Text

Core Operating Limits Report for Cycle 23 Operation, Revision 1
	ML23096A320
Person / Time
Site:	Browns Ferry
Issue date:	04/06/2023
From:	Sivaraman M; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	Download: ML23096A320 (1)
	v • d • e

Post Office Box 2000, Decatur, Alabama 35609-2000 April 6, 2023 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

Browns Ferry Nuclear Plant, Unit 2 Core Operating Limits Report for Cycle 23 Operation, Revision 1

Reference:

Letter from TVA to NRC, Browns Ferry Nuclear Plant, Unit 2 Core Operating Limits Report for Cycle 23 Operation, Revision 0, dated March 3, 2023 (ML23067A092)

In accordance with the requirements of Technical Specification (TS) 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), Unit 2, Cycle 23, Core Operating Limits Report (COLR). Revision 0 of the Unit 2 COLR included Modes 3 through 5. Revision 1 of the Unit 2 COLR includes all Modes of operation.

There are no new regulatory commitments in this letter. If you have any questions, please contact C. L. Vaughn, Nuclear Site Licensing Manager, at (256) 729-2636.

Respectfully, Manu Sivaraman Site Vice President

Enclosure:

Core Operating Limits Report, (120% OLTP, MELLLA+), for Cycle 23 Operation, TVA-COLR-BF2C23, Revision 1 M

Si

U.S. Nuclear Regulatory Commission Page 2 April 6, 2023 cc: (w/ Enclosure)

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 Core Operating Limits Report, (120% OLTP, MELLLA+), for Unit 2 Cycle 23 Operation, TVA-COLR-BF2C23, Revision 1 (See Attached)

[I!fil ECM L94 220223 800 QA Record BFE-4793, Revision 0 Reactor Engineering and Fuels - BWRFE 1101 Markel Street, Chatlanooga. TN 37402 Browns Ferry Unit 2 Cycle 23 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23 Revision 1 (Final)

March 2023 Prepared:

Verified:

Approved:

Reviewed:

Approved:

(Rovis10n Log, Page vi)

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ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page ii Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table of Contents Total Number of Pages = 70 (including review cover sheet)

List of Tables.......................................................................................................................... iv List of Figures.......................................................................................................................... v Revision Log........................................................................................................................... vi Nomenclature..........................................................................................................................vii References............................................................................................................................. ix 1

Introduction......................................................................................................................1 1.1 Purpose....................................................................................................................1 1.2 Scope.......................................................................................................................1 1.3 Fuel Loading.............................................................................................................2 1.4 Acceptability..............................................................................................................2 2

MCPR99.9% Safety Limit....................................................................................................3 3

APLHGR.........................................................................................................................4 3.1 Rated Power and Flow Limit: APLHGRRATED.............................................................4 3.2 Off-Rated Power Dependent Limit: APLHGRP...........................................................4 3.2.1 Startup without Feedwater Heaters....................................................................4 3.3 Off-Rated Flow Dependent Limit: APLHGRF.............................................................4 3.4 Single Loop Operation Limit: APLHGRSLO................................................................. 4 3.5 Equipment Out-Of-Service Corrections......................................................................7 4

LHGR Limits....................................................................................................................8 4.1 Rated Power and Flow Limit: LHGRRATED..................................................................8 4.2 Off-Rated Power Dependent Limit: LHGRP...............................................................8 4.2.1 Startup without Feedwater Heaters....................................................................8 4.3 Off-Rated Flow Dependent Limit: LHGRF..................................................................9 4.4 Equipment Out-Of-Service Corrections......................................................................9 5

OLMCPR Limits.............................................................................................................20 5.1 Flow Dependent MCPR Limit: MCPRF....................................................................20 5.2 Power Dependent MCPR Limit: MCPRP..................................................................20 5.2.1 Startup without Feedwater Heaters..................................................................20 5.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)................................21 5.2.3 Exposure Dependent Limits.............................................................................21 5.2.4 Equipment Out-Of-Service (EOOS) Options.....................................................22 5.2.5 Single-Loop-Operation (SLO) Limits................................................................. 22 5.2.6 Flow Flags.......................................................................................................22 5.2.6.1 Below Pbypass Limits....................................................................................22 6

Thermal-Hydraulic Stability Protection............................................................................51 7

APRM Flow Biased Rod Block Trip Settings...................................................................53 8

Rod Block Monitor (RBM) Trip Setpoints and Operability................................................54 9

Shutdown Margin Limit..................................................................................................56

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page iii Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Appendix A:

MBSP Maps.................................................................................................. A-1

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page iv Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

List of Tables Nuclear Fuel Types

.............................................................................................................2 MCPR99.9%................................................................................................................................3 Startup Feedwater Temperature Basis......................................................................................8 Nominal Scram Time Basis....................................................................................................21 MCPRP Limits for ATRIUM-10XM Fuel: Optimum Scram Time Basis

................................. 25 MCPRP Limits for ATRIUM-11 Fuel: Optimum Scram Time Basis

.......................................26 MCPRP Limits for ATRIUM-10XM Fuel: Nominal Scram Time Basis

...................................27 MCPRP Limits for ATRIUM-11 Fuel: Nominal Scram Time Basis

........................................31 MCPRP Limits for ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis

.............................35 MCPRP Limits for ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis

..................................39 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-10XM Fuel:

Nominal Scram Time Basis

...............................................................................................43 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-11 Fuel: Nominal Scram Time Basis

.............................................................................................................45 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-10XM Fuel:

Tech. Spec. Scram Time Basis

.........................................................................................47 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-11 Fuel: Tech.

Spec. Scram Time Basis

...................................................................................................49 ABSP Setpoints for the Scram Region....................................................................................51 Analyzed MBSP Endpoints: Nominal Feedwater Temperature...............................................52 Analyzed MBSP Endpoints: Reduced Feedwater Temperature..............................................52 Analytical RBM Trip Setpoints

...........................................................................................54 RBM Setpoint Applicability......................................................................................................54 Control Rod Withdrawal Error Results.....................................................................................55

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page v Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

List of Figures APLHGRRATED for ATRIUM-10XM Fuel.....................................................................................5 APLHGRRATED for ATRIUM-11 Fuel...........................................................................................6 LHGRRATED for ATRIUM-10XM Fuel........................................................................................10 LHGRRATED for ATRIUM-11 Fuel.............................................................................................11 Base Operation LHGRFACP for ATRIUM-10XM Fuel..............................................................12 Base Operation LHGRFACP for ATRIUM-11 Fuel...................................................................13 LHGRFACF for ATRIUM-10XM Fuel.......................................................................................14 LHGRFACF for ATRIUM-11 Fuel............................................................................................15 Startup Operation LHGRFACP for ATRIUM-10XM Fuel: Table 4.1 Temperature Range 1........16 Startup Operation LHGRFACP for ATRIUM-10XM Fuel: Table 4.1 Temperature Range 2........17 Startup Operation LHGRFACP for ATRIUM-11 Fuel: Table 4.1 Temperature Range 1.............18 Startup Operation LHGRFACP for ATRIUM-11 Fuel: Table 4.1 Temperature Range 2.............19 MCPRF for ATRIUM-10XM Fuel..............................................................................................23 MCPRF for ATRIUM-11 Fuel...................................................................................................24 MBSP Boundaries For Nominal Feedwater Temperature...................................................... A-2 MBSP Boundaries For Reduced Feedwater Temperature..................................................... A-3

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page vi Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Revision Log Number Page Description 1-R1 All Updated for Revision 1. New material added to support all operating MODES.

2-R1 vii-x Updated References 3-R1 1-2 Updated report scope, and References.

4-R1 3

Added new section 2 content regarding MCPR99.9 5-R1 4-7 Added new section 3 content regarding APLHGR 6-R1 8-19 Added new section 4 content regarding LHGR 7-R1 20-50 Added new section 5 content regarding MCPR 8-R1 51-52 Added new section 6 content regarding Thermal-Hydraulic Stability 9-R1 53 Added new section 7 content regarding APRM Flow Biased Rod Block 10-R1 54-55 Added new section 8 content regarding Rod Block Monitor Setpoints 11-R1 56 Previous Section 2 becomes Section 9 12-R1 A A-3 Added Appendix A 0-R0 All New document.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page vii Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Nomenclature ABSP Automatic Backup Stability Protection APLHGR Average Planar LHGR APRM Average Power Range Monitor AREVA NP Vendor (Framatome, Siemens)

BOC Beginning of Cycle BSP Backup Stability Protection BWR Boiling Water Reactor CAVEX Core Average Exposure CD Coast Down CMSS Core Monitoring System Software COLR Core Operating Limits Report CPR Critical Power Ratio CRWE Control Rod Withdrawal Error CSDM Cold SDM DIVOM Delta CPR over Initial CPR vs. Oscillation Magnitude DSS-CD Detect and Suppress Solution - Confirmation Density EOC End of Cycle EOCLB End-of-Cycle Licensing Basis EOOS Equipment OOS EPU Extended Power Uprate (120% OLTP)

FFTR Final Feedwater Temperature Reduction FFWTR Final Feedwater Temperature Reduction FHOOS Feedwater Heaters OOS ft Foot: English unit of measure for length GNF Vendor (General Electric, Global Nuclear Fuels)

GWd Giga Watt Day HTSP High TSP ICA Interim Corrective Action ICF Increased Core Flow (beyond rated)

IS In-Service kW kilo watt: SI unit of measure for power.

LCO License Condition of Operation LFWH Loss of Feedwater Heating LHGRFAC LHGR Multiplier (Power or Flow dependent)

LPRM Low Power Range Monitor LRNB Generator Load Reject, No Bypass

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page viii Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

MAPFAC MAPLHGR multiplier (Power or Flow dependent)

MBSP Manual Backup Stability Protection MCPR Minimum CPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+

Maximum Extended Load Line Limit Analysis Plus MSRV Moisture Separator Reheater Valve MSRVOOS MSRV OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit OLTP Original Licensed Thermal Power OOS Out-Of-Service OPRM Oscillation Power Range Monitor OSS Optimum Scram Speed PBDA Period Based Detection Algorithm Pbypass Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed PLU Power Load Unbalance PLUOOS PLU OOS PRNM Power Range Neutron Monitor RBM Rod Block Monitor RCPOOS Recirculation Pump OOS (SLO)

RDF Rated Drive Flow RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS RTP Rated Thermal Power SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page ix Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

References 1.

ANP-4033, Revision 0, Browns Ferry Unit 2 Cycle 23 Reload Analysis, Framatome, Inc., January 2023.

2.

ANP-3860P Revision 1, Mechanical Design Report for Browns Ferry ATRIUM 11 Fuel Assemblies, Framatome Inc., June 2022.

3.

ANP-3150P, Revision 4, Mechanical Design Report for Browns Ferry ATRIUM 10XM Fuel Assemblies, AREVA Inc., November 2017.

4.

ANP-3986P, Revision 0, Browns Ferry Unit 2 Cycle 23 Plant Parameters Document, Framatome Inc., February 2022.

5.

BFE-4774, Revision 0, Browns Ferry Unit 2 Cycle 23 In Core Shuffle, Calculation File, Tennessee Valley Authority, January 2023.

