ML24094A099
| ML24094A099 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/03/2024 |
| From: | Hardy J Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| GNRO2024-00010 | |
| Download: ML24094A099 (1) | |
Text
- ) entergy GNRO2024-00010 April 3, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Jeffery Hardy Manager Regulatory Assurance Grand Gulf Nuclear Station Tel: 802-380-5124 GGNS TS 5.6.5
SUBJECT:
Grand Gulf Nuclear Station (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 In accordance with 1 O CFR 50.36 and GGNS Technical Specification Section 5.6.5.d, GGNS is required to provide to the Nuclear Regulatory Commission any updates to the COLR.
Revision O of the GGNS Cycle 25 COLR is attached to this letter.
There are no commitments contained in this submittal. If you have any questions or need additional information, please contact me at 802-380-5124.
JH/ram
Attachment:
Core Operating Limits Report (COLR) Cycle 25, Revision O
GNRO2024-0001 0 Page 2 of 2 cc:
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Grand Gulf Nuclear Station Core Operating Limits Report Cycle 25 Revision 0
CORE OPERATING LIMITS REPORT REASON FOR REVISION Revision 0:
The Cycle 25 core operating limits are updated to provide cycle-specific MCPR and LHGRFAC multiplier values for the GNF3 fuel in Cycle 25. Figure 1-1 provides the APLHGR limits for the GNF3 fuel type. Figures 2-1 through 2-6 are updated with new MCPR limits and Figures 3-1 through 3-3 are updated with new LHGRFAC limits.
No other core operating limits are changed.
These limits are based on a core power of 4408 MWt.
CORE OPERATING LIMITS REPORT TABLE OF CONTENTS 1.0 PURPOSE 4
2.0 SCOPE 4
3.0 REFERENCES
5 3.1 Current Cycle References 5
4.0 DEFINITIONS 7
5.0 GENERAL REQUIREMENTS 9
5.1 Averaoe Planar Linear Heat Generation Rates 9
5.2 Minimum Criti cal Power Ratio 9
5.3 Linear Heat Generation Rate 10 5.4 Stabilitv 10 5.5 Applicability 11 5.6 Limitations and Conditions 11 Table 1 OPRM Upscale CDA Amplitude Discriminator 12 Setpoint Table 2 BSP Endpoints for Normal Feedwater Temperature 12 Table 3 BSP Endpoints for Reduced Feedwater 12 Temperature Table 4 ABSP Setpoints for the Scram Region 12 Table 5 Margin to Thermal Overpower and Mechanical 12 Overpower Limits Table 6 Application Conditions 13 Table 7 Rated OLMCPR Summary Table 13 Figure(s) 1 APLHGR Operating Limits 14 Figure(s) 2 MCPR Operating Limits 15 Fiaure(s) 3 LHGR Operatina Limits 26 Figure 4 Backup Stability Protection Region Boundaries 28 for Normal Feedwater Temperature Figure 5 Backup Stability Protection Region Boundaries 29 for Reduced Feedwater Temperature COLR Page 3 LBDCR 2024-0008
CORE OPERATING LIMITS REPORT 1.0 PURPOSE The C0LR is controlled as a License Basis Document and revised accordingly for each fuel cycle or remaining portion of a fuel cycle.
Any revisions to the C0LR must be submitted to the NRC for information as required by Tech Spec 5.6.5 and tracked by Licensing Commitment 29132.
This C0LR reports the Cycle 25 core operating limits and stability setpoint confirmation and regions.
2.0 SCOPE As defined in Technical Specification 1.1, the C0LR is the GGNS document that provides the core operating limits for the current fuel cycle.
This document is prepared in accordance with Technical Specification 5.6.5 for each reload cycle using NRC-approved analytical methods.
The Cycle 25 core operating and stability limits included in this report are:
the Average Planar Linear Heat Generation Rate (APLHGR),
the Minimum Critical Power Ratio (MCPR) (including EOC-RPT inoperable),
the Linear Heat Generation Rate (LHGR) limit, and the DSS-CD stability setpoint confirmation and regions.
CORE OPERATING LIMITS REPORT
3.0 REFERENCES
This section contains the cycle-specific references used in the safety analysis of Grand Gulf Cycle 25.
Methodology references are documented in Technical Specification 5.6.Sb.
3.1 Current Cycle References 3.1.1 ECH-NE-24-00003 Revision 0, Supplemental Reload Licensing Report for Grand Gulf-1 Reload 24 Cycle 25, December 2023.
3.1.2 GNF007N0437 Revision 0, Nuclear Design Report for Grand Gulf Nuclear Station Cycle 25, September 2023.
3.1.3 ECH-NE-24-00002 Revision 0, Fuel Bundle Information Report for Grand Gulf-1 Reload 24 Cycle 25, December 2023.
3.1.4 NEDC-32910P, Revision 1, Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident Analysis With Relaxed ECCS Parameters, October 1999 (GEXI-1999-00174).
3.1.5 GGNS-NE-12-00022 Revision 1, Grand Gulf Nuclear Station MELLLA+ Task T0407, ECCS-LOCA Performance, October 2019.
3.1.6 SC 21-04 Revision 3, Fuel Support Side Entry Orifice Meta-Stable Flow for 2 Beam Locations in the BWR/6 Reactors, February 2024.
