BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)

Cycle 22 Core Operating Limits Report (COLR)

ML18086B639
Person / Time
Site:	Brunswick
Issue date:	03/27/2018
From:	Wooten B Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 18-0042
Download: ML18086B639 (42)

Text

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-0017 Rev. 0 Page 2 LIST OF EFFECTIVE PAGES Page(s) Revision 1- 39 0 This document consists of 39 total pages.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 3 TABLE OF CONTENTS Subject Page Cover ............................................................................................................................................... 1 List of Effective Pages ...................................................................................................................... 2 Table of Contents ............................................................................................................................. 3 List of Tables .................................................................................................................................... 4 List of Figures .................................................................................................................................. 5 Nomenclature ................................................................................................................................... 6 Introduction and Summary ............................................................................................................... 8 APLHGR Limits ................................................................................................................................ 9 MCPR Limits .................................................................................................................................... 9 LHGR Limits ...................................................................................................................................

10 PBDA Setpoints .............................................................................................................................

10 RBM Setpoints ...............................................................................................................................

11 Equipment Out-of-Service ..............................................................................................................

11 Single Loop Operation ....................................................................................................................

12 Inoperable Main Turbine Bypass System .......................................................................................

12 Feedwater Temperature Reduction ................................................................................................ 13 References .....................................................................................................................................

14 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 4 References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.

LIST OF TABLES Table 1: RBM System Setpoints ................................................................................................. 16 Table 2: RBM Operability Requirements .....................................................................................

17 Table 3: PBDA Setpoints ............................................................................................................

18 Table 4: Exposure Basis for Brunswick Unit 1 Cycle 22 Transient Analysis

................................

19 Table 5: Power-Dependent MCPR p Limits ..................................................................................

20 NSS Insertion Times - BOC to < NEOC Table 6: Power-Dependent MCPR p Limits .................................................................................. 21 TSSS Insertion Times - BOC to < NEOC Table 7: Power-Dependent MCPR p Limits ..................................................................................

22 NSS Insertion Times - BOC to < EOCLB Table 8: Power-Dependent MCPR p Limits ..................................................................................

23 TSSS Insertion Times - BOC to < EOCLB Table 9: Power-Dependent MCPR p Limits ..................................................................................

24 NSS Insertion Times BOC to < MCE (FFTR/Coastdown) Table 10: Power-Dependent MCPR p Limits ..................................................................................

25 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown) Table 11: Flow-Dependent MCPR f Limits .....................................................................................

26 Table 12: AREVA Fuel Steady-State LHGR SS Limits ....................................................................

27 Table 13: AREVA Fuel Power-Dependent LHGRFAC p Multipliers ................................................

28 NSS Insertion Times - BOC to < EOCLB Table 14: AREVA Fuel Power-Dependent LHGRFAC p Multipliers ................................................

29 TSSS Insertion Times - BOC to < EOCLB Table 15: AREVA Fuel Power-Dependent LHGRFAC p Multipliers ................................................

30 NSS Insertion Times BOC to < MCE (FFTR/Coastdown) Table 16: AREVA Fuel Power-Dependent LHGRFAC p Multipliers ................................................

31 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown) Table 17: AREVA Fuel Flow-Dependent LHGRFAC f Multipliers ...................................................

32 Table 18: AREVA Fuel Steady-State MAPLHGR SS Limits .............................................................

33

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 5 References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.

LIST OF FIGURES Figure 1: Stability Option III Power/Flow Map .............................................................................. 34 OPRM Operable, Two Loop Operation, 2923 MWt Figure 2: Stability Option III Power/Flow Map ..............................................................................

35 OPRM Inoperable, Two Loop Operation, 2923 MWt Figure 3: Stability Option III Power/Flow Map ..............................................................................

36 OPRM Operable, Single Loop Operation, 2923 MWt Figure 4: Stability Option III Power/Flow Map ..............................................................................

37 OPRM Inoperable, Single Loop Operation, 2923 MWt Figure 5: Stability Option III Power/Flow Map ..............................................................................

38 OPRM Operable, FWTR, 2923 MWt Figure 6: Stability Option III Power/Flow Map ..............................................................................

39 OPRM Inoperable, FWTR, 2923 MWt Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 6 NOMENCLATU RE 2PT Two Recirculation Pump Trip APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor (Subsystem) ARTS APRM/RBM Technical Specification

BOC Beginning of Cycle BSP Backup Stability Protection BWROG BWR Owners Group CAVEX Core Average Exposure CO LR Core Operating Limits Report CRWE Control Rod Withdrawal Error DIVOM Delta CPR Over Initial MCPR Versus Oscillation Magnitude EFPD Effective Full Power Day EOC End of Cycle EOCLB End of Cycle Licensing Basis EOFP End of Full Power EOOS Equipment Out-of-Service F Flow (Total Core) FHOOS Feedwater Heater Out-of-Service FFTR Final Feedwater Temperature Reduction FWTR Feedwater Temperature Reduction GE General Electric HCOM Hot Channel Oscillation Magnitude HPSP High Power Set Point HTSP High Trip Set Point ICF Increased Core Flow IPSP Intermediate Power Set Point ITSP Intermediate Trip Set Point

