RA-20-0091, Unit 1 Cycle 23 Core Operating Limits Report (COLR

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Unit 1 Cycle 23 Core Operating Limits Report (COLR
ML20074B085
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 03/14/2020
From: Salazar S
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0091
Download: ML20074B085 (50)
v • d • e


Text

Brunswick Nuclear Plant

( ~ DUKE 8470 River Rd SE ENERGY~ Southport, NC 28461 MAR 1 4 2020 Serial: RA-20-0091 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 1 Renewed Facility Operating License No. DPR-71 Docket No. 50-325 Unit 1 Cycle 23 Core Operating Limits Report (COLR)

Reference Letter from Bryan B. Wooten (Duke Energy) to NRC Document Control Desk, Unit 1 Cycle 22 Core Operating Limits Report (COLR), dated March 27, 2018.

Ladies and Gentlemen:

Enclosed is a copy of the Core Operating Limits Report (COLR) for Brunswick Steam Electric Plant (BSEP}, Unit 1 Cycle 23 operation . Duke Energy Progress, LLC (Duke Energy}, is providing the enclosed COLR in accordance with Brunswick Unit 1 Technical Specification 5.6.5.d. The enclosed COLR supersedes the report previously submitted by letter dated March 27, 2018 (i.e. , Reference).

This letter and the enclosed COLR do not contain any regulatory commitments.

Please refer any questions regarding this submittal to Mr. Stephen Yodersmith, Brunswick Regulatory Affairs, at (910) 832-2568.

Sincerely, Sabrina Salazar Manager - Nuclear Support Services Brunswick Steam Electric Plant

U.S. Nuclear Regulatory Commission Page 2 of 2

Enclosure:

Brunswick Unit 1, Cycle 23 Core Operating Limits Report cc (with enclosure):

U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Laura Dudes, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net

RA-20-0091 Enclosure Brunswick Unit 1, Cycle 23 Core Operating Limits Report

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 1 BRUNSWICK UNIT 1, CYCLE 23 CORE OPERATING LIMITS REPORT March 2020 Prepared by: Signed Electronically Peter Noel Brunswick Nuclear Design Reviewed by: Signed Electronically Steve Evans Brunswick Nuclear Design Site Inspection by: Signed Electronically Allen Butler Brunswick Reactor Engineering Approved by: Signed Electronically Robert St. Clair Manager, Brunswick Nuclear Design

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 2 LIST OF EFFECTIVE PAGES Page(s) Revision 1- 47 0 This document consists of 47 total pages.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 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 ..................................................................................................................................... 6 Nomenclature ..................................................................................................................................... 7 Introduction and Summary ................................................................................................................. 9 APLHGR Limits ................................................................................................................................ 10 MCPR Limits .................................................................................................................................... 10 LHGR Limits ..................................................................................................................................... 11 CDA Setpoints .................................................................................................................................. 11 RBM Setpoints ................................................................................................................................. 12 Equipment Out-of-Service ................................................................................................................ 13 Single Loop Operation ...................................................................................................................... 14 Inoperable Main Turbine Bypass System ......................................................................................... 14 Feedwater Temperature Reduction .................................................................................................. 15 References ....................................................................................................................................... 16

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 4 CAUTION 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 Title Page Table 1: RBM System Setpoints ................................................................................................... 18 Table 2: RBM Operability Requirements ...................................................................................... 19 Table 3.1: BSP Endpoints for Nominal Feedwater Temperature ..................................................... 20 Table 3.2: BSP Endpoints for Reduced Feedwater Temperature ................................................... 20 Table 3.3: ABSP Setpoints for the Scram Region .......................................................................... 20 Table 4: Exposure Basis for Brunswick Unit 1 Cycle 23 Transient Analysis ................................ 21 Table 5: Power-Dependent MCPRp Limits.................................................................................... 22 NSS Insertion Times - BOC to < NEOC Table 6: Power-Dependent MCPRp Limits.................................................................................... 23 ESS Insertion Times - BOC to < NEOC Table 7: Power-Dependent MCPRp Limits.................................................................................... 24 TSSS Insertion Times - BOC to < NEOC Table 8: Power-Dependent MCPRp Limits.................................................................................... 25 NSS Insertion Times - BOC to < EOCLB Table 9: Power-Dependent MCPRp Limits.................................................................................... 26 ESS Insertion Times - BOC to < EOCLB Table 10: Power-Dependent MCPRp Limits.................................................................................... 27 TSSS Insertion Times - BOC to < EOCLB Table 11: Power-Dependent MCPRp Limits.................................................................................... 28 NSS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 12: Power-Dependent MCPRp Limits.................................................................................... 29 ESS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 13: Power-Dependent MCPRp Limits.................................................................................... 30 TSSS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 14: Flow-Dependent MCPRf Limits ....................................................................................... 31 Table 15: Shallow Control Rods Withdrawal Position Limits .......................................................... 32 Table 16: Framatome Fuel Steady-State LHGRSS Limits ............................................................... 33 Table 17: Framatome Fuel Power-Dependent LHGRFACp Multipliers ........................................... 34 NSS Insertion Times - BOC to < EOCLB Table 18: Framatome Fuel Power-Dependent LHGRFACp Multipliers ........................................... 35 ESS Insertion Times - BOC to < EOCLB Table 19: Framatome Fuel Power-Dependent LHGRFACp Multipliers ........................................... 36 TSSS Insertion Times - BOC to < EOCLB

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 5 Table 20: Framatome Fuel Power-Dependent LHGRFACp Multipliers ........................................... 37 NSS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 21: Framatome Fuel Power-Dependent LHGRFACp Multipliers ........................................... 38 ESS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 22: Framatome Fuel Power-Dependent LHGRFACp Multipliers ........................................... 39 TSSS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 23: Framatome Fuel Flow-Dependent LHGRFACf Multipliers .............................................. 40 Table 24: Framatome Fuel Steady-State MAPLHGRSS Limits ....................................................... 41

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 6 CAUTION 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 Title or Description Page Figure 1: MELLLA+ Power/Flow Map ............................................................................................ 42 OPRM Operable, Two Loop Operation, 2923 MWt Figure 2: MELLLA+ Power/Flow Map ............................................................................................ 43 OPRM Inoperable, Two Loop Operation, 2923 MWt Figure 3: MELLLA+ Power/Flow Map ............................................................................................ 44 OPRM Operable, Single Loop Operation, 2923 MWt Figure 4: MELLLA+ Power/Flow Map ............................................................................................ 45 OPRM Inoperable, Single Loop Operation, 2923 MWt Figure 5: MELLLA+ Power/Flow Map ............................................................................................ 46 OPRM Operable, FWTR, 2923 MWt Figure 6: MELLLA+ Power/Flow Map ............................................................................................ 47 OPRM Inoperable, FWTR, 2923 MWt

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 7 NOMENCLATURE 2PT Two Recirculation Pump Trip W SLO Flow Uncertainty ABSP Automated Backup Stability Protection APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor (Subsystem)

