ML21245A102

Core Operating Limits Report (COLR) Cycle 23 Revision 2

ML21245A102
Person / Time
Site:	Grand Gulf
Issue date:	09/02/2021
From:	Franssen R Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO2021/00026
Download: ML21245A102 (36)

Text

GGNS TS 5.6.5 GNRO2021/00026 September 2, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Core Operating Limits Report (COLR) Cycle 23 Revision 2 for Grand Gulf Nuclear Station, Unit 1 (GGNS)

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 Renewed License No. NPF-29

REFERENCES:

1.

Entergy Letter GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) 2.

Entergy Letter GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)

On May 5, 2020, in accordance with 10 CFR 50.36 GGNS submitted the Cycle 23 COLR (reference one above). The purpose of this letter is to submit Revision 2 of the Cycle 23 COLR to the Nuclear Regulatory Commission (NRC) in accordance with the GGNS Technical Specifications Section 5.6.5.d. The revised GGNS Cycle 23 COLR is attached to this letter.

This letter contains no new regulatory commitments. Should you have any questions concerning the content of this letter, please contact Jeffery Hardy, Manager Regulatory Assurance at 601-437-2103.

Entergy Operations, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150 Robert Franssen Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500

GNRO2021/00026 Page 2 of 2 Sincerely, Robert Franssen RF/saw

Attachment:

Core Operating Limits Report (COLR) Cycle 23 Revision 2 for Grand Gulf Nuclear Station, Unit 1 cc:

NRC Region IV - Document Control Desk NRC Senior Resident Inspector, Grand Gulf Nuclear Station NRR Project Manager

GNRO-2021/00026 Attachment Core Operating Limits Report (COLR) Cycle 23 Revision 2 for Grand Gulf Nuclear Station, Unit 1 (GGNS)

COLR Page 1 LBDCR 2021-050 Grand Gulf Nuclear Station Core Operating Limits Report Cycle 23 Revision 2

CORE OPERATING LIMITS REPORT COLR Page 2 LBDCR 2021-050 REASON FOR REVISION Revision 2:

The Cycle 23 core operating limits are revised to update the power and flow dependent MCPR limits in Figures 2 (2-1A through 2-9B) due to updated OLMCPR limits received from GNF for Cycle 23 [3.1.22]. These new limits account for the reduced margin specified in SC 21-04 Rev. 1 [3.1.23], due to a possible metastable flow condition resulting in a higher loss coefficient. All OLMCPR limits have been increased to ensure MCPR limits are not exceeded in the presence of a higher loss coefficient.

Revision 1:

The Cycle 23 core operating limits are revised to replace the BSP region boundaries for RFWT (Figure 5) with a corrected figure for Cycle 23. Cycle 23 COLR Revision 0 Figure 5 was still showing Cycle 22s BSP region boundaries for RFWT. Figure 4 was updated to remove A3 and B3 labels which are not provided in Table 2.

Revision 0:

The Cycle 23 core operating limits are updated to provide cycle-specific MCPR and LHGRFAC multiplier values for the GNF2 and GNF3 fuel type. Figure 1-1 and 1-2 provides the APLHGR limits for the GNF2 and GNF3 fuel types, respectively.

Figures 2-1 through 2-9 are updated with new MCPR limits and Figures 3-1 through 3-7 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 COLR Page 3 LBDCR 2021-050 TABLE OF CONTENTS 1.0 PURPOSE 4

2.0 SCOPE 4

3.0 REFERENCES

5-6 3.1 Current Cycle References 5-6 4.0 DEFINITIONS 7-8 5.0 GENERAL REQUIREMENTS 9-11 5.1 Average 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 10 5.6 Limitations and Conditions 11 Table 1 OPRM Upscale CDA Amplitude Discriminator Setpoint 12 Table 2 BSP Endpoints for Normal Feedwater Temperature 12 Table 3 BSP Endpoints for Reduced Feedwater Temperature 12 Table 4 ABSP Setpoints for the Scram Region 12 Table 5 Margin to Thermal Overpower and Mechanical Overpower Limits 12 Table 6 Application Conditions 13 Figure(s) 1 APLHGR Operating Limits 14 Figure(s) 2 MCPR Operating Limits 15-23 Figure(s) 3 LHGR Operating Limits 24-30 Figure 4 Backup Stability Protection Region Boundaries for Normal Feedwater Temperature 31 Figure 5 Backup Stability Protection Region Boundaries for Reduced Feedwater Temperature 32

CORE OPERATING LIMITS REPORT COLR Page 4 LBDCR 2021-050 1.0 PURPOSE The COLR 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 COLR must be submitted to the NRC for information as required by Tech Spec 5.6.5 and tracked by Licensing Commitment 29132. This COLR reports the Cycle 23 core operating limits and stability setpoint confirmation and regions.