Methodology References 6.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

7.

XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.

8.

EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

9.

ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

10.

XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

11.

XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

12.

EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

13.

XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

14.

ANP-10307PA, Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP Inc., June 2011.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page x Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 15.

EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001, as supplemented by the site specific approval in NRC safety evaluation dated February 15, 2013 and July 31, 2014.

16.

EMF-2292(P)(A) Revision 0, ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

17.

EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

18.

BAW-10247PA, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP Inc., February 2008.

19.

ANP-10298P-A, Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA Inc., March 2014.

20.

NEDC-33075P-A, Revision 8, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density, GE Hitachi, November 2013.

21.

BAW-10247P-A Supplement 2P-A Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods, Framatome Inc., August 2018.

22.

ANP-10300P-A Revision 1, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Framatome Inc.,

January 2018.

23.

ANP-10332P-A Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios, Framatome Inc.,

March 2019.

24.

ANP-10333P-A Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA), Framatome Inc.,

March 2018 (as supplemented by Section 6.4 of ANP-3908P Revision 4, Applicability of Framatome BWR Methods to Browns Ferry with ATRIUM 11 Fuel, Framatome Inc., June 2022) 25.

ANP-10335P-A Revision 0, ACE/ATRIUM 11 Critical Power Correlation, Framatome Inc., May 2018.

26.

ANP-10340P-A Revision 0, Incorporation of Chromia Doped Fuel Properties in AREVA Approved Methods, Framatome Inc., May 2018.

27.

ANP-3907P Revision 0, Application of BEO-III Methodology with the Confirmation Density Algorithm at Browns Ferry, Framatome Inc., April 2021.

Setpoint References 28.

EDQ2092900118, R39, Setpoint and Scaling Calculation for Neutron Monitoring System & Recirculation Flow Loops, Calculation File, Tennessee Valley Authority, October 14, 2022.

29.

Task T0500, Revision 0, Neutron Monitoring System w/RBM, Project Task Report, GE Hitachi Nuclear Energy, June 2017.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page xi Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 30.

Task T0506, Revision 0, TS Instrument Setpoints, Project Task Report, Tennessee Valley Authority, August, 2017.

31.

NEDC-33006P-A, Revision 3, General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus, GE Energy Nuclear, June 2009.

32.

NEDC-33075P-A, Revision 8, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density, GE Hitachi, November 2013.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 1 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 1 Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

1.1 Purpose The primary purpose of this document is to satisfy requirements identified by unit technical specification section 5.6.5. This document may be provided, upon final approval, to the NRC.

1.2 Scope This document will discuss the following areas:

3/4 Minimum Critical Power Ratio Safety Limit (MCPR99.9%)

(Technical Specifications 2.1.1.2, 3.2.2, and 5.6.5.a(3))

Applicability: Mode 1, 23% RTP (Technical Specifications definition of RTP) 3/4 Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specifications 3.2.1 and 3.7.5)

Applicability: Mode 1, 23% RTP (Technical Specifications definition of RTP) 3/4 Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.2.3, 3.3.4.1, and 3.7.5)

Applicability: Mode 1, 23% RTP (Technical Specifications definition of RTP) 3/4 Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, 3.7.5 and Table 3.3.2.1-1)

Applicability: Mode 1, 23% RTP (Technical Specifications definition of RTP) 3/4 Thermal-Hydraulic Stability Protection (Technical Specification Table 3.3.1.1)

Applicability: Mode 1, (as specified in Technical Specifications Table 3.3.1.1-1) 3/4 Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

Applicability: Mode 1, (as specified in Technical Requirements Manuals Table 3.3.4-1) 3/4 Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

Applicability: Mode 1, % RTP as specified in Table 3.3.2.1-1 (TS definition of RTP) 3/4 Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

Applicability: All Modes

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 2 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 1.3 Fuel Loading The core will contain fresh ATRIUM-11 and exposed ATRIUM-10XM. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented per Reference 5.

Table 1.1 Nuclear Fuel Types

Fuel Description Original Cycle Number of Assemblies Nuclear Fuel Type (NFT)

Fuel Names (Range)

ATRIUM-10XM XMLC-4087B-15GV80-FBH 21 37 21 FBH001-FBH176 ATRIUM-10XM XMLC-4036B-15GV80-FBH 21 31 22 FBH177-FBH264 ATRIUM-10XM XMLC-4093B-10GV80-FBH 21 56 23 FBH265-FBH320 ATRIUM-10XM XMLC-4058B-15GV80-FBJ 22 216 24 FBJ331-FBJ546 ATRIUM-10XM XMLC-4015B-15GV80-FBJ 22 92 25 FBJ547-FBJ638 ATRIUM 11 AT11-3974B-14GV100-FBK 23 84 26 FBK649-FBK732 ATRIUM 11 AT11-3971B-14GV100-FBK 23 160 27 FBK733-FBK892 ATRIUM 11 AT11-4175B-13GV80-FBK 23 88 28 FBK893-FBK980 1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 6 through 27.

The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified in this document.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 3 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 2 MCPR99.9% Safety Limit (Technical Specifications 2.1.1.2, and 3.2.2)

SLMCPR of Technical Specification 2.1.1.2 has been changed by approval of Traveler TSTF-564, Revision 2. Now, the SLMCPR of Technical Specification 2.1.1.2 represents the MCPR95/95, relative to the critical power correlations being used. Values in TS 2.1.1.2 would only potentially change if there is a change to critical power correlation being used or system measurement uncertainty.

Values provided in Table 2.1, per Reference 1, represent the integral MCPR99.9% considering all forms of uncertainties, and cycle specific fuel designs, core loading, and projected cycle operation.

Table 2.1 MCPR99.9%

TLO SLO SLMCPR BOC NEOC EOCLB to to to End of NEOC EOCLB Coast 1.09 1.09 1.09 1.08 1.08 1.08

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 4 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 3 APLHGR (Technical Specifications 3.2.1 & 3.7.5)

The APLHGR limit is determined by adjusting the rated power APLHGR limit for off-rated power, off-rated flow, and SLO conditions. The most limiting of these is then used as follows:

APLHGR limit = MIN ( APLHGRP, APLHGRF, APLHGRSLO )

where:

APLHGRP off-rated power APLHGR limit

[APLHGRRATED

MAPFACP]

APLHGRF off-rated flow APLHGR limit

[APLHGRRATED

MAPFACF]

APLHGRSLO SLO APLHGR limit

[APLHGRRATED

SLO Multiplier]

3.1 Rated Power and Flow Limit: APLHGRRATED The rated conditions APLHGR for all fuel are identified per Reference 1. The rated conditions APLHGR for ATRIUM-10XM fuel are shown in Figure 3.1. The rated conditions APLHGR for ATRIUM-11 are shown in Figure 3.2.

3.2 Off-Rated Power Dependent Limit: APLHGRP Reference 1 does not specify a power dependent APLHGR. Therefore, MAPFACP is set to a value of 1.0.

3.2.1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. No additional power dependent limitation is required.

3.3 Off-Rated Flow Dependent Limit: APLHGRF Reference 1 does not specify a flow dependent APLHGR. Therefore, MAPFACF is set to a value of 1.0.

3.4 Single Loop Operation Limit: APLHGRSLO The single loop operation multiplier for ATRIUM-10XM and ATRIUM-11 fuel is 0.85, per Reference 1.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 5 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0 3

6 9

12 15 0

20 40 60 80 APLHGR (kW/ft)

Planar Average Exposure (GWd/MTU)

Planar Avg.

APLHGR Exposure Limit (GWd/MTU)

(kW/ft) 0.0 13.0 15.0 13.0 67.0 7.6 Figure 3.1 APLHGRRATED for ATRIUM-10XM Fuel

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 6 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0 3

6 9

12 15 0

20 40 60 80 APLHGR (kW/ft)

Planar Average Exposure (GWd/MTU)

Planar Avg.

APLHGR Exposure Limit (GWd/MTU)

(kW/ft) 0.0 11.5 20.0 11.5 60.0 9

69.0 7.2 Figure 3.2 APLHGRRATED for ATRIUM-11 Fuel

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 7 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 3.5 Equipment Out-Of-Service Corrections The limits shown in Figure 3.1 and Figure 3.2 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.

In-Service All equipment In-Service

RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFWTR)

Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction RCPOOS One Recirculation Pump Out-Of-Service

All equipment service conditions assume 1 SRVOOS.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 8 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 4 LHGR Limits (Technical Specification 3.2.3, 3.3.4.1, & 3.7.5)

The LHGR limit is determined by adjusting the rated power LHGR limit for off-rated power and off-rated flow conditions. The most limiting of these is then used as follows:

LHGR limit = MIN ( LHGRP, LHGRF )

where:

LHGRP off-rated power LHGR limit

[LHGRRATED

LHGRFACP]

LHGRF off-rated flow LHGR limit

[LHGRRATED

LHGRFACF]

4.1 Rated Power and Flow Limit: LHGRRATED The rated conditions LHGR for all fuel are identified per Reference 1. The rated conditions LHGR for ATRIUM-10XM are shown in Figure 4.1. The rated conditions LHGR for ATRIUM-11 fuel is shown in Figure 4.2. The LHGR limits are consistent with References 2 & 3.

4.2 Off-Rated Power Dependent Limit: LHGRP LHGR limits are adjusted for off-rated power conditions using the LHGRFACP multiplier provided in Reference 1. The multiplier is split into two sub cases: turbine bypass valves in and out-of-service. The base case multipliers are shown in Figure 4.3 and Figure 4.4.

4.2.1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional limits are shown in Figure 4.7 through Figure 4.10, based on temperature conditions identified in Table 4.1.

Table 4.1 Startup Feedwater Temperature Basis Power Range 1 Range 2

(% Rated)

(°F)

(°F) 23 155.0 150.0 30 162.0 157.0 40 172.0 167.0 50 182.0 177.0 Temperature

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 9 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 4.3 Off-Rated Flow Dependent Limit: LHGRF LHGR limits are adjusted for off-rated flow conditions using the LHGRFACF multiplier provided in Reference 1. Multipliers are shown in Figure 4.5 through Figure 4.6.

4.4 Equipment Out-Of-Service Corrections The limits shown in Figure 4.1 and Figure 4.2 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.

In-Service All equipment In-Service RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFWTR)

Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction RCPOOS One Recirculation Pump Out-Of-Service Off-rated power corrections shown in Figure 4.3 and Figure 4.4 are dependent on operation of the Turbine Bypass Valve system. For this reason, separate limits are to be applied for TBVIS or TBVOOS operation. The limits have no dependency on RPTOOS, PLUOOS, FHOOS/FFWTR, or SLO.

Off-rated flow corrections shown in Figure 4.5 and Figure 4.6 are bounding for all EOOS conditions.

Off-rated power corrections shown in Figure 4.7 through Figure 4.10 are also dependent on operation of the Turbine Bypass Valve system. In this case, limits support FHOOS operation during startup. These limits have no dependency on RPTOOS, PLUOOS, or SLO.