ARTS APRM/RBM Technical Specification BEO-III Best-estimate Enhanced Option-III BOC Beginning of Cycle BSP Backup Stability Protection BWROG BWR Owners Group CAVEX Core Average Exposure CDA Confirmation Density Algorithm COLR Core Operating Limits Report CRWE Control Rod Withdrawal Error ECCS Emergency Core Cooling System 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 HFCL High Flow Control Line 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 LHGRSS Steady-State Maximum Linear Heat Generation Rate LHGRFAC Linear Heat Generation Rate Factor LHGRFACf Flow-Dependent Linear Heat Generation Rate Factor LHGRFACp Power-Dependent Linear Heat Generation Rate Factor LPRM Local Power Range Monitor (Subsystem)

LPSP Low Power Set Point LTSP Low Trip Set Point

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 8 NOMENCLATURE (continued)

MAPLHGR Maximum Average Planar Linear Heat Generation Rate MAPLHGRSS Steady-State Maximum Average Planar Linear Heat Generation Rate MAPFAC Maximum Average Planar Linear Heat Generation Rate Factor MAPFACf Flow-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFACp 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 MELLLA+ Maximum Extended Load Line Limit Analysis +

MEOD Maximum Extended Operating Domain MSIVIS Main Steam Isolation Valve In-Service MSIVOOS Main Steam Isolation Valve Out-of-Service N/A Not Applicable NCL Natural Circulation Line 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)

PRNM Power Range Neutron Monitoring (System)

RBM Rod Block Monitor (Subsystem)

RDF Rated Drive Flow RFWT Reduced Feedwater Temperature RPT Recirculation Pump Trip RTP Rated Thermal Power SAD Amplitude Discriminator Setpoint SLMCPR Safety Limit Minimum Critical Power Ratio SLO 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, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 9 CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.

Introduction and Summary The Brunswick Unit 1, Cycle 23 COLR provides values for the core operation limits and setpoints required by Technical Specifications (TS) 5.6.5.a.

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

(TS 5.6.5.b)

1. The Average Planar Linear Heat 1, 2, 6, 7,16, TS 3.2.1 Limiting Condition for Operation Generation Rate (APLHGR) for TS 3.2.1. 17, 26 (LCO) (APLHGR)

TS 3.4.1 LCO (Recirculation loops operating)

TS 3.7.6 LCO (Main Turbine Bypass out-of-service)

2. The Minimum Critical Power Ratio (MCPR) 1, 6, 7, 8, 9, TS 3.2.2 LCO (MCPR) for TS 3.2.2. 11, 12, 13, 19, TS 3.4.1 LCO (Recirculation loops 21, 22, 25 operating)

TS 3.7.6 LCO (Turbine bypass out-of-service)

3. The Linear Heat Generation Rate (LHGR) 3, 5, 6, 7, 8, 9, TS 3.2.3 LCO (LHGR) for TS 3.2.3. 12, 13, 20, 23, TS 3.4.1 LCO (Recirculation loops 24 operating)

TS 3.7.6 LCO (Turbine bypass out-of-service)

4. The Manual Backup Stability Protection 18, 19, 22 TS Table 3.3.1.1-1, Function 2.f (BSP) Scram Region (Region I), Manual (OPRM Upscale)

BSP Controlled Entry Region (Region II),

the modified Average Power Range TS 3.3.1.1, Condition I and J (Alternate Monitor (APRM) Simulated Thermal Power instability detection)

- High Scram setpoints used in the Automated BSP Scram Region, the BSP Boundary for TS 3.3.1.1.

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

Upscale Functions for TS 3.3.2.1.

The required core operating limits and setpoints listed in TS 5.6.5.a are presented in the COLR, have been determined using Nuclear Regulatory Commission (NRC) approved methodologies (COLR References 1 through 26) in accordance with TS 5.6.5.b, have considered all fuel types utilized in B1C23, 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 ranges including the stability ranges.

The generation of this COLR is documented in Reference 34 and is based on analysis results documented in References 31,32, 33, and 36.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 10 APLHGR Limits Steady-state MAPLHGRSS limits are provided for Framatome Fuel (Table 24). These steady-state MAPLHGRSS limits must be modified as follows:

  • 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 = MAPLHGRSS MAPLHGR LimitSLO = MAPLHGRSS x MAPFACSLO where MAPFACSLO = 0.80 for ATRIUM 10XM and where MAPFACSLO = 0.85 for ATRIUM 11 fuel Linear interpolation should be used to determine intermediate values between the values listed in the table.

MCPR Limits The MCPR limits presented in Tables 5 through 14 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 MCPRp limits are presented in Tables 5 through 13 while flow-dependent MCPRf limits are presented in Table 14.
  • Power-dependent MCPRP 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 Equipment Out-of-Service for a list of analyzed EOOS conditions. 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 MCPRp limits (Tables 5-13) 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 = (MCPRp, MCPRf)max MCPR LimitSLO = (MCPRp + 0.02, MCPRf)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. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 11 LHGR Limits Steady-state LHGRSS limits are provided for Framatome Fuel (Table 16). These steady-state LHGRSS limits must be modified as follows:

  • Framatome Fuel LHGR limits have a core power and core flow dependency. Framatome Fuel power-dependent LHGRFACp multipliers (Tables 17-22) and flow-dependent LHGRFACf multipliers (Table 23) must be used to modify the steady-state LHGRSS limits (Table 16) for off-rated conditions.
  • Framatome Fuel power-dependent LHGRFACp multipliers are dependent on CAVEX, SCRAM insertion speed, EOOS, fuel design, core flow and core thermal power. Values for the CAVEX breakpoints are provided in Table 4. See COLR section titled Equipment Out-of-Service for a list 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 = LHGRSS x (LHGRFACp, LHGRFACf)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. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.

The cycle-specific off-rated flow dependent LHGR set-down bounds those assumed in the MELLLA+ plant-specific ECCS-LOCA analyses.

CDA Setpoints Brunswick Unit 1 has implemented the Best-estimate Enhanced Option III (BEO-III) with the Confirmation Density Algorithm (CDA) stability solution using the Oscillation Power Range Monitor (OPRM) as described in References 19 and 22. The Detect and Suppress function of the BEO-III w/CDA solution based on the OPRM system relies on the CDA, which constitutes the licensing basis. The Backup Stability Protection (BSP) solution described in Reference 22 may be used by the plant in the event the OPRM Upscale function is declared inoperable.

The safety evaluation (Reference 30) concluded that the BEO-III w/CDA solution is acceptable subject to certain cycle-specific limitations and conditions (Reference 35). As described in Reference 33, these limitations and conditions are met for B1C23.

A reload BEO-III w/CDA evaluation has been performed in accordance with References 19 and 22. The MCPR limits presented in Tables 5 through 14 bound the minimum stability MCPR values determined for B1C23 in the reload evaluation. Analyses have shown that if shallow control blades (i.e. greater than Notch

36) are withdrawn, then the BEO-III acceptance criteria may not be met for ATRIUM 10XM fuel. Therefore, for B1C23 operation, control rods cannot be withdrawn further than their notch position specified in Table 15.