2.0 SCOPE As defined in Technical Specification 1.1, the COLR 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 23 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 COLR Page 5 LBDCR 2021-050

3.0 REFERENCES

This section contains the cycle-specific references used in the safety analysis of Grand Gulf Cycle 23.

Methodology references are documented in Technical Specification 5.6.5b 3.1 Current Cycle References 3.1.1 ECH-NE-20-00009 Revision 0, Supplemental Reload Licensing Report for Grand Gulf-1 Reload 22 Cycle 23, dated February 2020.

3.1.2 ECH-NE-10-00021 Revision 5, GNF2 Fuel Design Cycle-Independent Analyses for Entergy Grand Gulf Nuclear Station, dated February 2020.

3.1.3 ECH-NE-20-00010 Revision 0, Fuel Bundle Information Report for Grand Gulf-1 Reload 22 Cycle 23, dated November 2019.

3.1.4 NEDC-32910P, Revision 1, Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident Analysis With Relaxed ECCS Parameters, dated October 1999.

3.1.5 GGNS-NE-12-00022 Revision 0, Grand Gulf Nuclear Station MELLLA+ Task T0407, ECCS-LOCA Performance, dated September 2012.

3.1.6 GGNS-SA-09-00002 Revision 1, Grand Gulf Nuclear Station GNF2 ECCS-LOCA Evaluation, dated December 2009.

3.1.7 NEDC-33173P-A, Revision5, Applicability of GE Methods to Expanded Operating Domains (with Supplements 5P-A Rev. 1, and 6P-A Rev. 1),

dated October 2019 3.1.8 NEDC-33006P-A, Revision 3, GE BWR Maximum Extended Load Line Limit Analysis Plus, dated June 2009 3.1.9 ECH-NE-20-00012, Revision 1, GGNS Cycle 23 GESTAR Assessment, dated March 2020.

3.1.10 ECH-NE-20-00006 Revision 0, GNF3 Fuel Design Cycle-Independent Analyses for Grand Gulf Nuclear Station, dated February 2020.

3.1.11 GGNS-SA-19-00002 Revision 0 Grand Gulf Nuclear Station GNF3 ECCS-LOCA Evaluation Revision 1, dated October 2019 3.1.12 GEH-GGNS-AEP-632, GGNS MELLLA+ Final DSS-CD Settings Report, dated October 23, 2013.

3.1.13 NEDE-24011-P-A-29, General Electric Standard Application for Reactor Fuel (GESTAR-II), dated October 2019, (KGO-ENO-GEN-19-087).

3.1.14 Not Used.

3.1.15 NEDO-33612-A, Revision 0, Safety Analysis Report for GGNS Maximum Extended Load Line Limit Analysis Plus, September 2013.

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).

CORE OPERATING LIMITS REPORT COLR Page 6 LBDCR 2021-050 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 0 (GEH 0000-012101122-R0), GGNS EPU OptionB Scram Times, dated September 2010.

3.1.20 NEDC-33270P, Revision 9, GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), Dec 2017. (KGO-ENO-JB1-18-068).

3.1.21 NEDC-33879P, Revision 2, GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II), March 2018. (CIN2018-00052).

3.1.22 ECH-NE-20-00003 Revision 1, GGNS C23 OPL-7 Data for 3DM Databank, dated July 2021.

3.1.23 SC 21-04 R1 Fuel Support Side Entry Orifice Meta-Stable Flow for 2 Beam Locations in the BWR/6 Reactors June 17, 2021.

CORE OPERATING LIMITS REPORT COLR Page 7 LBDCR 2021-050 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 vendors 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 MCPR99.9%, 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) 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.

4.10 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.

4.11 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.

4.12 End of Rated (EOR) - The Cycle exposure corresponding to all rods out, 100%

power, 100% flow, and normal feedwater temperature [3.1.1].

4.13 Middle of Cycle (MOC) - The Cycle 23 MOC Core Average Exposure (CAE) is MOC

= EOR-2,862 MWd/ST [3.1.1].

4.14 End of Cycle (EOC) - The Cycle 23 EOC CAE is 30,594 MWd/ST [3.1.1].

4.15 Maximum Extended Load Line Limit Analysis Plus (MELLLA+) - The GGNS MELLLA+

operating domain is depicted in Figure 4.

