ML22125A057
| ML22125A057 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/05/2022 |
| From: | Hardy J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO2022-00017 | |
| Download: ML22125A057 (32) | |
Text
~ entergy GNRO2022-00017 May 5, 2022 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 24, Revision O Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 In accordance with 10 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. The updated GGNS Cycle 24 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 Jeff Hardy at 802-380-5124.
GNRO2022-00017 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 24 Revision 0
CORE OPERATING LIMITS REPORT REASON FOR REVISION Revision 0:
The Cycle 24 core operating limits are updated to provide cycle-specific MCPR and LHGRFAC multiplier values, independent of fuel type. Figure 1-1 and 1-2 provides the APLHGR limits for the GNF2 and GNF3 fuel types, respectively. Figures 2-1 through 2-5 are updated with new MCPR limits and Figures 3-1 through 3-4 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 Cvcle References 5
4.0 DEFINITIONS 7
5.0 GENERAL REQUIREMENTS 9
5.1 Averaqe Planar Linear Heat Generation Rates 9
5.2 Minimum Critical Power Ratio 9
5.3 Linear Heat Generation Rate 10 5.4 Stability 10 5.5 Applicability 11 5.6 Limitations and Conditions 11 Table 1 OPRM Upscale CDA All1)litude Discriminator 13 Setpoint Table 2 BSP Endpoints for Normal Feedwater Temperature 13 Table 3 BSP Endpoints for Reduced Feedwater 13 Temperature Table 4 ABSP Setpoints for the Scram Region 13 Table 5 Margin to Thermal Overpower and Mechanical 13 Overpower Limits Table 6 Application Conditions 14 Table 7 Rated OLMCPR Summary Table 14 Figure(s) 1 APLHGR Operating Limits 15 Figure(s) 2 MCPR Operating Limits 16 Fi au re Cs) 3 LHGR Qperatina Limits 25 Figure 4 Backup Stability Protection Region Boundaries 27 for Normal Feedwater Temperature Figure 5 Backup Stability Protection Region Boundaries 28 for Reduced Feedwater Temperature Figure 6 MCPRP Limit and K(P) Multiplier for EIS, FWH 29 005, EOC-RPT 005, FHW & EOC-RPT 005 Figure 7 MCPRP Limit and K(P) Multiplier for PR 005, PR 30
& FWH 005, PR & EOC-RPT 005, PR & FHW & EOC-RPT 005 COLR Page 3 LBDCR 2022-024
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 24 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 24 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 E0C-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 24.
Methodology references are documented in Technical Specification 5.6.Sb 3.1 Current Cycle References 3.1.1 ECH-NE-22-00002 Revision 0, Supplemental Reload Licensing Report for Grand Gulf-1 Reload 23 Cycle 24, March 2022.
3.1.2 ECH-NE-10-00021 Revision 5, GNF2 Fuel Design Cycle-Independent Analyses for Entergy Grand Gulf Nuclear Station, February 2020.
3.1.3 ECH-NE-22-00001 Revision 0, Fuel Bundle Information Report for Grand Gulf-1 Reload 23 Cycle 24, November 2019.
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 0, Grand Gulf Nuclear Station MELLLA+ Task T0407, ECCS-LOCA Performance, September 2012.
3.1.6 GGNS-SA-09-00002 Revision 1, Grand Gulf Nuclear Station GNF2 ECCS-LOCA Evaluation, December 2009.
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 ECH-NE-22-00010, Revision 0, GGNS Cycle 24 GESTAR Assessment, March 2022.
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 Electric Standard Application for Reactor Fuel (GESTAR-II). November 2020, (KGO-ENO-GEN-21-039).
3.1.14 ECH-NE-21-00025, Grand Gulf Nuclear Station TRACG Implementation for Reload Transient Analysis (T1309), December 2020.
3.1.15 NED0-33612-A, Revision 0, Safety Analysis Report for GGNS Maximum Extended Load Line Limit Analysis Plus, September 2013.
CORE OPERATING LIMITS REPORT 3.1.16 NEDC-33292P, Revision 3, GEXL17 Correlation for GNF2 Fuel, June 2009 (RA-ENO-GEN-10-034).
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.