The SAD setpoint value of 1.10 is applicable to TLO and SLO.

Reference 22 describes two BSP options that are based on selected elements from three distinct constituents: BSP Manual Regions, BSP Boundary, and Automated BSP (ABSP) setpoints.

Reference 22 defines the BSP boundary as the MELLLA boundary. The Manual BSP region boundaries were validated for Brunswick Unit 1 Cycle 23 for nominal feedwater temperature operation and reduced feedwater temperature. The endpoints of the regions are defined in Table 3.1 and Table 3.2. The Manual

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 12 BSP region boundary endpoints are calculated with the Reference 18 methodology and connected using the Generic Shape Function (GSF), which is described in Reference 29.

The ABSP Average Power Range Monitor (APRM) Simulated Thermal Power (STP) setpoints associated with the ABSP Scram Region are determined for Cycle 23 and are defined in Table 3.3. These ABSP setpoints are applicable to both TLO and SLO as well as nominal and reduced feedwater temperature operation.

The Manual Backup Stability Protection (BSP) Regions I and II are documented on the Power/Flow maps as is the modified APRM Simulated Thermal Power (STP) high SCRAM setpoints and the BSP Boundary.

The power/flow maps (Figures 1-6) were validated for B1C23 based on Reference 33 using the Reference 22 methodology to facilitate operation under BEO-III w/CDA as implemented by Function 2.f of Table 3.3.1.1-1 and LCO Conditions I and J of Technical Specification 3.3.1.1. The generation of these maps is documented in Reference 32. All maps illustrate the region of the power/flow map above 23% RTP and below 75% drive flow (correlated to core flow) where the OPRM 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 there is increased probability the OPRM system may generate a scram to avoid an instability event. Figures 2, 4, and 6 support an inoperable OPRM and highlight the Manual Backup Stability Regions I and II, the modified APRM STP high SCRAM setpoints, and the BSP Boundary. 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-217345217345which 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.

RBM Setpoints 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 27). These setpoints will ensure the power-dependent MCPR limits will provide adequate protection against violation of the SLMCPR during a postulated CRWE event. Reference 31 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.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 13 Equipment Out-of-Service Brunswick Unit 1, Cycle 23 is analyzed for the following operating conditions with applicable MCPR, APLHGR and LHGR limits.

  • Base Case Operation
  • 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.
  • 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, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 14 Single Loop Operation Brunswick Unit 1, Cycle 23 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.

These power and flow limitations also apply when operating with jet pump loop flow mismatch conditions (LCO 3.4.1). The following must be considered when operating in SLO:

  • SLO is not permitted with RFWT (FHOOS/FFTR).
  • SLO is not permitted with MSIVOOS.
  • SLO is not permitted within the MELLLA+ operating domain.

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-217345217345which 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.
  • If OPRMs are inoperable in SLO, the expansion of the ABSP region results in power being restricted to 39% RTP as shown in Figure 4.

Inoperable Main Turbine Bypass System Brunswick Unit 1, Cycle 23 may operate with an inoperable Main Turbine Bypass System over the entire MEOD range and in the MELLLA+ domain for all cycle exposures 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:

  • Prior to reaching the EOCLB exposure breakpoint, operation with FWTR >10F and reactor power 23% RTP requires use of the combined TBVOOS/FHOOS limits.
  • TBVOOS operation coincident with FHOOS is supported using the combined TBVOOS/FHOOS limits.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 15 Feedwater Temperature Reduction Brunswick Unit 1, Cycle 23 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 - 10F. NFWT and its allowable variation were assumed in the development of the Base Case Operation limits. The FHOOS limits and FFTR/Coastdown limits were developed for a maximum feedwater temperature reduction of 110.3F. The following must be considered 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 >10F and reactor power 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 MELLLA+ Power/Flow Maps (Figures 5 and 6) must be used.
  • FHOOS operation coincident with TBVOOS is supported using the combined TBVOOS/FHOOS limits.
  • FWTR operation within the MELLLA+ operating domain is not allowed.
  • NFWT limits have not been conservatively adjusted to eliminate the need to use RFWT limits below 50% RTP.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 16 References 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 26.

1. NEDE-24011-P-A, "GESTAR II - General Electric Standard Application for Reactor Fuel," and US Supplement, Revision 15, September 2005.
2. XN-NF-81-58(P)(A) and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Revision 2, March 1984.
3. XN-NF-85-67(P)(A), Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Revision 1, September 1986.
4. EMF-85-74(P) Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Revision 0, February 1998.
5. ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs, Revision 1, May 1995.
6. XN-NF-80-19(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, March 1983.
7. XN-NF-80-19(P)(A) Volume 4, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Revision 1, June 1986.
8. EMF-2158(P)(A), Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Revision 0, October 1999.
9. XN-NF-80-19(P)(A) Volume 3, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX:

Thermal Limits Methodology Summary Description, Revision 2, January 1987.

10. ANP-10333P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA), Revision 0, March 2018.
11. ANP-10307PA, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, Revision 0, June 2011.
12. ANP-10300P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Revision 1, January 2018.
13. ANF-1358(P)(A), The Loss of Feedwater Heating Transient in Boiling Water Reactors, Revision 3, September 2005.
14. EMF-2209(P)(A), SPCB Critical Power Correlation, Revision 3, September 2009.
15. EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Revision 0, August 2000.
16. EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model, Revision 0, May 2001.
17. EMF-2292(P)(A), ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients, Revision 0, September 2000.
18. EMF-CC-074(P)(A) Volume 4, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Revision 0, August 2000.
19. ANP-3703P, BEO-III Analysis Methodology for Brunswick Using RAMONA5-FA, Revision 0, August 2018.
20. BAW-10247PA, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Revision 0, April 2008.
21. ANP-10298P-A, ACE/ATRIUM 10XM Critical Power Correlation, Revision 1, March 2014.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 17

22. DPC-NE-1009-P, Brunswick Nuclear Plant Implementation of Best-estimate Enhanced Option-III, Revision 0, September 2018
23. BAW-10247P-A, Supplement 2P-A, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods, Revision 0, August 2018
24. ANP-10340P-A, Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods, Revision 0, May 2018
25. ANP-10335P-A, ACE/ATRIUM 11 Critical Power Correlation, Revision 0, May 2018
26. ANP-10332P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios, Revision 0, March 2019.
27. NEDC-31654P, Maximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant, February 1989.
28. BNP Design Calculation 0B21-1104(P), Revision 2, MELLLA+ Integrated Safety Analysis Report, July 2019.
29. OG02-0119-260, Backup Stability Protection (BSP) for Inoperable Option III Solution, July 2002.
30. BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS.

299 AND 327 TO REVISE TECHNICAL SPECIFICATION 5.6.5b TO ALLOW APPLICATION OF ADVANCED FRAMATOME ATRIUM 11 FUEL METHODOLOGIES (EPID L-2018-LLA-0273).