3.1.7 NEDC-33173P-A, Revision 5, Applicability of GE Methods to Expanded Operating Domains (with Supplements SP-A Rev. 1, and 6P-A Rev. 1). October 2019.
3.1.8 NEDC-33006P-A, Revision 3, GE BWR Maximum Extended Load Line Limit Analysis Plus, June 2009.
3.1.9 GGNS-SA-21-00002, Revision O (GEH 0000-0158-7807-Rl), Grand Gulf Nuclear Station PRNM System DSS-CD Settings, April 2020.
3.1.10 ECH-NE-20-00006 Revision 0, GNF3 Fuel Design Cycle-Independent Analyses for Grand Gulf Nuclear Station, February 2020.
3.1.11 GGNS-SA-19-00001 Revision O Grand Gulf Nuclear Station GNF3 ECCS-LOCA Evaluation Revision 1, October 2019.
3.1.12 GEH-GGNS-AEP-632, GGNS MELLLA+ Final DSS-CD Settings Report, October 23, 2013.
3.1.13 NEDE-24011-P-A-31, General Electri c Standard Application for Reactor Fuel (GESTAR-II), November 2020, (KGO-ENO-GEN-21-039).
3.1.14 ECH-NE-21-00025 Rev. 1, Grand Gulf Nuclear Station TRACG Implementation for Reload Transient Analysis (T1309). December 2023.
CORE OPERATING LIMITS REPORT 3.1.15 NED0-33612-A, Revision 0, Safety Analysis Report for GGNS Maximum Extended Load Line Limit Analysis Plus, September 2013.
3.1.16 NEDC-33879P, Revision 4, GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II), August 2020.
3.1.17 NEDC-33880P, Revision 1, GEXL21 Correlation for GNF3 Fuel, November 2017 (KGO-ENO-GEN-20-031).
3.1.18 NEDC-33840P-A, Revision 1, The PRIME Model for Transient Analysis of Fuel Rod Thermal - Mechanical Performance, August 2017.
3.1.19 GGNS-NE-10-00076, Revision O (GEH 0000-0121-1122-RO), GGNS EPU Option B Scram Times, September 2010.
CORE OPERATING LIMITS REPORT 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR) - the APLHGR shall be applicable to a specific planar height and is equal to the sum of the linear heat generation rates for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.
4.2 Average Planar Exposure - the Average Planar Exposure shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.
4.3 Critical Power Ratio (CPR) - the ratio of that power in the assembly, which is calculated by application of the fuel vendor's appropriate boiling correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
4.4 Core Operating Limits Report (COLR) - The Grand Gulf Nuclear Station specific document that provides core operating limits for the current reload cycle in accordance with Technical Specification 5.6.5.
4.5 Linear Heat Generation Rate (LHGR) - the LHGR shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
4.6 Minimum Critical Power Ratio (MCPR) - the MCPR shall be the smallest CPR which exists in the core.
4.7 MCPR Safety Limit - cycle specific SLMCPR, known as MCPR99.~, is the minimum value of the CPR at which the fuel could be operated to ensure that 99.9%
percent of the fuel in the core is not susceptible to the boiling transition.
4.8 Oscillation Power Range Monitor (OPRM) - Provides automatic detection and suppression of reactor core thermal-hydraulic instabilities through monitoring neutron flux changes.
4.9 Backup Stability Protection (BSP) Boundary - Defines the operation domain where potential instability events can be effectively addressed by specific operator action. Region of the power and flow operating domain that is not expected to be susceptible to instability events associated with a high initial growth rate.
4.10 Backup Stability Protection (BSP) Scram Region - The area of the core power and flow operating domain where the reactor is susceptible to reactor instabilities under conditions exceeding the licensing basis of the current reactor system.
An immediate manual scram is required upon entry.
4.11 Backup Stability Protection (BSP) Controlled Entry Region - The area of the core power and flow operating domain where the reactor is susceptible to reactor instabilities.
Compliance with at least one alternate stability control is required upon entry.
4.12 Automated Backup Stability Protection (ABSP) Scram Region - An automated reactor scram region that bounds the BSP Scram Region and is initiated by the APRM flow-biased scram setpoint upon entry.
4.13 End of Rated (EOR) - The Cycle exposure corresponding to all rods out, 100%
power, 100% flow, and normal feedwater temperature [3.1.1].
4.14 Middle of Cycle (MOC) - The Cycle 25 MOC Core Average Exposure (CAE) is MOC= EOR-4,000 MWd/ST [3.1.1].
4.15 End of Cycle (EOC) - The Cycle 25 EOC CAE is 33,334 MWd/ST [3.1.2].
4.16 Maximum Extended Load Line Limit Analysis Plus (MELLLA+) - The GGNS MELLLA+
operating domain is depicted in Figure 4.
