ML14052A217

Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report for Cycle 17 Operation

ML14052A217
Person / Time
Site:	Browns Ferry
Issue date:	02/18/2014
From:	Polson K J Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF3C17, Rev 0
Download: ML14052A217 (42)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 18, 201410 CFR 50.4ATTN: Document Control DeskU.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3Renewed Facility Operating License No. DPR-68NRC Docket No. 50-296

Subject:

Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report forCycle 17 Operation In accordance with the requirements of Technical Specification (TS) 5.6.5.d, theTennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN),Unit 3, Cycle 17, Core Operating Limits Report (COLR), Revision

0. Revision 0 of theBFN, Unit 3, Cycle 17, COLR includes all modes of operation (Modes 1 through 5).There are no new commitments contained in this letter. If you have any questions pleasecontact Jamie L. Paul at (256) 729-2636.

Respectfully, K. J. PoisonVice President

Enclosure:

Core Operating Limits Report, (105% OLTP), for Cycle 17 Operation TVA-COLR-BF3C17, Revision 0cc: (w/ Enclosure)

NRC Regional Administrator

-Region IINRC Senior Resident Inspector

-Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Page 2February 18, 2014JLP:REB:CSP bcc: (Enclosure)

NRC Project Manager -Browns Ferry Nuclear PlantG. C. Storey, LP 4G-CEDMS, WT CA-Kbcc: (w/o enclosure)

S. M. Bono, POB 2C-BFND. M. Czufin, LP 3R-CS. M. Douglas, LP 3R-CK. J. Poison, NAB 2A-BFNC. S. Putnam, SAB 2A-BFNE. D. Schrull, LP 4B-CJ. W. Shea, LP 3D-CP. B. Summers, NAB 1A-BFNS. A. Vance, W'T 6A-KP. R. Wilson, LP 4B-CNSRB Support, LP 5M-CS:\Licensing\LIC\EVERYONE\2014\Submittals\U3C17 COLR Enclosure Tennessee Valley Authority Browns Ferry Nuclear PlantUnit 3Core Operating Limits Report, (105% OLTP), for Cycle 17 Operation TVA-COLR-BF3C17, Revision 0(See Attached)

KEDMS L32 140123 801CA DocumentPages Affected:

AllBFE-3603, Revision 0Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga, TN 37402Browns Ferry Unit 3 Cycle 17Core Operating Limits Report, (105% OLTP)TVA-COLR-BF3CI 7 Revision 0 (Final)(Revision Log, Page v)January 2014Prepared:

c -'iýz /-,/IVerified:

Approved:

T. W. Eichenberg, Sr. Specialist B. C etitel, EngineerG. C. Storey, Manager, WR Fuel EngDate: ,Ij4.-,.

=23 ,2 d/VDate: / /23 // -YDate:ineering÷ -/Reviewed:

D. D. Co--fey,

Manager, Reactor Engineerir Approved:

Approved:

Date: _/__q__ _ngDate: 1""o" --Date: 31/4-m EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014N PG 1101 Market Street, Chattanooga TN 37402Table of ContentsTotal Number of Pages = 39 (including review cover sheet)L ist o f T a b le s .................................................................................................................................................

iiiL ist o f F ig u re s ................................................................................................................................................

ivR e v is io n L o g ...................................................................................................................................

vN o m e n c la tu re ................................................................................................................................................

v iR e fe re n c e s ..................................................................................................................................................

v iii1 Introduction

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

101.1 Purpose .......................................................................................................................

101 .2 S c o p e ..........................................................................................................................

1 01.3 Fuel Loading ................................................................................................................

101.4 Acceptability

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

112 APLHG R Lim its ..................................................................................................................

122.1 Rated Power and Flow Lim it: APLHG RRATED .........................................................

122.2 Off-Rated Power Dependent Lim it: APLHG Rp .......................................................

122.2.1 Startup without Feedwater Heaters ................................................................

122.3 Off-Rated Flow Dependent Lim it: APLHG RF .........................................................

122.4 Single Loop O peration Lim it: APLHG RSLO ..............................................................

122.5 Equipm ent O ut-Of-Service Corrections

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

143 LHG R Lim its .......................................................................................................................

153.1 Rated Power and Flow Lim it: LHG RRATED ...................................................................

153.2 Off-Rated Power Dependent Lim it: LHG Rp ............................................................

153.2.1 Startup without Feedwater Heaters ................................................................

153.3 Off-Rated Flow Dependent Lim it: LHG RF ..............................................................

163.4 Equipm ent O ut-Of-Service Corrections

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

164 O LM CPR Lim its .................................................................................................................

224.1 Flow Dependent M CPR Lim it: M CPRF ...................................................................

224.2 Power Dependent M CPR Lim it: M CPRp ................................................................

224.2.1 Startup without Feedwater Heaters ................................................................

224.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS) .............................

234.2.3 Exposure Dependent Lim its ............................................................................

234.2.4 Equipm ent O ut-Of-Service (EO OS) Options ..................................................

244.2.5 Single-Loop-Operation (SLO ) Lim its ..............................................................

244.2.6 Below Pbypass Lim its .....................................................................................

245 Oscillation Power Range Monitor (O PRM ) Setpoint

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

356 APRM Flow Biased Rod Block Trip Settings

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

367 Rod Block Monitor (RBM ) Trip Setpoints and O perability

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

378 Shutdown M argin Lim it .................................................................................................

39Browns Ferry Unit 3 Cycle 17 Page iiCore Operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014M N P G 1101 Market Street, Chattanooga TN 37402List of TablesN u cle a r F ue l T y pe s .....................................................................................................................

1 1Startup Feedwater Temperature Basis ...................................................................................

15N om inal Scram Tim e Basis ....................................................................................................

23MCPRp Limits for Optimum Scram Time Basis .....................................................................

26MCPRp Limits for Nominal Scram Time Basis .......................................................................

27MCPRP Limits for Technical Specification Scram Time Basis ................................................

29Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1: Technical Specification S cra m T im e B a s is .......................................................................................................................