31. BNP Design Calculation 1C51-0001, Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (1-C51-APRM-1 through 4 Loops and 1-C51 RBM-A and B Loops), Revision 4, September 2018.
32. BNP Design Calculation 0B21-2045, BNP Power/Flow Maps for MELLLA+, Revision 2, January 2020.
33. ANP-3808P, Brunswick Unit 1 Cycle 23 Reload Safety Analysis, Revision 0, October 2019.
34. BNP Design Calculation 1B21-2080, Preparation of the B1C23 Core Operating Limits Report, Revision 0, March 2020.
35. NRC E-mail Capture, Request for Additional Information - Brunswick ATRIUM 11 LAR, (ADAMS Accession Number ML19283C829), October 9, 2019.
36. Framatome EIR FS1-0041952, Revision 1.0, Brunswick Unit 1 Cycle 23 RSAR Supplement for AUTOSR5BDK Error, March 2020.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 18 Table 1 RBM System Setpoints1 Setpoint a Setpoint Value Allowable Value Lower Power Setpoint (LPSPb) < 27.7 < 29.0 Intermediate Power Setpoint (IPSPb) < 62.7 < 64.0 High Power Setpoint (HPSPb) < 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 (td2) 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, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 19 Table 2 RBM Operability Requirements2 IF the following conditions are met, THEN RBM Not Required Operable Thermal Power ATRIUM 10XM ATRIUM 11

(% rated) MCPR MCPR 29% and < 90% 1.59 TLO 1.49 TLO 1.62 SLO 1.52 SLO 90% 1.49 TLO 1.42 TLO 2

Requirements valid for all fuel designs, all SCRAM insertion times and all core average exposure ranges.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 20 Table 3.1 BSP Endpoints for Nominal Feedwater Temperature3,4 Power Flow Endpoint Definition

(%) (%)

Scram Region Boundary, A1 57.0 40.6 HFCL Scram Region Boundary, B1 42.0 31.7 NCL Controlled Entry Region A2 64.5 50.0 Boundary, HFCL Controlled Entry Region B2 28.9 31.9 Boundary, NCL Table 3.2 BSP Endpoints for Reduced Feedwater Temperature3,4 Power Flow Endpoint Definition

(%) (%)

Scram Region Boundary, A1 65.9 51.8 HFCL Scram Region Boundary, B1 36.5 31.9 NCL Controlled Entry Region A2 69.8 56.8 Boundary, HFCL Controlled Entry Region B2 28.9 31.9 Boundary, NCL Table 3.3 ABSP Setpoints for the Scram Region3,5 Parameter Symbol Value Slope of ABSP APRM flow-biased trip mTRIP 2.00 %RTP/%RDF linear segment.

ABSP APRM flow-biased trip setpoint power intercept. Constant Power Line for PBSP-TRIP 42.0 %RTP Trip from zero Drive Flow to Flow Breakpoint value.

ABSP APRM flow-biased trip setpoint drive WBSP-TRIP 37.5 %RDF flow intercept. Constant Flow Line for Trip.

Flow Breakpoint value WBSP-BREAK 25.0 %RDF 3

These tables are referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1) and 5.6.5.a.4.

4 The BSP Boundary for Nominal and Reduced Feedwater Temperature is defined by the MELLLA boundary line and extends from the natural circulation boundary to rated power.

5 When in SLO the ABSP STP Scram is modified by the applied SLO W as shown in Figure 4.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 21 Table 4 Exposure Basis6 for Brunswick Unit 1 Cycle 23 Transient Analysis Core Average Exposure (MWd/MTU) Comments Breakpoint for exposure dependent MCPRp 26,008 limits (NEOC)

Design basis rod patterns to EOFP + 15 35,829 EFPD (EOCLB)

End of cycle with FFTR/Coastdown -

37,355 Maximum Core Exposure (MCE) 6 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, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 22 Table 5 Power-Dependent MCPRp Limits7,8 NSS Insertion Times BOC to < NEOC EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.63 Base

> 65%F 65%F > 65%F 65%F case 50.0 1.89 1.79 1.90 1.68 operation 26.0 2.26 2.09 2.20 2.01 26.0 2.33 2.28 2.32 2.22 23.0 2.44 2.45 2.33 2.34 100.0 1.37 1.39 90.0 1.41 1.43 50.0 1.72 1.76

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.89 1.79 1.90 1.69 26.0 2.26 2.09 2.20 2.03 26.0 3.24 3.25 2.98 2.99 23.0 3.31 3.32 3.02 3.03 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.67

> 65%F 65%F > 65%F 65%F FHOOS 50.0 1.89 1.79 1.90 1.68 26.0 2.26 2.09 2.20 2.01 26.0 2.45 2.35 2.40 2.23 23.0 2.57 2.50 2.48 2.40 100.0 1.40 1.42 90.0 1.43 1.46 50.0 1.72 1.79 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.89 1.79 1.91 1.70 26.0 2.26 2.09 2.25 2.05 26.0 3.27 3.28 3.12 3.13 23.0 3.40 3.41 3.12 3.13 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.

FHOOS not permitted in the MELLLA+ domain.

8 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 23 Table 6 Power-Dependent MCPRp Limits9,10 ESS Insertion Times BOC to < NEOC EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.63 Base

> 65%F 65%F > 65%F 65%F case 50.0 1.89 1.79 1.90 1.68 operation 26.0 2.26 2.09 2.20 2.01 26.0 2.33 2.28 2.32 2.22 23.0 2.44 2.45 2.33 2.34 100.0 1.37 1.39 90.0 1.41 1.43 50.0 1.72 1.76

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.89 1.79 1.90 1.72 26.0 2.26 2.09 2.20 2.03 26.0 3.24 3.25 2.98 2.99 23.0 3.31 3.32 3.02 3.03 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.67

> 65%F 65%F > 65%F 65%F FHOOS 50.0 1.89 1.79 1.90 1.68 26.0 2.26 2.09 2.20 2.01 26.0 2.45 2.35 2.40 2.23 23.0 2.57 2.50 2.48 2.40 100.0 1.44 1.44 90.0 1.45 1.47 50.0 1.74 1.80 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.91 1.81 1.92 1.75 26.0 2.28 2.11 2.26 2.06 26.0 3.29 3.30 3.13 3.14 23.0 3.42 3.43 3.13 3.14 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.

FHOOS not permitted in the MELLLA+ domain.