4.17 Maximum Number of OPRM Cells Along an Instability Symmetry Axis CM.. ) - An OPRM configuration constant representing maximum number of OPRM cells along an instability symmetry axis. It is used to calculate the number of COLR Page 7 LBDCR 2024-0008
CORE OPERATING LIMITS REPORT unresponsive 0PRM cells. Per [3.1.12] the GGNS specific value is five (MAx = 5),
4.18 Application Conditions - The combination of equipment out of service conditions for which LHGRFAC and MCPR limits are determined [3.1.1]. The Application Conditions are specified in Table 6.
4.19 MCPR~ Safety Limit - Cycle-independent Technical Specification (TS) 2.1.1 SLMCPR, ensures there is a 95 percent probability at a 95 percent confidence level that no fuel rods will be susceptible to transition boiling.
CORE OPERATING LIMITS REPORT 5.0 GENERAL REQUIREMENTS 5.1 Average Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs shall not exceed the fuel type and exposure-dependent limits reported in Figure 1-1 [3.1.1].
5.2 Minimum Critical Power Ratio For Cycle 25, the cycle-specific MCPR Safety Limit (MCPRgg_""), is 1.12 for Two Loop Operation (TLO), and 1.12 for Single Loop Operation (SLO) [3.1.1].
GEH Safety Communication (SC) 21-04 [3.1.6] identifies a metastable flow condition that may exist in a BWR/6 in core locations fed by a side entry orifice adjacent to two core support cross beams. The vendor has been unable to determine the frequency of occurrence of this flow condition, if any. This flow condition results in a higher loss coefficient and lower CPR (applied as higher MCPR limits). To be conservative, it is assumed this condition always exists, so an MCPR penalty is always applied. All power-dependent MCPR limits in the COLR Tables and Figures apply the penalty recommended by SC 21-04 Rev. 3.
Consistent with Technical Specification 3.2.2, the MCPR shall be equal to or greater than the limits reported in Figure(s) 2 as functions of power, flow, exposure, and scram speed [3.1.1, 3.1.10, 3.1.19]. For operation at powers ~35.4%,
the power-dependent MCPR shall be determined based on scram time surveillance data as follows. [3.1.19]
- 1) If the average scram time ( T_,wt) satisfies the following:
T,IIE ~TB' then the power dependent MCPR shall be equal to or greater than the Option B limits reported in Figure(s) 2 as a function of exposure.
- 2)
If the average scram time T,11 "£ > T8 and, ::5 0.2, then the power-dependent MCPR shall be equal to or greater than the Tau= 0.2 limits reported in Figure(s) 2 as a function of exposure,
- 3)
If the average scram time T,-11"£ > T8 and, > 0.2, then the power-dependent MCPR shall be equal to or greater than the Option A limits reported in Figure(s) 2 as a function of exposure.
In the above equations:
~4~c = average scram time to the 20% insertion position as calculated by equation 1 of Reference 3.1.19, COLR Page 9 LBDCR 2024-0008
CORE OPERATING LIMITS REPORT r 8
= adjusted analysis mean scram time for 20% insertion as calculated by equation 3 of Reference 3.1.19 and T = T.fff -
TH TA -
TH where r A
= the technical specification limit on core average scram time to the 20 percent insertion position (0.503 seconds).
The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7. Additional MCPR operating limits are provided to support operation with EOC-RPT inoperable as described in Technical Specification 3.3.4.1.
Rated Operating Limit MCPR values (equipment in service, 100% power, OLMCPR's) are provided in Table 7. The power-dependent MCPR results in Figures 2-1 through 2-5 include the SC 21-04 Rev. 3 [3.1.6] penalties. The SC21-04 Rev. 3 penalties do not need to be applied to flow-dependent MCPR results.
5.3 Linear Heat Generation Rate Consistent with Technical Specification 3.2.3, the LHGRs for any GNF3 fuel rod at any axial location shall not exceed the nodal exposure-dependent limits reported in Reference 3.1.3 (by reference reported in [3.1.16]) multiplied by the smaller of either the power-dependent or flow-dependent LHGR factors reported in Figures 3-1 and 3-2, and Figures 3-3, respectively [3.1.1].
The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7.
5.4 Stability The OPRM Upscale Confirmation Density Algorithm (CDA) Amplitude Discriminator setpoint is reported in Table 1.
The Backup Stability Protection (BSP) regions boundaries are reported in Figures 4 and 5 [3.1.1]. BSP measures support operation with the OPRM upscale trip function inoperable as described in Technical Specification 3.3.1.1 Condition J. The endpoints for the BSP region boundaries are provided for normal (NFWT) and reduced (RFWT) feedwater temperature operations in Tables 2 and 3, respectively. Figures 4 and 5 depict the BSP region boundaries for NFWT and RFWT operations. Note that Figures 4 and 5 also depict the MELLLA+ and MELLLA domains, consistent with feedwater temperature operating limitations.
The ABSP APRM Simulated Thermal Power (STP) setpoints associated with the ABSP Scram Region are provided in Table 4. The ABSP setpoints are applicable to TLO and SLO, and to both normal and reduced feedwater temperature operations.
The BSP Boundary and Manual BSP region boundaries for normal feedwater temperature operations are valid for reductions in normal feedwater temperature as much as (and including) -10.0 °F [3.1.1].