3.1.20 NEDC-33270P, Revision 9, GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), Dec 2017. (KGO-ENO-JBl-18-068).
3.1.21 NEDC-33879P, Revision 4, GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II). August 2020.
3.1.22 GGNS-SA-21-00002, Revision O (GEH 0000-0158-7807-Rl), Grand Gulf Nuclear Station PRNM System DSS-CD Settings, April 2020 3.1.23 SC 21-04 Revision 1, Fuel Support Side Entry Orifice Meta-Stable Flow for 2 Beam Locations in the BWR/6 Reactors, June 2021.
3.1.24 GNF006N2281 Revision 0, Nuclear Design Report for Grand Gulf Nuclear Station Cycle 24, August 2021.
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 mini mum 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 24 MOC Core Average Exposure (CAE) is MOC= EOR-3,996 MWd/ST [3.1.1].
4.15 End of Cycle (EOC) - The Cycle 24 EOC CAE is 32,487 MWd/ST [3.1.24].
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 (M.x) - 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 2022-024
CORE OPERATING LIMITS REPORT unresponsive OPRM 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 MCPRlliil 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 Figures 1-1 and 1-2 [3.1.1].
5.2 Minimum Critical Power Ratio For Cycle 24, the cycle-specific MCPR Safety Limit (MCPR,u,), is 1.12 for Two Loop Operation (TLO), and 1.12 for Single Loop Operation (SLO) [3.1.1].
GEH Safety Communication 21-04 [3.1.23] 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 MCPR limits in the COLR Figures apply the penalty recommended by SC 21-04 Rev.
1 [3.1. 23].
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, 3.1.2, 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 ti me C r,w£) satisfies the following:
r _.11*£ ~rs' 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 r.-1 1*£ > r8 and r ~ 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 rA VE > f 8 and r > 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:
r_.JI"£ = average scram time to the 20% insertion position as calculated by equation 1 of Reference 3.1.19, COLR Page 9 LBDCR 2022-024
CORE OPERATING LIMITS REPORT
' n = adjusted analysis mean scram time for 20% insertion as calculated by equation 3 of Reference 3.1.19 and where
'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. These can be used with the Kp factors in Figures 6 and 7 to determine the appropriate power-dependent OLMCPR at a certain power level. The SC 21-04 Rev. 1 Attachment 5 [3.1.23] penalties must be applied after determining a power-dependent OLMCPR. The MCPR graphs in Figures 2-1 through 2-5 already incorporate the Kp factors and the SC 21-04 Rev. 1 [3.1.23] penalties.
When using Table 7 and Figures 6 & 7 to calculate power-dependent OLMCPR's, an intermediate OLMCPR should be calculated using the appropriate rated OLMCPR and Kp factors (see Figures 6 & 7). This intermediate value should be rounded to two decimals, then the SC 21-04 Rev. 1 [3.1.23] Attachment 5 penalties should be applied, and the final value rounded again to two decimals. For assistance in using Table 7 and Figures 6 & 7 to determine an OLMCPR value, contact Reactor Engineering or the BWR Core Design department.
When calculating SLO MCPR's, 0.03 should be added to Table 7 values before applying Kp factors. If the value after adding 0.03 is less than 1.29, it should be increased to 1.29 before applying Kp factors.
Note that all MCPR Figures (2-1 through 2-5) already apply the Kp factors and the SC 21-04 Rev. 1 penalties.
5.3 Linear Heat Generation Rate Consistent with Technical Specification 3.2.3, the LHGRs for any GNF2 or 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 [3.1.20] for GNF2 and
[3.1.21] for GNF3) 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 and 3-4, 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 COLR Page 10 LBDCR 2022-024
CORE OPERATING LIMITS REPORT 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].
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 reduced by a 0.83 SLO multiplier for GNF2 fuel bundles, and reduced by a 0.90 SLO multiplier for GNF3 fuel bundles.
[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. During SLO operation the SLO values will be used from Figures 3-3 and 3-4 [3.1.1].
- 3. The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2. Due to the application of SC 21-04 Rev. 1 penalties to the MCPR limits, a flat adder is not appropriate for SLO limits. SLO MCPR operating limits are displayed in Figures 2-1 through 2-4 "C" & "D" and Figure 2-5B [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 3-4. 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.
