Text

Core Operating Limits Report for Cycle 21 Operation, Revision O
	ML19064B304
Person / Time
Site:	Browns Ferry
Issue date:	03/05/2019
From:	Hughes D L; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML19064B304 (49)
	v • d • e

Tennessee Valley Authority , Post Offi c e Box 2000 , De c atur , Alabama 35609-2 000 March 5, 2019 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Browns F erry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260 Browns Ferry Nuclear Plant, Unit 2 Core Operating Limits Report for Cycle 21 Operation, Revision O 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 21, Core Operating Limits Report (COLR). Revision O of the Unit 2 COLR includes all Modes of operation (Modes 1 through 5). There are no new commitments contained in this letter. If you have any questions please contact M. W. Oliver at (256) 729-7874. D. L. Hughes Site Vice President

Enclosure:

Core Operating Limits Report, (120% OL TP), for Cycle 21 Operation , TVA-COLR-BF2C21, Revision 0 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), for Cycle 21 Operation, TVA-COLR-BF2C21, Revision 0 (See Attached)

USlNPG Reactor Engineering and Fuels -BWRFE 1101 Market Street , Chattanooga , TN 37402 Browns Ferry Unit 2 Cycle 21 Core Operating Limits Report, 120°/o OL TP TV A-COLR-BF2C21 Revision O (Final) (Re vi sion Log , Page v) February 2019 EDMS L94 190211 800 QA Document BFE-4400 , Revision 0 Prepared c;'=l,.,_

LL V Date: ;:(_,/ 1.:2., o2 6 lo/ T. W. Eichenberg, Sr. Specialist Verified:

Date: :.:s?t5".

Mitchell , Engineer Approved:~ Date: 2/zs/1~ W. B. Bird, Manager , BWR Fuel Engineering Reviewed: Date: z/i5/ir D. D. Coffey, Manage r, Reactor Engineering Approved: Chairman, PORC~ Approved: c. VUNt.J Plant Manag\ Date: o ;J... J;..-, }l'j Date: ____;: 3 1)...:....1 µ( 1_.!0, __

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page ii Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table of Contents Total Number of Pages

= 47 (including review cover sheet

) List of Tables

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

. iii List of Figures ................................

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

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

iv Revision Log

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

. v Nomenclature

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

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

vi References

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

.. viii 1 Introduction

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

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

1 1.1 Purpose ................................

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

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

1 1.2 Scope ................................

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

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

1 1.3 Fuel Loading

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

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

1 1.4 Acceptability

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

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

2 2 APLHGR Limits

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

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

3 2.1 Rated Power and Flow Limit: APLHGRRATED ................................

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

3 2.2 Off-Rated Power Dependent Limit: APLHGR P ................................

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

3 2.2.1 Startup without Feedwater Heaters

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

....... 3 2.3 Off-Rated Flow Dependent Limit: APLHGR F ................................

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

3 2.4 Single Loop Operation Limit: APLHGRSLO ................................

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

.... 3 2.5 Equipment Out

-Of-Service Corrections

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

......... 6 3 LHGR Limits

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

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

7 3.1 Rated Power and Flow Limit: LHGRRATED ................................

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

..... 7 3.2 Off-Rated Power Dependent Limit: LHGR P ................................

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

.. 7 3.2.1 Startup without Feedwater Heaters

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

....... 7 3.3 Off-Rated Flow Dependent Limit: LHGR F ................................

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

..... 8 3.4 Equipment Out

-Of-Service Corrections

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

......... 8 4 OLMCPR Limits

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

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

19 4.1 Flow Dependent MCPR Limit:

MCPR F ................................

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

....... 19 4.2 Power Dependent MCPR Limit:

MCPR P ................................

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

.... 19 4.2.1 Startup without Feedwater Heaters ................................

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

..... 19 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)

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

. 20 4.2.3 Exposure Dependent Limits

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

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

20 4.2.4 Equipment Out

-Of-Service (EOOS) Option s ................................

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

21 4.2.5 Single-Loop-Operation (SLO) Limits

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

... 21 4.2.6 Below Pbypass Limits

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

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

21 5 Oscillation Power Range Monitor (OPRM) Setpoint

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

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

33 6 APRM Flow Biased Rod Block Trip Setti ngs ................................

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

...... 34 7 Rod Block Monitor (RBM) Trip Setpoints and Operability

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

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

35 8 Shutdown Margin Limit

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

....... 37 EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page iii Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) List of Tables Nuclear Fuel Types

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

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

2 Startup Feedwater Temperature Basis

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

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

7 Nominal Scram Time Basis

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

......... 20 MCPR P Limits for All Fuel Types: Optimum Scram Time Basis

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

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23 MCPR P Limits for All Fuel Types: Nominal Scram Time Basis

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

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

24 MCPR P Limits for All Fuel Types: Technical Specification Scram Time Basis

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

26 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 1 for All Fuel Types: Nominal Scram Time Basis

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

..... 28 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 2 for All Fuel Types: Nominal Scram Time Basis

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

..... 29 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 1 for All Fuel Types: Technical Specification Scram Time Basis

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

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

30 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 2 for All Fuel Types: Technical Specification Scram Time Basis

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

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31 MCPR P Limits for All Fuel Types: Single Loop Operation for All Scram Times

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

32 OPRM Setpoint Range

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

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

33 OPRM Successive Confirmation Count Setpoint

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

........ 33 Analytical RBM Trip Setpoints

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

. 35 RBM Setpoint Applicability

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

..........