CORE OPERATING LIMITS REPORT 5.5 Applicability The following core operating limits are applicable for operation in the Maximum Extended Operating Domain (MEOD), with Feedwater Heaters Out of Service (FWHOOS),
Turbine Bypass Out of Service (TBVOOS), EOC-RPT inoperable, and Pressure Regulator Out of Service (PROOS).
For operation with one of the previous conditions mentioned, the alternate MCPR limits described in Section 5.2 above must be implemented. Table 6 provides an applicability condition list of events related to the Figures. For SLO, the following additional requirements must be satisfied.
- 1. THE APLHGRs shall not exceed the exposure-dependent limits determined in accordance with Section 5.1 [3.1.1].
- 2. THE LHGRs shall not exceed the smaller of the nodal exposure-dependent limits determined in accordance with Section 5.3 above or the nodal exposure-dependent limits reported in Reference 3.1.3.
- 3. The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.02. SLO MCPR operating limits are displayed in Figures 2-1 through 2-5 "C" & "D" and Figure 2-6 "B"
[3.1.1].
5.6 Limitations and Conditions As required by Limitation and Condition 9.10/9.ll of licensing topical report NEDC-33173P-A [3.1.7], the limiting Thermal and Mechanical Overpower results are reported in Table 5. The results are summarized as a percent margin to both of these limits.
The results are confirmed to meet the required 10% margin to the design limits [3.1.1].
As required by Limitation and Condition 12.10.b of licensing topical report NEDC-33006P-A [3.1.8], the off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the off-rated LHGR multipliers provided Figures 3-1 through 3-3. These off-rated LHGR multipliers provide adequate protection for MELLLA+ operation.
As required by Limitation and Condition 12.5.c of licensing topical report NEDC-33006P-A [3.1.8], the plant specific power/flow map specifying the GGNS licensed MELLLA+ operating domain is included as Figure 4.
As required by Limitation and Condition 12.5.b of licensing topical report NEDC-33006P-A [3.1.8], operation with Feedwater Heaters Out of Service (FWHOOS) is prohibited while in the MELLLA+ operating domain [3.1.1]. In addition, as required by Limitation and Condition 12.5.a of licensing topical report NEDC-33006P-A
[3.1.8], and described in GGNS TS 3.4.1 LCO, SLO is prohibited in the MELLLA+
operating domain [3.1.1].Therefore, operations with RFWT and/or SLO must adhere to the operating domain shown in Figure 5.
Endpoint Al CORE OPERATING LIMITS REPORT Table 1 OPRM Upscale CDA Amplitude Discriminator Setpoint Amplitude Discriminator Trip 1.10 Table 2 BSP Endpoints for Normal Feedwater Temperature Power(%)
Flow(%)
Definition 72.3 44.2 Scram Region Boundary, HFCL Bl 34.1
- 25. 2 Scram Reqion Boundary, NCL A2 67.3 50.0 Controlled Entry Reqion Boundary, HFCL 82 26.4 24.4 Controlled Entry Reoion Boundary, NCL Table 3 BSP Endpoints for Reduced Feedwater Temperature Endooint Power(%)
Flow(%)
Definition Al' 66.9 49.5 Scram Region Boundary, HFCL Bl' 28.6 24.6 Scram Reqion Boundary, NCL A2' 68.3
- 51. 2 Controlled Entry Reqion Boundary, HFCL B2' 26.4 24.4 Controlled Entry Reqion Boundary, NCL Table 4 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM fl ow-biased trip linear segment mTRIP 0.77 ABSP APRM flow-biased trip setpoint power intercept.
PssP-TRIP 31.0% RTP1 Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint.
ABSP APRM flow-biased trip setpoint drive flow WssP-TRIP 39.0% RDF1 intercept. Constant Flow Line for Trip.
Flow Breakpoint value WssP-BREAK 7.6% RDP
- 1. RTP - Rated Thermal Power
- 2. RDF - Reci rculation Drive Fl ow Table 5 Margin to Thermal Overpower and Mechanical Overpower Limits Criteria GNF3 Thermal Overpower Margin 39.83%
Mechanical Overpower Margin 47.65%
COLR Page 13 CORE OPERATING LIMITS REPORT Table 6 Application Conditions Application FWH 005 EOC-RPT PR 005 TBV 005 Condition 1
X 2
X X
3 X
X 4
X X
X 5
X X
6 X
X X
7 X
X X
8 X
X X
X Table 7 Rated OLMCPR Summary Table Application GNF3 OPT A GNF3 OPT B GNF3 OPT A GNF3 OPT B Condition BOC-MOC BOC-MOC MOC-EOC MOC-EOC 1
- 1. 37 1.30
- 1. 38
- 1. 30 2
- 1. 37 1.30
- 1. 38
- 1. 30 3
- 1. 37
- 1. 30
- 1. 39
- 1. 31 4
- 1. 37 1.30
- 1. 39 1.31 5
- 1. 38
- 1. 38 1.42 1.42 6
1.38 1.38 1.46 1.46 7
1.38
- 1. 38 1.42 1.42 8
- 1. 38 1.38 1.46 1.46 LBDCR 2024- 0008
15 000, 14 36 14 13 12 E 11
?;
- . 10 0:::
(!)
9
- c
...J a..