3 1Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2: Technical Specification S cra m T im e B a s is .......................................................................................................................

3 2Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1: Nominal Scram TimeB a s is ...........................................................................................................................................

3 3Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2: Nominal Scram TimeB a s is ...........................................................................................................................................

3 4O P RM S etpoint R ange ..........................................................................................................

35OPRM Successive Confirmation Count Setpoint

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

35Analytical RBM Trip Setpoints

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

37R BM S etpoint A pplicability

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

..37Control Rod Withdrawal Error Results ...................................................................................

38Browns Ferry Unit 3 Cyde 17Core Operating ULmits Report, (105% OLTP)Page iiiTVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 20141101 Market Street, Chattanooga TN 37402List of FiguresAPLHG RRATED for ATRIUM -10 Fuel .......................................................................................

13LHG RpATED for ATR IU M -10 Fuel ............................................................................................

17Base Operation LHGRFACp for ATRIUM-10 Fuel ................................................................

18LHG RFACF for ATR IUM -1 0 Fuel ...........................................................................................

19Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 1 ....... 20Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 2 ...... 21M C PR F for ATR IU M -10 Fuel ...............................................................................................

.25Browns Ferry Unit 3 Cycle 17Core Operating Limits Report (105% OLTP)Page ivTVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014EIMNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Revision LogINumber I Page Description O-ROAll New document.

Browns Ferry Unit 3 Cyde 17Core Operating Limits Report, (105% OLTP)Page vTVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014NPG 1101 Market Street, Chattanooga TN 37402Nomenclature APLHGR Average Planar LHGRAPRM Average Power Range MonitorAREVA NP Vendor (Framatome, Siemens)ARTS APRM/RBM Technical Specification Improvement BOC Beginning of CycleBWR Boiling Water ReactorCAVEX Core Average ExposureCD Coast DownCMSS Core Monitoring System SoftwareCOLR Core Operating Limits ReportCPR Critical Power RatioCRWE Control Rod Withdrawal ErrorCSDM Cold SDMDIVOM Delta CPR over Initial CPR vs. Oscillation Magnitude ECCS Emergency Core Cooling SystemEOC End of CycleEOCLB End-of-Cycle Licensing BasisEOOS Equipment OOSFFTR Final Feedwater Temperature Reduction FFWTR Final Feedwater Temperature Reduction FHOOS Feedwater Heaters OOSft Foot: English unit of measure for lengthGNF Vendor (General

Electric, Global Nuclear Fuels)GWd Giga Watt DayHTSP High TSPICA Interim Corrective ActionICF 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 HeatingLHGR Linear Heat Generation RateLHGRFAC LHGR Multiplier (Power or Flow dependent)

LPRM Low Power Range MonitorLRNB Generator Load Reject, No BypassBrowns Feny Unit 3 Cycle 17Core operating Limits Report, (105% OLTP)Page viTVA-COLR-BF3C17, Revision 0 (Finad) 0 !~NPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402MAPFACMCPRMELLMSRVMSRVOOSMTUMWd/MTUNEOCNRCNSSNTSPOLMCPROOSOPRMOSSPBDAPbypassPLUPLUOOSPRNMRBMRPSRPTRPTOOSSDMSLMCPRSLOSRVSRVOOSTBVTBVISTBVOOSTIPTIPOOSTLOTSPTSSSTVAMAPLHGR multiplier (Power or Flow dependent)

Minimum CPRMaximum Extended Load LineMoisture Separator Reheater ValveMSRV OOSMetric Ton UraniumMega Watt Day per Metric Ton UraniumNear EOCUnited States Nuclear Regulatory Commission Nominal Scram SpeedNominal TSPMCPR Operating LimitOut-Of-Service Oscillation Power Range MonitorOptimum Scram SpeedPeriod Based Detection Algorithm Power, below which TSV Position and TCV Fast Closure Scrams are BypassedPower Load Unbalance PLU OOSPower Range Neutron MonitorRod Block MonitorReactor Protection SystemRecirculation Pump TripRPT OOSShutdown MarginMCPR Safety LimitSingle Loop Operation Safety Relief ValveSRV OOSTurbine Bypass ValveTBV ISTBV OOSTransversing In-core ProbeTIP OOSTwo Loop Operation Trip SetpointTechnical Specification Scram SpeedTennessee Valley Authority Browns Feriy un~ 3 Cyde 17 Page viiBrowns Ferry Unit 3 Cycle 17Core operating Limits Report, (105% OLTP)Page viiTVA-C0LR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 20141101 Market Street, Chattanooga TN 37402References

1. ANP-3264, Revision 0, Browns Ferry Unit 3 Cycle 17 Reload Safety Report,AREVA NP, Inc., December, 2013.2. ANP-2838(P)

Revision 0, Mechanical Design Report for Browns Ferry Unit 3Reload BFE3-15 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., August 2009.3. ANP-3031P, Revision 0, Mechanical Design Report for Browns Ferry Units 1, 2,and 3 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., October 2011.4. ANP-3222(P)

Revision 0, Browns Ferry Unit 3 Cycle 17 Plant Parameters

Document, AREVA NP, Inc., May 2013.5. BFE-3600, Revision 0, Browns Ferry Unit 3 Cycle 17 Incore Shuffle, Tennessee Valley Authority,

January, 2014.Methodology References

6. XN-NF-81-58(P)(A)

Revision 2 and Supplements 1 and 2, RODEX2 Fuel RodThermal-Mechanical Response Evaluation Model, Exxon Nuclear Company,March 1984.7. XN-NF-85-67(P)(A)

Revision 1, Generic Mechanical Design for Exxon NuclearJet 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 PowerCorporation, February 1998.9. ANF-89-98(P)(A)

Revision 1 and Supplement 1, Generic Mechanical DesignCriteria 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 NuclearMethodology for Boiling Water Reactors

-Neutronic Methods for Design andAnalysis, Exxon Nuclear Company, March 1983.11. XN-NF-80-19(P)(A)