35 Control Rod Withdrawal Error Results

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

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

36 EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page iv Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) List of Figures APLHGRRATED for ATRIUM

-10XM Fu el ................................

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

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

4 APLHGRRATED for ATRIUM

-11 Fuel ................................

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

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

5 LHGRRATED for ATRIUM

-10XM Fuel ................................

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

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

9 LHGRRATED for ATRIUM

-11 Fuel ................................

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

. 10 Base Operation LHGRFAC P for ATRIUM

-10XM Fuel ................................

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

. 11 Base Operation LHGRFAC P for ATRIUM

-11 Fuel ................................

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

...... 12 LHGRFAC F for ATRIUM

-10XM Fuel ................................

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

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

13 LHGRFAC F for ATRIUM

-11 Fue l ................................

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

14 Startup Operation LHGRFAC P for ATRI UM-10XM Fuel: Table 3.1 Temperature Range 1

........ 15 Startup Operation LHGRFAC P for ATRIUM

-10XM Fuel: Table 3.1 Temperature Range 2

........ 16 Startup Operation LHGRFAC P for ATRIUM

-11 Fuel: Table 3.1 Temperature Rang e 1 ..............

17 Startup Operation LHGRFAC P for ATRIUM

-11 Fuel: Table 3.1 Temperature Range 2

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

18 MCPR F for All Fuel Types

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

...........

22 EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page v Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Revision Log Number Page Description 0-R0 All New docume nt.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page vi Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Nomenclature 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 C D Coast Down CMSS Cor e 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 EOC End of Cycle EOC LB End-of-Cycle Licensing Basis EOOS Equipment OOS 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

MAPFAC MAPLHGR multiplier (Power or Flow dependent)

MCPR Minimum CPR

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page vii Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) MSR V Moisture Separator Reheater Valve MSR VOOS MSR V OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day p er Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP

OLMCPR MCPR Operating Limit 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) RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS 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 T LO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page viii Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) References

1. ANP-3 7 37, Revision 0 , Browns Ferry Unit 2 Cycle 2 1 Reload Analysis , Framatome, Inc., December 201 8. 2. ANP-3031P, Revision 3 , Mechanical Design Report for Browns Ferry Unit s 1, 2, and 3 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., May 20 14. 3. ANP-3150P, Revision 4 , Mechanical Design Report for Browns Ferry ATRIUM 10XM Fuel Assemblies, AREVA Inc., November 2017

. 4. ANP-3 706 P, Revision 0 , Browns Ferry Unit 2 Cycle 2 1 Plant Parameters Document , Framatome Inc., June 201 8. 5. BFE-4 xxx, Revision 0, Browns Ferry Unit 2 Cycle 2 1 In Core Shuffle, Calculation File, Tennessee Valley Authority, February 201 9. 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, Septemb er 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. XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal

-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page ix Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 15. ANP-10307PA, Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP Inc., June 2011.

16. ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

17. ANF-1358(P)(A) Revision 3 , The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 2005. 18. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation , AREVA NP Inc., September 2009.

19. EM F-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 , 201 4. 20. EMF-2292(P)(A) Revision 0, ATRIUMŽ-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

21. 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. 22. BAW-10255(P)(A), Revisio n 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code , AREVA NP Inc., May 2008.

23. BAW-10247PA, Revision 0, Realistic Thermal

-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP Inc., April 2008.

24. ANP-10298PA, Revision 0, ACE/ATRIUM 10XM Critical Power Correlation , AREVA NP Inc., March 2010.

25. ANP-3140(P), Revision 0, Browns Ferry Units 1, 2, and 3 Improved K

-factor Model for ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP Inc., August 2012. PRNM Setpoint References

26. EDQ2092900118, R27, Setpoint and Scaling Calculation for Neutron Monitoring & Recirculation Flow Loops, Calculation File, Tennessee Valley Authority, November 16, 2017. 27. Task T0500, Revision 0, Neutron Monitoring System, Project Task Report, GE Hitachi Nuclear Energy, April 2015. 28. Task T0506, Revision 2, TS Instrument Setpoints, Project Task Report, Tennessee Valley Authority, July 201

5. 29. NEDC-32433P, Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3, GE Nuclear Energy, April 1995.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page x Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 30. NEDO-32465-A, Licensing Topical Report

- Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, GE Nuclear Energy, August 199

6.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 1 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (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:

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)

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)

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)

Oscillation Power Range Monitor (OPRM) Setpoint (Technical Specification Table 3.3.1.1)

Applicability: Mode 1, (as specified in Technical Specifications Table 3.3.1.1

-1) 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 Manual s Table 3.3.4

-1) 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)

Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

Applicability: All Mode s 1.3 Fuel Loading The core will contain fresh and exposed ATRIUM-10 XM, as well as a limited number of ATRIUM-11 lead fuel assemblies. 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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 2 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 1.1 Nuclear Fuel Types

Fuel Description Original Cycle Number of Assemblies Nuclear Fuel Type (NFT) Fuel Names (Range) ATRIUM 10XM XMLC-3904B-15GV80-FBF 19 93 15 FBF401-FBF572 ATRIUM 10XM XMLC