<(
8
- E 7
6 5
4 0
COLR Page 14 10 CORE OPERATING LIMITS REPORT 20 30
..io Average Planar Exposure (GWd/ S11 Figure 1-1 50 GNF3 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits descnbed in Sections 5.1 and 5.5 63 50, 600 60 70 LBDCR 2024-0008
2.2 2.1 2.0 1.9 1 8 i:i: 1.7 ci' 1.6 Cl.
li 1.5 1.4 1.3 1.2 1.1 1.0 0
2.2 2.1 2.0 1.9 1.8 i:i: 1.7 ii" 1.6 Cl. u
- E 1.5 1.4 1.3 1.2 1.1 1.0 0
COLR Page 15 CORE OPERATING LIMITS REPORT
- . 50% Core Flow 218, 208 I
21.8, 1.97
< 50% Core Flow /
35.4, 1.90 Option A 10 20 21 8, 2.08 21.8, 1.97 35.4, 1.68 35 4, 1 62 354, 160
- 40. 1.68
- 40. 1 60 70, 1.43 so, 1 53
- 70. 1 46 50, 1.51/
70, 1 38 Option B 70, 1 36 30 40 50 60 Core Power (0.4 Rated)
Figure 2-1A 70 Cycle 25 Power-Dependent MCPR Limits, EIS BOC to MOC, TLO
- . 50% Core Flow
< 50% Core Flow /
354, 190 Option A
/
ro.*53 10 20 35.4, 1.69 354, 162 35 4, 1 60 30 40, 1 62 40, 1 60 40 50 60 Core Power (% Rated)
Figure 2-1B 70, 1 36 70 Cycle 25 Power-Dependent MCPR Limits, EIS MOC to EOC, TLO Tau z 0.2 85, 1.42 80 90 100 Tau* 0.2 80 90 100 LBDCR 2024-0008
2.2 2.1 2.0 1.9 1.8
~ 1.7 ii' 1.6 C.
!i 1.5 1.4 1.3 1.2 1.1 1.0 0
2.2 2.1 2.0 1.9 1.8
~ 1.7 ii' 1.6 C.
u
- E 1.5 1.4 1.3 1.2 1.1 1.0 0
COLR Page 16 CORE OPERATING LIMITS REPORT 21.8, 2.10 21.8, 1.99
< 50% Core Flow /
10 20 35.4, 1.70 35.4, 1.64 35 4. 1 62 30 35.4, 1.92 70, 1.45 70,140 70, 1 46
- 70. 138 Option B 40 50 60 70 Core Power ('k Rated)
Figure 2-1c Cycle 25 Power-Dependent MCPR Limits, EIS BOC to MOC, SLO 218, 210
/
21.8. 1.99
< 50% Core Flow /
35.4. 1.71
~ 50% Core Flow 35.4. 1.92 40, 1 71 Option A I,....
85, 1.44 85, 1 39
- 85. 1 37 80 35 4, 1 64 35 4, 1 62 70, 146 Tau= 0.2 100. 1 39 100, 1.34 100, 1 32 90 100 Tau* 0.2 40, 1 64 50, 151/
85, 1.45 10 20 30 40, 1.62 SO, 1 55 70, 1 48 Option B 70, 140 40 50 60 Core Power (% Rated)
Figure 2-10 70, 1 46 70, 1 38 70 Cycle 25 Power-Dependent MCPR Limits, EIS MOC to EOC, SLO 100, 1.40 100, 1.34 85, 1 39 100, 1 32 85, 1 37 80 90 100 LBDCR 2024-0008
2.2 2.1 2.0 1.9 1.8 a: 1.7 ix Q.
1.6
!i 1.5 1.4 1.3 1.2 1.1 1.0 0
2.2 2.1 2.0 1.9 1.8 a: 1.7 ix 1.6 C.
u
- Ii 1.5 1.4 1.3 1.2 1.1 1.0 0
COLR Page 17 CORE OPERATING LIMITS REPORT
- . 50% Core Flow 21.8, 2.08 21.8, 1.97 35,4, 1.90 Option A 40, 1.68 35.4, 1 68
/70, 1.52 35 4, 1 62 70, 1 48 35 4, 1 60
- 40. 1 60 50, 1 53 70,146 70, 1 43 Option B 70, 1 44
- 70. 1.41 10 20 30 40 50 60 70 Core Power (% Rated)
Figure2-2A Cycle 25 Power-Dependent MCPR Limits With FWH 00S 21.8, 2.08 21 8. 1,97 BOC to MOC, TLO
- . 50% Core Flow I
< 50% Core Flow /
35 4, 1 90 10 20 35.4, 1 69 35 4. 1 62 35.4, 1.60 30 40, 1.69 40,162 40, 1 60 40 50, 155 /
50, 1 53 Option B 50 60 Core Power (% Rated)
Figure 2-2B 70, 1.53 70, I 46 70, 1 43 70, 1 44 70, 141 70 Cycle 25 Power-Dependent MCPR Limits With FWH 00S MOC to EOC, TLO 85, 1 43 85, 1 41 80 85, 1.43 85, I 41 80 Tau= 0.2 100. 1.37 100, 1 32 100, 1 30 90 100 Tau= 0.2 100, 1.38 100. 1 32 100, 1 30 90 100 LBDCR 2024-0008
2.2 2.1 2.0 1.9 1.8 ii: 1.7 ex 1.6 Q. u
- E 1.5 1.4 1.3 1.2 1.1 1.0 0
2.2 2.1 2.0 1.9 1.8 a: 1.7 ex 1.6 Q.