All equipment service conditions assume 1 SRVOOS.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 10 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0 3

6 9

12 15 0

20 40 60 80 LHGR (kW/ft)

Pellet Exposure (GWd/MTU)

Pellet LHGR Exposure Limit (GWd/MTU)

(kW/ft) 0.0 14.1 18.9 14.1 74.4 7.4 Figure 4.1 LHGRRATED for ATRIUM-10XM Fuel

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 11 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0 3

6 9

12 15 0

20 40 60 80 100 LHGR (kW/ft)

Pellet Exposure (GWd/MTU)

Pellet LHGR Exposure Limit (GWd/MTU)

(kW/ft) 0.0 13.6 21.0 13.6 53.0 10.2 80.0 3.5 Figure 4.2 LHGRRATED for ATRIUM-11 Fuel

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 12 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 20 30 40 50 60 70 80 90 100 110 LHGRFACP Core Power (% Rated)

Turbine Bypass Valve Out-of-Service, TBVOOS Turbine Bypass Valve In-Service, TBVIS TBVIS, > 50% Core Flow 7%9,6&RUH)ORZ TBVOOS, > 50% Core Flow 7%9226&RUH)ORZ Core Core Power LHGRFACP Power LHGRFACP

(% Rated)

(% Rated) 100.0 0.99 100.0 0.99 26.0 0.60 26.0 0.60 26.0 0.41 26.0 0.40 23.0 0.40 23.0 0.36 26.0 0.48 26.0 0.48 23.0 0.48 23.0 0.48 Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Flow > 50% Rated Core Flow > 50% Rated

&RUH)ORZ5DWHG

&RUH)ORZ5DWHG Figure 4.3 Base Operation LHGRFACP for ATRIUM-10XM Fuel (Independent of other EOOS conditions)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 13 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 20 30 40 50 60 70 80 90 100 110 LHGRFACP Core Power (% Rated)

Turbine Bypass Valve Out-of-Service, TBVOOS Turbine Bypass Valve In-Service, TBVIS TBVIS, > 50% Core Flow 7%9,6&RUH)ORZ TBVOOS, > 50% Core Flow 7%9226&RUH)ORZ Core Core Power LHGRFACP Power LHGRFACP

(% Rated)

(% Rated) 100.0 0.95 100.0 0.93 26.0 0.54 26.0 0.54 26.0 0.37 26.0 0.35 23.0 0.35 23.0 0.31 26.0 0.42 26.0 0.42 23.0 0.42 23.0 0.42 Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Flow > 50% Rated Core Flow > 50% Rated

&RUH)ORZ5DWHG

&RUH)ORZ5DWHG Figure 4.4 Base Operation LHGRFACP for ATRIUM-11 Fuel (Independent of other EOOS conditions)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 14 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.05 1.10 25 35 45 55 65 75 85 95 105 LHGRFACF Core Flow (% Rated)

Core Flow LHGRFACF

(% Rated) 0.0 0.60 30.0 0.60 77.5 1.00 107.0 1.00 Figure 4.5 LHGRFACF for ATRIUM-10XM Fuel (Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, ICF)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 15 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.05 1.10 25 35 45 55 65 75 85 95 105 LHGRFACF Core Flow (% Rated)

Core Flow LHGRFACF

(% Rated) 0.0 0.6 30.0 0.6 79.3 1.00 107.0 1.00 Figure 4.6 LHGRFACF for ATRIUM-11 Fuel (Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, ICF)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 16 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 20 30 40 50 60 70 80 90 100 110 LHGRFACP Core Power (% Rated)

Turbine Bypass Valve Out-of-Service, TBVOOS Turbine Bypass Valve In-Service, TBVIS TBVIS, > 50% Core Flow 7%9,6&RUH)ORZ TBVOOS, > 50% Core Flow 7%9226&RUH)ORZ Core Core Power LHGRFACP Power LHGRFACP

(% Rated)

(% Rated) 100.0 0.99 100.0 0.99 26.0 0.58 26.0 0.54 26.0 0.41 26.0 0.39 23.0 0.39 23.0 0.34 26.0 0.45 26.0 0.45 23.0 0.44 23.0 0.44 Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Flow > 50% Rated Core Flow > 50% Rated

&RUH)ORZ5DWHG

&RUH)ORZ5DWHG Figure 4.7 Startup Operation LHGRFACP for ATRIUM-10XM Fuel:

Table 4.1 Temperature Range 1 (no Feedwater heating during startup)

(Limits valid at and below 50% power)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 17 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 20 30 40 50 60 70 80 90 100 110 LHGRFACP Core Power (% Rated)

Turbine Bypass Valve Out-of-Service, TBVOOS Turbine Bypass Valve In-Service, TBVIS TBVIS, > 50% Core Flow 7%9,6&RUH)ORZ TBVOOS, > 50% Core Flow 7%9226&RUH)ORZ Core Core Power LHGRFACP Power LHGRFACP

(% Rated)

(% Rated) 100.0 0.99 100.0 0.99 26.0 0.58 26.0 0.53 26.0 0.41 26.0 0.38 23.0 0.38 23.0 0.34 26.0 0.44 26.0 0.44 23.0 0.43 23.0 0.43 Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Flow > 50% Rated Core Flow > 50% Rated

&RUH)ORZ5DWHG

&RUH)ORZ5DWHG Figure 4.8 Startup Operation LHGRFACP for ATRIUM-10XM Fuel:

Table 4.1 Temperature Range 2 (no Feedwater heating during startup)

(Limits valid at and below 50% power)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 18 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 20 30 40 50 60 70 80 90 100 110 LHGRFACP Core Power (% Rated)

Turbine Bypass Valve Out-of-Service, TBVOOS Turbine Bypass Valve In-Service, TBVIS TBVIS, > 50% Core Flow 7%9,6&RUH)ORZ TBVOOS, > 50% Core Flow 7%9226&RUH)ORZ Core Core Power LHGRFACP Power LHGRFACP

(% Rated)

(% Rated) 100.0 0.95 100.0 0.93 26.0 0.50 26.0 0.45 26.0 0.36 26.0 0.34 23.0 0.34 23.0 0.30 26.0 0.40 26.0 0.40 23.0 0.39 23.0 0.39 Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Flow > 50% Rated Core Flow > 50% Rated

&RUH)ORZ5DWHG

&RUH)ORZ5DWHG Figure 4.9 Startup Operation LHGRFACP for ATRIUM-11 Fuel:

Table 4.1 Temperature Range 1 (no Feedwater heating during startup)

(Limits valid at and below 50% power)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 19 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 20 30 40 50 60 70 80 90 100 110 LHGRFACP Core Power (% Rated)

Turbine Bypass Valve Out-of-Service, TBVOOS Turbine Bypass Valve In-Service, TBVIS TBVIS, > 50% Core Flow 7%9,6&RUH)ORZ TBVOOS, > 50% Core Flow 7%9226&RUH)ORZ Core Core Power LHGRFACP Power LHGRFACP

(% Rated)

(% Rated) 100.0 0.95 100.0 0.93 26.0 0.50 26.0 0.44 26.0 0.36 26.0 0.34 23.0 0.34 23.0 0.30 26.0 0.40 26.0 0.40 23.0 0.39 23.0 0.39 Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Flow > 50% Rated Core Flow > 50% Rated

&RUH)ORZ5DWHG

&RUH)ORZ5DWHG Figure 4.10 Startup Operation LHGRFACP for ATRIUM-11 Fuel:

Table 4.1 Temperature Range 2 (no Feedwater heating during startup)

(Limits valid at and below 50% power)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 20 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 5 OLMCPR Limits (Technical Specification 3.2.2, 3.3.4.1, & 3.7.5)

OLMCPR is calculated to be the most limiting of the flow or power dependent values OLMCPR limit = MAX ( MCPRF, MCPRP )

where:

MCPRF core flow-dependent MCPR limit MCPRP power-(and flow flag) dependent MCPR limit 5.1 Flow Dependent MCPR Limit: MCPRF MCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated or Increased Core Flow, ICF). MCPRF limits are shown in Figure 5.1 for ATRIUM-10XM; Figure 5.2 for ATRIUM-11 fuel, per Reference 1. Limits are valid for all EOOS combinations. No adjustment is required for SLO conditions.

5.2 Power Dependent MCPR Limit: MCPRP MCPRP limits are dependent upon:

Core Power (% of Rated) for a specified flow flag bin.

Technical Specification Scram Speed (TSSS), Nominal Scram Speed (NSS), or Optimum Scram Speed (OSS)

Cycle Operating Exposure (NEOC, EOC, and CD - as defined in this section)

Equipment Out-Of-Service Options

Two or Single recirculation Loop Operation (TLO vs. SLO)

The MCPRP limits are provided in Table 5.2 through Table 5.7, where each table contains the limits for a single fuel type, and EOOS options (for a specified scram speed and exposure range). The CMSS determines MCPRP limits, from these tables, based on linear interpolation between the specified powers.

5.2.1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional power dependent limits are shown in Table 5.8 through Table 5.11 based on temperature conditions identified in Table 4.1.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 21 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 5.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)

MCPRP limits are provided for three different sets of assumed scram speeds. The Technical Specification Scram Speed (TSSS) MCPRP limits are applicable at all times, as long as the scram time surveillance demonstrates the times in Technical Specification Table 3.1.4-1 are met. Both Nominal Scram Speeds (NSS) and/or Optimum Scram Speeds (OSS) may be used, as long as the scram time surveillance demonstrates Table 5.1 times are applicable.

Table 5.1 Nominal Scram Time Basis Notch Nominal Optimum Position Scram Timing Scram Timing (index)

(seconds)

(seconds) 46 0.380 0.350 36 0.960 0.930 26 1.590 1.560 6

2.900 2.800 In demonstrating compliance with the NSS and/or OSS scram time basis, surveillance requirements from Technical Specification 3.1.4 apply; accepting the definition of SLOW rods should conform to scram speeds shown in Table 5.1. If conformance is not demonstrated, TSSS based MCPRP limits are applied.

On initial cycle startup, TSSS limits are used until the successful completion of scram timing confirms NSS and/or OSS based limits are applicable.

5.2.3 Exposure Dependent Limits Exposures are tracked on a Core Average Exposure basis (CAVEX, not Cycle Exposure).

Higher exposure MCPRP limits are NOT always more limiting. Per Reference 1, MCPRP limits are provided for the following exposure ranges:

BOC to NEOC NEOC corresponds to 31,103.3 MWd / MTU NEOC to EOCLB EOCLB corresponds to 33,983.2 MWd / MTU EOCLB to End of Coast End of Coast 35,678.9 MWd / MTU The EOCLB exposure point is not the true End-Of-Cycle exposure. Instead, it corresponds to a licensing exposure window exceeding expected end-of-full-power-life.

Reference 1 analysis results are based on information identified in Reference 4.

Drop out times consistent with method used to perform actual timing measurements (i.e., including pickup/dropout effects).

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 22 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

The End of Coast exposure point represents a licensing exposure point exceeding the expected end-of-cycle exposure including cycle extension options.