-40 35B-13GV80-FBF 19 58 16 FBF573-FBF652 ATRIUM 11 A11

-3693B-13GV80-FBF 19 6 17 FBF653-FBF660 ATRIUM 10XM XMLC

-4102B-11GV70-FBG-B 20 48 18 FBG701-FBG748 ATRIUM 10XM XMLC-4062B-13GV80-FBG-C 20 15 1 19 FBG749-FBG900 ATRIUM 10XM XMLC

-3948B-13GV70-FBG-B 20 88 20 FBG901-FBG988 ATRIUM-10XM XMLC-408 7 B-1 5 GV 8 0-F B H 21 1 76 2 1 F BH 001-F BH 1 76 ATRIUM-10XM XMLC-4036 B-1 5 GV 8 0-F BH 21 88 22 F BH 1 77-F BH 2 6 4 ATRIUM-10XM XMLC-409 3 B-1 0 GV 8 0-F B h 21 56 23 F BH 2 65-F BH 32 0 1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 6 through 25.

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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 3 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 2 APLHGR Limits (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 ( APLHGR P , APLHGR F, APLHGRSLO ) where: APLHGR P off-rated power APLHGR limit [APLHGRRATED

MAPFAC P] APLHGR F off-rated flow APLHGR limit

[APLHGRRATED

MAPFAC F] APLHGRSLO SLO APLHGR limit

[APLHGRRATED

SLO Multiplier]

2.1 Rated Power and Flow Limit: APLHGRRATED The rated conditions APLHGR for all fuel are identified per Reference 1. The rated conditions APLHGR for ATRIUM

-10 XM fuel are shown in Figure 2.1. The rated conditions APLHGR for ATRIUM-1 1 are shown in Figure 2.2. 2.2 Off-Rated Power Dependent Limit: APLHGR P Reference 1 does not specify a power dependent APLHGR. Therefore, MAPFAC P is set to a value of 1.0. 2.2.1 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 reach ed a significant operating power level. No additional power dependent limitation is required.

2.3 Off-Rated Flow Dependent Limit: APLHGR F Reference 1 does not specify a flow dependent APLHGR. Therefore, MAPFAC F is set to a value of 1.0. 2.4 Single Loop Operation Limit: APLHGRSLO The single loop operation multiplier for ATRIUM

-10 and ATRIUM

-10XM fuel is 0.85, per Reference

1.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 4 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0 3 6 9 12 15 0 20 40 60 80APLHGR (kW/ft)Planar Average Exposure (GWd/MTU)

Planar Avg.APLHGRExposureLimit(GWd/MTU)(kW/ft)0.013.015.013.067.07.6 Figure 2.1 APLHGRRATED for ATRIUM

-10 XM Fuel EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 5 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0 3 6 9 12 15 0 20 40 60 80APLHGR (kW/ft)Planar Average Exposure (GWd/MTU)

Planar Avg.APLHGRExposureLimit(GWd/MTU)(kW/ft)0.0 1010.0 1067.05.9 Figure 2.2 APLHGRRATED fo r ATRIUM-1 1 Fuel EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 6 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 2.5 Equipment Out

-Of-Service Corrections The limit s shown in Figure 2.1 and Figure 2.2 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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 7 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 3 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 ( LHGR P, LHGR F ) where: LHGR P off-rated power LHGR limit

[LHGRRATED

LHGRFAC P] LHGR F off-rated flow LHGR limit

[LHGRRATED

LHGRFAC F] 3.1 Rated Power and Flow Limit: LHGRRATED The rated conditions LHGR for all fuel are identified per Reference

1. The rated conditions LHGR for ATRIUM

-10 XM are shown in Figure 3.1. The rated conditions LHGR for ATRIUM

-1 1 fuel is shown in Figure 3.2. The LHGR limit is consistent with References 2 and 3. 3.2 Off-Rated Power Dependent Limit: LHGR P LHGR limits are adjusted for off

-rated power conditions using the LHGRFAC P multiplier provided in Reference

1. The multiplier is split into two sub cases: turbine b y pass valves in and out-of-service. The base case multipliers are shown in Figure 3.3 and Figure 3.4. 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 reach ed a significant operating power level. Additional limits are shown i n Figure 3.7 through Figure 3.10 , based on temperature conditions identified in Table 3.1. Table 3.1 Startup Feedwater Temperature Basis PowerRange 1Range 2(% Rated)(°F)(°F)23155.0150.0 30162.0157.0 40172.0167.0 50182.0177.0Temperature

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 8 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 3.3 Off-Rated Flow Dependent Limit: LHGR F LHGR limits are adjusted for off

-rated flow conditions using the LHGRFAC F multiplier provided in Reference

1. Multiplier s are shown in Figure 3.5 through Figure 3.6. 3.4 Equipment Out

-Of-Service Corrections The limit s 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 O ff-rated power corrections shown in Figure 3.3 and Figure 3.4 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 3.5 and Figure 3.6 are bounding for all EOOS conditions.

Of f-rated power corrections shown in Figure 3.7 through Figure 3.10 are also dependent on operation of the Turbine Bypass Valve system. In this case, limits support FHOOS operation during startup. The se limits have no dependency on RPTOOS, PLUOOS, or SLO.