4.16 Maximum Number of OPRM Cells Along an Instability Symmetry Axis (MAX) - An OPRM configuration constant representing maximum number of OPRM cells along an instability symmetry axis. It is used to calculate the number of unresponsive OPRM cells. Per [3.1.12] the GGNS specific value is five (MAX = 5).

CORE OPERATING LIMITS REPORT COLR Page 8 LBDCR 2021-050 4.17 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.

4.18 MCPR95/95 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 COLR Page 9 LBDCR 2021-050 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 23, the cycle-specific MCPR Safety Limit (MCPR99.9%), 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 a MCPR penalty is always applied.

Revision 2 to the COLR updates all MCPR limits to 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 time (

AVE

) satisfies the following:

B AVE

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 B

AVE

and 2.

0

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 B

AVE

and 2.

0

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:

AVE

= average scram time to the 20% insertion position as calculated by equation 1 of Reference 3.1.19,

CORE OPERATING LIMITS REPORT COLR Page 10 LBDCR 2021-050 B

= adjusted analysis mean scram time for 20% insertion as calculated by equation 3 of Reference 3.1.19 and B

A B

AVE

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.

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 through 3-6 and 3-7, 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 oF.

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

CORE OPERATING LIMITS REPORT COLR Page 11 LBDCR 2021-050 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 3-7 [3.1.1].

3. The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.00 to account for the difference between the two-loop and single-loop MCPR safety limits for the allowable range of single-loop operation [3.1.1].

5.6 Limitations and Conditions As required by Limitation and Condition 9.10/9.11 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 3-7. 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.

CORE OPERATING LIMITS REPORT COLR Page 12 LBDCR 2021-050 Table 1 OPRM Upscale CDA Amplitude Discriminator Setpoint Amplitude Discriminator Trip 1.10 Table 2 BSP Endpoints for Normal Feedwater Temperature Endpoint Power(%)

Flow(%)

Definition A1 72.3 44.2 Scram Region Boundary, HFCL B1 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 Region Boundary, NCL Table 3 BSP Endpoints for Reduced Feedwater Temperature Endpoint Power(%)

Flow(%)

Definition A1 65.9 48.3 Scram Region Boundary, HFCL B1 28.5 24.6 Scram Region Boundary, NCL A2 68.8 51.8 Controlled Entry Region Boundary, HFCL B2 26.4 24.4 Controlled Entry Region Boundary, NCL Table 4 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM flow-biased trip linear segment mTRIP 0.77 ABSP APRM flow-biased trip setpoint power intercept.

Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint.

PBSP-TRIP 31.0% RTP 1

ABSP APRM flow-biased trip setpoint drive flow intercept. Constant Flow Line for Trip.

WBSP-TRIP 39.0% RDF 2

Flow Breakpoint value WBSP-BREAK 7.5% RDF 2

1. RTP - Rated Thermal Power

2. RDF - Recirculation Drive Flow Table 5 Margin to Thermal Overpower and Mechanical Overpower Limits Criteria GNF3 GNF2 Thermal Overpower Margin 54.74%

51.02%

Mechanical Overpower Margin 55.03%

55.03%

CORE OPERATING LIMITS REPORT COLR Page 13 LBDCR 2021-050 Table 6 Application Conditions Application Condition FWH OOS EOC-RPT PROOS TBVOOS 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

• These are the limiting conditions evaluated in [3.1.1] and the only ones monitored.

CORE OPERATING LIMITS REPORT COLR Page 14 LBDCR 2021-050 15 14 0.00, 13.78 13 12 f

11

, 10 Ct'.

C) 9 I

..J Q.

<(

Ji:

8 7

6 5

4 0

10 15 0.00, 1 4.36 14 13 12

~ 11

~

, 10 Ct'.

C) 9 I

..J Q.

<(

Ji:

8 7

6 5

4 0

10 17.52, 13.78 20 30 40 50 Average Planar Exposure (GWd/STI Figure 1-1 GNF2 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections 5.1 and 5.5 20 30 40 50 Average Planar Exposure (GWd/STI Figure 1-2 GNFJ Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections 5.1 and 5.5 63.50, 6.69 60 70 57.60, 8.00 6.00 60 70

CORE OPERATING LIMITS REPORT COLR Page 15 LBDCR 2021-050 2.5 2.4 2.3 2.2 2.1 2.0 a: 1.9

~

a.

u 1.8

~

1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 a: 1.9

~

a.