5.2.4 Equipment Out-Of-Service (EOOS) Options EOOS options

covered by MCPRP limits are given by the following:

In-Service All equipment In-Service RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service RPTOOS+TBVOOS Combined RPTOOS and TBVOOS PLUOOS Power Load Unbalance Out-Of-Service PLUOOS+RPTOOS Combined PLUOOS and RPTOOS PLUOOS+TBVOOS Combined PLUOOS and TBVOOS PLUOOS+TBVOOS+RPTOOS Combined PLUOOS, RPTOOS, and TBVOOS FHOOS (or FFWTR)

Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction)

RCPOOS One Recirculation Pump Out-Of-Service For exposure ranges up to NEOC and EOCLB, additional combinations of MCPRP limits are also provided including FHOOS. The coast down exposure range assumes application of FFWTR. FHOOS based MCPRP limits for the coast down exposure are redundant because the temperature setdown assumption is identical with FFWTR.

5.2.5 Single-Loop-Operation (SLO) Limits When operating in RCPOOS conditions, MCPRp limits are constructed differently from the normal operating RCP conditions. The limiting event for RCPOOS is a pump seizure scenario, which sets the upper bound for allowed core power and flow. This event is not impacted by scram time assumptions. Specific MCPRP limits are shown with all other limits identified per Table 5.2 through Table 5.7, using the RCPOOS equipment out-of-service descriptor.

5.2.6 Flow Flags A flow flag is simply a point on the core flow axis of the power/flow map defining core flow bins where limits are applicable. For the cycle, a 90% core flow flag is employed. Hence, there are 2 core flow bins generated. While not every flow flag bin pair has a benefit, there are two MCPRP values for each exposure bin, and each power level, (values for a bin pair may be equal).

5.2.6.1 Below Pbypass Limits Below Pbypass (26% rated power), a flow flag of 50% is utilized.

All equipment service conditions assume 1 SRVOOS.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 23 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 1.00 1.20 1.40 1.60 1.80 2.00 30 40 50 60 70 80 90 100 110 MCPRF Core Flow (% Rated)

Core Flow MCPRf

(% Rated) 30.0 1.64 84.0 1.40 107.0 1.40 Figure 5.1 MCPRF for ATRIUM-10XM Fuel (Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, ICF)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 24 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 1.00 1.20 1.40 1.60 1.80 2.00 30 40 50 60 70 80 90 100 110 MCPRF Core Flow (% Rated)

Core Flow MCPRf

(% Rated) 30.0 1.70 84.0 1.45 107.0 1.45 Figure 5.2 MCPRF for ATRIUM-11 Fuel (Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, ICF)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 25 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.2 MCPRP Limits for ATRIUM-10XM Fuel: Optimum Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.54 1.54 1.54 1.54 1.57 1.57 90 1.66 1.66 1.66 1.66 1.66 1.66 77.6 1.71 1.71 1.71 1.71 1.77 1.77 65 1.91 1.91 1.91 1.91 1.99 1.99 50 2.05 2.05 2.05 2.05 2.10 2.10 26 2.45 2.45 2.45 2.45 2.55 2.55 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.76 2.51 2.76 2.51 2.87 2.51 23 2.86 2.59 2.86 2.59 2.87 2.59 100 1.57 1.57 1.57 1.57 90 1.66 1.66 1.66 1.66 77.6 1.77 1.77 1.77 1.77 65 1.99 1.99 1.99 1.99 50 2.10 2.10 2.10 2.10 26 2.55 2.55 2.55 2.55 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.87 2.51 2.87 2.51 23 2.87 2.59 2.87 2.59 Base Case FHOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR/FHOOS is supported for the EOCLB to End of Coast limits.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 26 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.3 MCPRP Limits for ATRIUM-11 Fuel: Optimum Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.51 1.51 1.52 1.52 1.58 1.58 90 1.60 1.60 1.56 1.56 1.64 1.64 77.6 1.75 1.75 1.86 1.86 1.86 1.86 65 1.82 1.82 1.99 1.99 1.99 1.99 50 2.06 2.06 2.10 2.10 2.10 2.10 26 2.39 2.39 2.26 2.26 2.33 2.33 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.63 2.43 2.45 2.43 2.48 2.43 23 2.79 2.57 2.57 2.57 2.57 2.57 100 1.62 1.62 1.58 1.58 90 1.65 1.65 1.64 1.64 77.6 1.84 1.84 1.86 1.86 65 1.95 1.95 1.99 1.99 50 2.19 2.19 2.10 2.10 26 2.74 2.74 2.33 2.33 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.89 2.43 2.48 2.43 23 2.90 2.57 2.57 2.57 FHOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast Base Case

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR/FHOOS is supported for the EOCLB to End of Coast limits.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 27 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.4 MCPRP Limits for ATRIUM-10XM Fuel: Nominal Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.54 1.54 1.54 1.54 1.60 1.60 90 1.67 1.67 1.67 1.67 1.70 1.70 77.6 1.79 1.79 1.79 1.79 1.86 1.86 65 1.97 1.97 1.97 1.97 2.09 2.09 50 2.13 2.13 2.13 2.13 2.21 2.21 26 2.52 2.52 2.52 2.52 2.61 2.61 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.76 2.51 2.76 2.51 2.87 2.51 23 2.86 2.59 2.86 2.59 2.87 2.59 100 1.62 1.62 1.62 1.62 1.65 1.65 90 1.76 1.76 1.76 1.76 1.76 1.76 77.6 1.85 1.85 1.85 1.85 1.91 1.91 65 1.99 1.99 1.99 1.99 2.09 2.09 50 2.16 2.16 2.16 2.16 2.22 2.22 26 2.52 2.52 2.52 2.52 2.67 2.67 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.09 2.88 3.09 2.88 3.25 2.88 23 3.33 3.03 3.33 3.03 3.47 3.03 100 1.60 1.60 1.60 1.60 90 1.70 1.70 1.70 1.70 77.6 1.86 1.86 1.86 1.86 65 2.09 2.09 2.09 2.09 50 2.21 2.21 2.21 2.21 26 2.61 2.61 2.61 2.61 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.87 2.51 2.87 2.51 23 2.87 2.59 2.87 2.59 100 1.54 1.54 1.54 1.54 1.60 1.60 90 1.67 1.67 1.67 1.67 1.70 1.70 77.6 1.79 1.79 1.79 1.79 1.86 1.86 65 1.97 1.97 1.97 1.97 2.09 2.09 50 2.13 2.13 2.13 2.13 2.21 2.21 26 2.52 2.52 2.52 2.52 2.61 2.61 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.76 2.51 2.76 2.51 2.87 2.51 23 2.86 2.59 2.86 2.59 2.87 2.59 to End of Coast BOC to NEOC NEOC to EOCLB EOCLB Base Case TBVOOS FHOOS PLUOOS

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 28 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.4 MCPRP Limits for ATRIUM-10XM Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.65 1.65 1.65 1.65 90 1.76 1.76 1.76 1.76 77.6 1.91 1.91 1.91 1.91 65 2.09 2.09 2.09 2.09 50 2.22 2.22 2.22 2.22 26 2.67 2.67 2.67 2.67 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.25 2.88 3.25 2.88 23 3.47 3.03 3.47 3.03 100 1.62 1.62 1.62 1.62 1.65 1.65 90 1.76 1.76 1.76 1.76 1.76 1.76 77.6 1.85 1.85 1.85 1.85 1.91 1.91 65 1.99 1.99 1.99 1.99 2.09 2.09 50 2.16 2.16 2.16 2.16 2.22 2.22 26 2.52 2.52 2.52 2.52 2.67 2.67 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.09 2.88 3.09 2.88 3.25 2.88 23 3.33 3.03 3.33 3.03 3.47 3.03 100 1.60 1.60 1.60 1.60 90 1.70 1.70 1.70 1.70 77.6 1.86 1.86 1.86 1.86 65 2.09 2.09 2.09 2.09 50 2.21 2.21 2.21 2.21 26 2.61 2.61 2.61 2.61 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.87 2.51 2.87 2.51 23 2.87 2.59 2.87 2.59 100 1.65 1.65 1.65 1.65 90 1.76 1.76 1.76 1.76 77.6 1.91 1.91 1.91 1.91 65 2.09 2.09 2.09 2.09 50 2.22 2.22 2.22 2.22 26 2.67 2.67 2.67 2.67 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.25 2.88 3.25 2.88 23 3.47 3.03 3.47 3.03 BOC NEOC EOCLB to to to End of NEOC EOCLB Coast TBVOOS FHOOS TBVOOS PLUOOS FHOOS PLUOOS TBVOOS FHOOS PLUOOS