10 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 24 Table 7 Power-Dependent MCPRp Limits11,12 TSSS Insertion Times BOC to < NEOC EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.46 1.44 90.0 1.47 1.47 50.0 1.75 1.75 Base

> 65%F 65%F > 65%F 65%F case 50.0 1.92 1.82 1.92 1.78 operation 26.0 2.29 2.12 2.22 2.03 26.0 2.36 2.31 2.34 2.24 23.0 2.47 2.48 2.35 2.36 100.0 1.52 1.50 90.0 1.53 1.54 50.0 1.78 1.85

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.95 1.85 1.95 1.89 26.0 2.32 2.15 2.25 2.20 26.0 3.30 3.31 3.03 3.04 23.0 3.37 3.38 3.07 3.08 100.0 1.46 1.44 90.0 1.47 1.47 50.0 1.75 1.76

> 65%F 65%F > 65%F 65%F FHOOS 50.0 1.92 1.82 1.92 1.78 26.0 2.29 2.12 2.22 2.03 26.0 2.48 2.38 2.42 2.25 23.0 2.60 2.53 2.50 2.42 100.0 1.52 1.56 90.0 1.56 1.60 50.0 1.80 1.95 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.95 1.85 1.98 1.92 26.0 2.32 2.15 2.50 2.28 26.0 3.33 3.34 3.19 3.20 23.0 3.46 3.47 3.19 3.20 11 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.

FHOOS not permitted in the MELLLA+ domain.

12 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 25 Table 8 Power-Dependent MCPRp Limits13,14 NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.40 1.40 90.0 1.44 1.43 50.0 1.75 1.66 Base

> 65%F 65%F > 65%F 65%F case 50.0 1.89 1.79 1.90 1.69 operation 26.0 2.26 2.09 2.20 2.01 26.0 2.33 2.28 2.32 2.22 23.0 2.44 2.45 2.33 2.34 100.0 1.46 1.48 90.0 1.49 1.52 50.0 1.78 1.83

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.92 1.82 1.94 1.76 26.0 2.29 2.12 2.24 2.07 26.0 3.27 3.28 3.02 3.03 23.0 3.34 3.35 3.06 3.07 100.0 1.40 1.40 90.0 1.44 1.43 50.0 1.75 1.70

> 65%F 65%F > 65%F 65%F FHOOS 50.0 1.89 1.79 1.90 1.69 26.0 2.26 2.09 2.20 2.01 26.0 2.45 2.35 2.40 2.23 23.0 2.57 2.50 2.48 2.40 100.0 1.48 1.50 90.0 1.51 1.53 50.0 1.79 1.86 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.93 1.83 1.95 1.78 26.0 2.30 2.13 2.29 2.09 26.0 3.31 3.32 3.16 3.17 23.0 3.44 3.45 3.16 3.17 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. 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.

FHOOS not permitted in the MELLLA+ domain.

14 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 26 Table 9 Power-Dependent MCPRp Limits15,16 ESS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM MCPRp ATRIUM 11 Condition (% rated) MCPRp 100.0 1.40 1.42 90.0 1.44 1.44 50.0 1.75 1.67 Base

> 65%F 65%F > 65%F 65%F case 50.0 1.89 1.79 1.91 1.70 operation 26.0 2.26 2.09 2.21 2.02 26.0 2.33 2.28 2.33 2.23 23.0 2.44 2.45 2.34 2.35 100.0 1.48 1.50 90.0 1.50 1.53 50.0 1.79 1.84

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.93 1.83 1.95 1.77 26.0 2.30 2.13 2.25 2.08 26.0 3.28 3.29 3.03 3.04 23.0 3.35 3.36 3.07 3.08 100.0 1.40 1.42 90.0 1.44 1.44 50.0 1.75 1.71

> 65%F 65%F > 65%F 65%F FHOOS 50.0 1.89 1.79 1.91 1.70 26.0 2.26 2.09 2.21 2.02 26.0 2.45 2.35 2.41 2.24 23.0 2.57 2.50 2.49 2.41 100.0 1.48 1.52 90.0 1.51 1.54 50.0 1.79 1.87 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.93 1.83 1.96 1.79 26.0 2.30 2.13 2.30 2.10 26.0 3.31 3.32 3.17 3.18 23.0 3.44 3.45 3.17 3.18 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. 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.

FHOOS not permitted in the MELLLA+ domain.

16 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 27 Table 10 Power-Dependent MCPRp Limits17,18 TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.58 1.60 90.0 1.59 1.61 50.0 1.84 1.86 Base

> 65%F 65%F > 65%F 65%F case 50.0 1.98 1.88 2.00 1.86 operation 26.0 2.35 2.18 2.30 2.11 26.0 2.42 2.37 2.42 2.32 23.0 2.53 2.54 2.43 2.44 100.0 1.62 1.66 90.0 1.63 1.67 50.0 1.86 1.98

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 2.00 1.90 2.03 1.97 26.0 2.37 2.20 2.33 2.28 26.0 3.35 3.36 3.11 3.12 23.0 3.42 3.43 3.15 3.16 100.0 1.58 1.60 90.0 1.59 1.61 50.0 1.84 1.87

> 65%F 65%F > 65%F 65%F FHOOS 50.0 1.98 1.88 2.00 1.86 26.0 2.35 2.18 2.30 2.11 26.0 2.54 2.44 2.50 2.33 23.0 2.66 2.59 2.58 2.50 100.0 1.62 1.66 90.0 1.64 1.68 50.0 1.88 2.03 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 2.00 1.90 2.03 1.97 26.0 2.37 2.20 2.55 2.33 26.0 3.38 3.39 3.24 3.25 23.0 3.51 3.52 3.24 3.25 17 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.

FHOOS not permitted in the MELLLA+ domain.

18 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 28 Table 11 Power-Dependent MCPRp Limits19,20 NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.40 1.40 Base case 90.0 1.44 1.43 Operation 50.0 1.75 1.70

> 65%F 65%F > 65%F 65%F (FFTR/FHOOS 50.0 1.89 1.79 1.90 1.69 Included) 26.0 2.26 2.09 2.20 2.01 26.0 2.45 2.35 2.40 2.23 (Bounds 23.0 2.57 2.50 2.48 2.40 operation with NFWT) 100.0 1.50 1.50 TBVOOS 90.0 1.52 1.53 50.0 1.80 1.86 (FFTR/FHOOS > 65%F 65%F > 65%F 65%F Included) 50.0 1.94 1.84 1.95 1.78 26.0 2.31 2.14 2.29 2.09 (Bounds 26.0 3.32 3.33 3.16 3.17 operation with 23.0 3.45 3.46 3.16 3.17 NFWT) 19 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.

FHOOS not permitted in the MELLLA+ domain.

20 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 29 Table 12 Power-Dependent MCPRp Limits21,22 ESS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.42 1.42 Base case 90.0 1.45 1.44 Operation 50.0 1.76 1.71

> 65%F 65%F > 65%F 65%F (FFTR/FHOOS 50.0 1.90 1.80 1.91 1.70 Included) 26.0 2.27 2.10 2.21 2.02 26.0 2.46 2.36 2.41 2.24 (Bounds 23.0 2.58 2.51 2.49 2.41 operation with NFWT) 100.0 1.50 1.52 TBVOOS 90.0 1.52 1.54 50.0 1.80 1.87 (FFTR/FHOOS > 65%F 65%F > 65%F 65%F Included) 50.0 1.94 1.84 1.96 1.79 26.0 2.31 2.14 2.30 2.10 (Bounds 26.0 3.32 3.33 3.17 3.18 operation with 23.0 3.45 3.46 3.17 3.18 NFWT) 21 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.