u 1.8

~

1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.44 21.8, 2.33

< 50% Core Flow 35.4, 1.75 35.4, 1.72 35.4, 1.71 1.. 50% Core Flow 35.4, 2.27 35.4, 2.13 40, 1.75 40, 1.72 40, 1.71 50, 1.75 SO, 1.69 SO, 1.67 Option A I 70, 1.69 Tau = 0.2 100, 1.54 70, 1.57 85, 1.47 100, 1.43 70, 1.54 Options /

100, 1.40 10 10 20 30 40 50 60 70 21.8, 2.42 21.8, 2.33 Core Power (% Rated)

Figure 2-1A Cycle 23 GNF2 Power-Dependent MCPR Limits, EIS BOC to MOC

~ 50% Core Flow 35.4, 2.13 Option A I

50, 1.69 35.4, 1.71 70, 1.64 40, 1.71 80 90 100 Tau = 0.2

~.,1/

so, 1.67 70, 1.59 70, 1.56

~~~~~~~t~

1~ 1~

100, 1.43 70, 1.54 85, 1.48 100, 1.41 Option B 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-18 Cycle 23 GNF3 Power-Dependent MCPR Limits, EIS BOC to MOC

CORE OPERATING LIMITS REPORT COLR Page 16 LBDCR 2021-050 2.5 2.4 2.3 2.2 2.1 2.0 c:: 1.9

"° c.. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 c:: 1.9

"° c.. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.44 21.8, 2.33

< 50% Core Flow I :".. 50% Core Flow 35.4, 2.27 35.4, 2.13 40, 1.76 so. 1.76 40, 1.71 50, 1.69 so, 1.67 Option A I

85, 1.51 OptionB /

10 20 30 40 50 60 Core Power (% Rated)

Figure 2-2A 70 80 Cycle 23 GNF2 Power-Dependent MCPR Limits with FWH OOS BOC to MOC 21.8, 2.42 21.8, 2.33

".. 50% Core Flow

< 50% Core Flow /

35.4, 2.25 35.4, 2.13 10 35.4, 1.71 20 30 Option A 40, 1.71 50, 1.70 I

50, 1.67 I 70, 1.57 Option B 40 50 60 Core Power (% Rated)

Figure 2-2B 70 85, 1.51 80 Cycle 23 GNF3 Power-Dependent MCPR Limits with FWH OOS BOC to MOC 90 90 Tau= 0.2 100, 1.56 100, 1.45 100, 1.42 100 Tau= 0.2 100, 1.53 100, 1.46 100, 1.44 100

CORE OPERATING LIMITS REPORT COLR Page 17 LBDCR 2021-050 2.5 2.4 2.3 2.2 2.1 2.0 C: 1.9 cf c.. u 1.8

~

1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 C: 1.9 cf c.. u 1.8

~

1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.44 21.8, 2.33

< 50% Core Flow /

'.. 50% Core Flow 35.4, 2.13 85, 1.69 85, 1.57 85, 1.54 OptiooB /

10 20 30 40 50 60 Core Power (% Rated)

Figure 2-3A 70 80 Cycle 23 GNF2 Power-Dependent MCPR Limits with PR+FWH OOS BOC to MOC 21.8, 2.43 21.8, 2.33

< 50% Core Flow/

I :'.. 50% Core Flow 35.4, 2.26 Option A 90 85, 1.80 10 85, 1.65 85, 1.57 ~-*~;

Option B 20 30 40 50 60 Core Power (% Rated)

Figure 2-38 70 80 Cycle 23 GNF3 Power-Dependent MCPR Limits with PR+FWH OOS BOC to MOC 90 Tau = 0.2 100, 1.56 100, 1.45 100, 1.42 100 Tau = 0.2 100, 1.53 100, 1.46 100, 1.44 100

CORE OPERATING LIMITS REPORT COLR Page 18 LBDCR 2021-050 2.5 2.4 2.3 2.2 2.1 2.0 ci: 1.9 ct" Cl. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 ci: 1.9 ct" Cl. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.44 21.8, 2.33

< 50% Core Flow /

I ?::. 50% Core Flow 35.4, 2.27 35.4, 2.13 85, 1.69 85, 1.57 85, 1.54 OptiooB I 10 20 30 40 50 60 Core Power (% Rated)

Figure 2--4A 70 80 Cycle 23 GNF2 Power-Dependent MCPR Limits with PR+EOC-RPT +FWH OOS BOC to MOC 21.8, 2.43 21.8, 2.33

< 50% Core Flow /

I :::. 50% Core Flow 35.4, 2.26 35.4, 2.13

/

OptionA 70, 1.90 85, 1.65 85, 1.57 90 85, 1.55 /