CORE OPERATING LIMITS REPORT 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 Reqion Boundary, HFCL Bl 34.2 25.2 Scram Region Boundary, NCL A2 67.3 50.0 Controlled Entry Region Boundary HFCL B2 26.4 24.4 Controlled Entry Reqion Boundarv, NCL Table 3 BSP Endpoints for Reduced Feedwater Temperature Endpoint Power(%)
Flow(%)
Definition Al' 67.5 50.2 Scram Reqion Boundary, HFCL Bl' 28.2 24.5 Scram Region Boundary, NCL A2' 69.7 52.9 Controlled Entry Region Boundary, HFCL B2' 26.4 24.4 Controlled Entry Reqion Boundarv, 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.
PBsP-TRIP 31.0% RTP1 Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint.
ABSP APRM flow-biased trip setpoint drive flow WBSP-TRIP 39.0% RDF2 intercept. Constant Flow Line for Trip.
Flow Breakpoint value WBSP-BREAK
- 7. 5% RDF2
- 1. RTP - Rated Thermal Power
- 2. RDF - Rec1rculat1on Drive Flow Table 5 Margin to Thermal Overpower and Mechanical Overpower Limits Criteria GNF3 Thermal Overpower Margin 30.21%
Mechanical Overpower Margin
- 49. 54%
COLR Page 14 CORE OPERATING LIMITS REPORT Table 6 Application Conditions Application FWH 00S EOC-RPT PR 00S TBV OOS 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 Sunvnary Table Application GNF3 OPT A GNF3 OPT A GNF3 OPT B GNF3 OPT B Condition BOC-MOC MOC-EOC BOC-MOC MOC-EOC 1
- 1. 33 1.36
- 1. 25 1.28 2
- 1. 33 1.36
- 1. 25 1.28 3
- 1. 33 1.37
- 1. 25 1.29 4
- 1. 33 1.37
- 1. 25 1.29 5
- 1. 35
- 1. 37
- 1. 35
- 1. 37 6
- 1. 35 1.41
- 1. 35 1.41 7
- 1. 35
- 1. 37
- 1. 35
- 1. 37 8
- 1. 35 1.41
- 1. 35 1.41 LBDCR 2022-024
15 14 000, 1378 13 12 e 11
~
~ 10 a:: i 9
..J
- a. i 8
7 6
5 CORE OPERATING LIMITS REPORT 17 52, 13 78 4+-~~~-~~~~-~~~~+-~~~-~~~~-~~~~+-~~~'--i 0
10 15 0 00. 14 36 14 13 12 e 11
~ 10 a::
C) 9
- c
..J
- a. i 8
7 6
5 4
0 10 COLR Page 15 20 30 40 Average Planar Exposure (GWd/Sl)
Figure 1-1 50 GNF2 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections 5.1 and 5.5 20 30 40 Average Planar Exposure (GWd/Sl)
Figure 1-2 50 GNF3 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections 5.1 and 5.5 60 70 60 70 LBDCR 2022-024
22 2.1 20 1.9 1.8 a: 1.7 ci" 1.6 C.
~ 1 5 1.4 1 3 1.2 1.1 1.0 0
2.2 2 1 20 1 9 1 8 a: 1.7 ci" 1.6 C.
ti 1.5 1.4 1.3 1 2 1.1 1 0 0
COLR Page 16 CORE OPERATING LIMITS REPORT 21 8. 2.12 218, 200
< 50% Co,o Flow /
35 4, 1 72 35 4. 1 64 354, 1 62 35.4. 2.00 Option A 40, 172 70, 1 52 so. 156 40, 1 62 SO, 1 S4
/
70 1 44
/
70, 1 41 70 1 42 70, 1 39 Option B
- 85. 1 41 85, 139 10 20 30 40 50 60 70 80 Core Power (% Rated)
Figure 2-1A cycle 24 Power-Dependent MCPR Limits, EIS or FWH OOS BOC to MOC, 11.0
?. 50% Core Flow 21 8, 2 12
~~200 ---~- 35~200
< 50% Core Flow ~
-4. 1 77 354, 169 354166 10 20 30
- 40. 169
/
- 70. 1 43
/
~0, 144 Option B 50 60 Core Power(% Rated)
Figure 2-18 Option A 70, 1.55 70 146 70 I 42 70 cycle 24 Power-Dependent MCPR Limits, EIS or FWH oos MOC to EOC, 11.0
- 85. 144 85, 1 42 80 90 90 Tau= 0.2 100, 1.40 100, 1 33 100, 1 31 100 Tau= 0.2 100, 1 43 100. 1 36 100, 1 34 100 LBDCR 2022-024
22 2.1 2.0 1.9 1.8 CL 1.7 ii"" 1.6
- 0.