All equipment service conditions assume 1 SRVOOS.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0 3 6 9 12 15 0 20 40 60 80LHGR (kW/ft)Pellet Exposure (GWd/MTU)

PelletLHGRExposureLimit(GWd/MTU)(kW/ft)0.014.118.914.174.47.4 Figure 3.1 LHGRRATED for ATRIUM

-10 XM Fuel EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 10 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0 3 6 9 12 15 0 20 40 60 80LHGR (kW/ft)Pellet Exposure (GWd/MTU)

PelletLHGRExposureLimit(GWd/MTU)(kW/ft)0.012.218.912.274.46.4 Figure 3.2 LHGRRATED for ATRIUM

-1 1 Fuel EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 11 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.200.300.400.500.600.700.800.901.001.10 20 30 40 50 60 70 80 90100110LHGRFAC PCore Power (% Rated)Turbine Bypass Valve Out

-of-Service, TBVOOSTurbine Bypass Valve In

-Service, TBVISTBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow CoreCorePowerLHGRFAC PPowerLHGRFAC P(% Rated)(% Rated)100.01.00100.01.0026.00.6226.00.6126.00.4526.00.3823.00.4223.00.3526.00.4826.00.4823.00.4523.00.43Turbine Bypass In-ServiceTurbine Bypass Out-of-ServiceCore Flow > 50% RatedCore Flow > 50% Rated Figure 3.3 Base Operati on LHGRFAC P for ATRIUM

-10 XM Fuel (Independent of other EOOS conditions

)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 12 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.200.300.400.500.600.700.800.901.001.10 20 30 40 50 60 70 80 90100110LHGRFAC PCore Power (% Rated)Turbine Bypass Valve Out

-of-Service, TBVOOSTurbine Bypass Valve In

-Service, TBVISTBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow CoreCorePowerLHGRFAC PPowerLHGRFAC P(% Rated)(% Rated)100.01.00100.01.0026.00.6226.00.6126.00.4526.00.3823.00.4223.00.3526.00.4826.00.4823.00.4523.00.43Turbine Bypass In-ServiceTurbine Bypass Out-of-ServiceCore Flow > 50% RatedCore Flow > 50% Rated Figure 3.4 Base Operation LHGRFAC P for ATRIUM-1 1 Fuel (Independent of other EOOS conditions

)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.600.650.700.750.800.850.900.951.001.051.10 25 35 45 55 65 75 85 95105LHGRFAC FCore Flow (% Rated)

CoreFlowLHGRFAC F(% Rated)0.00.6330.00.6376.61.00107.01.00 Figure 3.5 LHGRFAC F for ATRIUM

-10 XM Fuel (Values bound all EOOS conditions

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

)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 14 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.600.650.700.750.800.850.900.951.001.051.10 25 35 45 55 65 75 85 95105LHGRFAC FCore Flow (% Rated)

CoreFlowLHGRFAC F(% Rated)0.00.6630.00.6673.71.00107.01.00 Figure 3.6 LHGRFAC F for ATRIUM-1 1 Fuel (Values bound all EOOS conditions

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

)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 15 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.200.300.400.500.600.700.800.901.001.10 20 30 40 50 60 70 80 90100110LHGRFAC PCore Power (% Rated)Turbine Bypass Valve Out

-of-Service, TBVOOSTurbine Bypass Valve In

-Service, TBVISTBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow CoreCorePowerLHGRFAC PPowerLHGRFAC P(% Rated)(% Rated)100.01.00100.01.0026.00.5126.00.5126.00.3926.00.3423.00.3623.00.3126.00.4126.00.4123.00.4123.00.39Turbine Bypass In-ServiceTurbine Bypass Out-of-ServiceCore Flow > 50% RatedCore Flow > 50% Rated Figure 3.7 Startup Operation LHGRFAC P for ATRIUM

-10 XM Fuel: Table 3.1 Temperature Range 1 (no Feedwater hea ting during startup

) (Limits valid at and below 50% power)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.200.300.400.500.600.700.800.901.001.10 20 30 40 50 60 70 80 90100110LHGRFAC PCore Power (% Rated)Turbine Bypass Valve Out

-of-Service, TBVOOSTurbine Bypass Valve In

-Service, TBVISTBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow CoreCorePowerLHGRFAC PPowerLHGRFAC P(% Rated)(% Rated)100.01.00100.01.0026.00.5126.00.5126.00.3926.00.3423.00.3523.00.3026.00.4126.00.4123.00.4023.00.38Turbine Bypass In-ServiceTurbine Bypass Out-of-ServiceCore Flow > 50% RatedCore Flow > 50% Rated Figure 3.8 Startup Operation LHGRFAC P for ATRIUM

-10 XM Fuel: Table 3.1 Temperature Range 2 (no Feedwater hea ting during startup

) (Limits valid at and below 50% power)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 17 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.200.300.400.500.600.700.800.901.001.10 20 30 40 50 60 70 80 90100110LHGRFAC PCore Power (% Rated)Turbine Bypass Valve Out

-of-Service, TBVOOSTurbine Bypass Valve In

-Service, TBVISTBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow CoreCorePowerLHGRFAC PPowerLHGRFAC P(% Rated)(% Rated)100.01.00100.01.0026.00.5126.00.5126.00.3926.00.3423.00.3623.00.3126.00.4126.00.4123.00.4123.00.39Turbine Bypass In-ServiceTurbine Bypass Out-of-ServiceCore Flow > 50% RatedCore Flow > 50% Rated Figure 3.9 Startup Operation LHGRFAC P for ATRIUM