Option B 10 20 30 40 50 60 Core Power (% Rated)

Figure 2--4B 70 80 Cycle 23 GNF3 Power-Dependent MCPR Limits with PR+EOC-RPT+FWH OOS BOC to MOC 90 Tau = 0.2 100, 1.58 100, 1.47 100, 1.44 100 Tau = 0.2 100, 1.56 100, 1.49 100, 1.47 100

CORE OPERATING LIMITS REPORT COLR Page 19 LBDCR 2021-050 2.6 2.5 2.4 2.3 2.2 2.1 0: 2.0

~ 1.9 c..

u

E 1.8 1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 0: 1.9

~

c.. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.51 21.8, 2.42

< 50% Co" Flow /

35.4, 1.82 35.4, 1.74 35.4, 1.71 35.4, 2.31 35.4, 2.18 Option A 40, 1.82 50, 1.82 40, 1.74 40, 1.71 50, 1.67 70, 1.63 85, 1.58 85, 1.1/

Option B 10 20 30 40 50 60 70 21.8, 2.46 21.8, 2.38 Core Power (% Rated)

Figure 2-5A Cycle 23 GNF2 Power-Dependent MCPR Limits, EIS MOC to EOC

< 50% c,,. Flow /

35.4, 2.27 35.4, 2.15 10 35.4, 1.76 35.4, 1.72 35.4, 1.71 20 30 40, 1.76 50, 1.76 40, 1.72 50, 1.69 40, 1.71 50, 1.67 40 50 60 Core Power (% Rated)

Figure 2-5B 70 Cycle 23 GNF3 Power-Dependent MCPR Limits, EIS MOC to EOC 80 90 Option B 80 90 Tau = 0.2 100, 1.55 100, 1.47 100, 1.44 100 Tau = 0.2 100, 1.51 100, 1.45 100, 1.43 100

CORE OPERATING LIMITS REPORT COLR Page 20 LBDCR 2021-050 2.6 2.5 2.4 2.3 2.2 2.1 0: 2.0

~ 1.9 a.. u

~ 1.8 1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 0: 1.9

~

a.. u 1.8

~

1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.51 21.8, 2.42

< 50% Core Flow /

35.4, 1.82 35.4, 1.74 35.4, 1.71 35.4, 2.31 35.4, 2.18 40, 1.82 40 1.74 40, 1.71 Option A 50, 1.82 50, 1.67 70, 1.63 ~-/

Option B 10 20 30 40 50 60 Core Power (% Rated)

Figure 2-6A 70 80 Cycle 23 GNF2 Power-Dependent MCPR Limits with FWH 00S MOC to EOC 21.8, 2.46 21.8, 2.38

/

. 50% Core Flow

< 50% Co,e Flow /

35.4, 2.27 35.4, 2.15 35.4, 1.76 40, 1.76 50, 1.76 35.4, 1.72 35.4, 1.71 40, 1.72 50, 1.69 40, 1.71 50, 1.67 70, 1.62 85, 1.57 90 70, 1.60 '"1/

Option B 10 20 30 40 50 60 Core Power (% Rated)

Figure 2-6B 70 80 Cycle 23 GNF3 Power-Dependent MCPR Limits with FWH 00S MOC to EOC 90 Tau = 0.2 100, 1.56 100, 1.48 100, 1.45 100 100, 1.54 100, 1.48 100, 1.46 100

CORE OPERATING LIMITS REPORT COLR Page 21 LBDCR 2021-050 2.6 2.5 2.4 2.3 2.2 2.1 0:: 2.0

~ 1.9 c..

u

E 1.8 1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 0:: 1.9

~

c.. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.51 21.8, 2.42

< 50% Core Flow/

. 50% Core Flow 85, 1.70 85, 1.61 85, 1.58 OptiooB/

10 20 30 40 50 60 70 80 Core Power (% Rated)

Figure 2-7A Cycle 23 GNF2 Power-Dependent MCPR Limits with PR+FWH 00S MOC to EOC 21.8, 2.46 21.8, 2.38

. 50% Core Flow

< 50% Co" Flow I 85, 1.65 85, 1.59 85, 1.57 90

. /

Option B 10 20 30 40 50 60 Core Power (% Rated)

Figure 2-78 70 80 Cycle 23 GNF3 Power-Dependent MCPR Limits with PR+FWH 00S MOC to EOC 90 Tau = 0.2 100, 1.56 100, 1.48 100, 1.45 100 Tau = 0.2 100, 1.54 100, 1.48 100, 1.46 100

CORE OPERATING LIMITS REPORT COLR Page 22 LBDCR 2021-050 2.6 2.5 2.4 2.3 2.2 2.1 ci: 2.0

~ 1.9 Cl. u

E 1.8 1.7 1.6 1.5 1.4 1.3 1.2 0

2.5 2.4 2.3 2.2 2.1 2.0 ci: 1.9

~

Cl. u 1.8