~ 1.5 1.4 1 3 1 2 1.1 1.0 0
22 21 2.0 1 9 1.8 CL 1 7 ii"" 1.6
- 0.
!i 1.5 1.4 1 3 1 2 1 1 1 0 0
COLR Page 17 CORE OPERATING LIMITS REPORT 218. 215 21 8. 2 03
- '° CO<* Flow l.
w 35 4 1 69 354, 167
~ 50% Core Flow 354, 203 40, 177
- 70. 1 4S 70. 1 47 70, 1 43 85, 1 45 115. 1 43 Option B 10 20 30 40 50 60 70 80 Core Power (% Rated)
Figure 2-1C Cycle 24 Power-Dependent MCPR Limits, EIS or FWH OOS BOC to MOC, SLO 218, 215 21 8, 203
....;;::,,_ 35 4, 2.03
< '°" COM F*w i.. '
80 35 4, 1 72 10 35 4 1 69 20 30 40, 180 70, 1 S9 40, 1 69 SO, 1 64
- 50. 1 6;
- I 70 1 52 I
- 70. 1 47 70. 1 50 Option B 70, 1 45 40 50 60 Core Power(% Rated)
Figure 2-10 70 Cycle 24 Power-Dependent MCPR Limits, EIS or FWH OOS MOC to EOC, SLO as. 1 47 as. 1 45 80 Tau* 0.2 90 90 100. 1 43 100. 1 37 100. 1 35 100 Tau* 0.2 100, 1.46 100, 1 40 100, 133 100 LBDCR 2022-024
22 2 1 2.0 1.9 1.8 C: 1.7 ii"'
0..
1.6 u
- E 1.5 1.4 1 3 1 2 11 1 0 0
22 2.1 2.0 1 9 1 8 C: 1.7 ii"' 1.6 0..
~ 1.5 1.4 1.3 1.2 1.1 1 0 0
CORE OPERATING LIMITS REPORT 218. 212
~ 50% Core Flow 218, 200 354, 200
<SO%c,,.,.. /
40, 1 72 35 4, 1 72 35 4, 1 64 35 4, 1 62 70, 1 44
- 85. 1 41 70 1 41 85, 139 Opt.ion B 70, 1 42 70 1 39 10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-2A Cycle 24 Power-Dependent MCPR Limits with EOC-RPT 00S, or EOC-RPT & FWH 00S BOC to MOC, TLO 21.8. 2 12 21 8, 2.00
....,. 354, 200 40, 1 78
< 50% Core Flow 35 4, 1 78 35 4 1 70 70, 156 35 4, 1 67 Tau= 0.2 100, 1.40 100 1 33 100, 1 31 100 Tau,. 0.2
- o. 1 &7 70 !1~*9======85=:=_=1=-.5:=:::::::::::::1.=-
70_ 1 47 70 1 43 10* 1 45 85, 1 *3 100, 1.44 100, 1 37 100, 1 35 10 20 30 Option B 40 50 60 Core Power (% Rated )
Figure 2-2B 70 80 90 Cycle 24 Power-Dependent MCPR Limits with EOC-RPT 00S, or EOC-RPT & FWH 00S MOC to EOC, TLO 100 COLR Page 18 LBDCR 2022-024
22 2.1 2.0 1.9 1 8 a: 1.7
~ 1 6 Q.
~ 1 5 1.4 1.3 1.2 1.1 1 0 0
22 21 2.0 1 9 1 8 ci: 17
~ 1 6 Q.
~ 1 5 1.4 1 3 1.2 11 1.0 0
CORE OPERATING LIMITS REPORT 21 8, 2.15
! 50% Core Flow 218,203 35A, 2.03 I
< 50% Core Flow 35 4. 1 77
- 40. 1 77 35 4. 1 69 35 4, 1 67 85, 1 52 70, 1 49 85, 145
- 70. 1 45 85, 1 43 Option B
- 70. 1 47 70 1 43 10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2*2C cycle 24 Power-Dependent MCPR Limits With EOC-RPT 00S, or EOC-RPT & FWH 00S BOC to MOC, SLO 21.8, 2 15
"'*"' I.