Volume 4 Revision 1, Exxon Nuclear Methodology forBoiling 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 forBoiling 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 forBoiling Water Reactors, THERMEX:

Thermal Limits Methodology SummaryDescription, Exxon Nuclear Company, January 1987.14. XN-NF-84-105(P)(A)

Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T:

AComputer Code for BWR Transient Thermal-Hydraulic Core Analysis, ExxonNuclear Company, February 1987.Browns Ferry Unit 3 CyRee 17Core operating Limits Report, (105% OLTP)Page viiiTVA-C0LR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014I,,1NPG Dt:Jnay321 1101 Market Street, Chattanooga TN 3740215. ANF-524(P)(A)

Revision 2 and Supplements 1 and 2, ANF Critical PowerMethodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.16. 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 BoilingWater Reactors, Advanced Nuclear Fuels Corporation, September 2005.18. EMF-2209(P)(A)

Revision 3, SPCB Critical Power Correlation, AREVA NP Inc.,September 2009.19. EMF-2361(P)(A)

Revision 0, EXEM BWR-2000 ECCS Evaluation Model,Framatome ANP Inc., May 2001, as supplemented by the site specific approval inNRC safety evaluation dated February 15, 2013.20. EMF-2292(P)(A)

Revision 0, ATRIUMTM -10: Appendix K Spray Heat TransferCoefficients, 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, August2000.22. BAW-10255(P)(A),

Revision 2, Cycle-Specific DIVOM Methodology Using theRAMONA5-FA Code, AREVA NP Inc., Inc., May, 2008.PRNM Setpoint References

23. Filtered Setpoints

-EDE-28-0990 Rev. 3 Supplement E, "PRNM (APRM, RBM, andRFM) Setpoint Calculations

[ARTS/MELLL (NUMAC) -Power-Uprate Condition]

forTennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.24. Unfiltered Setpoints

-EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, RBM,and RFM) Setpoint Calculations

[ARTS/MELLL (NUMAC) -Power-Uprate Condition]

for Tennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.25. GE Letter LB#: 262-97-133, Browns Ferry Nuclear Plant Rod Block Monitor SetpointClarification

-GE Proprietary Information, September 12, 1997.26. NEDC-32433P, Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3, GE NuclearEnergy, April 1995.27. NEDO-32465-A, Licensing Topical Report -Reactor Stability Detect andSuppress Solutions Licensing Basis Methodology for Reload Applications, GENuclear Energy, August 1996.Browns Ferry Unit 3 Cyde 17Core Operating Limits Report, (105% OLTP)Page ixTVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014NPG Jnay31101 Market Street, Chattanooga TN 374021 Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

1.1 PurposeThe 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 ScopeThis 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, > 25% 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, > 25% RTP (Technical Specifications definition of RTP)> Minimum Critical Power Ratio Operating Limit (OLMCPR)(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)Applicability:

Mode 1, : 25% 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) o 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)> 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 Modes1.3 Fuel LoadingThe core will contain previously exposed and fresh AREVA NP, Inc., ATRIUM-10 fuel. Nuclearfuel types used in the core loading are shown in Table 1.1. The core shuffle and final loadingwere explicitly evaluated for BOC cold shutdown margin performance as documented inReference 5.Browns Ferry Unit 3 Cycle 17Core Operang Limits Report, (105% OLTP)Page 10TVA-COLR-BF3C17, Revision 0 (Final)

IM NPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 1.1 Nuclear Fuel Types*NuclearOriginal Number of Fuel Type Fuel NamesFuel Description Cycle Assemblies (NFT) (Range)ATRIUM-10 A10-3831B-15GV80-FCD 15 120 6 FCDO01-FCD200 ATRIUM-10 A10-3403B-9GV80-FCD 15 20 7 FCD257-FCD276 ATRIUM-10 A10-3392B-10GV80-FCD 15 7 8 FCD221-FCD256 ATRIUM-10 A1O-4218B-15GV80-FCC 15 2 9 FCC217-FCC218 ATRIUM-10 AIO-4218B-13GV80-FCC 15 4 10 FCC307-FCC310 ATRIUM-10 A10-3757B-1OGV80-FCC 15 40 11 FCC335-FCC374 ATRIUM-i10 Al 0-3440B-11 GV80-FCE 16 144 12 FCE001-FCE144 ATRIUM-10 Al 0-3826B-1 3GV80-FCE 16 44 13 FCE145-FCE188 ATRIUM-10 A10-4075B-13GV80-FCE 16 47 14 FCE189-FCE236 ATRIUM-1 0 Al 0-4081 B-1 2GV80-FCE 16 48 15 FCE237-FCE284 ATRIUM-10 A10-3849B-13GV80-FCF 17 176 16 FCF301-FCF476 ATRIUM-10 AIO-3882B-10GV70-FCF 17 40 17 FCF477-FCF516 ATRIUM-10 A10-4116B-12GV70-FCF 17 72 18 FCF517-FCF588

1.4 Acceptability

Limits discussed in this document were generated based on NRC approved methodologies perReferences 6 through 22.The table identifies the expected fuel type breakdown in anticipation of final core loading.

The final composition of the core depends uponuncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due tounforeseen events, will conform to the safety and monitoring requirements identified in this document.

Browns Ferry Unit 3 Cycle 17Core operating Umits Report, (105% OLTP)Page 11TVA-C0LR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014M PG 1101 Market Street, Chattanooga TN 374022 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 (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]

2.1 Rated Power and Flow Limit: APLHGRRATED The rated conditions APLHGR for ATRIUM-10 fuel is identified in Reference 1 and shown inFigure 2.1.2.2 Off-Rated Power Dependent Limit: APLHGRpReference 1, for ATRIUM-10 fuel, does not specify a power dependent APLHGR. Therefore, MAPFACp is set to a value of 1.0.2.2. 1 Startup without Feedwater HeatersThere is a range of operation during startup when the feedwater heaters are not placed intoservice until after the unit has reached a significant operating power level. No Additional powerdependent limitation is required.