E 1.7 1.6 1.5 1.4 1.3 1.2 0

21.8, 2.51 21.8, 2.42

< 50% Core Flow /

85, 1.70 85, 1.61 as.,~/

Option B 10 20 30 40 50 60 70 80 90 Core Power (% Rated)

Figure 2-8A Cycle 23 GNF2 Power-Dependent MCPR Limits with PR+EOC-RPT+FWH 00S MOC to EOC 21.8, 2.46 21.8, 2.38

< 50% Coco Flow /

Option A 85, 1.66 85, 1.59 "*/

Option B 10 20 30 40 50 60 Core Power (% Rated)

Figure 2-8B 70 80 Cycle 23 GNF3 Power-Dependent MCPR Limits with PR+EOC-RPT +FWH 00S MOC to EOC 90 Tau = 0.2 100, 1.59 100, 1.51 100, 1.48 100 Tau = 0.2 100, 1.56 100, 1.50 100, 1.48 100

CORE OPERATING LIMITS REPORT COLR Page 23 LBDCR 2021-050 1.70 1.65 1.60 1.55 1.50 c-1.45 20, 1.42 30, 1.42

~ 1.40 0.. u

E 1.35 1.30 1.25 90, 1.29 105, 1.29 1.20 1.15 1.10 0

10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Figure 2-9A Cycle 23 GNF2 Flow-Dependent MCPR Limits, All Application conditions 1.80 1.75 1.70 1.65 1.60 1.55 c-1.50

~ 1.45 0..

u

E 1.40 1.35 1.30 100, 1.26 1.25 1.20 96.2, 1.26 110, 1.26 1.15 1.10 0

10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Figure 2-9B Cycle 23 GNF3 Flow-Dependent MCPR Limits, All Application Conditions

CORE OPERATING LIMITS REPORT COLR Page 24 LBDCR 2021-050 1 05 1.00 0.95 0.90 C: u

~

0.85 ct:

C) 0.80

c:

...I 0.75 0.70 0.65 0.60 0

1 05 1.00 0.95 0.90 C: u

~

0.85 ct: 0.80 C)

c:

...I 0.75 0.70 0.65 0.60 0

35.4, 1.000 50, 1.000 70, 1.000 85, 1.000 100, 1.000 35.4, 0.885

< 50% Core Flow --..._

21.8, 0.761

".. 50% Core Flow 35.4, 0.702 21.8, 0.671 10 20 30 40 50 60 70 80 90 Power (% Rated)

Figure 3-1A Cycle 23 GNF2 Power-Dependent LHGR Factor BOC-MOC, EIS Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 35.4, 1.000 50, 1.000

< 50% Core Flow --

21.8, 0.802 21.8, 0.707 10 20 30 35.4, 0.933 35.4, 0.740 40 50 60 Power (% Rated)

Figure 3-18 70, 1.000 85, 1.000 70 80 90 Cycle 23 G NF3 Power-Dependent LHGR Factor BOC-MOC, EIS Note: These factors to be applied to the exposure-dependent limits as de sci bed in Section 5.3 100 100, 1.000 100 110 11 0

CORE OPERATING LIMITS REPORT COLR Page 25 LBDCR 2021-050 1.05 1.00 0.95 0.90

-a: u

~

0.85 O!'. 0.80 C)

I

..J 0.75 0.70 0.65 0.60 0

< 50% Core Flow -..

21.8, 0.752 10 20 35.4, 1.000 50, 1.000 30 35.4, 0.865 35.4, 0.702 40 50 60 Power (% Rated)

Figure 3-2A 70, 1.000 85, 1.000 100, 1.000 70 80 90 100 Cycle 23 GNF2 Power-Dependent LHGR Factor BOC-MOC with FWHOOS Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 110

CORE OPERATING LIMITS REPORT COLR Page 26 LBDCR 2021-050 105 1.00 0.95 0.90 C: u

~

0.85 Ir:

(!) 0.80 J:

0.75 0.70 0.65 0.60 0

1.05 1.00 0.95 0.90 C: u 0.85

~

0:: 0.80

(!)

I:

..J 0.75 0.70 0.65 0.60 0

35.4, 1.000 50, 1.000 70, 1.000 85, 1.000 100, 1.000 35.4, 0.912 35.4, 0.912

< 50% Core Flow 21.8, 0.794 35.4, 0.740 21.8, 0.707 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

Figure 3-2B Cycle 23 GNFJ Power-Dependent LHGR Factor BOC-MOC with FWHOOS Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 100, 1.000 85, 0.918 35.4, 0.865 70, 0.860

< 50% Core Flow --

21.8, 0.752 50, 0.770

'.'.'.. 50% Core Flow ------