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 29 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.4 MCPRP Limits for ATRIUM-10XM Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.55 1.55 1.55 1.55 1.61 1.61 90 1.68 1.68 1.68 1.68 1.71 1.71 77.6 1.80 1.80 1.80 1.80 1.87 1.87 65 1.98 1.98 1.98 1.98 2.10 2.10 50 2.14 2.14 2.14 2.14 2.22 2.22 26 2.53 2.53 2.53 2.53 2.62 2.62 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.77 2.52 2.77 2.52 2.88 2.52 23 2.87 2.60 2.87 2.60 2.88 2.60 100 1.63 1.63 1.63 1.63 1.66 1.66 90 1.77 1.77 1.77 1.77 1.77 1.77 77.6 1.86 1.86 1.86 1.86 1.92 1.92 65 2.00 2.00 2.00 2.00 2.10 2.10 50 2.17 2.17 2.17 2.17 2.23 2.23 26 2.53 2.53 2.53 2.53 2.68 2.68 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.10 2.89 3.10 2.89 3.26 2.89 23 3.34 3.04 3.34 3.04 3.48 3.04 100 1.61 1.61 1.61 1.61 90 1.71 1.71 1.71 1.71 77.6 1.87 1.87 1.87 1.87 65 2.10 2.10 2.10 2.10 50 2.22 2.22 2.22 2.22 26 2.62 2.62 2.62 2.62 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.88 2.52 2.88 2.52 23 2.88 2.60 2.88 2.60 100 1.55 1.55 1.55 1.55 1.61 1.61 90 1.68 1.68 1.68 1.68 1.71 1.71 77.6 1.80 1.80 1.80 1.80 1.87 1.87 65 1.98 1.98 1.98 1.98 2.10 2.10 50 2.14 2.14 2.14 2.14 2.22 2.22 26 2.53 2.53 2.53 2.53 2.62 2.62 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.77 2.52 2.77 2.52 2.88 2.52 23 2.87 2.60 2.87 2.60 2.88 2.60 Base Case RCPOOS RCPOOS TBVOOS RCPOOS FHOOS RCPOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 30 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.4 MCPRP Limits for ATRIUM-10XM Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.66 1.66 1.66 1.66 90 1.77 1.77 1.77 1.77 77.6 1.92 1.92 1.92 1.92 65 2.10 2.10 2.10 2.10 50 2.23 2.23 2.23 2.23 26 2.68 2.68 2.68 2.68 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.26 2.89 3.26 2.89 23 3.48 3.04 3.48 3.04 100 1.63 1.63 1.63 1.63 1.66 1.66 90 1.77 1.77 1.77 1.77 1.77 1.77 77.6 1.86 1.86 1.86 1.86 1.92 1.92 65 2.00 2.00 2.00 2.00 2.10 2.10 50 2.17 2.17 2.17 2.17 2.23 2.23 26 2.53 2.53 2.53 2.53 2.68 2.68 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.10 2.89 3.10 2.89 3.26 2.89 23 3.34 3.04 3.34 3.04 3.48 3.04 100 1.61 1.61 1.61 1.61 90 1.71 1.71 1.71 1.71 77.6 1.87 1.87 1.87 1.87 65 2.10 2.10 2.10 2.10 50 2.22 2.22 2.22 2.22 26 2.62 2.62 2.62 2.62 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.88 2.52 2.88 2.52 23 2.88 2.60 2.88 2.60 100 1.66 1.66 1.66 1.66 90 1.77 1.77 1.77 1.77 77.6 1.92 1.92 1.92 1.92 65 2.10 2.10 2.10 2.10 50 2.23 2.23 2.23 2.23 26 2.68 2.68 2.68 2.68 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.26 2.89 3.26 2.89 23 3.48 3.04 3.48 3.04 RCPOOS TBVOOS FHOOS RCPOOS TBVOOS PLUOOS RCPOOS FHOOS PLUOOS RCPOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 31 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.5 MCPRP Limits for ATRIUM-11 Fuel: Nominal Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.53 1.53 1.55 1.52 1.63 1.52 90 1.61 1.61 1.62 1.53 1.74 1.56 77.6 1.75 1.75 1.92 1.65 1.92 1.72 65 1.82 1.82 2.00 1.79 2.00 1.79 50 2.06 2.06 2.10 2.10 2.10 2.10 26 2.45 2.45 2.26 2.22 2.33 2.28 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.63 2.43 2.45 2.43 2.48 2.43 23 2.79 2.57 2.57 2.57 2.57 2.57 100 1.68 1.68 1.61 1.61 1.87 1.87 90 1.82 1.82 1.81 1.81 2.07 2.07 77.6 2.23 2.23 2.15 2.15 2.15 2.15 65 2.38 2.38 2.35 2.35 2.35 2.35 50 2.38 2.38 2.35 2.35 2.35 2.35 26 2.58 2.58 2.35 2.35 2.35 2.35 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.75 2.88 2.75 2.97 2.75 23 3.29 2.98 2.98 2.98 3.03 2.98 100 1.65 1.65 1.63 1.52 90 1.68 1.68 1.74 1.56 77.6 1.84 1.84 1.92 1.72 65 1.95 1.95 2.00 1.79 50 2.19 2.19 2.10 2.10 26 2.75 2.75 2.33 2.28 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.89 2.43 2.48 2.43 23 2.90 2.57 2.57 2.57 100 1.53 1.53 1.55 1.55 1.63 1.63 90 1.61 1.61 1.62 1.62 1.74 1.74 77.6 1.75 1.75 1.92 1.92 1.92 1.92 65 1.82 1.82 2.00 2.00 2.00 2.00 50 2.06 2.06 2.10 2.10 2.10 2.10 26 2.45 2.45 2.26 2.26 2.33 2.33 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.63 2.43 2.45 2.43 2.48 2.43 23 2.79 2.57 2.57 2.57 2.57 2.57 Base Case TBVOOS FHOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 32 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.5 MCPRP Limits for ATRIUM-11 Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.95 1.95 1.87 1.87 90 1.95 1.95 2.07 2.07 77.6 2.26 2.26 2.15 2.15 65 2.38 2.38 2.35 2.35 50 2.50 2.50 2.35 2.35 26 3.13 3.13 2.35 2.35 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.16 2.75 2.97 2.75 23 3.40 2.98 3.03 2.98 100 1.68 1.68 1.61 1.61 1.87 1.87 90 1.82 1.82 1.81 1.81 2.07 2.07 77.6 2.23 2.23 2.15 2.15 2.15 2.15 65 2.38 2.38 2.35 2.35 2.35 2.35 50 2.38 2.38 2.35 2.35 2.35 2.35 26 2.58 2.58 2.35 2.35 2.35 2.35 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.75 2.88 2.75 2.97 2.75 23 3.29 2.98 2.98 2.98 3.03 2.98 100 1.65 1.65 1.63 1.63 90 1.68 1.68 1.74 1.74 77.6 1.84 1.84 1.92 1.92 65 1.95 1.95 2.00 2.00 50 2.19 2.19 2.10 2.10 26 2.75 2.75 2.33 2.33 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.89 2.43 2.48 2.43 23 2.90 2.57 2.57 2.57 100 1.95 1.95 1.87 1.87 90 1.95 1.95 2.07 2.07 77.6 2.26 2.26 2.15 2.15 65 2.38 2.38 2.35 2.35 50 2.50 2.50 2.35 2.35 26 3.13 3.13 2.35 2.35 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.16 2.75 2.97 2.75 23 3.40 2.98 3.03 2.98 TBVOOS FHOOS TBVOOS PLUOOS FHOOS PLUOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 33 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.5 MCPRP Limits for ATRIUM-11 Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.54 1.54 1.56 1.53 1.64 1.53 90 1.62 1.62 1.63 1.54 1.75 1.57 77.6 1.76 1.76 1.93 1.66 1.93 1.73 65 1.83 1.83 2.01 1.80 2.01 1.80 50 2.07 2.07 2.11 2.11 2.11 2.11 26 2.46 2.46 2.27 2.23 2.34 2.29 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.64 2.44 2.46 2.44 2.49 2.44 23 2.80 2.58 2.58 2.58 2.58 2.58 100 1.69 1.69 1.62 1.62 1.88 1.88 90 1.83 1.83 1.82 1.82 2.08 2.08 77.6 2.24 2.24 2.16 2.16 2.16 2.16 65 2.39 2.39 2.36 2.36 2.36 2.36 50 2.39 2.39 2.36 2.36 2.36 2.36 26 2.59 2.59 2.36 2.36 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.76 2.89 2.76 2.98 2.76 23 3.30 2.99 2.99 2.99 3.04 2.99 100 1.66 1.66 1.64 1.53 90 1.69 1.69 1.75 1.57 77.6 1.85 1.85 1.93 1.73 65 1.96 1.96 2.01 1.80 50 2.20 2.20 2.11 2.11 26 2.76 2.76 2.34 2.29 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.90 2.44 2.49 2.44 23 2.91 2.58 2.58 2.58 100 1.54 1.54 1.56 1.56 1.64 1.64 90 1.62 1.62 1.63 1.63 1.75 1.75 77.6 1.76 1.76 1.93 1.93 1.93 1.93 65 1.83 1.83 2.01 2.01 2.01 2.01 50 2.07 2.07 2.11 2.11 2.11 2.11 26 2.46 2.46 2.27 2.27 2.34 2.34 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.64 2.44 2.46 2.44 2.49 2.44 23 2.80 2.58 2.58 2.58 2.58 2.58 Base Case RCPOOS RCPOOS TBVOOS RCPOOS FHOOS RCPOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 34 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.5 MCPRP Limits for ATRIUM-11 Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.96 1.96 1.88 1.88 90 1.96 1.96 2.08 2.08 77.6 2.27 2.27 2.16 2.16 65 2.39 2.39 2.36 2.36 50 2.51 2.51 2.36 2.36 26 3.14 3.14 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.17 2.76 2.98 2.76 23 3.41 2.99 3.04 2.99 100 1.69 1.69 1.62 1.62 1.88 1.88 90 1.83 1.83 1.82 1.82 2.08 2.08 77.6 2.24 2.24 2.16 2.16 2.16 2.16 65 2.39 2.39 2.36 2.36 2.36 2.36 50 2.39 2.39 2.36 2.36 2.36 2.36 26 2.59 2.59 2.36 2.36 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.76 2.89 2.76 2.98 2.76 23 3.30 2.99 2.99 2.99 3.04 2.99 100 1.66 1.66 1.64 1.64 90 1.69 1.69 1.75 1.75 77.6 1.85 1.85 1.93 1.93 65 1.96 1.96 2.01 2.01 50 2.20 2.20 2.11 2.11 26 2.76 2.76 2.34 2.34 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.90 2.44 2.49 2.44 23 2.91 2.58 2.58 2.58 100 1.96 1.96 1.88 1.88 90 1.96 1.96 2.08 2.08 77.6 2.27 2.27 2.16 2.16 65 2.39 2.39 2.36 2.36 50 2.51 2.51 2.36 2.36 26 3.14 3.14 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.17 2.76 2.98 2.76 23 3.41 2.99 3.04 2.99 RCPOOS TBVOOS FHOOS RCPOOS TBVOOS PLUOOS RCPOOS FHOOS PLUOOS RCPOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 35 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.6 MCPRP Limits for ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.58 1.58 1.58 1.58 1.62 1.62 90 1.68 1.68 1.68 1.68 1.77 1.77 77.6 1.89 1.89 1.89 1.89 1.95 1.95 65 2.07 2.07 2.07 2.07 2.17 2.17 50 2.26 2.26 2.26 2.26 2.35 2.35 26 2.59 2.59 2.59 2.59 2.64 2.64 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.76 2.51 2.76 2.51 2.87 2.51 23 2.86 2.59 2.86 2.59 2.87 2.59 100 1.74 1.74 1.74 1.74 1.75 1.75 90 1.80 1.80 1.80 1.80 1.81 1.81 77.6 1.98 1.98 1.98 1.98 1.98 1.98 65 2.09 2.09 2.09 2.09 2.19 2.19 50 2.32 2.32 2.32 2.32 2.40 2.40 26 2.66 2.66 2.66 2.66 2.74 2.74 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.09 2.88 3.09 2.88 3.25 2.88 23 3.33 3.03 3.33 3.03 3.47 3.03 100 1.62 1.62 1.62 1.62 90 1.77 1.77 1.77 1.77 77.6 1.95 1.95 1.95 1.95 65 2.17 2.17 2.17 2.17 50 2.35 2.35 2.35 2.35 26 2.64 2.64 2.64 2.64 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.87 2.51 2.87 2.51 23 2.87 2.59 2.87 2.59 100 1.58 1.58 1.58 1.58 1.62 1.62 90 1.68 1.68 1.68 1.68 1.77 1.77 77.6 1.89 1.89 1.89 1.89 1.95 1.95 65 2.07 2.07 2.07 2.07 2.17 2.17 50 2.26 2.26 2.26 2.26 2.35 2.35 26 2.59 2.59 2.59 2.59 2.64 2.64 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.76 2.51 2.76 2.51 2.87 2.51 23 2.86 2.59 2.86 2.59 2.87 2.59 Base Case TBVOOS FHOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 36 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.6 MCPRP Limits for ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.75 1.75 1.75 1.75 90 1.81 1.81 1.81 1.81 77.6 1.98 1.98 1.98 1.98 65 2.19 2.19 2.19 2.19 50 2.40 2.40 2.40 2.40 26 2.74 2.74 2.74 2.74 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.25 2.88 3.25 2.88 23 3.47 3.03 3.47 3.03 100 1.74 1.74 1.74 1.74 1.75 1.75 90 1.80 1.80 1.80 1.80 1.81 1.81 77.6 1.98 1.98 1.98 1.98 1.98 1.98 65 2.09 2.09 2.09 2.09 2.19 2.19 50 2.32 2.32 2.32 2.32 2.40 2.40 26 2.66 2.66 2.66 2.66 2.74 2.74 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.09 2.88 3.09 2.88 3.25 2.88 23 3.33 3.03 3.33 3.03 3.47 3.03 100 1.62 1.62 1.62 1.62 90 1.77 1.77 1.77 1.77 77.6 1.95 1.95 1.95 1.95 65 2.17 2.17 2.17 2.17 50 2.35 2.35 2.35 2.35 26 2.64 2.64 2.64 2.64 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.87 2.51 2.87 2.51 23 2.87 2.59 2.87 2.59 100 1.75 1.75 1.75 1.75 90 1.81 1.81 1.81 1.81 77.6 1.98 1.98 1.98 1.98 65 2.19 2.19 2.19 2.19 50 2.40 2.40 2.40 2.40 26 2.74 2.74 2.74 2.74 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.25 2.88 3.25 2.88 23 3.47 3.03 3.47 3.03 TBVOOS FHOOS TBVOOS PLUOOS FHOOS PLUOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 37 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.6 MCPRP Limits for ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.59 1.59 1.59 1.59 1.63 1.63 90 1.69 1.69 1.69 1.69 1.78 1.78 77.6 1.90 1.90 1.90 1.90 1.96 1.96 65 2.08 2.08 2.08 2.08 2.18 2.18 50 2.27 2.27 2.27 2.27 2.36 2.36 26 2.60 2.60 2.60 2.60 2.65 2.65 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.77 2.52 2.77 2.52 2.88 2.52 23 2.87 2.60 2.87 2.60 2.88 2.60 100 1.75 1.75 1.75 1.75 1.76 1.76 90 1.81 1.81 1.81 1.81 1.82 1.82 77.6 1.99 1.99 1.99 1.99 1.99 1.99 65 2.10 2.10 2.10 2.10 2.20 2.20 50 2.33 2.33 2.33 2.33 2.41 2.41 26 2.67 2.67 2.67 2.67 2.75 2.75 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.10 2.89 3.10 2.89 3.26 2.89 23 3.34 3.04 3.34 3.04 3.48 3.04 100 1.63 1.63 1.63 1.63 90 1.78 1.78 1.78 1.78 77.6 1.96 1.96 1.96 1.96 65 2.18 2.18 2.18 2.18 50 2.36 2.36 2.36 2.36 26 2.65 2.65 2.65 2.65 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.88 2.52 2.88 2.52 23 2.88 2.60 2.88 2.60 100 1.59 1.59 1.59 1.59 1.63 1.63 90 1.69 1.69 1.69 1.69 1.78 1.78 77.6 1.90 1.90 1.90 1.90 1.96 1.96 65 2.08 2.08 2.08 2.08 2.18 2.18 50 2.27 2.27 2.27 2.27 2.36 2.36 26 2.60 2.60 2.60 2.60 2.65 2.65 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.77 2.52 2.77 2.52 2.88 2.52 23 2.87 2.60 2.87 2.60 2.88 2.60 Base Case RCPOOS RCPOOS TBVOOS RCPOOS FHOOS RCPOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 38 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.6 MCPRP Limits for ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.76 1.76 1.76 1.76 90 1.82 1.82 1.82 1.82 77.6 1.99 1.99 1.99 1.99 65 2.20 2.20 2.20 2.20 50 2.41 2.41 2.41 2.41 26 2.75 2.75 2.75 2.75 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.26 2.89 3.26 2.89 23 3.48 3.04 3.48 3.04 100 1.75 1.75 1.75 1.75 1.76 1.76 90 1.81 1.81 1.81 1.81 1.82 1.82 77.6 1.99 1.99 1.99 1.99 1.99 1.99 65 2.10 2.10 2.10 2.10 2.20 2.20 50 2.33 2.33 2.33 2.33 2.41 2.41 26 2.67 2.67 2.67 2.67 2.75 2.75 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.10 2.89 3.10 2.89 3.26 2.89 23 3.34 3.04 3.34 3.04 3.48 3.04 100 1.63 1.63 1.63 1.63 90 1.78 1.78 1.78 1.78 77.6 1.96 1.96 1.96 1.96 65 2.18 2.18 2.18 2.18 50 2.36 2.36 2.36 2.36 26 2.65 2.65 2.65 2.65 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.88 2.52 2.88 2.52 23 2.88 2.60 2.88 2.60 100 1.76 1.76 1.76 1.76 90 1.82 1.82 1.82 1.82 77.6 1.99 1.99 1.99 1.99 65 2.20 2.20 2.20 2.20 50 2.41 2.41 2.41 2.41 26 2.75 2.75 2.75 2.75 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.26 2.89 3.26 2.89 23 3.48 3.04 3.48 3.04 RCPOOS TBVOOS FHOOS RCPOOS TBVOOS PLUOOS RCPOOS FHOOS PLUOOS RCPOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 39 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.7 MCPRP Limits for ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.60 1.60 1.60 1.56 1.63 1.56 90 1.70 1.70 1.63 1.56 1.79 1.57 77.6 1.84 1.84 1.92 1.68 1.92 1.74 65 1.91 1.91 2.04 1.80 2.04 1.82 50 2.16 2.16 2.10 2.10 2.10 2.10 26 2.60 2.60 2.28 2.22 2.33 2.28 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.63 2.43 2.45 2.43 2.48 2.43 23 2.79 2.57 2.57 2.57 2.57 2.57 100 2.10 2.10 1.71 1.71 1.87 1.87 90 2.22 2.22 1.87 1.87 2.19 2.19 77.6 2.65 2.65 2.27 2.27 2.27 2.27 65 2.65 2.65 2.35 2.35 2.35 2.35 50 2.65 2.65 2.35 2.35 2.35 2.35 26 2.81 2.81 2.35 2.35 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.75 2.88 2.75 2.97 2.75 23 3.29 2.98 2.98 2.98 3.03 2.98 100 1.87 1.87 1.63 1.56 90 1.87 1.87 1.79 1.57 77.6 1.94 1.94 1.92 1.74 65 2.08 2.08 2.04 1.82 50 2.29 2.29 2.10 2.10 26 2.80 2.80 2.33 2.28 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.89 2.43 2.48 2.43 23 2.90 2.57 2.57 2.57 100 1.60 1.60 1.60 1.60 1.63 1.63 90 1.70 1.70 1.63 1.63 1.79 1.79 77.6 1.84 1.84 1.92 1.92 1.92 1.92 65 1.91 1.91 2.04 2.04 2.04 2.04 50 2.16 2.16 2.10 2.10 2.10 2.10 26 2.60 2.60 2.28 2.28 2.33 2.33 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.63 2.43 2.45 2.43 2.48 2.43 23 2.79 2.57 2.57 2.57 2.57 2.57 Base Case TBVOOS FHOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 40 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.7 MCPRP Limits for ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.27 2.27 1.87 1.87 90 2.27 2.27 2.19 2.19 77.6 2.86 2.86 2.27 2.27 65 2.86 2.86 2.35 2.35 50 2.86 2.86 2.35 2.35 26 3.35 3.35 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.35 2.75 2.97 2.75 23 3.40 2.98 3.03 2.98 100 2.10 2.10 1.72 1.72 1.87 1.87 90 2.22 2.22 1.87 1.87 2.19 2.19 77.6 2.65 2.65 2.27 2.27 2.27 2.27 65 2.65 2.65 2.35 2.35 2.35 2.35 50 2.65 2.65 2.35 2.35 2.35 2.35 26 2.81 2.81 2.35 2.35 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.75 2.88 2.75 2.97 2.75 23 3.29 2.98 2.98 2.98 3.03 2.98 100 1.87 1.87 1.63 1.63 90 1.87 1.87 1.79 1.79 77.6 1.94 1.94 1.92 1.92 65 2.08 2.08 2.04 2.04 50 2.29 2.29 2.10 2.10 26 2.80 2.80 2.33 2.33 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.89 2.43 2.48 2.43 23 2.90 2.57 2.57 2.57 100 2.27 2.27 1.87 1.87 90 2.27 2.27 2.19 2.19 77.6 2.86 2.86 2.27 2.27 65 2.86 2.86 2.35 2.35 50 2.86 2.86 2.35 2.35 26 3.35 3.35 2.36 2.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.35 2.75 2.97 2.75 23 3.40 2.98 3.03 2.98 TBVOOS FHOOS TBVOOS PLUOOS FHOOS PLUOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 41 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.7 MCPRP Limits for ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 1.61 1.61 1.61 1.57 1.64 1.57 90 1.71 1.71 1.64 1.57 1.80 1.58 77.6 1.85 1.85 1.93 1.69 1.93 1.75 65 1.92 1.92 2.05 1.81 2.05 1.83 50 2.17 2.17 2.11 2.11 2.11 2.11 26 2.61 2.61 2.29 2.23 2.34 2.29 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.64 2.44 2.46 2.44 2.49 2.44 23 2.80 2.58 2.58 2.58 2.58 2.58 100 2.11 2.11 1.72 1.72 1.88 1.88 90 2.23 2.23 1.88 1.88 2.20 2.20 77.6 2.66 2.66 2.28 2.28 2.28 2.28 65 2.66 2.66 2.36 2.36 2.36 2.36 50 2.66 2.66 2.36 2.36 2.36 2.36 26 2.82 2.82 2.36 2.36 2.37 2.37 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.76 2.89 2.76 2.98 2.76 23 3.30 2.99 2.99 2.99 3.04 2.99 100 1.88 1.88 1.64 1.57 90 1.88 1.88 1.80 1.58 77.6 1.95 1.95 1.93 1.75 65 2.09 2.09 2.05 1.83 50 2.30 2.30 2.11 2.11 26 2.81 2.81 2.34 2.29 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.90 2.44 2.49 2.44 23 2.91 2.58 2.58 2.58 100 1.61 1.61 1.61 1.61 1.64 1.64 90 1.71 1.71 1.64 1.64 1.80 1.80 77.6 1.85 1.85 1.93 1.93 1.93 1.93 65 1.92 1.92 2.05 2.05 2.05 2.05 50 2.17 2.17 2.11 2.11 2.11 2.11 26 2.61 2.61 2.29 2.29 2.34 2.34 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.64 2.44 2.46 2.44 2.49 2.44 23 2.80 2.58 2.58 2.58 2.58 2.58 Base Case RCPOOS RCPOOS TBVOOS RCPOOS FHOOS RCPOOS PLUOOS BOC NEOC EOCLB to to to End of NEOC EOCLB Coast