FHOOS not permitted in the MELLLA+ domain.

22 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 30 Table 13 Power-Dependent MCPRp Limits23,24 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.64 1.66 Base case 90.0 1.65 1.67 Operation 50.0 1.87 1.90

> 65%F 65%F > 65%F 65%F (FFTR/FHOOS 50.0 2.01 1.91 2.03 1.89 Included) 26.0 2.38 2.21 2.33 2.14 26.0 2.57 2.47 2.53 2.36 (Bounds 23.0 2.69 2.62 2.61 2.53 operation with NFWT) 100.0 1.70 1.72 TBVOOS 90.0 1.71 1.73 50.0 1.92 2.06 (FFTR/FHOOS > 65%F 65%F > 65%F 65%F Included) 50.0 2.04 1.94 2.06 2.00 26.0 2.41 2.24 2.58 2.36 (Bounds 26.0 3.42 3.43 3.27 3.28 operation with 23.0 3.55 3.56 3.27 3.28 NFWT) 23 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.

FHOOS not permitted in the MELLLA+ domain.

24 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 31 Table 14 Flow-Dependent MCPRf Limits25,26 Core Flow ATRIUM 10XM ATRIUM 11

(% of rated) MCPRf MCPRf 0.0 1.66 1.57 31.0 1.66 1.57 60.0 1.50 --

75.0 -- --

77.0 -- 1.30 81.0 1.30 1.30 100.0 1.30 1.30 107.0 1.30 1.30 25 Limits valid for all SCRAM insertion times, all core average exposure ranges, all EOOS scenarios, and both TLO &

SLO.

26 Limits are only valid if control rods are no further withdrawn than their position specified in Table 15.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 32 Table 1527 Shallow Control Rods Withdrawal Position Limits Sequence Control Rods Maximum Withdrawn Position 1st A2 18-27 40 34-27 40 26-35 40 26-19 40 1st B2 22-11 40 22-27 40 22-43 40 30-11 40 30-27 40 30-43 40 1st A1 22-23 40 30-31 40 14-39 42 14-15 42 38-39 42 38-15 42 1st B1 10-31 40 10-23 40 18-39 40 18-15 40 34-39 40 34-15 40 42-31 40 42-23 40 2nd A2 18-27 40 34-27 40 26-35 40 26-19 40 Thereafter No restrictions 27 If rods are withdrawn further than the position identified above, LCO 3.2.2 must be entered.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 33 Table 16 Framatome Fuel Steady-State LHGRSS Limits28 Peak ATRIUM 10XM ATRIUM 11 Pellet Exposure LHGR LHGR (GWd/MTU) (kW/ft) (kW/ft) 0.0 14.1 13.6 6.0 14.1 --

18.9 14.1 --

21.0 -- 13.6 53.0 -- 10.2 54.0 10.6 --

74.4 5.4 --

80.0 N/A 3.5 28 indicates that the fuel limit has no breakpoint at this exposure.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 34 Table 17 Framatome Fuel Power-Dependent LHGRFACp Multipliers29 NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.96 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.49 0.51 0.45 0.48 23.0 0.49 0.51 0.45 0.48 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.92

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.45 0.51 0.41 0.48 23.0 0.41 0.50 0.37 0.45 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.90

> 65%F 65%F > 65%F 65%F FHOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.98 90.0 1.00 0.97 50.0 0.96 0.87 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42 29 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. FHOOS not permitted in the MELLLA+

domain.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 35 Table 18 Framatome Fuel Power-Dependent LHGRFACp Multipliers30 ESS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.96 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.49 0.51 0.45 0.48 23.0 0.49 0.51 0.45 0.48 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.92

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.45 0.51 0.41 0.48 23.0 0.41 0.50 0.37 0.45 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.90

> 65%F 65%F > 65%F 65%F FHOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.97 90.0 1.00 0.97 50.0 0.96 0.87 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42 30 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. FHOOS not permitted in the MELLLA+

domain.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 36 Table 19 Framatome Fuel Power-Dependent LHGRFACp Multipliers31 TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 -

50.0 1.00 0.93 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.49 0.51 0.45 0.48 23.0 0.49 0.51 0.45 0.48 100.0 1.00 0.99 90.0 1.00 -

50.0 0.95 0.85

> 65%F 65%F > 65%F 65%F TBVOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.45 0.51 0.41 0.48 23.0 0.41 0.50 0.37 0.45 100.0 1.00 0.96 90.0 1.00 -

50.0 0.96 0.88

> 65%F 65%F > 65%F 65%F FHOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.94 90.0 1.00 -

50.0 0.90 0.82 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 0.90 1.00 0.82 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42 31 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. FHOOS not permitted in the MELLLA+

domain.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 37 Table 20 Framatome Fuel Power-Dependent LHGRFACp Multipliers32 NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 Base case 90.0 1.00 1.00 operation 50.0 1.00 0.90 (FFTR/FHOOS included) > 65%F 65%F > 65%F 65%F 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 (Bounds operation 26.0 0.47 0.49 0.43 0.46 with NFWT) 23.0 0.46 0.49 0.42 0.46 100.0 1.00 0.98 TBVOOS 90.0 1.00 0.97 50.0 0.96 0.87 (FFTR/FHOOS included)

> 65%F 65%F > 65%F 65%F 50.0 0.92 1.00 0.85 0.93 (Bounds operation 26.0 0.75 0.86 0.67 0.79 with NFWT) 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42 32 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. FHOOS not permitted in the MELLLA+

domain.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 38 Table 21 Framatome Fuel Power-Dependent LHGRFACp Multipliers33 ESS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 Base case 90.0 1.00 1.00 operation 50.0 1.00 0.90 (FFTR/FHOOS included) > 65%F 65%F > 65%F 65%F 50.0 0.92 1.00 0.85 0.93 (Bounds 26.0 0.75 0.86 0.67 0.79 operation with 26.0 0.47 0.49 0.43 0.46 NFWT) 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.97 TBVOOS 90.0 1.00 0.97 50.0 0.96 0.87 (FFTR/FHOOS included)

> 65%F 65%F > 65%F 65%F (Bounds operation with 50.0 0.92 1.00 0.85 0.93 NFWT) 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42 33 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. FHOOS not permitted in the MELLLA+

domain.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 39 Table 22 Framatome Fuel Power-Dependent LHGRFACp Multipliers34 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 0.96 Base case 90.0 1.00 -

operation 50.0 0.96 0.88 (FFTR/FHOOS included) > 65%F 65%F > 65%F 65%F 50.0 0.92 1.00 0.85 0.93 (Bounds 26.0 0.75 0.86 0.67 0.79 operation with 26.0 0.47 0.49 0.43 0.46 NFWT) 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.94 TBVOOS 90.0 1.00 -