2.3 Off-Rated Flow Dependent Limit: APLHGRFReference 1, for ATRIUM-10 fuel, does not specify a flow dependent APLHGR. Therefore, MAPFACF is set to a value of 1.0.2.4 Single Loop Operation Limit: APLHGRSLO The single loop operation multiplier for ATRIUM-10 fuel is 0.85, per Reference 1.IBrowns Ferry Unit 3 Cyde 17Core Operating Umits Report, (105% OLTP)Page 12TVA-COLR-BF3C17, Revision 0 (Final)

[M IiNPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374021512CL49630020406080PlanarAverage Exposure (GWdlMTU)

Planar Avg. APLHGRExposure Limit(G1 (kWft)0.0 12.515.0 12.567.0 7.3Figure 2.1 APLHGRRATED for ATRIUM-10 FuelBrowns FerryUnk3 Cycle 17Core Operfing LimblsReport (105% OLTP)Page 13TVA-COLR-BF3C17, Revision 0 (F'wil)

EDMS: L32 140123 801Date: January 23, 2014[M NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374022.5 Equipment Out-Of-Service Corrections The limits shown in Figure 2.1 are applicable for operation with all equipment In-Service as wellas the following Equipment Out-Of-Service (EOOS) options; including combinations of theoptions.In-Service RPTOOSTBVOOSPLUOOSFHOOS (or FFWTR)All equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s)

Out-Of-Service Power Load Unbalance Out-Of-Service Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to therated APLHGR limits as described previously.

• All equipment service conditions assume 1 SRVOOS.Browns FerryUnit 3Cycle 17Core OeakinqLkir~t Report, (105% OLTP)Page 14"VA-COLR-BF3C17, Revision 0 (Final)

[M liNPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374023 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 andoff-rated flow conditions.

The most limiting of these is then used as follows:LHGR limit = MIN (LHGRp, LHGRF)where:LHGRpLHGRFoff-rated power LHGR limitoff-rated flow LHGR limit[LHGRRATED

• LHGRFACp]

[LHGRRATED

• LHGRFACF]

3.1 Rated Power and Flow Limit: LHGRRATED The rated conditions LHGR for all fuel types, is identified in Reference 1 and shown in Figure3.1. The LHGR limit is consistent with References 2 and 3.3.2 Off-Rated Power Dependent Limit: LHGRpLHGR 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 andout-of-service.

The multipliers are shown in Figure 3.2.3.2.1 Startup without Feedwater HeatersThere is a range of operation during startup when the feedwater heaters are not placed intoservice until after the unit has reached a significant operating power level. Additional limits areshown in Figure 3.4 and Figure 3.5, based on temperature conditions identified in Table 3.1.Table 3.1 Startup Feedwater Temperature BasisTemperature Power Range 1 Range 225 160.0 155.030 165.0 160.040 175.0 170.050 185.0 180.0BownsFenyunt3cydel7 Page 15Browis Ferry Unit 3 Cycle 17Core OPM*alV Lhft# Report (105% OLTP)Page 15TVA-C0LR-BF3C17, Reh3bn 0 (Fiffial)

EDMS: L32 140123 801Date: January 23, 2014EIMiNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374023.3 Off-Rated Flow Dependent Limit: LHGRFThe LHGR limit is adjusted for off-rated flow conditions using the LHGRFACF multiplier providedin Reference

1. The multiplier are shown in Figure 3.3.3.4 Equipment Out-Of-Service Corrections The limit shown in Figure 3.1 is applicable for operation with all equipment In-Service as well asthe following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*

In-Service RPTOOSTBVOOSPLUOOSFHOOS (or FFWTR)SLOAll equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s)

Out-Of-Service Power Load Unbalance Out-Of-Service Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction Single Loop Operation, One Recirculation Pump Out--Of-Service Off-rated power corrections shown in Figure 3.2 are dependent on operation of the TurbineBypass Valve system. For this reason, separate limits are to be applied for TBVIS or TBVOOSoperation.

The limits have no dependency on RPTOOS, PLUOOS, FHOOS/FFWTR, or SLO.Off-rated flow corrections shown in Figure 3.3 are bounding for all EOOS conditions.

Off-rated power corrections shown in Figure 3.4 and Figure 3.5 are also dependent on operation of the Turbine Bypass Valve system. In this case, limits support FHOOS operation duringstartup.

These limits have no dependency on RPTOOS, PLUOOS, or SLO..All equipment service conditions assumfe 1 SRVOOS.Bit~ns Fetry Unit 3 C~de 17 Page 16Core Oetlig Units Report (105% OLTP) 1ACL-FC7 eso F~Page 16TVA-C0LR-BF3C17, Revisim 0 Frd)

EDMS: L32 140123 801Date: January 23, 2014[M NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 3740215120-j9630020 40 60Pellet Exposure (GWd/MTU) 80Pellet LHGRExposure Limit0.0 13.418.9 13.474.4 7.1Figure 3.1 LHGRRATED for ATRIUM-10 FuelBroaws Ferry Unit 3 Cyde 17Core LimitrReport, (105% OLTP)Page 17TVA-COUR-F3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014[M ~NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402L-II.U-C,,1.101.000.90Turbine BypassValve In-Service, TBVIS0.80Turbine Bypass Valve Out-of-Service, TBVOOS0.700.60TBVIS, < 50% Core Flow0.50 TBVIS, >50% Core FlowTBVOOS, 5 50% Core FlowTBVOOS, > 50% Core Flow0.40 j0.3020 30 40 50 60 70 80 90 100 110Core Power (% Rated)Turbine Bypass In-Service CorePower LHGRFACp100.0 1.0030.0 0.61Core Flow > 50% Rated30.0 F 0.4825.0 0.43Core Flow < 500/6 Rated30.0 0.5025.0 0.45Turbine Bypass Out-of-Service CorePower LHGRFACp100.0 0.9530.0 0.61Core Flow > 50% Rated30.0 0.4325.0 0.41Core Flow S 50% Rated30.0 0.4825.0 0.41Figure 3.2 Base Operation LHGRFACp for ATRIUM-10 Fuel(Independent of other EOOS conditions)