-1 1 Fuel: Table 3.1 Temperature Range 1 (no Feedwater heating during startup

) (Limits valid at and below 50% power)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 0.200.300.400.500.600.700.800.901.001.10 20 30 40 50 60 70 80 90100110LHGRFAC PCore Power (% Rated)Turbine Bypass Valve Out

-of-Service, TBVOOSTurbine Bypass Valve In

-Service, TBVISTBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow CoreCorePowerLHGRFAC PPowerLHGRFAC P(% Rated)(% Rated)100.01.00100.01.0026.00.5126.00.5126.00.3926.00.3423.00.3523.00.3026.00.4126.00.4123.00.4023.00.38Turbine Bypass In-ServiceTurbine Bypass Out-of-ServiceCore Flow > 50% RatedCore Flow > 50% Rated Figure 3.10 Startup Operation LHGRFAC P for ATRIUM-1 1 Fuel: Table 3.1 Temperature Range 2 (no Feedwater heating during startup

) (Limits valid at and below 50% power)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 19 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 4 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 ( MCPR F , MCPR P ) where: MCPR F core flow-dependent MCPR limit MCPR P power-dependent MCPR limit 4.1 Flow Dependent MCPR Limit: MCPR F MCPR F limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated or Increased Core Flow, ICF). MCPR F limits are shown in Figure 4.1, per Reference

1. Limits are valid for all EOOS combinations. No adjustment is required for SLO conditions.

4.2 Power Dependent MCPR Limit:

MCPR P MCPR P limits are dependent upon:

Core Power Level (% of Rated)

Technical Specification Scram Speed (TSS S), 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 MCPR P limits are provided in Table 4.2 through Table 4.9 , where each table contains the limits for all fuel types and EOOS options (for a specified scram speed and exposure range).

The CMSS determines MCPR P limits, from these tables, based on linear interpolation between the specified powers.

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 reach ed a significant operating power level. Additional power dependent limits are shown in Table 4.5 through Table 4.8 based on temperature conditions identified in Table 3.1.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS) MCPR P limits are provided for three different sets of assumed scram speeds. The Technical Specification Scram Speed (TSSS) MCPR P 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 4.1 times are applicable.

f Table 4.1 Nominal Scram Time Basis NotchNominalOptimumPositionScram TimingScram Timing(index)(seconds)(seconds)460.4200.380 360.9800.875 261.6001.465 62.9002.900 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 4.1. If conformance is not demonstra ted, TSSS based MCPR P 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.

4.2.3 Exposure Dependent Limits Exposures are tracked on a Core Average Exposure basis (CAVEX, not Cycle Exposure). Higher exposure MCPR P limits are always more limiting and may be used for any Core Average Exposure up to the ending exposure. Per Reference 1, MCPR P limits are provided for the following exposure ranges: BOC to NEOC NEOC corresponds to 29,305.7 MWd / MTU BOC to EOC LB EOC LB corresponds to 34,273.7 MWd / MTU BOC to End of Coast End of Coast 35,998.1 MWd / MTU NEOC refers to a Near EOC exposure point.

Reference 1 analysis results are based on information identified in Reference

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

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) The EOC LB exposure point is not the true End

-Of-Cycle exposure. Instead it corresponds to a licensing exposure window exceeding expected end

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

4.2.4 Equipment Out

-Of-Service (EOOS) Options EOOS options

covered by MCPR P 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 EOC LB, additional combinations of MCPR P limits are also provided including FHOOS. The coast down exposure range assumes application of FFWTR. FHOOS based MCPR P limits for the coast down exposure are redundant because the temperature setdown assumption is identical with FFWTR.

4.2.5 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

f. This event is not impacted by scram time assumptions. Specific MCPR P limits are shown in Table 4.9. 4.2.6 Below Pbypass Limit s Below Pbypass (26% rated power), MCPR P limits depend upon core flow. One set of MCPR P limits applies for core flow above 50% of rated; a second set applies if the core flow is less than or equal to 50% rated.

All equipment service conditions assume 1 SRVOOS

. f 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 Mlb m/hr.

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 1.001.201.401.601.802.00 30 40 50 60 70 80 90100110MCPR FCore Flow (% Rated)

CoreFlowMCPR F(% Rated)30.01.5884.01.34107.01.34 Figure 4.1 MCPR F for All Fuel Types (Values bound all EOOS conditions

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

)

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.2 MCPR P Limits for All Fuel Types

Optimum Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.371.391.411.361.421.43 901.421.431.461.421.451.47 651.591.591.631.581.581.64 501.681.681.751.731.731.81 501.811.811.811.911.911.91 401.881.881.911.991.992.03 262.302.302.422.512.512.6626 at > 50%F2.542.542.652.682.682.8123 at > 50%F2.692.692.812.932.933.052.422.422.512.632.632.722.552.552.672.932.933.05 1001.411.41---1.401.43---901.461.46---1.451.47---651.631.63---1.641.64---501.751.75---1.811.81---501.811.81---1.911.91---401.911.91---2.032.03---262.422.42---2.662.66---26 at > 50%F2.652.65---2.812.81---23 at > 50%F2.812.81---3.053.05---2.512.51---2.722.72---2.672.67---3.053.05---ATRIUM-11Operating ConditionBase CaseFHOOSATRIUM-10XM

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 BOC to End of Coast limits.

