file, CNC-1553.05-00-0197. The Catawba Nuclear Engineering Section will control this information via computer file (s) and should be contacted if there is a nerd to access this information.
?
a t