Browns Ferry Unit 3 Cye17CoreOeraling Units Report~ (105% OLTP)Page 18TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014[M JiNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374021.101.051.00ILU40-J0.950.900.850.800 1020 30 40 50 60 70 80 90 100 110Core Flow (% Rated)CoreFlow LHGRFACF6 IRated)0.0 0.9330.0 0.9346.4 1107.0 1Figure 3.3 LHGRFACF for ATRIUM-10 Fuel(Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, ICF)Brons Ferry Unit 3 Cyde 17Core Operating Limits Report (105% OLTP)Page 19TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014REi NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374020.IL-J-LJ1.101.000.900.800.700.600.500.400.30Turbine Bypass Valve In-Service, TBVISTurbine Bypass Valve Out-of-Service, TBVOOST 0ITBVIS, S 50% Core FlowTBVooS >50% Core Flow.;7 TBVIS, > 50% Core FlowTBVOOS, > 50% Core Flow20 30 40 50 60 70 80 90 100 110Core Power (% Rated)Turbine Bypass In-Service CorePower LHGRFACp(% Rated) _100.0 f 1.0030.0 0.56Core Row > 50% Rated30.0 j 0.4225.0 0.37Core Flow < 50% Rated30.0 0.4525.0 1 0.39Turbine Bypass Out-of-Service CorePower LHGRFACp(% Rated) (100.0 0.9530.0 0.56Core Row > 50% Rated30.0 0.3825.0 0.33Core Row $ 50% Rated30.0 0.4325.0 1 0.36Figure 3.4 Startup Operation LHGRFACp for ATRIUM-10 Fuel:Table 3.1 Temperature Range 1(no Feedwater heating during startup)Browns Ferry Unit 3 Cycle 17Core Operatirg Lits Report, (105% OLTP)Page 20TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014RE ~iNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402ILL0-J1.101.000.900.800.700.600.500.400.30Turbine Bypass Valve In-Service, TBVISTurbine Bypas Valve Out-of-Service, TBV0OSTBVIS, s 50% Core FlowTBVOOS, S50% Core FlowTBVIS, > 50% Core FlowO I 5TBVOOS, > 50% Core Flow20 30 40 50 60 70 80 90 100 110Core Power (% Rated)Turbine Bypass In-Service CorePower LHGRFACpTurbine Bypass Out-of-Service CorePower LHGRFACp(% Rated) _100.0 1.0030.0 0.56Core Fow > 50% Rated30.0 0.4225.0 0.37Core Flow < 50% Rated30.0 0.4425.0 I 0.39(% Rated) ______100.0 0.9530.0 0.56Core Fow > 50% Rated30.0 0.3725.0 0.33Core Flow < 50% Rated30.0 0.4325.0 0.36Figure 3.5 Startup Operation LHGRFACp for ATRIUM-10 Fuel:Table 3.1 Temperature Range 2(no Feedwater heating during startup)Bn~wns Ferry Unit 3 Cyde 17 Page 21Brows Ferry Unit 3 Cycle 17Core opera"n Lirnts Report, (105% OLTP)Page 21TVA-C0LR-l3F3C17, ReArjon 0 (Frial)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 20141101 Market Street, Chattanooga TN 374024 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 valuesOLMCPR limit = MAX ( MCPRF, MCPRp)where:MCPRF core flow-dependent MCPR limitMCPRp power-dependent MCPR limit4.1 Flow Dependent MCPR Limit: MCPRFMCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated orIncreased Core Flow, ICF). MCPRF limits are shown in Figure 4.1, consistent with Reference 1.Limits are valid for all EOOS combinations.

No adjustment is required for SLO conditions.

4.2 Power Dependent MCPR Limit: MCPRPMCPRp limits are dependent upon:" Core Power Level (% of Rated)" Technical Specification Scram Speed (TSSS), Nominal Scram Speed (NSS), orOptimum 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 the following tables, where each table contains the limits forall fuel types and EOOS options (for a specified scram speed and exposure range). The CMSSdetermines MCPRp limits, from these tables, based on linear interpolation between the specified powers.4.2.1 Startup without Feedwater HeatersThere is a range of operation during startup when the feedwater heaters are not placed intoservice until after the unit has reached a significant operating power level. Additional powerdependent limits are shown in Table 4.5 through Table 4.8, based on temperature conditions identified in Table 3.1.Brovm FerryUnk 3 Cycle17Core peraing Li~t Report (105% OLTP)Page 22TVACOLAR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014[M 1iNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374024.2.2 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 thescram time surveillance demonstrates the times in Technical Specification Table 3.1.4-1 aremet. 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.*t Table 4.1 Nominal Scram Time BasisNotch Nominal OptimumPosition Scram Timing Scram Timing(index) (seconds)

(seconds) 46 0.420 0.38036 0.980 0.87526 1.600 1.4656 2.900 2.900In 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 rodsshould conform to scram speeds shown in Table 4.1. 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 timingconfirms NSS and/or OSS based limits are applicable.

4.2.3 Exposure Dependent LimitsExposures are tracked on a Core Average Exposure basis (CAVEX, not Cycle Exposure).

Higher exposure MCPRp limits are always more limiting and may be used for any Core AverageExposure up to the ending exposure.

Per Reference 1, MCPRp limits are provided for thefollowing exposure ranges:BOC to NEOCBOC to EOCLBBOC to End of CoastNEOC corresponds toEOCLB corresponds toEnd of Coast27,393.0 MWd / MTU31,304.9 MWd / MTU32,724.6 MWd I MTUNEOC refers to a Near EOC exposure point..Reference 1 analysis results are based on information identified in Reference 4.t Drop out times consistent with method used to perform actual timing measurements (i.e., including pickup/dropout effects).

Browns Ferry Unit 3 Cycle 17Core OpertfiM Limits Report (105% OLTP)Page 23"VA-COLR-BF3C17, Revision 0 (Fwral)

EDMS: L32 140123 801Date: January 23, 2014EI!MNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402The EOCLB exposure point is not the true End-Of-Cycle exposure.