LCO Limiting Condition of Operation LHGR Linear Heat Generation Rate LHGR SS Steady-State Maximum Linear Heat Generation Rate LHGRFAC Linear Heat Generation Rate Factor LHGRFAC f Flow-Dependent Linear Heat Generation Rate Factor LHGRFAC p Power-Dependent Linear Heat Generation Rate Factor LPRM Local Power Range Monitor (Subsystem)

LPSP Low Power Set Point LTSP Low Trip Set Point

MAPLHGR Maximum Average Planar Linear Heat Generation Rate MAPLHGR SS Steady-State Maximum Average Planar Linear Heat Generation Rate MAPFAC Maximum Average Planar Linear Heat Generation Rate Factor

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 7 NOMENCLATURE (continued)

MAPFAC f Flow-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFAC p Power-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFACSLO Maximum Average Planar Linear Heat Generation Rate Factor when in SLO MCE Maximum Core Exposure MCPR Minimum Critical Power Ratio MCPRf Flow-Dependent Minimum Critical Power Ratio MCPRp Power-Dependent Minimum Critical Power Ratio MELLL Maximum Extended Load Line Limit MEOD Maximum Extended Operating Domain MSIVOOS Main Steam Isolation Valve Out-of-Service NEOC Near End of Cycle NFWT Nominal Feedwater Temperature NRC Nuclear Regulatory Commission NSS Nominal SCRAM Speed

OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor OOS Out-of-Service P Power (Total Core Thermal)

PBDA Period Based Detection Algorithm PRNM Power Range Neutron Monitoring (System)

RBM Rod Block Monitor (Subsystem)

RFWT Reduced Feedwater Temperature RPT Recirculation Pump Trip RTP Rated Thermal Power

SLMCPR Safety Limit Minimum Critical Power Ratio S LO Single Loop Operation SRV Safety Relief Valve SRVOOS Safety Relief Valve Out-of-Service SS Steady-State STP Simulated Thermal Power

TBV Turbine Bypass Valve TBVINS Turbine Bypass Valves In Service TBVOOS Turbine Bypass Valves Out-of-Service (all bypass valves OOS) TIP Traversing Incore Probe TLO Two Loop Operation TS Technical Specification TSSS Technical Specification SCRAM Speed

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 8 References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.

The Brunswick Unit 1, Cycle 22 COLR provides values for the core operation limits and setpoints required by Technical Specifications (TS) 5.6.5.a.

Required Core Operating Limit (TS 5.6.5.a ) NRC Approved Methodology (TS 5.6.5.b) Related TS Items

1. APLHGR for TS 3.2.1. 1, 2, 6, 7,16, 17 TS 3.2.1 LCO (APLHGR)

TS 3.4.1 LCO (Recirculation loops operating)

TS 3.7.6 LCO (Main Turbine Bypass out-of-service) 2. MCPR for TS 3.2.2. 1, 2, 6, 7, 8, 9, 10, 11, 12, 13, 14, 21 TS 3.2.2 LCO (MCPR)

TS 3.4.1 LCO (Recirculation loops operating)

TS 3.7.6 LCO (Main Turbine bypass out-of-service) 3. LHGR for TS 3.2.3. 2, 3, 4, 5, 6, 7, 8, 9, 10, 12, 13, 20 TS 3.2.3 LCO (LHGR)

TS 3.4.1 LCO (Recirculation loops operating)

TS 3.7.6 LCO (Main Turbine bypass out-of-service) 4. PBDA setpoint for Function 2.f, APRM

- OPRM Upscale, for TS 3.3.1.1. 8, 14, 18, 19, 21 TS Table 3.3.1.1-1, Function 2.f (APRM - OPRM Upscale)

TS 3.3.1.1, Condition I (Alternate instability detection and suppression)

5. The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for TS 3.3.2.1. 6, 8 TS Table 3.3.2.1-1, Function 1 (RBM upscale and operability requirements)

The required core operating limits and setpoints listed in TS 5.6.5.a are presented in the COLR, have been determined using NRC approved methodologies (COLR References 1 through 21) in accordance with TS 5.6.5.b, have considered all fuel types utilized in B 1 C2 2 , and are established such that all applicable limits of the plant safety analysis are met in accordance with TS 5.6.5.c. In addition to the TS required core operating limits and setpoints, this COLR also includes maps showing the allowable power/flow operating range including the Option III stability ranges.