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 42 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.7 MCPRP Limits for ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.28 2.28 1.88 1.88 90 2.28 2.28 2.20 2.20 77.6 2.87 2.87 2.28 2.28 65 2.87 2.87 2.36 2.36 50 2.87 2.87 2.36 2.36 26 3.36 3.36 2.37 2.37 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.36 2.76 2.98 2.76 23 3.41 2.99 3.04 2.99 100 2.11 2.11 1.73 1.73 1.88 1.88 90 2.23 2.23 1.88 1.88 2.20 2.20 77.6 2.66 2.66 2.28 2.28 2.28 2.28 65 2.66 2.66 2.36 2.36 2.36 2.36 50 2.66 2.66 2.36 2.36 2.36 2.36 26 2.82 2.82 2.36 2.36 2.37 2.37 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.76 2.89 2.76 2.98 2.76 23 3.30 2.99 2.99 2.99 3.04 2.99 100 1.88 1.88 1.64 1.64 90 1.88 1.88 1.80 1.80 77.6 1.95 1.95 1.93 1.93 65 2.09 2.09 2.05 2.05 50 2.30 2.30 2.11 2.11 26 2.81 2.81 2.34 2.34 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 2.90 2.44 2.49 2.44 23 2.91 2.58 2.58 2.58 100 2.28 2.28 1.88 1.88 90 2.28 2.28 2.20 2.20 77.6 2.87 2.87 2.28 2.28 65 2.87 2.87 2.36 2.36 50 2.87 2.87 2.36 2.36 26 3.36 3.36 2.37 2.37 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.36 2.76 2.98 2.76 23 3.41 2.99 3.04 2.99 RCPOOS TBVOOS FHOOS RCPOOS TBVOOS PLUOOS RCPOOS FHOOS PLUOOS RCPOOS TBVOOS FHOOS PLUOOS NEOC EOCLB Coast BOC NEOC EOCLB to to to End of