Instead it corresponds to alicensing exposure window exceeding expected end-of-full-power-life.

The End of Coast exposure point represents a licensing exposure point exceeding the expectedend-of-cycle exposure including cycle extension options.4.2.4 Equipment Out-Of-Service (EOOS) OptionsEOOS options*

covered by MCPRp limits are given by the following:

In-Service RPTOOSTBVOOSRPTOOS+TBVOOS PLUOOSPLUOOS+RPTOOS PLUOOS+TBVOOS PLUOOS+TBVOOS+RPTOOS FHOOS (or FFWTR)All equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s)

Out-Of-Service Combined RPTOOS and TBVOOSPower Load Unbalance Out-Of-Service Combined PLUOOS and RPTOOSCombined PLUOOS and TBVOOSCombined PLUOOS, RPTOOS, and TBVOOSFeedwater Heaters Out-Of-Service (or FinalFeedwater Temperature Reduction)

For exposure ranges up to NEOC and EOCLB, additional combinations of MCPRp limits arealso provided including FHOOS. The coast down exposure range assumes application ofFFWTR. FHOOS based MCPRp limits for the coast down exposure are redundant because thetemperature setdown assumption is identical with FFWTR.4.2.5 Sin-gle-Loop-Operation (SLO) LimitsMCPRp limits are increased by 0.02 to support SLO, per Reference 1.4.2.6 Below Pbypass LimitsBelow Pbypass (30% rated power), MCPRp limits depend upon core flow. One set of MCPRplimits applies for core flow above 50% of rated; a second set applies if the core flow is less thanor equal to 50% rated..All equipment service conditions assume 1 SRVOOS.BEo~sFenyUnit3Cyde 17 Page 24Brow.ns Ferry Unit 3 Cycle 17Core Opwafing Limits Repot (105% OLTP)Page 24TVA-C0LR-l3F3C17, Revision 0 (Finad)

EDMS: L32 140123 801Date: January 23, 2014EIMNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374022.001.801.60I.1.401.201.0030 40 50 60 70 80 90 100 110Core Flow (% Rated)CoreFlow MCPRF(%Rated)30.0 1.6178.0 1.28107.0 1.28Figure 4.1 MCPRF for ATRIUM-10 Fuel(Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, ICF)Browns Fery Unit 3 Cycle 17Core Operaling LUit Repot (105% OLTP)Page 25"VA-COLR-BF3C17, Revisio 0 (Finl)

EDMS: L32 140123 801Date: January 23, 2014EIM NPGReactor Engineering and Fuels -BBWRFE110 1 Market Street, Chattanooga TN 37402Table 4.2 MCPRp Limits for Optimum Scram Time Basis*BOC BOC BOCFower to to to End ofOperating Condition

(% of rated) NEOC EOCLB Coast100 1.38 1.41 1.4375 1.51 1.51 1.5565 1.57 1.57 1.6150 1.70 1.70 1.7650 1.93 1.93 1.93Base Case 40 2.03 2.03 2.0330 2.19 2.19 2.3030 at > 50%F 2.53 2.53 2.6325 at > 50%F 2.77 2.77 2.8930 at < 50%F 2.45 2.45 2.5225 at 5 50%F 2.68 2.68 2.80100 1.40 1.43 ---75 1.55 1.5565 1.61 1.6150 1.76 1.7650 1.93 1.93FHOOS 40 2.03 2.0330 2.30 2.3030 at > 50%F 2.63 2.6325 at > 50%F 2.89 2.8930 at < 50%F 2.52 2.5225 at 5 50%F 2.80 2.80* 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.

For single-loop operation, MCPRP limits will be 0.02higher.FFWTRIFHOOS is supported for the BOC to End of Coast limits.Browns Ferry Unit 3 Cycle 17Core Operating Limits Report, (105% OLTP)Page 26TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014IM NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.3 MCPRp Limits for Nominal Scram Time Basis*BOC BOC BOCPower to to to End ofOperating Condition

(% of rated) NBOC BOCLB Coast100 1.40 1.42 1.4375 1.53 1.53 1.5665 1.59 1.59 1.6250 1.72 1.72 1.7950 1.93 1.93 1.94Base Case 40 2.04 2.04 2.0430 2.22 2.22 2.3330 at > 50%F 2.53 2.53 2.6325 at > 50%F 2.77 2.77 2.8930 at : 50%F 2.45 2.45 2.5225 at < 50%F 2.68 2.68 2.80100 1.44 1.46 1.4775 1.57 1.57 1.6065 1.62 1.63 1.6650 1.75 1.75 1.8150 1.93 1.93 1.94TBVOOS 40 2.04 2.04 2.0430 2.23 2.23 2.3430 at > 50%F 3.14 3.14 3.2625 at > 50%F 3.53 3.53 3.6430 at < 50%F 2.74 2.74 2.8825 at! <50%F 3.17 3.17 3.32100 1.43 1.43 ---75 1.55 1.56 ---65 1.62 1.62 ---50 1.79 1.79 ---50 1.94 1.94 ---FHOOS 40 2.04 2.04 ---30 2.33 2.33 ---30 at > 50%F 2.63 2.63 ---25 at > 50%F 2.89 2.89 ---30 at < 50%F 2.52 2.52 ---25 at < 50%F 2.80 2.80 ---100 1.40 1.42 1.4375 1.53 1.53 1.5665 1.82 1.82 1.8350 ... ... ...50 1.94 1.94 1.94PLUOOS 40 2.04 2.04 2.0430 2.22 2.22 2.3330 at > 50%F 2.53 2.53 2.6325 at > 50%F 2.77 2.77 2.8930 at < 50%F 2.45 2.45 2.5225 at < 50%F 2.68 2.68 2.80All 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.

For single-loop operation, MCPRp limits will be 0.02higher.FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for BOC to End of COASTdue to redundancy.

Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively boundFHOOS limits for earlier exposure applicability windows.A 50% power step change for PLUOOS limits is not supported.