50.0 0.90 0.82

> 65%F 65%F > 65%F 65%F (FFTR/FHOOS included) 50.0 0.90 1.00 0.82 0.93 26.0 0.75 0.86 0.67 0.79 (Bounds 26.0 0.42 0.49 0.37 0.46 operation with 23.0 0.38 0.47 0.34 0.42 NFWT) 34 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. FHOOS not permitted in the MELLLA+

domain.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 40 Table 23 Framatome Fuel Flow-Dependent LHGRFACf Multipliers35 Core Flow ATRIUM 10XM and

(% of rated) ATRIUM 11 LHGRFACf 0.0 0.52 31.0 0.52 75.0 1.00 107.0 1.00 35 Multipliers valid for all SCRAM insertion times and all core average exposure ranges.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 41 Table 24 Framatome Fuel Steady-State MAPLHGRSS Limits36, 37 Average Planar ATRIUM 10XM ATRIUM 11 Exposure MAPLHGR MAPLHGR (GWd/MTU) (kW/ft) (kW/ft) 0.0 13.1 12.0 15.0 13.1 --

20.0 -- 12.0 60.0 -- 9.0 67.0 7.7 --

69.0 N/A 7.2 36 Framatome Fuel MAPLHGR limits do not have a power, flow, or EOOS dependency.

37 ATRIUM 10XM MAPLHGR limits must be adjusted by a 0.80 multiplier when in SLO. ATRIUM 11 MAPLHGR limits must be adjusted by a 0.85 multiplier when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 42 Figure 1 MELLLA+ Power/Flow Map OPRM Operable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 l 120.0 1

111111111 Minimum Minimum Maximum (MELLLA) (MELLLA+) (ICF)

APRM STP Scram T I I Ill 1-,~ I I I I T 111 I 111 11 110.0 MELLLA+ Line I

Power Core Flow Core Flow Core Flow

% Mlbs/hr Mlbs/hr Mlbs/hr APRM STP Rod Block I - - - -- - -

II ~-

,I 100 76.19 65.45 80.47

~ '-

100.0 I 99 98 75.04 73.89 64.42 63.39 80.47 80.47 l l 97 72.75 62.35 80.47 I I 96 71.61 61.32 80.47 95 70.49 60.29 80.47 90.0 I'

'I 94 69.36 59.26 80.47 93 68.25 58.22 80.47 I 92 67.13 57.19 80.47 91 66.03 56.16 80.47 80.0 ' 90 64.93 55.13 80.47 70.0

~ ---r

--.. J/ 89 88 87 86 63.83 62.74 61.66 60.58 54.10 53.06 52.03 51.00 80.47 80.47 80.51 80.60 I :lY I

[ 85 84 59.50 58.43 49.97 48.94 80.69 80.79

% Power 83 57.37 47.90 80.90 60.0 . ,/ I 82 81 80 79 56.31 55.25 54.20 53.16 46.87 45.84 44.81 43.77 81.05 81.21 81.36 81.51 l

R 50.0 MELLLA Line and ----SLO-------- 78 52.12 42.74 81.67 40.0 11 BSP Boundary I I I I l 1 1 1 11 11 I /, J~ . ------ Entry Rod Line I e C g F i 77 76 75 74 51.08 50.05 49.02 48.00 81.82 81.98 82.13 82.29 Scram Avoidance Region ..,1r->-~

-~ t T I++

o n

73 72 71 70 46.98 45.96 44.95 43.94 82.44 82.60 82.75 82.91 30.0 --- --,- ---,-- I' 69 42.94 --- 83.06 I

WI 68 41.94 --- 83.22 l 67 40.95 --- 83.37

- 66 39.96 --- 83.52 20.0 T

""' N I 65 38.97 --- 83.68 WI 64 37.99 --- 83.83 63 37.01 --- 83.99 Natural OPRM Enabled Region 62 36.04 --- 84.14 10.0 Circulation 11 " 61 60 35.06 34.10 84.30 84.45 Line

~ 35% Approximate 111111111 59 33.13 --- 84.61 0.0 I Minimum Pump Speed l Minimum Power Line l 58 32.17 --- 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow

Reference:

0B21-2045, Revision 2

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 43 Figure 2 MELLLA+ Power/Flow Map OPRM Inoperable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum Minimum Maximum (MELLLA) (MELLLA+) (ICF)

APRM STP Scram Core Core Core 110.0 MELLLA+ Line Power Flow Flow Flow

% Mlbs/hr Mlbs/hr Mlbs/hr APRM STP Rod Block 100 76.19 65.45 80.47 100.0 99 98 75.04 73.89 64.42 63.39 80.47 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 90.0 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 ABSP STP Scram 91 66.03 56.16 80.47 80.0 90 64.93 55.13 80.47 89 63.83 54.10 80.47 ABSP STP Rod Block 88 62.74 53.06 80.47 87 61.66 52.03 80.51 70.0 86 85 60.58 59.50 51.00 49.97 80.60 80.69 84 58.43 48.94 80.79

% Power 83 57.37 47.90 80.90 60.0 82 81 56.31 55.25 46.87 45.84 81.05 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 R

50.0 MELLLA Line and I e 78 77 52.12 51.08 42.74 81.67 81.82 BSP Boundary SLO Entry 76 50.05 --- 81.98 Rod Line C g 75 49.02 --- 82.13 74 48.00 --- 82.29 40.0 Region I - Manual Scram F i 73 46.98 --- 82.44 o 72 45.96 --- 82.60 71 44.95 --- 82.75 Region II - Controlled Entry n 70 43.94 --- 82.91 30.0 69 42.94 --- 83.06 68 41.94 --- 83.22 Operator Awareness 67 40.95 --- 83.37 66 39.96 --- 83.52 20.0 65 64 38.97 37.99 83.68 83.83 63 37.01 --- 83.99 Natural OPRM Enabled Region 62 36.04 --- 84.14 10.0 Circulation 61 60 35.06 34.10 84.30 84.45 Line 35% Approximate 59 33.13 --- 84.61 Minimum Pump Speed Minimum Power Line 58 32.17 --- 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow

Reference:

0B21-2045, Revision 2

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 44 Figure 3 MELLLA+ Power/Flow Map OPRM Operable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum Minimum Maximum MELLLA+ Line (MELLLA+ Operations APRM STP Scram (MELLLA) (MELLLA+) (ICF)

Core Core Core 110.0 prohibited during SLO) Power Flow Flow Flow

% Mlbs/hr Mlbs/hr Mlbs/hr 100 76.19 65.45 80.47 100.0 99 98 75.04 73.89 64.42 63.39 80.47 80.47 APRM 97 72.75 62.35 80.47 96 71.61 61.32 80.47 STP Rod 95 70.49 60.29 80.47 90.0 Block 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 80.0 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 70.0 86 85 60.58 59.50 51.00 49.97 80.60 80.69 84 58.43 48.94 80.79

% Power 83 57.37 47.90 80.90 60.0 82 81 56.31 55.25 46.87 45.84 81.05 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 R