< 50% Core Flow 35 4* 1 82 35 4, 1 74 35 4, t 71 10 20 30 354, 203 40, 1 71
~... I 50, t 63 Option B 40 50 60 Core Power (% Rated)
Figure 2-20 85, 1 56 70, 1 53 85, t 49 70, t 49
- 85. 1 47
- 70. 1 51 70, 1 47 70 80 90 cycle 24 Power-Dependent MCPR Limits With EOC-RPT 00S, or EOC-RPT & FWH 00S MOC to EOC, SLO C0LR Page 19 Tau* 0.2 100, 1.43 100, 1 37 100, t 35 100 Tau
- 0.2 100, 1.47 100. 1 41 100, 139 100 LBDCR 2022-024
22 2 1 2.0 1 9 1.8 ci: 1 7 i%" 1.6 Q.
~ 1.5 1.4 1 3 1 2 1 1 1 0 0
22 2 1 20 1.9 1 8 a: 1 7 i%" 1 6 Q.
u
- Ii:
1 5 1 4 1 3 1 2 1 1 1 0 0
COLR Page 20 CORE OPERATING LIMITS REPORT
! 50% Core Flow 21 8, 2 12 218, 200 ---.....a:.. 354, 200
< 50% Co,o Flow /
35 4, U9 so. 1 89 10 20 30 40 50 60 70 80 90 Core Power ("lo Rated)
Figure 2-3A cycle 24 Power-Dependent MCPR LimitS With PR 00S or PR & EOC RPT 00S BOC to MOC, TLO 21 8 2 12 21 8. 2 00
< 50% Core Flow/
10 20 30
! 50% Core Flow 35 4, 1 92 50, 1 92 40 50 60 Core Power (1/o Rated)
Figure 2-3B 70 80 90 Cycle 24 Power-Dependent MCPR LlmitS with PR 00S or PR & EOC RPT 00S MOC to EOC, TLO 100, 1 42 100 100, I 44 100 LBDCR 2022-024
2.2 2.1 20 1 9 1 8 ci: 1 7
~ 1.6 Q,. u
- E 1 5 1 4 1 3 1 2 1 1 1 0 0
22 2 1 20 1 9 1 8 C: 1 7
~ 1 6 Q,.
~ 1 5 1 4 1 3 1 2 t1 1 0 0
COLR Page 21 CORE OPERATING LIMITS REPORT 218,215
- 50% Core Flow 21 8, 2 03 ___
...,;:,.. 35.4 2 03
- 50% c,..,,_ I 35 4, 1 93 50, 193 10 20 30 40 50 60 70 80 90 Core Power (% Rated)
Figure 2-3C Cycle 24 Power-Dependent MCPR Limits with PR 00S or PR & EOC RPT 00S BOC to MOC, SLO 218, 215 218, 203
< 50% Core Flow/
10 20
- 50% Core Flow 35 4, 1 96 50, 1 96 30 40 50 60 Core Power (% Rated)
Figure 2-3D 70 80 90 Cycle 24 Power-Dependent MCPR Limits with PR 00S or PR & EOC RPT 00S MOC to EOC, SLO 100, 1 45 100 100, 1 47 100 LBDCR 2022-024
ii ii" a.. u
~
ii ii" a.. 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 22 2 1 20 1 9 1 8 1 7 1 6 1 5 1.4 1 3 1 2 1 1 0
21.8. 2 12 218, 200
< 50% Core Flow 10 20 CORE OPERATING LIMITS REPORT
~ 50% Core Flow 35 4, 1 89 SO, 1 89 30 40 50 60 Core Power (% Rated)
Figure 2-4A 70, 189 70 80 100, 1 42 90 100 Cycle 24 Power-Dependent MCPR Limits with PR & FWH 00S or PR & FWH & EOC-RPT 00S BOC to MOC, TLO
~ 50% Core Flow 21 8. 2 12 70, 1 97 21 8. 2 00 SO, 1 97
< 50% Core Flow 100, 1 48 1 0 0
10 20 30 40 50 60 Core Power (% Rated)
Figure 2-48 70 80 90 Cycle 24 Power-Dependent MCPR Limits with PR & FWH 00S or PR & FWH & EOC-RPT 00S MOC to EOC, TLO 100 COLR Page 22 LBDCR 2022-024
ci: er Q. u
- I:
ci: er Q.