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.3 MCPR P Limits for All Fuel Types

Nominal Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.401.411.441.401.431.45 901.451.461.491.451.471.49 651.611.611.661.611.611.67 501.711.711.771.761.761.84 501.811.811.811.921.921.92 401.881.881.942.002.002.06 262.332.332.452.552.552.6926 at > 50%F2.542.542.652.682.682.8123 at > 50%F2.692.692.812.932.933.052.422.422.512.632.632.722.552.552.672.932.933.05 1001.431.441.461.451.491.49 901.481.491.521.491.521.54 651.641.641.691.651.651.69 501.731.731.781.781.781.85 501.811.811.811.921.921.92 401.881.881.942.002.002.06 262.332.332.452.552.552.6926 at > 50%F3.113.113.233.283.283.3823 at > 50%F3.353.353.473.573.573.692.782.782.903.043.043.163.043.043.183.323.323.56 1001.441.44---1.431.45---901.491.49---1.481.49---651.661.66---1.671.67---501.771.77---1.841.84---501.811.81---1.921.92---401.941.94---2.062.06---262.452.45---2.692.69---26 at > 50%F2.652.65---2.812.81---23 at > 50%F2.812.81---3.053.05---2.512.51---2.722.72---2.672.67---3.053.05---1001.401.411.441.401.441.45 901.451.461.491.451.471.49 651.731.731.731.831.831.83 50------------------501.811.811.811.921.921.92 401.881.881.942.002.002.06 262.332.332.452.552.552.6926 at > 50%F2.542.542.652.682.682.8123 at > 50%F2.692.692.812.932.933.052.422.422.512.632.632.722.552.552.672.932.933.05ATRIUM-10XMATRIUM-11Operating ConditionBase CaseTBVOOSFHOOSPLUOOS

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 BOC to End of COAST due to redundancy. Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively bound FHOOS limits for earlier exposure applicability windows.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.3 MCPR P Limits for All Fuel Types

Nominal Scram Time Basis (conti nued)* BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.461.46---1.471.49---901.521.52---1.521.54---651.691.69---1.691.69---501.781.78---1.851.85---501.811.81---1.921.92---401.941.94---2.062.06---262.452.45---2.692.69---26 at > 50%F3.233.23---3.383.38---23 at > 50%F3.473.47---3.693.69---2.902.90---3.163.16---3.183.18---3.563.56---1001.431.441.461.451.491.49 901.481.491.521.491.521.54 651.731.731.731.831.831.83 50------------------501.811.811.811.921.921.92 401.881.881.942.002.002.06 262.332.332.452.552.552.6926 at > 50%F3.113.113.233.283.283.3823 at > 50%F3.353.353.473.573.573.692.782.782.903.043.043.163.043.043.183.323.323.56 1001.441.44---1.431.45---901.491.49---1.481.49---651.731.73---1.831.83---50------------------501.811.81---1.921.92---401.941.94---2.062.06---262.452.45---2.692.69---26 at > 50%F2.652.65---2.812.81---23 at > 50%F2.812.81---3.053.05---2.512.51---2.722.72---2.672.67---3.053.05---1001.461.46---1.471.49---901.521.52---1.521.54---651.731.73---1.831.83---50------------------501.811.81---1.921.92---401.941.94---2.062.06---262.452.45---2.692.69---26 at > 50%F3.233.23---3.383.38---23 at > 50%F3.473.47---3.693.69---2.902.90---3.163.16---3.183.18---3.563.56---ATRIUM-10XMATRIUM-11TBVOOS FHOOSTBVOOS PLUOOSFHOOS PLUOOSTBVOOS FHOOS PLUOOSOperating Condition

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 BOC to End of COAST due to redundancy. Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively bound FHOOS limits for earlier exposure applicability windows

.

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, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.4 MCPR P Limits for All Fuel Types

Technical Specification Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.431.431.471.431.451.46 901.481.481.521.471.491.51 651.631.631.681.641.641.70 501.731.731.801.791.791.86 501.821.821.821.931.931.93 401.891.891.962.012.012.08 262.352.352.472.572.572.7226 at > 50%F2.542.542.652.682.682.8123 at > 50%F2.692.692.812.932.933.052.422.422.512.632.632.722.552.552.672.932.933.05 1001.461.471.491.481.511.51 901.511.511.541.521.541.56 651.661.661.711.671.671.72 501.751.751.811.811.811.88 501.821.821.821.931.931.93 401.891.891.962.012.012.09 262.362.362.472.572.572.7226 at > 50%F3.113.113.233.283.283.3823 at > 50%F3.353.353.473.573.573.692.782.782.903.043.043.163.043.043.183.323.323.56 1001.471.47---1.451.46---901.521.52---1.511.51---651.681.68---1.701.70---501.801.80---1.861.86---501.821.82---1.931.93---401.961.96---2.082.08---262.472.47---2.722.72---26 at > 50%F2.652.65---2.812.81---23 at > 50%F2.812.81---3.053.05---2.512.51---2.722.72---2.672.67---3.053.05---1001.431.431.471.431.451.49 901.481.481.521.471.491.51 651.741.741.741.841.841.84 50------------------501.821.821.821.931.931.93 401.891.891.962.012.012.08 262.352.352.472.572.572.7226 at > 50%F2.542.542.652.682.682.8123 at > 50%F2.692.692.812.932.933.052.422.422.512.632.632.722.552.552.672.932.933.05ATRIUM-10XMATRIUM-11Operating ConditionBase CaseTBVOOSFHOOSPLUOOS