50.0 MELLLA Line and I e 78 77 52.12 51.08 42.74 81.67 81.82 BSP Boundary 76 50.05 --- 81.98 C g 75 49.02 --- 82.13 74 48.00 --- 82.29 40.0 F i 73 46.98 --- 82.44 o 72 45.96 --- 82.60 Scram Avoidance Region 71 44.95 --- 82.75 n 70 43.94 --- 82.91 30.0 69 42.94 --- 83.06 68 41.94 --- 83.22 67 40.95 --- 83.37 66 39.96 --- 83.52 20.0 45 Mlb/hr Max Core Flow 65 64 38.97 37.99 83.68 83.83 63 37.01 --- 83.99 Natural OPRM Enabled Region 62 36.04 --- 84.14 10.0 Circulation 61 60 35.06 34.10 84.30 84.45 Line 35% Approximate 59 33.13 --- 84.61 Minimum Pump Speed Minimum Power Line 58 32.17 --- 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow

Reference:

0B21-2045, Revision 2

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 45 Figure 4 MELLLA+ Power/Flow Map OPRM Inoperable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum Minimum Maximum MELLLA+ Line (MELLLA+ Operations APRM STP Scram (MELLLA) (MELLLA+) (ICF)

Core Core Core 110.0 prohibited during SLO) Power Flow Flow Flow

% Mlbs/hr Mlbs/hr Mlbs/hr 100 76.19 65.45 80.47 100.0 99 98 75.04 73.89 64.42 63.39 80.47 80.47 APRM 97 72.75 62.35 80.47 96 71.61 61.32 80.47 STP Rod 95 70.49 60.29 80.47 90.0 Block 94 69.36 59.26 80.47 93 68.25 58.22 80.47 ABSP STP Scram 92 67.13 57.19 80.47 91 66.03 56.16 80.47 80.0 90 64.93 55.13 80.47 89 63.83 54.10 80.47 ABSP STP Rod Block 88 62.74 53.06 80.47 87 61.66 52.03 80.51 70.0 86 85 60.58 59.50 51.00 49.97 80.60 80.69 84 58.43 48.94 80.79

% Power 83 57.37 47.90 80.90 60.0 82 81 56.31 55.25 46.87 45.84 81.05 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 R

50.0 MELLLA Line and I e 78 77 52.12 51.08 42.74 81.67 81.82 BSP Boundary 76 50.05 --- 81.98 C g 75 49.02 --- 82.13 74 48.00 --- 82.29 40.0 Region I - Manual Scram F i 73 46.98 --- 82.44 o 72 45.96 --- 82.60 71 44.95 --- 82.75 Region II - Controlled Entry n 70 43.94 --- 82.91 30.0 69 42.94 --- 83.06 68 41.94 --- 83.22 Operator Awareness 67 40.95 --- 83.37 66 39.96 --- 83.52 20.0 45 Mlb/hr Max Core Flow 65 64 38.97 37.99 83.68 83.83 63 37.01 --- 83.99 Natural OPRM Enabled Region 62 36.04 --- 84.14 10.0 Circulation 61 60 35.06 34.10 84.30 84.45 Line 35% Approximate 59 33.13 --- 84.61 Minimum Pump Speed Minimum Power Line 58 32.17 --- 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow

Reference:

0B21-2045, Revision 2

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 46 Figure 5 MELLLA+ Power/Flow Map OPRM Operable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum Minimum Maximum MELLLA+ Line (MELLLA) (MELLLA+) (ICF)

(MELLLA+ Operations APRM STP Scram 110.0 prohibited during FWTR) Power Core Flow Core Flow Core Flow

% Mlbs/hr Mlbs/hr Mlbs/hr APRM STP Rod Block 100 76.19 65.45 80.47 100.0 99 98 75.04 73.89 64.42 63.39 80.47 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 90.0 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 80.0 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 70.0 86 85 60.58 59.50 51.00 49.97 80.60 80.69 84 58.43 48.94 80.79

% Power 83 57.37 47.90 80.90 60.0 82 81 56.31 55.25 46.87 45.84 81.05 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 R

50.0 MELLLA Line and I e 78 77 52.12 51.08 42.74 81.67 81.82 BSP Boundary SLO Entry 76 50.05 --- 81.98 Rod Line C g 75 49.02 --- 82.13 74 48.00 --- 82.29 40.0 (SLO prohibited F i 73 46.98 --- 82.44 during FWTR) o 72 45.96 --- 82.60 Scram Avoidance Region 71 44.95 --- 82.75 n 70 43.94 --- 82.91 30.0 69 42.94 --- 83.06 68 41.94 --- 83.22 67 40.95 --- 83.37 66 39.96 --- 83.52 20.0 65 64 38.97 37.99 83.68 83.83 63 37.01 --- 83.99 Natural OPRM Enabled Region 62 36.04 --- 84.14 10.0 Circulation 61 60 35.06 34.10 84.30 84.45 Line 35% Approximate 59 33.13 --- 84.61 Minimum Pump Speed Minimum Power Line 58 32.17 --- 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow

Reference:

0B21-2045, Revision 2

Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-2080 Rev 0 B1C23 Core Operating Limits Report, BNEI-0400-0033 Rev. 0 Page 47 Figure 6 MELLLA+ Power/Flow Map OPRM Inoperable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum Minimum Maximum MELLLA+ Line (MELLLA) (MELLLA+) (ICF)

(MELLLA+ Operations APRM STP Scram Core Core Core 110.0 prohibited during FWTR) Power Flow Flow Flow

% Mlbs/hr Mlbs/hr Mlbs/hr APRM STP Rod Block 100 76.19 65.45 80.47 100.0 99 98 75.04 73.89 64.42 63.39 80.47 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 90.0 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 ABSP STP Scram 91 66.03 56.16 80.47 80.0 90 64.93 55.13 80.47 89 63.83 54.10 80.47 ABSP STP Rod Block 88 62.74 53.06 80.47 87 61.66 52.03 80.51 70.0 86 85 60.58 59.50 51.00 49.97 80.60 80.69 84 58.43 48.94 80.79

% Power 83 57.37 47.90 80.90 60.0 82 81 56.31 55.25 46.87 45.84 81.05 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 R

50.0 MELLLA Line and I e 78 77 52.12 51.08 42.74 81.67 81.82 BSP Boundary SLO Entry 76 50.05 --- 81.98 Rod Line C g 75 49.02 --- 82.13 74 48.00 --- 82.29 40.0 Region I - Manual Scram (SLO prohibited F i 73 46.98 --- 82.44 during FWTR) o 72 45.96 --- 82.60 71 44.95 --- 82.75 Region II - Controlled Entry n 70 43.94 --- 82.91 30.0 69 42.94 --- 83.06 68 41.94 --- 83.22 Operator Awareness 67 40.95 --- 83.37 66 39.96 --- 83.52 20.0 65 64 38.97 37.99 83.68 83.83 63 37.01 --- 83.99 Natural OPRM Enabled Region 62 36.04 --- 84.14 10.0 Circulation 61 60 35.06 34.10 84.30 84.45 Line 35% Approximate 59 33.13 --- 84.61 Minimum Pump Speed Minimum Power Line 58 32.17 --- 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120  % Core Flow

Reference:

0B21-2045, Revision 2

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