~
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, 2 15 21 8 2 03
< 50% Core Flow 10 20 CORE OPERATING LIMITS REPORT 30
~ 50% Core Flow so, 1 93 40 50 60 Core Power ("4 Rated)
Figure 2-4C 70, 1 93 70 100, 1 45 80 90 100 Cycle 24 Power-Dependent MCPR Limits with PR & FWH 00S or PR & FWH & EOC-RPT 00S BOC to MOC, SLO 22
~ 50% Core Flow 218, 215 2.1
- 70. 2 02 20 218, 203 354, 202 50, 202 1 9 1 8
< 50% Core Flow 1 7 1 6 1 5 100, 1 52 1 4 1 3 1 2 1 1 1 0 0
10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-40 Cycle 24 Power-Dependent MCPR Limits with PR & FWH 00S or PR & FWH & EOC*RPT 00S MOC to EOC, SLO COLR Page 23 LBDCR 2022-024
CORE OPERATING LIMITS REPORT 1 90 1 85 1 80 1 75 1 70 1 65 1 60 1 55
~ 1.50
- a. u 1 45
- E 1 40
- 90. 1 38 11 o. 1 38 1 35 81 5. 1.38 100, 1 38 1 30 1 25 1 20 1 15 1 10 0
10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
Figure 2-5A Cycle 24 Flow-Dependent MCPR Limits, TLO, All Application Conditions 1 90 1 85 1 80 1 75 1 70 1 65 1 60 1 55
~ 1 50
- a. u 1 45
- E
- 90. 1 41 110. 1 41 1.40 1 35 81 5, 1 41 100, 1 41 1 30 1 25 1 20 1 15 1 10 0
10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
Figure 2-58 Cycle 24 Flow-Dependent MCPR Limits, SLO, All Application Conditions C0LR Page 24 LBDCR 2022-024
CORE OPERATING LIMITS REPORT 1 05 35 4, 1 000 50, 1 000 70, 1 000
- 85. 1 000 100, 1 000 1 00 095 0 90 35 4, 0 896 ci:
< 50% Core Flow '-.
u 085 Lf
~ 0 80 t!I
- x:
...J 218, 0 760 0 75 35 4 0 730 0 70
- ".. 50% Core Flow -
065 21 8 0 645 060 0
10 20 30 40 50 60 70 80 90 100 110 Power(% Rated)
Figure 3-1 Cycle 24 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 1 05 85 1 000 100 1 000 1.00 0.95 0.90
< 50% Core Flow ci: u 0.85 50 0 849 Lf
~ 0.80 t!I
- x:
...J 21 8, 0 760 0.75 0.70
- ".. 50% Core Flow 0.65 21 8, 0 645 0.60 0
10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Figure 3-2 Cycle 24 Power-Dependent LHGR Factor PR OOS, PR & FWH OOS, PR & EOC-RPT OOS, PR & EOC-RPT & FWH OOS Note: These factors to be applied to the exposure.dependent limits as desclbed In Section 5.3 C0LR Page 25 LBDCR 2022-024
£ 1.05 1.00 0.95 0.90
~ 0.85
~
CJ 0.80 3
0.75 0.70 0.65 CORE OPERATING LIMITS REPORT 80 3, 1 000 90, 1 000 110, 1 000 TLO -----:.:
998 100, 1 000 110,0830
~
I SLO 0.60 +-~--i.---'--+-~~-~--....... --+-~-~-+-~--i--'--+-.__-+-__,_ __ __.__
r;::::-
1.05 1.00 095 0.90 0 085 CJ 0.80 3
0.75 070 0.65 0
10 20 30 40 50 60 70 Core Flow (% Rated)
Figure 3-3 80 Cycle 24 GNF2 Flow-Dependent LHGR Factor 90 100 110 Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 80 3, 1 000 90, 1 000 110, 1 000 TLO 100, 1 000 110, 0 900
~
SLO 120 0.60 +-...... __
...... -+--'---+-~--...... --__._--+--'--+--'---+-~--~-----'---<
0 C0LR Page 26 10 20 30 40 50 60 70 Core Flow(% Rated)
Figure 3-4 80 Cycle GNF3 24 Flow-Dependent LHGR Factor 90 100 Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 110 120 LBDCR 2022-024
0 110 100 90 80
-10 1
1! 60
~
~
CORE OPERATING LIMITS REPORT CORE FLOW (% rated) 10 20 30 40 50 60 70 80 90 Cycle 24 BSP Region I Implemented BSP Boundary 1-nu, IUU
~2.8, noo Boundaries for NFWT
-r---::a ~
~
j,,,I"""" i...,...----
I MELLLA+ Boundary I
./
I
~
~
...... ~~ ~
- II,,.,,
~5. 80. ~........ ~
~
~,,-~.,,,-
I
~1 j
-~ /
I MELLLA Boundary I
['-..