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 BOC to End of COAST due to redundancy. Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively bound FHOOS limits for earlier exposure applicability windows.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 27 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.4 MCPR P Limits for All Fuel Types

Technical Specification Scram Time Basis (continued)* BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.491.49---1.501.51---901.541.54---1.551.56---651.711.71---1.721.72---501.811.81---1.881.88---501.821.82---1.931.93---401.961.96---2.092.09---262.472.47---2.722.72---26 at > 50%F3.233.23---3.383.38---23 at > 50%F3.473.47---3.693.69---2.902.90---3.163.16---3.183.18---3.563.56---1001.461.471.491.481.511.51 901.511.511.541.521.541.56 651.741.741.741.841.841.84 50------------------501.821.821.821.931.931.93 401.891.891.962.012.012.09 262.362.362.472.572.572.7226 at > 50%F3.113.113.233.283.283.3823 at > 50%F3.353.353.473.573.573.692.782.782.903.043.043.163.043.043.183.323.323.56 1001.471.47---1.451.46---901.521.52---1.511.51---651.741.74---1.841.84---50------------------501.821.82---1.931.93---401.961.96---2.082.08---262.472.47---2.722.72---26 at > 50%F2.652.65---2.812.81---23 at > 50%F2.812.81---3.053.05---2.512.51---2.722.72---2.672.67---3.053.05---1001.491.49---1.501.51---901.541.54---1.551.56---651.741.74---1.841.84---50------------------501.821.82---1.931.93---401.961.96---2.092.09---262.472.47---2.722.72---26 at > 50%F3.233.23---3.383.38---23 at > 50%F3.473.47---3.693.69---2.902.90---3.163.16---3.183.18---3.563.56---ATRIUM-10XMATRIUM-11TBVOOS FHOOSTBVOOS PLUOOSFHOOS PLUOOSTBVOOS FHOOS PLUOOSOperating Condition

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 BOC to End of COAST due to redundancy. Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively bound FHOOS limits for earlier exposure applicability windows.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 28 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.5 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 1 for All Fuel Types

Nominal Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.441.441.441.431.451.45 901.491.491.491.481.491.49 651.731.731.731.831.831.83 50------------------501.931.931.932.022.022.02 402.162.162.162.292.292.29 262.772.772.773.073.073.0726 at > 50%F3.063.063.063.123.123.1223 at > 50%F3.153.153.153.423.423.422.792.792.793.073.073.073.013.013.013.373.373.37 1001.461.461.461.471.491.49 901.521.521.521.521.541.54 651.731.731.731.831.831.83 50------------------501.931.931.932.022.022.02 402.162.162.162.292.292.29 262.772.772.773.073.073.0726 at > 50%F3.553.553.553.603.603.6023 at > 50%F3.713.713.714.004.004.003.143.143.143.393.393.393.453.453.453.893.893.89ATRIUM-11Operating ConditionTBVISTBVOOSATRIUM-10XM

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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 29 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.6 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 2 for All Fuel Types

Nominal Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.441.441.441.431.451.45 901.491.491.491.481.491.49 651.731.731.731.831.831.83 50------------------501.941.941.942.022.022.02 402.172.172.172.302.302.30 262.792.792.793.093.093.0926 at > 50%F3.093.093.093.143.143.1423 at > 50%F3.173.173.173.443.443.442.812.812.813.093.093.093.033.033.033.393.393.39 1001.461.461.461.471.491.49 901.521.521.521.521.541.54 651.731.731.731.831.831.83 50------------------501.941.941.942.022.022.02 402.172.172.172.302.302.30 262.792.792.793.093.093.0926 at > 50%F3.583.583.583.623.623.6223 at > 50%F3.733.733.734.024.024.023.153.153.153.403.403.403.463.463.463.903.903.90ATRIUM-11Operating ConditionTBVISTBVOOSATRIUM-10XM

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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 30 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.7 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 1 for All Fuel Types: Technical Specification Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.471.471.471.451.461.49 901.521.521.521.511.511.51 651.741.741.741.841.841.84 50------------------501.961.961.962.042.042.04 402.182.182.182.322.322.32 262.792.792.793.103.103.1026 at > 50%F3.063.063.063.123.123.1223 at > 50%F3.153.153.153.423.423.422.792.792.793.103.103.103.013.013.013.403.403.40 1001.491.491.491.501.511.51 901.541.541.541.551.561.56 651.741.741.741.841.841.84 50------------------501.961.961.962.052.052.05 402.182.182.182.322.322.32 262.792.792.793.103.103.1026 at > 50%F3.553.553.553.603.603.6023 at > 50%F3.713.713.714.004.004.003.143.143.143.393.393.393.453.453.453.893.893.89ATRIUM-11Operating ConditionTBVISTBVOOSATRIUM-10XM

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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 31 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.8 Startup Operation MCPR P Limits for Table 3.1 Temperature Range 2 for All Fuel Types: Technical Specification Scram Time Basis

BOCBOCBOCBOCBOCBOCPower to toto End of to toto End of(% of rated)NEOCEOCLBCoastNEOCEOCLBCoast 1001.471.471.471.451.461.49 901.521.521.521.511.511.51 651.741.741.741.841.841.84 50------------------501.961.961.962.052.052.05 402.192.192.192.332.332.33 262.812.812.813.123.123.1226 at > 50%F3.093.093.093.143.143.1423 at > 50%F3.173.173.173.443.443.442.812.812.813.123.123.123.033.033.033.423.423.42 1001.491.491.491.501.511.51 901.541.541.541.551.561.56 651.741.741.741.841.841.84 50------------------501.961.961.962.052.052.05 402.192.192.192.332.332.33 262.812.812.813.123.123.1226 at > 50%F3.583.583.583.623.623.6223 at > 50%F3.733.733.734.024.024.023.153.153.153.403.403.403.463.463.463.903.903.90ATRIUM-11Operating ConditionTBVISTBVOOSATRIUM-10XM

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.