The generation of this COLR is documented in Reference 30 and is based on analysis results documented in References 27-29.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 9 Steady-state MAPLHGR SS limits are provided for AREVA Fuel (Table 18

). These steady-state MAPLHGR SS limits must be modified as follows:

AREVA Fuel MAPLHGR limits do not have a power, flow, or EOOS dependency. The applied MAPLHGR limit is dependent on the number of recirculation loops in operation. The steady-state MAPLHGR limit must be modified by a MAPFACSLO multiplier when in SLO. MAPFACSLO has a fuel design dependency as shown below.

The applied TLO and SLO MAPLHGR limits are determined as follows:

MAPLHGR LimitTLO = MAPLHGR SS MAPLHGR LimitSLO = MAPLHGR SS x MAPFACSLO where MAPFACSLO = 0.80 for ATRIUM 10XM Linear interpolation should be used to determine intermediate values between the values listed in the table. The MCPR limits presented in Tables 5 through 11 are based on the TLO and SLO SLMCPRs listed in Technical Specification 2.1.1.2 of 1.07 and 1.09, respectively. MCPR limits have a core power and core flow dependency. Power-dependent MCPR p limits are presented in Tables 5 through 10 while flow-dependent MCPR f limits are presented in Table

11. Power-dependent MCPR P limits are dependent on CAVEX, SCRAM insertion speed, EOOS, fuel design, number of operating recirculation loops (i.e., TLO or SLO), core flow and core thermal power. Values for the CAVEX breakpoints are provided in Table 4. See COLR section titled Out-of-Care should be used when selecting the appropriate limits set. The MCPR limits are established such that they bound all pressurization and non-pressurization events. The power-dependent MCPR p limits (Tables 5-

10) must be adjusted by an adder of +0.02 when in SLO. The applied TLO and SLO MCPR limits are determined as follows:

MCPR LimitTLO = (MCPR p, MCPR f)max MCPR LimitSLO = (MCPR p + 0.02, MCPR f)max Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show step changes at 26.0%P and 50.0%P. performing a hand calculation of a limit the power is exactly on the breakpoint (i.e. 26.0 or 50.0), select the most restrictive limit associated with the breakpoint.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 10 Steady-state LHGR SS limits are provided for AREVA Fuel (Table 12). These steady-state LHGR SS limits must be modified as follows:

AREVA Fuel LHGR limits have a core power and core flow dependency. AREVA Fuel power-dependent LHGRFAC p multipliers (Tables 13-16) and flow-dependent LHGRFAC f multipliers (Table 17) must be used to modify the steady-state LHGR SS limits (Table 12) for off-rated conditions. AREVA Fuel power-dependent LHGRFAC p multipliers are dependent on CAVEX, SCRAM insertion speed, EOOS, fuel design, core flow and core thermal power. Values for the CAVEX

-of-of analyzed EOOS conditions. Care should be used when selecting the appropriate multiplier set. The applied LHGR limit is not dependent on the number of operating recirculation loops. No adjustment to the LHGR limit is necessary for SLO. The applied LHGR limit is determined as follows:

LHGR Limit = LHGR SS x (LHGRFAC p, LHGRFAC f)min Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show step changes at 26.0%P and 50.0%P. performing a hand calculation of a limit the power is exactly on the breakpoint (i.e. 26.0 or 50.0), select the most restrictive limit associated with the breakpoint. Brunswick Unit 1 has implemented BWROG Long Term Stability Solution Option III (OPRM) with the methodology described in Reference 23. Plant specific analysis incorporating the Option III hardware is described in Reference 24. Reload validation has been performed in accordance with Reference 19. The analysis was performed at 100%P assuming a two pump trip (2PT) and at 45%F assuming steady-state (SS) conditions at the highest rod line power (60.6%). The PBDA setpoints are set such that either the least limiting MCPR p limit or the least limiting MCPR f limit will provide adequate protection against violation of the SLMCPR during a postulated reactor instability. Based on the MCPR limits presented in Tables 5 through 11, the required Amplitude Trip Setpoint () is set by the least limiting 100%P MCPR p limit (1.35) with an allowance for conservative margin, which has an associated Confirmation Count Setpoint

(). The PBDA setpoints shown in Table 3 are valid for any feedwater temperature.

Evaluations by GE have shown that the generic DIVOM curves specified in Reference 19 may not be conservative for current plant operating conditions for plants which have implemented Stability Option III.

To address this issue, AREVA has performed calculations for the relative change in CPR as a function of the calculated HCOM. These calculations were performed with the RAMONA5-FA code in accordance with Reference 26. This code is a coupled neutronic-thermal-hydraulic three-dimensional transient model for the purpose of determining the rplant specific basis. The stability-based OLMCPRs are based upon using the most limiting CPR calculated for a given oscillation magnitude or the generic value provided in Reference

19. In cases where the OPRM system is declared inoperable, Backup Stability Protection (BSP) in accordance with Reference 25 is provided. Analyses have been performed to support operation with nominal feedwater temperature conditions and reduced feedwater temperature conditions (FHOOS and FFTR).