u
- E 1.5 1.4 1.3 1.2 1.1 1.0 0
COLR Page 18 CORE OPERATING LIMITS REPORT 21 8, 2.10 21.8, 1.99
~ 50% Core Flow
< 50% Core Flow /
35.4, 1.92 10 20 35.4, 1.70 35 4. 1 64 35 4. 1 62 30
- 40. 1.70 40, 1.62 SO, 157 /
so, 1 55 Option B 40 50 60 Core Power (% Rated)
Figure2-2C 70, 1.43
~ 50% core Flow 21 8, 2.10
/
35,4, 1 92 Option A
< 50% Core Flow
- 40. 1.71 I,._rn 10 20 35 4. 1.71 35 4, 1 64 35 4. 1 62 30 40, 1 62 50, 157 /
SO, 1 55 Option B 40 50 60 Core Power (*~ Rated)
Figure 2-2D 70, 1.43 70, 1 45
- 70. 1 46 70, 1 43 70 Cycle 25 Power-Dependent MCPR Limits with FWH 00S MOC to EOC, SLO 80 85, 1 45 85, 1 43 80 90 90 Tau* 0.2 100. 1.39 100. 1.34 100. 1 32 100 Tau= 0.2 100. 1.40 100, 1 34 100, 1 32 100 LBDCR 2024-0008
2.2 2.1 2.0 1.9 1.8 a: 1.7 ii"' 1.6 Q.
u
- E 1.5 1.4 1.3 1.2 1.1 1.0 0
2.2 2.1 2.0 1.9 1.8 a: 1.7 ii"' 1.6 Q.
u
- E 1.5 1.4 1.3 1.2 1.1 1 0 0
CORE OPERATING LIMITS REPORT
- !. SO% Core Flow 21 8, 2,08 21 8. 1,97 35 4, 1.90 Option A 40, 1.68 35.4. 1 68
/70, 1.52 35 4, 1.62 70, 1 48 35 4, 1 60
- 40. 1 60 so, 1.53 70, 1 46
- 70. 1 43 Option B 70, 1 44 70, 1 41 10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-3A Cycle 25 Power-Dependent MCPR Limits wi1h EOC-RPT OOS, or EOC-RPT & FWH OOS BOC to MOC, TLO
- !. SO% Core Flow 21 8, 2.08 I
21.8, 1.97
< SO% Core Flow /
35.4. 1.90 40, 1.71 354, 171 70, 1.54 35 4, 1 63 35 4, 1.61 40, 1 63 40, 1 61 50, 1 56 I 50, 154 70, 147 85, 1 44 70, 1 44 85, 1 42 Option B 70, 1 45
- 70. 1 42 10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Flgure2-3B Cycle 25 Power-Dependent MCPR Limits wi1h EOC-RPT OOS, or EOC-RPT & FWH OOS MOC to EOC, TLO Tau~ 0.2 100, 1,37 100, 1 32 100, 1 30 100 Tau* 0.2 100, 1,39 100. 1 33 100, 1 31 100 COLR Page 19 LBDCR 2024- 0008
22 2.1 2.0 1.9 1.8 i:i: 1.7 ix 1.6
- a.
u
- E 1.5 1.4 1.3 1.2 1.1 1 0 22 2.1 2.0 1.9 1.8 i:i: 1 7 ix
- a.
1.6
~ 1.5 1.4 1.3 1.2 1.1 1.0 0
CORE OPERATING LIMITS REPORT 21.8, 2 10 218,199
< 50% Core Flow /
10 20 35.4, 1.70 35 4, 1 64 35.4, 1 62 30
- . 50% Core Flow
- 40. 162 50"7 /
50, 155 Option B 40 50 60 Core Power (% Rated)
Figure 2-3C 70, 1 48 85, 1 45 70, 1 45
- 35. 1 43 70, 1 46 70, 1 43 70 80 90 Cycle 25 Power-Dependent MCPR Limits with EOC-RPT 00S, or EOC-RPT & FWH 00S BOC to MOC, SLO
- _ 50% Core Flow 21.8, 2.10
/
35.4, 1.92
< 50% Core Flow 40, 1.73 35.4, 1.73 35 4, 1 65 35 4, 1 63 40 1 63 "**~ I 85, 1 46 so. 1 56 70, 1 49 70, I 46 85, 1 44 Option B 70, 1 47 70, 1 44 0
10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-30 Cycle 25 Power-Dependent MCPR Limits with EOC-RPT 00S, or EOC-RPT & FWH 00S MOC to EOC, SLO Tau* 0.2 100, 1.39 100, 1 34 100, 1 32 100 Tau a 0.2 100. 1.41 100, 1 35 100. I 33 100 COLR Page 20 LBDCR 2024-0008
22 2 1 20 1 9 1 8
=
1 7
~ 1 6 C. u
- E 1 5 1_4 1 3 1 2 1 1 1 0 0
22 2 1 2 0 1 9 1 8 C:
1 7 ii" 1 6 C.