21.8, 0.671 10 20 30 40 50 60 70 80 90 100 Power(% Rated)

Figure 3-3A 110 110 Cycle 23 GNF2 Power-DependentLHGR Factor BOC-MOC with PROOS, FWHOOS and EOC-RPT (Application Conditions 6 and 8); Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 27 LBDCR 2021-050 1.05 1.00 0.95 0.90 a: u

~

0.85 fl!

(!) 0.80 I

..J 0.75 0.70 0.65 0.60 0

< 50% Core Flow 21.8, 0.794 21.8, 0.707

.::: 50% Core Flow 10 20 30 100, 1.000 35.4, 0.912 70, 0.905 50, 0.812 40 50 60 70 80 90 100 11 0 Power (% Rated)

I Figure J-JB Cycle 23 GNFJ Power-Dependent LHGR Factor BOC-MOC with PROOS, FW HOOS and EOC-RPT (Application Conditions 6 and 8); Note: These factors to be applied to the exposure-dependent limits as de sci bed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 28 LBDCR 2021-050 a: u

~

It:

(!)

J:

_J a:

1.05 1.00 0.95 0.90 0.85 0.80 0.75 0.70 0.65 0.60 1.05 1.00 0.95 0.90 u 0.85

~

ffi 0.80 I

_J 0.75 0.70 0.65 0

0 35.4, 1.000 50, 1.000 70, 1.000 85, 1.000 100, 1.000

< 50% Core Flow

~

35.4, 0.843 21.8, 0.751 /

50% Core Flow ~

21.8, 0.657 35.4, 0.693 10 20 30 40 50 60 70 80 90 100 11 0 Power (% Rated)

Figure 3-4A Cycle 23 GNF2 Power-Dependent LHGR Factor MOC-EOC, EIS Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 35.4, 1.000 50, 1.000 70, 1.000 85, 1.000 100, 1.000 35.4, 0.907

< 50% Core Flow '----..

21.8, 0.792

?: 50% Core Flow 35.4, 0.730 21.8, 0.693 10 20 30 40 50 60 70 80 90 100 11 0 Power (% Rated)

Figure 3-48 Cycle 23 GNF3 Power-Dependent LHGR Factor MOC-EOC, EIS Note: These fa.ctors to be applied to the exposure-dependentlimits as de sci bed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 29 LBDCR 2021-050 1 05 35.4, 1.000 50, 1.000 70, 1.000 85, 1.000 100, 1.000 1.00 0.95 0.90 c:: u 0.85

< 50% Core Flow

~

~

35.4, 0.836 ct: 0.80 C)

J:

...I 0.75 21.8, 0.741 0.70 35.4, 0.693 0.65 21.8, 0.657 0.60 0

10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Figure 3-5A Cycle 23 GNF2 Power-Dependent LHGR Factor MOC-EOC with FW HOOS Note: Toese factors to be applied to the exposure-dependent limits as de sci bed in Section 5.3 1 05 35.4, 1.000 50, 1.000 70, 1.000 85, 1.000 100, 1.000 1.00 0.95 0.90 35.4, 0.899 c::

< 50% Core Flow u

~

0.85

~

ct: 0.80 C) 21.8, 0.782 J:

...I 0.75 35.4, 0.730 0.70 21.8, 0.693 0.65 0.60 0

10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Figure 3-58 Cycle 23 GNF3 Power-Dependent LHGR Factor MOC-EOC with FW HOOS Note: niese factors to be applied to the exposure-dependent limits as de sci bed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 30 LBDCR 2021-050 C: u

~

ct:

C)

c:

...I C:

1 05 1.00 0.95 0.90 0.85

< 50% Core Flow 0.80 0.75 21.8, 0.741 0.70 0.65 21.8, 0.657 0.60 0

10 20 30 35.4, 0.836 40 50, 0.766 50 60 Power (% Rated)

Figure 3-6A 70 100, 1.000 85, 0.903 80 90 100 110 Cycle 23 GNF2 Power-Dependent LHGR Factor MOC-EOC with PROOS, FWHOOS and EOC-RPT (Application Conditions 6 and 8); Note: Tilese factors to be applied to the exposure-dependent limits as descibed in Section 5.3 1 05 1.00 0.95 0.90 35.4, 0.899 70, 0.870 100, 1.000 85, 0.952 u 0.85