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 11 The power/flow maps (Figures 1-

6) were validated for B1 C22 based on Reference 29 to facilitate operation under Stability Option III as implemented by Function 2.f of Table 3.3.1.1-1 and LCO Condition I of Technical Specification 3.3.1.1. The generation of these maps is documented in Reference 28. All maps illustrate the region of the power/flow map above 25% RTP and below 60% drive flow (correlated to core flow) where the system is required to be enabled. Figures 1-6 were included in the COLR as an operator aid and not a licensing requirement. Figures 5 and 6 are the power/flow maps for use in FWTR.

The maps supporting an operable OPRM (Figures 1, 3 and 5) show a Scram Avoidance Region, which is not a licensing requirement but is an operator aid to illustrate where the OPRM system may generate a scram to avoid an instability event. Note that the STP scram and rod block limits are defined in Technical Specifications, the Technical Requirements Manual, and/or Plant procedures, and are included in the COLR as an operator aid rather than a licensing requirement.

Figures 3 and 4 implement the corrective action for AR-217345 which restricts reactor power to no more than 50% RTP when in SLO with OPRM operable or inoperable. This operator aid is intended to mitigate a spurious OPRM trip signal which could result from APRM noise while operating at high power levels. The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation are presented in Table 1 and were determined to be consistent with the bases of the ARTS program (Reference 22). These setpoints will ensure the power-dependent MCPR limits will provide adequate protection against violation of the SLMCPR during a postulated CRWE event. Reference 27 revised these setpoints to reflect changes associated with the installation of the NUMAC PRNM system. RBM operability requirements, consistent with Notes (a) through (e) of Technical Specification Table 3.3.2.1-1, are provided in Table

2. Brunswick Unit 1, Cycle 22 is analyzed for the following operating conditions with applicable MCPR, APLHGR and LHGR limits.

Base Case Operation SLO TBVOOS FHOOS Combined TBVOOS and FHOOS Base Case Operation as well as the above-listed EOOS conditions assume all the items OOS below. These conditions are general analysis assumptions used to ensure conservative analysis results and were not meant to define specific EOOS conditions beyond those already defined in Technical Specifications.

Any 1 inoperable SRV 1 inoperable TBV (Note that for TBVOOS, TBVOOS/FHOOS, all 4 TBVs are assumed inoperable) Up to 40% of the TIP channels OOS Up to 50% of the LPRMs OOS Please note that during FFTR/Coastdown, FHOOS is included in Base Case Operation, and TBVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 12 Brunswick Unit 1 , Cycle 22 may operate in SLO up to a maximum core flow of 45 Mlbm/hr which corresponds to a maximum power level of 71.1% RTP with applicable MCPR, APLHGR and LHGR limits.

The following must be considered when operating in SLO:

SLO is not permitted with RFWT (FHOOS/FFTR). SLO is not permitted with TBVOOS. SLO is not permitted with MSIVOOS.

Various indicators on the Power/Flow Maps are provided not as operating limits but rather as a convenience for the operators. The purposes for some of these indicators are as follows:

The SLO Entry Rod Line is shown on the TLO maps to avoid regions of instability in the event of a pump trip. A maximum core flow line is shown on the SLO maps to avoid vibration problems. APRM STP Scram and Rod Block nominal trip setpoint limits are shown at the estimated core flow corresponding to the actual drive flow-based setpoints to indicate where the Operator may encounter these setpoints (See LCO 3.3.1.1, Reactor Protection System Instrumentation Function 2.b: Average Power Range Monitors Simulated Thermal Power - High Allowable Value). When in SLO, Figures 3 and 4 implement the corrective action for AR-217345 which restricts reactor power to no more than 50% RTP with OPRM operable or inoperable. This operator aid is intended to mitigate a spurious OPRM trip signal which could result from APRM noise while operating at high power levels.

Brunswick Unit 1 , Cycle 22 may operate with an inoperable Main Turbine Bypass System over the entire MEOD range and cycle with applicable APLHGR, MCPR and LHGR limits as specified in the COLR. An operable Main Turbine Bypass System with only one inoperable bypass valve was assumed in the development of the Base Case Operation limits. Base Case Operation is synonymous with TBVINS. The following must be considered when operating with TBVOOS:

Two or more inoperable bypass valves renders the entire Main Turbine Bypass System inoperable requiring the use of TBVOOS limits. The TBVOOS analysis supports operation with all bypass valves inoperable.