u
- E 1 5 1 4 1 3 1 2 1 1 1 0 0
COLR Page 21 CORE OPERATING LIMITS REPORT
~ 50% Core Flow so 1 87 10 20 30 40 50 60 70 BO 90 Core Power (3/4 Rated)
Figure 2-4A Cycle 25 Power-Dependent MCPR Limits with PR OOS or PR & EOC RPT OOS BOC to MOC, TLO 21 8 2 08 21 8 1 97
< 50% Core Flow /
10 20 30
- . 50% Core Flow 35 4, 1 93 50 1 93 40 50 60 Core Power (3/4 Rated)
Figure 2-48 70 80 90 Cycle 25 Power-Dependent MCPR Limits with PR OOS or PR & EOC RPT OOS MOC to EOC, TLO 100, 1 38 100 100, I 42 100 LBDCR 2024-0008
22 2 1 20 1 9 1 8
- §; 1 7 c::
1 6 a.. u
==
1 5 14 1 3 1 2 1 1 1 0 0
22 2 1 20 1 9 1 8
- §; 1 7 c::
1 6 c.. u
==
1 5 1 4 1 3 1 2 1 1 1 0 0
COLR Page 22 CORE OPERATING LIMITS REPORT 218,210 218,199
< 50% Core Flow /
~ 50% Core Flow 35 4, 1 95 35 4 I 89 so 1 89 10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-4C Cycle 25 Power-Dependent MCPR L1m1ts with PR 00S or PR & EOC RPTOOS BOC to MOC, SLO 21 6, 2 10 21 8 I 99
< 50% Core Flow /
10 20
~ 50% Core Flow 35 4 I 95 50, I 95 30 40 50 60 70 80 Core Power (3/4 Rated)
Figure 2-40 90 Cycle 25 Power-Dependent MCPR Limits wtth PR 00S or PR & EOC RPT 005 MOC to EOC, SLO 100, 1 40 100 100, 1 44 100 LBDCR 2024-0008
22 2 1 20 1 9 1 8 a: 1 7 cc 1 6
- a.
u
- E 1 5 1 4 1 3 1 2 1 1 1 0 22 2 1 20 1 9 1 8 a: 1 7 cc 1 6
- a.
u
- E 1 5 1 4 1 3 1 2 1 1 1 0 CORE OPERATING LIMITS REPORT 21 8 2 03 21 8 1 98
< 50% Core Flow /
~ 50% Core Flow 70,186 35 4 1 87 50 1 87 100 1 38 0
10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-5A Cycle 25 Power-Dependent MCPR Limits with PR & FWH OOS or PR & FWH & EOC-RPT OOS BOC to MOC, TLO
~ 50% Core Flow 21 8 2 08 70, I 97 218 198
/
35 4, 1 98
< 50% Core Flow 50 I 98 100 100 1 46 0
10 20 30 40 50 60 Core Power(% Rated)
Figure 2-58 70 80 90 Cycle 25 Power-Dependent MCPR Limits with PR & FWH OOS or PR & FWH & EOC-RPT OOS MOC to EOC, TLO 100 COLR Page 23 LBDCR 2024-0008
~
c::
- 0.
u
- E
~
ex 0.. u
- i:
22 2 1 20 1 9 1 8 1 7 1 6 1 5 1 4 1 3 1 2 1 1 1 0 0
21 8 210 21 8 2 00 CORE OPERATING LIMITS REPORT
~ 50% Core Flow 70 1 88
< 50'!t. Core Flow /
35 4 1 89 50 1 39 10 20 30 so 60 Core Pow er (% Rated)
Figure 2-5C 70 80 100 I 40 90 100 Cycle 25 Power-Dependent MCPR Limits with PR & FWH OOS or PR & FWH & EOC-RPT OOS BOC to MOC, SLO 22 2 1 20 1 9 1 8 1 7 1 6 1 5 1.4 1 3 1 2 1 1 1 0
~ 50% Core Flow 21 8 2 10 218,200 / 4 35 4 2 00
< 50% Core Flow 50 2 00 70 t 99 100, I 48 0
10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-50 cycle 25 Power-Dependent MCPR Limits with PR & FWH oos or PR & FWH & EOC-RPT oos MOC to EOC, SLO 100 COLR Page 24 LBDCR 2024-0008
CORE OPERATING LIMITS REPORT 2 00 1 95 1 90 1 85 1 80 1 75 1 70 c-1 65 ii" 1 60
- a. u 1 55 1 50 1 45 1 40 1 35 90 1 31 110 1 31 1 30 1 25 812,131 100 1 31 1 20 0
10 20 30
.\\0 50 60 70 80 90 100 110 Core Flow(% R.ited)
Figure 2-6A Cycle 25 Flow-Dependent MCPR Limits. TLO, All Applic.ition Conditions 1 85 1 80 1 75 1 70 C' 1 65 ii" 1 60
- a.
u 1 55
- 1:
1 50 1 45 1 40 1 35 90 1 33 110 1 33 1 30 81 2, 1 33 100 1 33 1 25 1 20 0
10 20 30 40 50 60 70 80 90 100 110 Core Flow (% R.ited)
Figure 2-68 Cycle 25 Flow-Dependent MCPR Limits. SLO, All Applic.ition Conditions COLR Page 25 LBDCR 2024-0008
1.05 1 00 0.95 0 90 ci: u 0.85
<(
- u.