All limits, including Base Case, support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for EOCLB to End of COAST due to redundancy.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 43 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.8 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-10XM Fuel: Nominal Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.21 2.21 2.21 2.21 2.21 2.21 50 2.21 2.21 2.21 2.21 2.21 2.21 26 2.84 2.84 2.84 2.84 2.84 2.84 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.13 2.51 3.13 2.51 3.13 2.51 23 3.13 2.59 3.13 2.59 3.13 2.59 100 2.22 2.22 2.22 2.22 2.22 2.22 50 2.22 2.22 2.22 2.22 2.22 2.22 26 2.84 2.84 2.84 2.84 2.84 2.84 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.51 2.88 3.51 2.88 3.51 2.88 23 3.74 3.03 3.74 3.03 3.74 3.03 100 2.21 2.21 2.21 2.21 2.21 2.21 50 2.21 2.21 2.21 2.21 2.21 2.21 26 2.84 2.84 2.84 2.84 2.84 2.84 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.13 2.51 3.13 2.51 3.13 2.51 23 3.13 2.59 3.13 2.59 3.13 2.59 100 2.22 2.22 2.22 2.22 2.22 2.22 50 2.22 2.22 2.22 2.22 2.22 2.22 26 2.84 2.84 2.84 2.84 2.84 2.84 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.51 2.88 3.51 2.88 3.51 2.88 23 3.74 3.03 3.74 3.03 3.74 3.03 Startup FHOOS 2 TBVIS Startup FHOOS 2 TBVOOS NEOC EOCLB Coast Startup FHOOS 1 TBVIS Startup FHOOS 1 TBVOOS BOC NEOC EOCLB to to to End of

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 44 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.8 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-10XM Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.22 2.22 2.22 2.22 2.22 2.22 50 2.22 2.22 2.22 2.22 2.22 2.22 26 2.85 2.85 2.85 2.85 2.85 2.85 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.14 2.52 3.14 2.52 3.14 2.52 23 3.14 2.60 3.14 2.60 3.14 2.60 100 2.23 2.23 2.23 2.23 2.23 2.23 50 2.23 2.23 2.23 2.23 2.23 2.23 26 2.85 2.85 2.85 2.85 2.85 2.85 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.52 2.89 3.52 2.89 3.52 2.89 23 3.75 3.04 3.75 3.04 3.75 3.04 100 2.22 2.22 2.22 2.22 2.22 2.22 50 2.22 2.22 2.22 2.22 2.22 2.22 26 2.85 2.85 2.85 2.85 2.85 2.85 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.14 2.52 3.14 2.52 3.14 2.52 23 3.14 2.60 3.14 2.60 3.14 2.60 100 2.23 2.23 2.23 2.23 2.23 2.23 50 2.23 2.23 2.23 2.23 2.23 2.23 26 2.85 2.85 2.85 2.85 2.85 2.85 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.52 2.89 3.52 2.89 3.52 2.89 23 3.75 3.04 3.75 3.04 3.75 3.04 Startup RCPOOS FHOOS 1 TBVIS Startup RCPOOS FHOOS 1 TBVOOS Startup RCPOOS FHOOS 2 TBVIS Startup RCPOOS FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 45 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.9 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-11 Fuel: Nominal Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.20 2.20 2.20 2.20 2.20 2.20 50 2.20 2.20 2.20 2.20 2.20 2.20 26 2.75 2.75 2.75 2.75 2.75 2.75 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.43 3.05 2.43 3.05 2.43 23 3.05 2.57 3.05 2.57 3.05 2.57 100 2.50 2.50 2.50 2.50 2.50 2.50 50 2.50 2.50 2.50 2.50 2.50 2.50 26 3.13 3.13 3.13 3.13 3.13 3.13 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.45 2.75 3.45 2.75 3.45 2.75 23 3.65 2.98 3.65 2.98 3.65 2.98 100 2.20 2.20 2.20 2.20 2.20 2.20 50 2.20 2.20 2.20 2.20 2.20 2.20 26 2.75 2.75 2.75 2.75 2.75 2.75 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.43 3.05 2.43 3.05 2.43 23 3.05 2.57 3.05 2.57 3.05 2.57 100 2.50 2.50 2.50 2.50 2.50 2.50 50 2.50 2.50 2.50 2.50 2.50 2.50 26 3.13 3.13 3.13 3.13 3.13 3.13 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.45 2.75 3.45 2.75 3.45 2.75 23 3.65 2.98 3.65 2.98 3.65 2.98 Startup FHOOS 1 TBVIS Startup FHOOS 1 TBVOOS Startup FHOOS 2 TBVIS Startup FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 46 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.9 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-11 Fuel: Nominal Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.21 2.21 2.21 2.21 2.21 2.21 50 2.21 2.21 2.21 2.21 2.21 2.21 26 2.76 2.76 2.76 2.76 2.76 2.76 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.44 3.06 2.44 3.06 2.44 23 3.06 2.58 3.06 2.58 3.06 2.58 100 2.51 2.51 2.51 2.51 2.51 2.51 50 2.51 2.51 2.51 2.51 2.51 2.51 26 3.14 3.14 3.14 3.14 3.14 3.14 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.46 2.76 3.46 2.76 3.46 2.76 23 3.66 2.99 3.66 2.99 3.66 2.99 100 2.21 2.21 2.21 2.21 2.21 2.21 50 2.21 2.21 2.21 2.21 2.21 2.21 26 2.76 2.76 2.76 2.76 2.76 2.76 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.44 3.06 2.44 3.06 2.44 23 3.06 2.58 3.06 2.58 3.06 2.58 100 2.51 2.51 2.51 2.51 2.51 2.51 50 2.51 2.51 2.51 2.51 2.51 2.51 26 3.14 3.14 3.14 3.14 3.14 3.14 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.46 2.76 3.46 2.76 3.46 2.76 23 3.66 2.99 3.66 2.99 3.66 2.99 Startup RCPOOS FHOOS 1 TBVIS Startup RCPOOS FHOOS 1 TBVOOS Startup RCPOOS FHOOS 2 TBVIS Startup RCPOOS FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 47 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.10 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.35 2.35 2.35 2.35 2.35 2.35 50 2.35 2.35 2.35 2.35 2.35 2.35 26 2.88 2.88 2.88 2.88 2.88 2.88 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.13 2.51 3.13 2.51 3.13 2.51 23 3.13 2.59 3.13 2.59 3.13 2.59 100 2.40 2.40 2.40 2.40 2.40 2.40 50 2.40 2.40 2.40 2.40 2.40 2.40 26 2.92 2.92 2.92 2.92 2.92 2.92 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.51 2.88 3.51 2.88 3.51 2.88 23 3.74 3.03 3.74 3.03 3.74 3.03 100 2.35 2.35 2.35 2.35 2.35 2.35 50 2.35 2.35 2.35 2.35 2.35 2.35 26 2.88 2.88 2.88 2.88 2.88 2.88 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.13 2.51 3.13 2.51 3.13 2.51 23 3.13 2.59 3.13 2.59 3.13 2.59 100 2.40 2.40 2.40 2.40 2.40 2.40 50 2.40 2.40 2.40 2.40 2.40 2.40 26 2.92 2.92 2.92 2.92 2.92 2.92 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.51 2.88 3.51 2.88 3.51 2.88 23 3.74 3.03 3.74 3.03 3.74 3.03 Startup FHOOS 1 TBVIS Startup FHOOS 1 TBVOOS Startup FHOOS 2 TBVIS Startup FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 48 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.10 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-10XM Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.36 2.36 2.36 2.36 2.36 2.36 50 2.36 2.36 2.36 2.36 2.36 2.36 26 2.89 2.89 2.89 2.89 2.89 2.89 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.14 2.52 3.14 2.52 3.14 2.52 23 3.14 2.60 3.14 2.60 3.14 2.60 100 2.41 2.41 2.41 2.41 2.41 2.41 50 2.41 2.41 2.41 2.41 2.41 2.41 26 2.93 2.93 2.93 2.93 2.93 2.93 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.52 2.89 3.52 2.89 3.52 2.89 23 3.75 3.04 3.75 3.04 3.75 3.04 100 2.36 2.36 2.36 2.36 2.36 2.36 50 2.36 2.36 2.36 2.36 2.36 2.36 26 2.89 2.89 2.89 2.89 2.89 2.89 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.14 2.52 3.14 2.52 3.14 2.52 23 3.14 2.60 3.14 2.60 3.14 2.60 100 2.41 2.41 2.41 2.41 2.41 2.41 50 2.41 2.41 2.41 2.41 2.41 2.41 26 2.93 2.93 2.93 2.93 2.93 2.93 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.52 2.89 3.52 2.89 3.52 2.89 23 3.75 3.04 3.75 3.04 3.75 3.04 Startup RCPOOS FHOOS 1 TBVIS Startup RCPOOS FHOOS 1 TBVOOS Startup RCPOOS FHOOS 2 TBVIS Startup RCPOOS FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 49 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.11 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.33 2.33 2.33 2.33 2.33 2.33 50 2.33 2.33 2.33 2.33 2.33 2.33 26 2.80 2.80 2.80 2.80 2.80 2.80 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.43 3.05 2.43 3.05 2.43 23 3.05 2.57 3.05 2.57 3.05 2.57 100 2.86 2.86 2.86 2.86 2.86 2.86 50 2.86 2.86 2.86 2.86 2.86 2.86 26 3.35 3.35 3.35 3.35 3.35 3.35 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.45 2.75 3.45 2.75 3.45 2.75 23 3.65 2.98 3.65 2.98 3.65 2.98 100 2.33 2.33 2.33 2.33 2.33 2.33 50 2.33 2.33 2.33 2.33 2.33 2.33 26 2.80 2.80 2.80 2.80 2.80 2.80 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.05 2.43 3.05 2.43 3.05 2.43 23 3.05 2.57 3.05 2.57 3.05 2.57 100 2.86 2.86 2.86 2.86 2.86 2.86 50 2.86 2.86 2.86 2.86 2.86 2.86 26 3.35 3.35 3.35 3.35 3.35 3.35 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.45 2.75 3.45 2.75 3.45 2.75 23 3.65 2.98 3.65 2.98 3.65 2.98 Startup FHOOS 1 TBVIS Startup FHOOS 1 TBVOOS Startup FHOOS 2 TBVIS Startup FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 50 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 5.11 Startup Operation MCPRP Limits for Table 4.1 Temperature Ranges, ATRIUM-11 Fuel: Tech. Spec. Scram Time Basis (continued)