23% RTP requires use of the combined TBVOOS/FHOOS limits. TBVOOS operation coincident with FHOOS is supported using the combined TBVOOS/FHOOS limits. SLO is not permitted with TBVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 13 Brunswick Unit 1, Cycle 22 may operate with RFWT over the entire MEOD range and cycle with applicable APLHGR, MCPR and LHGR limits as specified in the COLR. NFWT is defined as the range of feedwater temperatures from NFWT to NFWT - the development of the Base Case Operation limits. The FHOOS limits and FFTR/Coastdown limits were d when operating with RFWT:

Although the acronyms FWTR, FHOOS, RFWT and FFTR all involve reduced feedwater temperature, the use of FFTR is reserved for cycle energy extension using reduced feedwater temperature at and beyond a core average exposure of EOCLB using FFTR/Coastdown limits. Prior to reaching the EOCLB exposure breakpoint, operation with FWTR 23% RTP requires use of the FHOOS limits. Until a core average exposure of EOCLB is reached, implementation of the FFTR/Coastdown limits is not required even if coastdown begins early. When operating with RFWT, the appropriate Stability Option III Power/Flow Maps (Figures 5 and 6) must be used. FHOOS operation coincident with TBVOOS is supported using the combined TBVOOS/FHOOS limits. SLO is not permitted with RFWT. NFWT limits have been conservatively adjusted to eliminate the need to use RFWT limits below 50% RTP.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 14 In accordance with Brunswick Unit 1 Technical Specification 5.6.5.b, the analytical methods for determining Brunswick Unit 1 core operating limits have been specifically reviewed and approved by the NRC and are listed as References 1 through 21.

1. NEDE-24011-P-A, "GESTAR II - General Electric Standard Application for Reactor Fuel," and US Supplement, Revision 15, September 2005.

2. XN-NF-81--Mechanical Response 3. XN-NF-85-Revision 1, September 1986.

4. EMF-85-R) Fuel Rod Thermal- 5. ANF-89-1995. 6. XN-NF Methodology for Boiling Water Reactors - 7. XN-NF-80-6. 8. EMF-and Validation of CASMO-4/MICROBURN- 9. XN-NF-80-RMEX: 10. XN-NF-84--T: A Computer Code for BWR Transient Thermal- Revision 0, February 1987.

11. ANP-June 2011.

12. ANF-gust 1990.

13. ANF-September 2005.

14. EMF- 15. EMF-ower Corporation's Critical Power Correlations to Co- 16. EMF-- 17. EMF-TM-evision 0, September 2000.

18. EMF-CC-- Assessment of STAIF with Input from MICROBURN- 19. NEDO-32465-or 20. BAW--Revision 0, April 2008.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 15 21. ANP-10298P- 22. NEDC- 23. NEDO-31960--Term Stability Solutions Licensing Methodology 93A211. 24. GENE-C51-00251-00-Revision 0, March 2001.

25. OG02-0119-Energy, July 17, 2002.

26. BAW--Specific DIVOM Methodology Using the RAMONA5-May 2008.

27. BNP Design Calculation 1C51-ainty and Scaling Calculation (1-C51-APRM-1 through 4 Loops and 1-C51 RBM-Revision 3, May 2004.

28. BNP Design Calculation 0B21- 29. ANP-3631 Cycle 22 December 2017.

30. BNP Design Calculation 1B21-2050Preparation of the B1C22 Core Operating Limits Report,Revision 0, March 2018.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 16 Table 1 RBM System Setpoints 1 Lower Power Setpoint (LPSP b) < 27.7 < 29.0 Intermediate Power Setpoint (IPSP b) < 62.7 < 64.0 High Power Setpoint (HPSP b) < 82.7 < 84.0 Low Trip Setpoint (LTSPc,d) < 117.1 < 117.6 Intermediate Trip Setpoint (ITSPc,d) < 112.3 < 112.8 High Trip Setpoint (HTSPc,d) < 107.3 < 107.8 RBM Time Delay (t d2) 0 seconds < 2.0 seconds a See Table 2 for RBM Operability Requirements.

b Setpoints in percent of Rated Thermal Power.

c Setpoints relative to a full scale reading of 125. For example, < 117.1 means

< 117.1/125.0 of full scale.

d Trip setpoints and allowable values are based on a HTSP Analytical Limit of 110.2 with RBM filter.

1 This table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1) and 5.6.5.a.5.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 17 Table 2 RBM Operability Requirements 2 the following conditions are met, Thermal Power

(% rated) MCPR 9 TLO 1.92 SLO 49 TLO 2 Requirements valid for all fuel designs, all SCRAM insertion times and all core average exposure ranges.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 18 Table 3 PBDA Setpoints 3 1.05 1.16 1.1 9 1.06 1.18 1.20 1.07 1.19 1.22 1.08 1.21 1.24 1.09 1.23 1.26 1.10 1.25 1.28 1.12 1.29 1.32 1.13 1.31 1.34 1.14 1.33 1.36 1.151.351.3 9Acceptance CriteriaOff-rated OLMCPR @ 45% Flow Rated Power OLMCPR Amplitude Trip (S p) Confirmation Count (N p) 3 This table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-

1) and 5.6.5.a.4.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 19 Table 4 Exposure Basis 4 for Brunswick Unit 1 Cycle 22 Transient Analysis 34,2 84 Breakpoint for exposure dependent MCPR p limits (NEOC) 35,4 84 Design basis rod patterns to EOFP + 15 EFPD (EOCLB) 36,948 End of cycle with FFTR/Coastdown