When core power is < 50%, the LRNB event is the same with, or withoutPLUOOS.Browns Ferry Unit 3 Cycle 17Core Operating Limits Report, (105% OLTP)Page 27TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014U@ INPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.3 MCPRp Limits for Nominal Scram Time Basis (continued)*

BOC BOC BOCPower to to to End ofOperating Condition

(% of rated) NEOC E0CLB Coast100 1.46 1.47 ---75 1.59 1.60 --65 1.66 1.66 ---50 1.81 1.81 ---50 1.94 1.94 --EHOOS 40 2.04 2.04 ---30 2.34 2.34 ---30 at > 50%F 3.26 3.26 ---25 at > 50%F 3.64 3.64 ---30 at < 50%F 2.88 2.88 ---25 at < 50%F 3.32 3.32 ---100 1.44 1.46 1.4775 1.57 1.57 1.6065 1.82 1.82 1.8350 ... ... ...-BVOOS 50 1.94 1.94 1.94PtuOOS 40 2.04 2.04 2.0430 2.23 2.23 2.3430 at > 50%F 3.14 3.14 3.2625 at > 50%F 3.53 3.53 3.6430 at5 <50%F 2.74 2.74 2.8825 at < 50%F 3.17 3.17 3.32100 1.43 1.43 ---75 1.55 1.56 ---65 1.83 1.83 ---50 ... ... ...A-OS 50 1.94 1.94 ---PtUOOS 40 2.04 2.04 ---30 2.33 2.33 ---30 at > 50%F 2.63 2.63 ---25 at > 50%F 2.89 2.89 ---30 at 5 50%F 2.52 2.52 ---25 at < 50%F 2.80 2.80 ---100 1.46 1.4775 1.59 1.6065 1.83 1.83 ---50 ... ......TBVOOS 50 1.94 1.94 ---FHOOS 40 2.04 2.04 ---PLUJOOS 30 2.34 2.34 ---30 at > 50%F 3.26 3.26 ---25 at > 50%F 3.64 3.64 ---30 at < 50%F 2.88 2.88 ---25 at < 50%F 3.32 3.32 ---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.

For single-loop operation, MCPRp limits will be 0.02higher.FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for BOC to End of COASTdue to redundancy.

Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively boundFHOOS limits for earlier exposure applicability windows.A 50% power step change for PLUOOS limits is not supported.

When core power is < 50%, the LRNB event is the same with, or withoutPLUOOS.Browns Ferry Unit 3 Cycle 17Core Operating Urmits Report (105% OLTP)Page 28TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014[M NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis*BOC BOC BOCPower to to to End ofOperating Condition

(% of rated) NEOC EOCLB Coast100 1.42 1.43 1.4475 1.55 1.55 1.5765 1.60 1.60 1.6450 1.75 1.75 1.8250 1.94 1.94 1.95Base Case 40 2.05 2.05 2.0530 2.24 2.24 2.3630 at > 50%F 2.53 2.53 2.6325 at > 50%F 2.77 2.77 2.8930 at < 50%F 2.45 2.45 2.5225 at ! 50%F 2.68 2.68 2.80100 1.46 1.47 1.4875 1.59 1.59 1.6165 1.64 1.64 1.6850 1.77 1.77 1.8350 1.94 1.94 1.95TBVOOS 40 2.05 2.05 2.0730 2.26 2.26 2.3730 at > 50%F 3.14 3.14 3.2625 at > 50%F 3.53 3.53 3.6430 at < 50%F 2.74 2.74 2.8825 at5 <50%F 3.17 3.17 3.32100 1.44 1.44 ---75 1.57 1.57 ---65 1.64 1.64 ---50 1.82 1.82 ---50 1.95 1.95 ---FHOOS 40 2.05 2.05 ---30 2.36 2.36 ---30 at > 50%F 2.63 2.63 ---25 at > 50%F 2.89 2.89 ---30 at < 50%F 2.52 2.52 ---25 at 5 50%F 2.80 2.80 ---100 1.42 1.43 1.4475 1.55 1.55 1.5765 1.83 1.83 1.8450 ... ... ...50 1.95 1.95 1.95PLLUOOS 40 2.05 2.05 2.0530 2.24 2.24 2.3630 at > 50%F 2.53 2.53 2.6325 at > 50%F 2.77 2.77 2.8930 at < 50%F 2.45 2.45 2.5225 at < 50%F 2.68 2.68 2.80All 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.

For single-loop operation, MCPRP limits will be 0.02higher.FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for BOC to End of COASTdue to redundancy.

Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively boundFHOOS limits for earlier exposure applicability windows.A 50% power step change for PLUOOS limits is not supported.

When core power is < 50%, the LRNB event is the same with, or withoutPLUOOS.Browns Ferry Unit 3 Cycle 17Core Operating Limit Report, (105% OLTP)Page 29TVA-COLR-BF3C1 7, Revision 0 (Final)

[M ~NPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis (continued)*

BOC BOC BOGOperating Pow er to to to End ofCondition

(% of rated) NEOC EOCLB Coast100 1.48 1.48 ---75 1.61 1.6165 1.68 1.68 ---50 1.83 1.83 ---TBVOOS 50 1.95 1.95FHOOS 40 2.07 2.07 ---30 2.37 2.37 ---30 at > 50%F 3.26 3.26 ---25 at > 50%F 3.64 3.64 ---30 at < 50%F 2.88 2.88 ---25 at < 50%F 3.32 3.32 ---100 1.46 1.47 1.4875 1.59 1.59 1.6165 1.83 1.83 1.8450 ... ... ...TBVOOS 50 1.95 1.95 1.95P..uoos 40 2.05 2.05 2.0730 2.26 2.26 2.3730 at > 50%F 3.14 3.14 3.2625 at > 50%F 3.53 3.53 3.6430 at < 50%F 2.74 2.74 2.8825 at: <50%F 3.17 3.17 3.32100 1.44 1.4475 1.57 1.57 ---65 1.84 1.84 ---50 ... ... ...50 1.95 1.95 ---mUOOS 40 2.05 2.05 ---30 2.36 2.36 ---30 at > 50%F 2.63 2.6325 at > 50%F 2.89 2.8930 at < 50%F 2.52 2.52 ---25 at 5 50%F 2.80 2.80 ---100 1.48 1.48 ---75 1.61 1.6165 1.84 1.8450 --- .-..TBVOOS 50 1.95 1.95FHOOS 40 2.07 2.07 ---PLUOOS 30 2.37 2.37 ---30 at > 50%F 3.26 3.26 ---25 at > 50%F 3.64 3.64 ---30 at < 50%F 2.88 2.88 ---25 at < 50%F 3.32 3.32 ---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.