Power

(% of rated)

Flow Flag -->

> 90%F

)

> 90%F

)

> 90%F

)

100 2.34 2.34 2.34 2.34 2.34 2.34 50 2.34 2.34 2.34 2.34 2.34 2.34 26 2.81 2.81 2.81 2.81 2.81 2.81 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.44 3.06 2.44 3.06 2.44 23 3.06 2.58 3.06 2.58 3.06 2.58 100 2.87 2.87 2.87 2.87 2.87 2.87 50 2.87 2.87 2.87 2.87 2.87 2.87 26 3.36 3.36 3.36 3.36 3.36 3.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.46 2.76 3.46 2.76 3.46 2.76 23 3.66 2.99 3.66 2.99 3.66 2.99 100 2.34 2.34 2.34 2.34 2.34 2.34 50 2.34 2.34 2.34 2.34 2.34 2.34 26 2.81 2.81 2.81 2.81 2.81 2.81 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.06 2.44 3.06 2.44 3.06 2.44 23 3.06 2.58 3.06 2.58 3.06 2.58 100 2.87 2.87 2.87 2.87 2.87 2.87 50 2.87 2.87 2.87 2.87 2.87 2.87 26 3.36 3.36 3.36 3.36 3.36 3.36 NDS Flow Flag

> 50%F

)

> 50%F

)

> 50%F

)

26 3.46 2.76 3.46 2.76 3.46 2.76 23 3.66 2.99 3.66 2.99 3.66 2.99 Startup RCPOOS FHOOS 1 TBVIS Startup RCPOOS FHOOS 1 TBVOOS Startup RCPOOS FHOOS 2 TBVIS Startup RCPOOS FHOOS 2 TBVOOS NEOC EOCLB to to to End of NEOC EOCLB Coast BOC

Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Limits are only valid up to 50% rated core power.

RCPOOS limits are only valid up to 43.75% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 51 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 6 Thermal-Hydraulic Stability Protection (Technical Specification 3.3.1.1)

Technical Specification Table 3.3.1.1-1, Function 2f, identifies the function.

Instrument setpoints are established, such that the reactor will be tripped before an oscillation can grow to the point where the SLMCPR is exceeded. With application of Reference 31, the DSS-CD stability solution as originally per Reference 32 is now used in a hybrid manner, per Reference 27. The DSS-CD SAD setpoint is 1.10 for TLO and SLO.

New analyses have been developed based on Reference 27. With the implementation of the MELLLA+ operating domain expansion, an ABSP trip is required when the OPRM is out-of-service. The ABSP trip settings define a region of the power to flow map within which an automatic reactor scram occurs. The ABSP trip settings are provided in Table 6.1. If both the OPRM and ABSP are out-of-service, operation within the MELLLA+ domain is not allowed and the MBSP Regions provide stability protection. Table 6.2 and Table 6.3 provide the endpoints for the MBSP regions for nominal and reduced feedwater temperature conditions.

Table 6.1 ABSP Setpoints for the Scram Region Parameter Symbol Setting Value (unit)

Comments Slope for Trip mTRIP 2.00 (% RTP/% RDF)

Slope of ABSP APRM low Flow Biased Trip Linear Segment Constant Power Line for Trip PBSP-TRIP 35.0 (% RTP)

ABSP APRM Flow Biased Trip Setpoint Power Intercept. Constant Power Line for Trip from Zero Drive Flow to Flow Breakpoint Value Constant Flow Line for Trip WBSP-TRIP 49 (% RDF)

ABSP APRM Flow Biased Trip Setpoint Drive Flow Intercept.

Constant Flow Line for Trip (see Note 1 below)

Flow Breakpoint WBSP-BREAK 30.0 (% RDF)

Flow Breakpoint Value Note 1: WBSP-TRIP can be set to 49.0 % RDF or any higher value up to the intersection of the ABSP sloped line with the APRM Flow Biased STP scram line.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 52 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 6.2 Analyzed MBSP Endpoints: Nominal Feedwater Temperature Endpoint Power

(% Rated)

Core Flow

(% Rated)

Definition A1 75.9 52.7 Scram Region (Region I)

Boundary Intercept on MELLLA+

Line B1 35.5 29.0 Scram Region (Region I)

Boundary Intercept on Natural Circulation Line (NCL)

A2 66.1 52.0 Controlled Entry Region (Region II) Boundary Intercept on MELLLA Line B2 25.5 29.0 Controlled Entry Region (Region II) Boundary Intercept on Natural Circulation Line (NCL)

Table 6.3 Analyzed MBSP Endpoints: Reduced Feedwater Temperature Endpoint Power

(% Rated)

Core Flow

(% Rated)

Definition A1 64.9 50.5 Scram Region (Region I)

Boundary Intercept on MELLLA Line B1 29.4 29.0 Scram Region (Region I)

Boundary Intercept on Natural Circulation Line (NCL)

A2 68.3 54.9 Controlled Entry Region (Region II) Boundary Intercept on MELLLA Line B2 24.5 29.0 Controlled Entry Region (Region II) Boundary Intercept on Natural Circulation Line (NCL)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 53 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 7 APRM Flow Biased Rod Block Trip Settings (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

The APRM rod block trip setting is based upon References 28 & 30, and is defined by the following:

for two loop operation:

SRB d (0.61Wd + 63.3)

Allowable Value SRB d (0.61Wd + 62.0)

Nominal Trip Setpoint (NTSP) where:

SRB

=

Rod Block setting in percent of rated thermal power (3952 MWt)

Wd

=

Recirculation drive flow rate in percent of rated (100% drive flow required to achieve 100% core power and flow) and for single loop operation:

SRB d (0.55(Wd-'W) + 60.5)

Allowable Value SRB d (0.55(Wd-'W) + 58.5)

Nominal Trip Setpoint (NTSP) where:

SRB

=

Rod Block setting in percent of rated thermal power (3952 MWt)

Wd

=

Recirculation drive flow rate in percent of rated (100% drive flow required to achieve 100% core power and flow)

'W

=

Difference between two-loop and single-loop effective recirculation flow at the same core flow ('W=0.0 for two-loop operation)

The APRM rod block trip setting is clamped at a maximum allowable value of 115%

(corresponding to a NTSP of 113%).

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 54 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 8 Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

The RBM trip setpoints and applicable power ranges, based on References 29, are shown in Table 8.1. Setpoints are based on an HTSP, unfiltered analytical limit of 114%. Unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds; filtered setpoints are consistent with a nominal RBM filter setting less than 0.5 seconds. Cycle specific CRWE analyses of OLMCPR are documented in Reference 1, superseding values reported in References 28, 29, and 30.

Table 8.1 Analytical RBM Trip Setpoints

RBM Trip Setpoint Allowable Value (AV)

Nominal Trip Setpoint (NTSP)

LPSP 27%

25%

IPSP 62%

60%

HPSP 82%

80%

LTSP - unfiltered

- filtered 121.7%

120.7%

120.0%

119.0%

ITSP

- unfiltered

- filtered 116.7%

115.7%

115.0%

114.0%

HTSP - unfiltered

- filtered 111.7%

110.9%

110.0%

109.2%

DTSP 90%

92%

As a result of cycle specific CRWE analyses, RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable as shown in Table 8.2. Cycle specific setpoint analysis results are shown in Table 8.3, per Reference 1.

Table 8.2 RBM Setpoint Applicability Thermal Power

(% Rated)

Applicable MCPR Notes from Table 3.3.2.1-1 Comment 27% and < 90%

< 2.02 (a), (b), (f), (h) two loop operation

< 2.04 (a), (b), (f), (h) single loop operation 90%

< 1.52 (g) two loop operation

Values are considered maximums. Using lower values, due to RBM system hardware/software limitations, is conservative, and acceptable.

MCPR values shown correspond with, (support), values identified in Table 1.1.

Greater than 90% rated power is not attainable in single loop operation.

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 55 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Table 8.3 Control Rod Withdrawal Error Results RBM CRWE HTSP Analytical Limit OLMCPR Unfiltered 107 1.35 111 1.39 114 1.42 117 1.48 Results, compared against the base case OLMCPR results of Table 5.2 & Table 5.3, indicate Table 2.1 MCPR99.9 remains protected for RBM inoperable conditions (i.e., 114% unblocked).

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page 56 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 9 Shutdown Margin Limit (Technical Specification 3.1.1)

Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLE control blades are fully inserted, the core shall be sub-critical and meet the following minimum shutdown margin:

SDM 0.38% dk/k

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page A-1 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final)

Appendix A: MBSP Maps

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page A-2 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0 10 20 30 40 50 60 70 80 90 100 110 0

10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated: 100% =102.5 MLbm/hr)

Core Power (% Rated: 100% = 3952MWt)

Natural Circulation MELLLA Region ICF Region 20% Pump Speed Line Min. Power Line Min. Flow Control 87.5% Rod Line MELLLA Upper Boundary MELLLA+ Region Manual Scram Region I Controlled Entry Region II BSP Boundary Figure A.1 MBSP Boundaries For Nominal Feedwater Temperature (Operation in the MELLLA+ Region Prohibited for Feedwater Temperature greater than 10 degrees F below the Nominal Feedwater Temperature)

ECM: L94 220223 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 2, 2023 Browns Ferry Unit 2 Cycle 23 Page A-3 Core Operating Limits Report, (120% OLTP, MELLLA+)

TVA-COLR-BF2C23, Revision 1 (Final) 0 10 20 30 40 50 60 70 80 90 100 110 0

10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated: 100% =102.5 MLbm/hr)

Core Power (% Rated: 100% = 3952MWt)

Natural Circulation MELLLA Region ICF Region 20% Pump Speed Line Min. Power Line Min. Flow Control 87.5% Rod Line MELLLA Upper Boundary MELLLA+ Region Controlled Entry Region II Manual Scram Region I BSP Boundary Figure A.2 MBSP Boundaries For Reduced Feedwater Temperature (Operation in the MELLLA+ Region Prohibited for a Reduced Feedwater Temperature greater than 10 degrees F below the Nominal Feedwater Temperature)

ML23096A320

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