~
C) 0.80
- i:
..J 0 75 0.70 0 65 060 1 05 1 00 0 95 0 90 ci: u 0.85
~
~ 0 80 C)
- i:
..J 0 75 0 70 0 65 060 CORE OPERATING LIMITS REPORT 35 4, 1 000 50 1 000 70 1 000 85 1 000 100 1 000 35 4. 0 896
< so*a Core Flow
~
21 8 0 760 a so,, c,,. Flow 7 35 4 0.730 218 06~5 0
10 20 30 40 50 60 70 80 90 100 Power (% Rated)
Figure 3-1 Cycle 25 Power-Dependent LHGR Factor, EIS, FWH OOS, EOC-RPT OOS, EOC-RPT & FWH OOS Note: These factors to be applied to the exposure.dependent limits as descibed in Section 5.3
< 500,o Core Flow 2180760
- . 50°a Core Flow--
21 8 0 6~5 0
10 20 30 35 4, 0 896
/
35 4. 0 735 35 ~ 0 730 40 50 50 0 849 60 Power (% Rated)
Figure 3-2 85 1 000 100 1 000 70.0 ~
70 80 90 100 110 110 Cycle 25 Power-Dependent LHGR Factor PR OOS, PR & FWH O0S, PR & EOC-RPT OOS, PR & EOC-RPT & FWH 0OS Note: These factors to be applied to the exposure dependent limits as descibed in Section 5.l COLR Page 26 LBDCR 2024-0008
c-1.10 1 05 100 095 0 90 0.85 u 0.80
~ 0 75 0::
~ 070
...1 065 060 055 0 50 045 CORE OPERATING LIMITS REPORT SO 3, 1 000 90, 1 000 11 O 1 000 100 1 000 040 +-~----,,_~--~---~-+-----<>--+-~-+-~--~---~--+-~-+--~-+-~-----<
0 COLR Page 27 10 20 30 40 50 60 70 Core Flow (% Rated)
Figure 3-3 80 Cycle 25 GNF3 Flow-Dependent LHGR F.:ictor 90 100 Note: These factors to be applied to the exposu re-dependent hm1ts as descibed m Section 5.3 110 120 LBDCR 2024-0008
0 110 100 90 80
-10 J
1! 60
~
~
CORE OPERATING LIMITS REPORT CORE FLOW (% rated) 10 20 30 40 50 60 70 80 90 Cycle 25 BSP Region I Implemented BSP Boundary 1-ou, IUV 1:12.8, ~00 Boundaries for NFWT
-r--:. ~
~
i,,,-""'" 1..........-
I MELLLA+ Boundary I
~
~ I
~
~
....I,,,,,,,,.,-~ i..-----
-:JI,.,.,
!5, 80 6....... ~
,.,,- -::...t
~
~
I
~1 J
~I, /
I J MELLLA Boundary I I
I I I"-.
I
,;'_,, Ks 71.3 I
"r-..
,~
~
I 111 ~
1/ I I
I
~
,,,,.,-/
OPRM Armed Region 100 110.
100, 00 05, 1 k)O 0:: 50
~
r---
Saam Region I
.. /
I Q. 40
~
0 30 0
20 10 0 -
0
~ ~" '
~
I
/
~Ii"',
I V
V' Controlled Entry I I
I I
A* ' j --
~
I ----,...-
,_ -- i-
~ -----
/
Ca ~itatlc n Pr1,tecti i>f1 Note:
/
/
SLO is prohibited in M ELLLA+ region
./
V i---i--"'"
/
10 20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (MLB/HR)
Figure 4 Backup Stability Protection Region Boundaries for Normal Feedwater Temperature (NFWT)
0.0 110 10.0 20.0 30.0 100 90 80
-10 J
1!50
~
~
150 0.40
~
030 0
20 10 0
- Cycle 25 BSP Region
- Boundaries for RFWT I MELLLA Boundary I I
I"'-,
.. ~
~~
~ Saam Region L
I
~ ~-.....
~
u1*1
-,,,. V D~ J-,,,,_.
,_ ii-- i-I
/
/
/
'/
~ --
/
CORE OPERATING LIMITS REPORT CORE FLOW(% rated) 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0
(~2.8',100) l Implemented BSP Boundary :
~
___...- V 105~,,10(
r--
~
.... ~
~
-..... ~~ ~
~
~~
..... ~
v--
I A2' t...,.,..-/
~
I I
A.1',,,c.. V I
~ ~
1 I
~
1/ /I I
V J /
OPRM Armed Region h
' I
,/. ~
I V
I Controlled Entry I I
I I
I L..---
I
~
i.------
~i..---
Ce t,itati 1>n Pr 1>tectl ~
0 10 20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (MLB/HR)
Figure 5 Backup Stability Protection Region Boundaries for Reduced Feedwater Temperature (RFWT)