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 32 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 4.9 MCPR P Limits for All Fuel Types: Single Loop Operation for All Scram Times

Power(% of rated)ATRIUM-10XMATRIUM-11 1002.002.0543.752.002.05 402.002.10 262.492.7426 at > 50%F2.672.8323 at > 50%F2.833.072.532.742.693.07 1002.002.0543.752.002.05 402.002.11 262.492.7426 at > 50%F3.253.4023 at > 50%F3.493.712.923.183.203.58 1002.122.2443.752.122.24 402.202.34 262.813.1226 at > 50%F3.573.6223 at > 50%F3.734.023.163.413.473.91 1002.132.2543.752.132.25 402.212.35 262.833.1426 at > 50%F3.603.6423 at > 50%F3.754.043.173.423.483.92RCPOOS TBVOOS FHOOS2All Cycle ExposuresOperating ConditionRCPOOS FHOOSRCPOOS TBVOOS PLUOOS FHOOSRCPOOS TBVOOS FHOOS1

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-servic e. FFWTR and FHOOS assume the same value of temperature drop.

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

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 33 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 5 Oscillation Power Range Monitor (OPRM) Setpoint (Technical Specification 3.3.1.1)

Technical Specification Table 3.3.1.1

-1, Function 2f, identifies the OPRM upscale 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. An Option III stability analysis is performed for each reload core to determine allowable OLMCPR's as a function of OPRM setpoint. Analyses consider both steady state startup operation, and the case of a two recirculation pump trip from rated power.

The resulting stability based OLMCPR's are reported in Reference

1. The OPRM setpoin t (sometimes referred to as the Amplitude Trip, S p) is selected

, such that required margin to the SLMCPR is provided without stability being a limiting event. Analyses are based on cycle specific DIVOM analyses performed per Reference

22. The calculated OLMCPR's are shown in Table 5.1. Review of results shown in COLR Table 4.2 indicates an OPRM setpoint of 1.1 4 may be used. The successive confirmation count (sometimes referred to as N p) is provided in Table 5.2, per Reference 30. Table 5.1 OPRM Setpoint Range* Table 5.2 OPRM Successive Confirmation Count Setpoint OPRMOLMCPROLMCPRSetpoint (SS)(2PT)1.051.151.071.061.171.081.071.191.101.081.201.121.091.221.141.101.241.161.111.261.171.121.281.191.131.301.211.141.331.231.151.351.25 Count 61.04 81.05 101.07 121.09 141.11 161.14 181.18 201.24OPRMSetpoint

Extrapolation beyond a setpoint of 1.15 is not allowed EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 34 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 6 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 26 & 28, and is defined by the following:

SRB (0.55 (W-W) + 60.5%) Allowable Value SRB (0.55 (W-W) + 58.5%) Nominal Trip Setpoint (NTSP) where: SRB = Rod Block setting in percent of rated thermal power (3952 MW t) W = Loop recirculation flow rate in percent of rated 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%).

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 35 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 7 Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Tabl e 3.3.2.1-1) The RBM trip setpoints and applicable power ranges, based on References 26 & 27, are shown in Table 7.1. Setpoints are based on an HTSP, unfiltered analytical limit of 11 4%. 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 26 , 27 , and 29. Table 7.1 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 12 1.7% 12 0.7% 12 0.0% 11 9.0% ITSP - unfiltered - filtered 11 6.7% 11 5.7% 11 5.0% 11 4.0% HTSP - unfiltered

- filtered 11 1.7% 11 0.9% 11 0.0% 1 09.2% 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 7.2. Cycle specific setpoint analysis results are shown in Table 7.3, per Reference

1. Table 7.2 RBM Setpoint Applicability Thermal Power

(% Rated) Applicable MCPRf Notes from Table 3.3.2.1

-1 Comment > 27% and < 90%

< 1.66 (a), (b), (f), (h) two loop operation < 1.7 0 (a), (b), (f), (h) single loop operation 90% < 1.36 (g) two loop operation

Values are considered maximums. Using lower values, due to RBM system hardware/software limitations, is conservative, and acceptable. f MCPR values shown correspond with, (support), SLMPCR values identified in Reference

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

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 36 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) Table 7.3 Control Rod Withdrawal Error Results RBMCRWEHTSP Analytical LimitOLMCPRUnfiltered 1071.29 1111.32 1141.33 1171.34 Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 11 4% unblocked).

EDMS: L94 190211 800 N PG Reactor Engineering and Fuels

- BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 12, 2019 Browns Ferry Unit 2 Cycle 21 Page 37 Core Operating Limits Report

, 120% OLTP TVA-COLR-BF 2 C 21, Revision 0 (Final) 8 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

ML19064B304

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