I
,,,.,.,. ~
5 7U
' I'.
.1~ ~
I
...... ~
V
/
I I
~
,,,, /
OPRM Armed Region 100 110 100, 00 05, 1 k>O a: 50
~
Saam Region L.-- -...
. /
0.. 40
~
0 30 0
20 10 0
~ --
0 10 I --- ~
V I "
R J.- ~
/
L V
/
20 30 I"
,. ~ '
/
,.I'""""-.
I V
Controlled Entry I I
V I
I
-~
I"""
I -~
J--
i-
/
Ca fitatic n Pr,,tecti,,n Note:
SLO is prohibited in M ELLLA+ region 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
~ Cycle 24 BSP Region 100 90 80
-10 1
l!50
- I?
~ I 50 0.40 w
a:
030 0
20 10 0
.... Boundaries for RFWT I MELLLA Boundary I I
~~
~
~ Saam Region I,
r--
I
~ r-.....
~
m*
__,, ~
1:1~ J;;.,_.
I/
/
/
_,,,~
V
~
/
CORE OPERATING LIMITS REPORT CORE FLOW (% rated) 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0
(~2.s,i,100]
I Implemented BSP Boundary I
~ ~
L---"'
105,,1ot I
I --
~
~_,,,,,.. f-"'""
...... ~ v---
~
..... i..,:. v-I A2' [/
II"'""_......... I'"
I I
"1' r'Z v-I
~
.....-1 ~/
I
~
1/ /j' I
V
- " /
OPRM Anned Region h,.,
I I
~.,, I"'
I
~ Controlled Entry I I
~
I I
lo""~
I ----c
__I~
Ca r.,ltaU mPr 1>tecU t>n 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)
II
- 0.
2100 CORE OPERATING LIMITS REPORT Operating Limit MCPR (P) = K(P)
- Operating Limit MCPR(100)
.o 2 000 0..
V 0..
~
For P<21.8%* No Thermal limits Monitoring Required, No limits specified.
For 21.8%SPSP(Bypass), P(Bypass)=35.4%
OLMCPR(P)=1.88.
Flow<50%
OLMCPR(P)=1.88 +0 00809*(35 4%-P). Flow~50%
J!
1 500 i:'
~
I..
Q...
- i a:
0..
u
~
"U
! II a:
1 400 1300 1200 1100 1000 I
20 COLR Page 29 30 40 50 60 For P>P(Bypass)
K(P)=1.225, 35 4% < P s 40%
K(P)=1.166+0.00590"(50%-P), 40% < P s 50%
K(P)=1.083+0 00415.(70%-P), 50% < P s 70%
K(P)=1.057, 70% < P s 85%
K(P)=1 000+0.00380"(100%-P). 85% < P S:100%
70 80 90 100 Power (% rated)
Fieure 6 110 MCPRp Limit and K(P) Multiplier for EIS, FWH OOS, EOC-RPT OOS, FWH & EOC-RPT 00S LBDCR 2022-024
2 1 I
I 2
1 9 ~
18 1 7 16 15 1 4 1 3 1 2 1 l 1
20 I
30 CORE OPERATING LIMITS REPORT 40 so 60 Operating Limit MCPR (P) = K(P)
- Operating Limit MCPR(100)
For P<21 8%: No Thermal Limits Monitoring Required, No limits specified For 21 8%SPSP(Bypass). P(Bypass)=35 4%
OLMCPR(P)=1.88, Flow<50%
OLMCPR(P)=1.88 +0 00809.(35 4%-P). Flow.e50%
For P>P(Bypass)
K(P)=1.319, 35.4% < P s 70%
K(P)=1.160+0 01060'(85%-P). 70% < P s 85%
K(P)=1.000+0.00693'(100%-P). 85% < P S100%
70 90 100 Power (% rated)
Fieure 7 110 MCPRp limit and K(P) Multiplier for PR OOS, PR & FWH OOS, PR & EOC-RPT OOS, PR & FWH