< 50% Core Flow

~

ffi 0.80

c:

...I 0.75 0.70 0.65 0

21.8, 0.782 21.8, 0.693 10 20 30 40 50, 0.808 50 60 Power (% Rated)

Figure 3~68 70 80 90 100 110 Cycle 23 GNF3 Power-Dependent LHGR Factor MOC-EOC with PROOS, FWHOOS and EOC-RPT (Application Conditions 6 and 8); Note: Tilese factors to be applied to the exposure-dependent limits as descibed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 31 LBDCR 2021-050 1 05 1.00 0.95 0.90 C' u

~

0.85 0::

C) 0.80

c

....I 0.75 0.70 0.65 0.60 0

1 05 1.00 0.95 0.90 C' u

~

0.85 0::

C) 0.80

c

....I 0.75 0.70 0.65 0.60 0

10 20, 0_652 30, 0_652 20 30 71.4, 1.00 TLO ------.

51.18, 0.83 40 50 60 70 Core Flow (% Rated)

Figure 3-7A 80 Cycle 23 GNF2 Flow-Dependent LHGR Factor 105, 1.00 105, 0_83 1 ~

SLO 90 100 11 0 Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 10 20 30, 0.660 30 40 TLO 80.3, 1.000 80, 0.998 90, 1.000 110, 1.000 100, 1.000 65.52, 0_!)00 70* 0-930 110, 0.900

---

~

50 60 70 Core Flow (% Rated)

Figure 3-78 80 l

SLO 90 100 11 0 Cycle 23 GNF3 Flow-Dependent LHGR Factor Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 120 120

CORE OPERATING LIMITS REPORT COLR Page 32 LBDCR 2021-050 Figure 4 Backup Stability Protection Region Boundaries for Normal Feedwater Temperature (NFWT) 0 110 I

10 I'

I 20 30 I

I I

~ Cycle 23 BSP Region 100 90 80 ffi 50

~

0

0. 40 w

c:::

0 30

(.)

20 10 0

~ Boundaries for NFWT

MELLLA Boundary

~

I 1---

Scram Region I - I.L" ~

/'

/

I I

B,_ --

I

/

/

V i..---

/

0 10 20 30 CORE FLOW (% rated) 40 50 60 70 80 90 100 110 7

7 7

I Implemented BSP Boundary 1---

!IU, o*o 92.8, ~00 100, 00

-r---, k"""

~

~ __,,,,,,--

~

05, 1 00 I MELLLA+ Boundary 7

./

i,, I

~

i-

....J..,...... ~

~-

15, 80 6.,. V 1........-.....

..,..,-1 i---

~ i,,,,"""'_ I.,-/

I.

11.1

_i..,.,,,,. ------.....

I 7

. /'. J-.--,--is: 71. 3 I

I'-..

l.,. L,".,....,..,,c I

"-...........-: v 7 I

~

V/

I

~

OPRM Armed Region I/... /

~.

I

/

.I/'-......

I

/

Controlled Entry I I

/

I I

~ -

I

~~

-/

Ca ltitatic *n Pr, ~tecti on Note:

SLO is pro hibited in M ELLLA+ regio n

~

40 50 60 70 80 90 100 110 120 CORE FLOW (MLB/HR)

CORE OPERATING LIMITS REPORT COLR Page 33 LBDCR 2021-050 Figure 5 Backup Stability Protection Region Boundaries for Reduced Feedwater Temperature (RFWT) 0 110 10 20 30

,_ Cycle 23 BSP Region 100,.._ Boundaries for RFWT 90 80 J MELLLA Boundary I I

I"'

~

ffi 50

~

~

v Scram Region I.

0. 40 w

c:::

0 30

(.)

20 10 0

~

./,,

i-----

J ---

' i<'

A? ;;.,_

I

/

/

r--....

/

~

V

~ --

i-

/

/

/

CORE FLOW (% rated) 40 50 60 70 80 90 100

( 2.8% 100)

I-"""' 1.------"'

~

Implemented BSP Boundary :

~i--,_

i...,.,-

v-

,,,- ~ i.---------

~....... -P-...

~--i....-----

I

~

I A2' /

r ~ ~

I

~1*..,"f...... V I

,,,,..,....r I I

/, 1/' /1 I

V I /

OPRM Armed Region

/,1' I

/ ~

I

"'/

Controlled Entry I I

I I

i..--...

I -

~r Ca yitati,,n Pr ~tecti on 0

10 20 30 40 50 60 70 80 90 100 110 CORE FLOW (MLB/HR) 110 105%,100 120