- Maximum Core Exposure (MCE) 4 The exposure basis for the defined break points is the core average exposure (CAVEX) values shown above regardless of the actual BOC CAVEX value of the As-Loaded Core.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 20 Table 5 Power-Dependent MCPR p Limits 5 NSS Insertion Times BOC to < NEOC EOOS Power ATRIUM 10XM Condition (% rated) MCPR p 100.0 1.35 90.0 1.37 Base 50.0 1.66 Case > 65%F Operation 50.0 1.91 1.78 26.0 2.34 2.22 26.0 2.38 2.34 23.0 2.45 2.43 100.0 1.38 90.0 1.40 50.0 1.66 TBVOOS > 65%F 50.0 1.91 1.78 26.0 2.34 2.22 26.0 2.94 2.85 23.0 3.14 3.05 100.0 1.35 90.0 1.37 50.0 1.66 FHOOS > 65%F 50.0 1.91 1.78 26.0 2.34 2.22 26.0 2.51 2.46 23.0 2.60 2.59 100.0 1.38 90.0 1.40 TBVOOS 50.0 1.66 and > 65%F FHOOS 50.0 1.91 1.78 26.0 2.34 2.22 26.0 3.03 2.96 23.0 3.22 3.20 5 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.02. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 21 Table 6 Power-Dependent MCPR p Limits 6 TSSS Insertion Times BOC to < NEOC EOOS Power ATRIUM 10XM Condition (% rated) MCPR p Base Case Operation 100.0 1.39 90.0 1.40 50.0 1.66 > 65%F 50.0 1.93 1.80 26.0 2.36 2.25 26.0 2.38 2.34 23.0 2.45 2.4 3 TBVOOS 100.0 1.41 90.0 1.44 50.0 1.66 > 65%F 50.0 1.93 1.80 26.0 2.36 2.25 26.0 2.94 2.85 23.0 3.14 3.05 FHOOS 100.0 1.39 90.0 1.40 50.0 1.66 > 65%F 50.0 1.93 1.80 26.0 2.36 2.25 26.0 2.51 2.46 23.0 2.60 2.59 100.0 1.41 90.0 1.44 TBVOOS 50.0 1.66 and > 65%F FHOOS 50.0 1.93 1.80 26.0 2.36 2.25 26.0 3.03 2.96 23.0 3.22 3.20 6 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.02. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 22 Table 7 Power-Dependent MCPR p Limits 7 NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM Condition (% rated) MCPR p 100.0 1.36 90.0 1.37 Base 50.0 1.66 Case > 65%F Operation 50.0 1.91 1.78 26.0 2.34 2.22 26.0 2.38 2.34 23.0 2.45 2.43 100.0 1.38 90.0 1.40 50.0 1.66 TBVOOS > 65%F 50.0 1.91 1.78 26.0 2.34 2.22 26.0 2.94 2.85 23.0 3.14 3.05 100.0 1.36 90.0 1.37 50.0 1.66 FHOOS > 65%F 50.0 1.91 1.78 26.0 2.34 2.22 26.0 2.51 2.46 23.0 2.60 2.59 100.0 1.38 90.0 1.40 TBVOOS 50.0 1.66 and > 65%F FHOOS 50.0 1.9 1 1.78 26.0 2.34 2.22 26.0 3.03 2.96 23.0 3.22 3.20 7 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.02. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 23 Table 8 Power-Dependent MCPR p Limits 8 TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM Condition (% rated) MCPR p Base Case Operation 100.0 1.39 90.0 1.40 50.0 1.66 > 65%F 65%F 50.0 1.93 1.80 26.0 2.36 2.25 26.0 2.38 2.34 23.0 2.45 2.43 TBVOOS 100.0 1.41 90.0 1.44 50.0 1.66 > 65%F 50.0 1.93 1.80 26.0 2.36 2.25 26.0 2.94 2.85 23.0 3.14 3.05 FHOOS 100.0 1.39 90.0 1.40 50.0 1.66 > 65%F 65%F 50.0 1.93 1.80 26.0 2.36 2.25 26.0 2.51 2.46 23.0 2.60 2.59 100.0 1.41 90.0 1.44 TBVOOS 50.0 1.66 and > 65%F FHOOS 50.0 1.93 1.80 26.0 2.36 2.25 26.0 3.03 2.96 23.0 3.22 3.20 8 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.02. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 24 Table 9 Power-Dependent MCPR p Limits 9 NSS Insertion Times BOC to < MCE (FFTR/Coastdown) EOOS Power ATRIUM 10XM Condition (% rated) MCPR p Base Case 100.0 1.37 Operation 90.0 1.37 50.0 1.66 (FFTR/FHOOS

> 65%F included) 50.0 1.91 1.78 26.0 2.34 2.22 (Bounds operation 26.0 2.51 2.46 with NFWT) 23.0 2.60 2.59 TBVOOS 100.0 1.38 90.0 1.40 (FFTR/FHOOS 50.0 1.66 included) > 65%F 50.0 1.91 1.78 (Bounds operation 26.0 2.34 2.22 with NFWT) 26.0 3.03 2.96 23.0 3.22 3.20 9 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.02. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 25 Table 10 Power-Dependent MCPR p Limits 10 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM Condition (% rated) MCPR p Base Case 100.0 1.39 Operation 90.0 1.40 50.0 1.66 (FFTR/FHOOS

> 65%F included) 50.0 1.93 1.80 26.0 2.36 2.25 (Bounds operation 2 6.0 2.51 2.46 with NFWT) 23.0 2.60 2.59 TBVOOS 100.0 1.41 90.0 1.44 (FFTR/FHOOS 50.0 1.66 included) > 65%F 50.0 1.93 1.80 (Bounds operation 26.0 2.36 2.25 with NFWT) 26.0 3.03 2.96 23.0 3.22 3.20 10 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.02. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 26 Table 11 Flow-Dependent MCPR f Limits 11 Core Flow ATRIUM 10XM

(% of rated)

MCPR f 0.0 1.55 31.0 1.55 60.0 1.47 80.0 1.30 100.0 1.30 107.0 1.30 11 Limits valid for all SCRAM insertion times, all core average exposure ranges, all EOOS scenarios, and both TLO & SLO.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 27 Table 12 AREVA Fuel Steady-State LHGR SS Limits Peak ATRIUM 10XM Pellet Exposure LHGR (GWd/MTU) (kW/ft) 0.0 15.1 6.0 14.1 18.9 14.1 54.0 10.6 74.4 5.4 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 28 Table 13 AREVA Fuel Power-Dependent LHGRFAC p Multipliers 12 NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM Condition (% rated) LHGRFACp Base Case Operation 100.0 1.00 90.0 1.00 50.0 1.00 > 65%F 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.51 0.53 23.0 0.49 0.50 TBVOOS 100.0 1.00 90.0 1.00 50.0 1.00 > 65%F 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.42 0.48 23.0 0.39 0.43 FHOOS 100.0 1.00 90.0 1.00 50.0 0.97 > 65%F 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.46 0.48 23.0 0.44 0.46 100.0 1.00 90.0 1.00 TBVOOS 50.0 0.96 and > 65%F FHOOS 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.39 0.44 23.0 0.37 0.40 12 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 29 Table 14 AREVA Fuel Power-Dependent LHGRFAC p Multipliers 13 TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM Condition (% rated) LHGRFACp Base Case Operation 100.0 1.00 90.0 1.00 50.0 1.00 > 65%F 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.51 0.53 23.0 0.49 0.50 TBVOOS 100.0 1.00 90.0 1.00 50.0 1.00 > 65%F 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.42 0.48 23.0 0.39 0.43 FHOOS 100.0 1.00 90.0 1.00 50.0 0.97 > 65%F 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.46 0.48 23.0 0.44 0.46 100.0 1.00 90.0 1.00 TBVOOS 50.0 0.96 and > 65%F FHOOS 50.0 0.89 0.95 26.0 0.63 0.77 26.0 0.39 0.44 23.0 0.37 0.40 13 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 30 Table 15 AREVA Fuel Power-Dependent LHGRFAC p Multipliers 14 NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM Condition (% rated) LHGRFACp Base Case 100.0 1.00 Operation 90.0 1.00 50.0 0.97 (FFTR/FHOOS

> 65%F included) 50.0 0.89 0.95 26.0 0.63 0.77 (Bounds operation 26.0 0.46 0.48 with NFWT) 23.0 0.44 0.46 TBVOOS 100.0 1.00 90.0 1.00 (FFTR/FHOOS 50.0 0.96 included) > 65%F 50.0 0.89 0.95 (Bounds operation 26.0 0.63 0.77 with NFWT) 26.0 0.39 0.44 23.0 0.37 0.40 14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 31 Table 16 AREVA Fuel Power-Dependent LHGRFAC p Multipliers 15 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM Condition (% rated) LHGRFACp Base Case 100.0 1.00 Operation 90.0 1.00 50.0 0.97 (FFTR/FHOOS

> 65%F included) 50.0 0.89 0.95 26.0 0.63 0.77 (Bounds operation 26.0 0.46 0.48 with NFWT) 23.0 0.44 0.46 TBVOOS 100.0 1.00 90.0 1.00 (FFTR/FHOOS 50.0 0.96 included) > 65%F 50.0 0.89 0.95 (Bounds operation 26.0 0.63 0.77 with NFWT) 26.0 0.39 0.44 23.0 0.37 0.40 15 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 32 Table 17 AREVA Fuel Flow-Dependent LHGRFAC f Multipliers 16 Core Flow ATRIUM 10XM

(% of rated)

LHGRFAC f 0.0 0.58 31.0 0.58 75.0 1.00 107.0 1.00 16 Multipliers valid for all SCRAM insertion times and all core average exposure ranges.

Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 1B21-2050 Rev 0 B1C22 Core Operating Limits Report, BNEI-0400-00 17 Rev. 0 Page 33 Table 18 AREVA Fuel Steady-State MAPLHGR SS Limits 17 , 18 Average Planar ATRIUM 10XM Exposure MAPLHGR (GWd/MTU) (kW/ft) 0.0 13.1 15.0 13.1 67.0 7.7 17 AREVA Fuel MAPLHGR limits do not have a power, flow, or EOOS dependency.

18 ATRIUM 10XM MAPLHGR limits must be adjusted by a 0.80 multiplier when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Figure 1Stability Option III Power/Flow Map This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3APRM STP ScramAPRM STP Rod Block10076.1980.479975.0480.479873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079

Reference:

0B21-1015, Revision 7 SLO Entry Rod Line0 10 20 30 40 50 60 70 80 90 100 110 120  % Core FlowScram Avoidance Region8458.4380.798357.3780.908256.3181.058155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70OPRM Enabled Region APRM S TP Scra m APRM STP Rod Bloc k Scram Avoidance Re g io n OPRM Enabled Re g io n Figure 2 Stability Option III Power/Flow Map

APRM STP ScramAPRMSTP Rod Block10076.1980.479975.0480.479873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3

Reference:

0B21-1015, Revision 7

Region A -Manual SCRAM Region B -Immediate Exit5% Buffer RegionSLO Entry Rod Line0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow8458.4380.798357.3780.908256.3181.058155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70OPRM Enabled RegionAPRM S TP Scra m APRM STP Rod Bloc k Re gion A -Manual SCRAM Re gion B -Immediate Exit 5% Bu ff er Re gion OPRM Enabled Re g io n Figure 3Stability Option III Power/Flow Map

APRM STP ScramAPRM STP Rod Block10076.1980.479975.0480.479873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3APRM STP ScramAPRM STP Rod Block10076.1980.479975.0480.47 9873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3

Reference:

0B21-1015, Revision 7

0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow 84 58.43 80.798357.3780.908256.3181.05 8155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70OPRM Enabled RegionScram Avoidance Region0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow 84 58.43 80.798357.3780.908256.3181.05 8155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70 APRM S TP Scra m APRM STP Rod Bl oc k OPRM Enabled Re g io n Scram Avoidance Re g io n Figure 4 Stability Option III Power/Flow Map

APRM STP ScramAPRM STP Rod Block10076.1980.479975.0480.479873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3

Reference:

0B21-1015, Revision 7

0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow 84 58.43 80.798357.3780.908256.3181.05 8155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70OPRM Enabled RegionRegion A -Manual SCRAM Region B -Immediate Exit5% Buffer Region APRM S TP Scra mAPRM STP Rod Bl oc k OPRM Enabled Re g io n Re gion A -Manual SCRAM Re gion B -Immediate Exit 5% Bu ff er Re g io n Figure 5Stability Option III Power/Flow Map

APRM STP ScramAPRM STP Rod Block10076.1980.479975.0480.479873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3

Reference:

0B21-1015, Revision 7

Scram Avoidance RegionSLO Entry Rod Line (SLO prohibited during FWTR)0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow8458.4380.798357.3780.908256.3181.058155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70OPRM Enabled Region APRM S TP Scra m APRM STP Rod Bloc k Scram Avoidance Re g io n OPRM Enabled Re g io n Figure 6 Stability Option III Power/Flow Map

APRM STP ScramAPRM STP Rod Block10076.1980.479975.0480.479873.8980.47 9772.7580.47 9671.6180.47 9570.4980.47 9469.3680.479368.2580.479267.1380.47 9166.0380.47 9064.9380.47 8963.8380.47 8862.7480.47 8761.6680.51 8660.5880.60 8559.5080.69 8458438079This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3

Reference:

0B21-1015, Revision 7

Region A -Manual SCRAM Region B -Immediate ExitSLO Entry Rod Line(SLO prohibited during FWTR)0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow8458.4380.798357.3780.908256.3181.058155.2581.21 8054.2081.36 7953.1681.51 7852.1281.67 7751.0881.82 7650.0581.98 7549.0282.13 7448.0082.29 7346.9882.44 7245.9682.60 7144.9582.75 7043.9482.91 6942.9483.06 6841.9483.22 6740.9583.37 6639.9683.52 6538.9783.68 6437.9983.83 6337.0183.99 6236.0484.146135.0684.306034.1084.45 5933.1384.61 5832.1784.70OPRM Enabled Region5% Buffer RegionAPRM S TP Scra m APRM STP Rod Block Re gion A -Manual SCRAM Re gion B -Immediate Exit OPRM Enabled Re g io n 5% Bu ff er Re g io n