For single-loop operation, MCPRp limits will be 0.02higher.FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for BOC to End of COASTdue to redundancy.

Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively boundFHOOS limits for earlier exposure applicability windows.A 50% power step change for PLUOOS limits is not supported.

When core power is s 50%, the LRNB event is the same with, or withoutPLUOOS.Browns Ferry Unit 3 Cyde 17Core Operating ULmits Report, (105% OLTP)Page 30TVA-COLR-BF3C17, Revision 0 (Fnal)

[M NPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.5 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:Technical Specification Scram Time Basis*BOC BOC BOCPow er to to to End ofOperating Condition

(% of rated) NEOC EOCLB Coast100 1.44 1.44 1.4475 1.57 1.57 1.5765 1.84 1.84 1.8450 1.95 1.95 1.9550 1.99 1.99 1.99TBVIS 40 2.24 2.24 2.2430 2.61 2.61 2.6130 at > 50%F 2.88 2.88 2.8825 at > 50%F 3.21 3.21 3.2130 at < 50%F 2.79 2.79 2.7925 at < 50%F 3.07 3.07 3.07100 1.48 1.48 1.4875 1.61 1.61 1.6165 1.84 1.84 1.8450 1.95 1.95 1.9550 1.99 1.99 1.99TBVOOS 40 2.25 2.25 2.2530 2.61 2.61 2.6130 at > 50%F 3.44 3.44 3.4425 at > 50%F 3.85 3.85 3.8530 at 5 50%F 3.10 3.10 3.1025 at < 50%F 3.54 3.54 3.54" Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number ofTIP channels),

and up to 50% of the LPRMs out-of-service.

For single-loop operation, MCPRp limits will be 0.02 higher.Limits are applicable for all other EOOS scenarios, apart from TBV.Brons Ferry Unit 3 Cye1e 17Core Operating Limits Report, (1105% OLTP)Page 31TVA-COLR-BF3C1 7, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014V ~NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.6 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:Technical Specification Scram Time Basis*BOC BOC BOCOperating Pow er to to to End ofCondition

(% of rated) NEOC EOCLB Coast100 1.44 1.44 1.4475 1.57 1.57 1.5765 1.84 1.84 1.8450 1.95 1.95 1.9550 2.00 2.00 2.00TBVIS 40 2.26 2.26 2.2630 2.63 2.63 2.6330 at > 50%F 2.90 2.90 2.9025 at > 50%F 3.23 3.23 3.2330 at < 50%F 2.80 2.80 2.8025 at < 50%F 3.09 3.09 3.09100 1.48 1.48 1.4875 1.61 1.61 1.6165 1.84 1.84 1.8450 1.95 1.95 1.9550 2.00 2.00 2.00TBVOOS 40 2.26 2.26 2.2630 2.63 2.63 2.6330 at > 50%F 3.45 3.45 3.4525 at > 50%F 3.86 3.86 3.8630 atS 50%F 3.12 3.12 3.1225 at < 50%F 3.56 3.56 3.56Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number ofTIP channels),

and up to 50% of the LPRMs out-of-service.

For single-loop operation, MCPRP limits will be 0.02 higher.Limits are applicable for all other EOOS scenarios, apart from TBV.Brewns Ferry Unit 3 Cy(le 17Core Operating Limits Report, (105% OLTP)Page 32TVA-C0LR-I3F3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014IM NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.7 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:Nominal Scram Time Basis*BOC BOC BOCPower to to to End ofOperating Condition

(% of rated) NEOC EOCLB Coast100 1.43 1.43 1.4375 1.55 1.56 1.5665 1.83 1.83 1.8350 1.94 1.94 1.9450 1.96 1.96 1.96TBVIS 40 2.22 2.22 2.2230 2.58 2.58 2.5830 at > 50%F 2.88 2.88 2.8825 at > 50%F 3.21 3.21 3.2130 at < 50%F 2.79 2.79 2.7925 at 5 50%F 3.07 3.07 3.07100 1.46 1.47 1.4775 1.59 1.60 1.6065 1.83 1.83 1.8350 1.94 1.94 1.9450 1.96 1.96 1.96TBVOOS 40 2.22 2.22 2.2230 2.58 2.58 2.5830 at > 50%F 3.44 3.44 3.4425 at > 50%F 3.85 3.85 3.8530 ats 50%F 3.10 3.10 3.1025 at < 50%F 3.54 3.54 3.54* Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number ofTIP channels),

and up to 50% of the LPRMs out-of-service.

For single-loop operation, MCPRp limits will be 0.02 higher.Limits are applicable for all other EOOS scenarios, apart from TBV.Browns Ferry Unit 3 Cycle 17Core Operating Limits Report, (105% OLTP)Page 33TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014IM NPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 4.8 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:Nominal Scram Time Basis*Operating Condition BOC BOC BOCPower to to to End of(% of rated) NEOC EOCLB CoastTBVIS100 1.43 1.43 1.4375 1.55 1.56 1.5665 1.83 1.83 1.8350 1.94 1.94 1.9450 1.97 1.97 1.9740 2.23 2.23 2.2330 2.60 2.60 2.6030 at > 50%F 2.90 2.90 2.9025 at > 50%F 3.23 3.23 3.2330 at < 50%F 2.80 2.80 2.8025 at < 50%F 3.09 3.09 3.094TBVOOS100 1.46 1.47 1.4775 1.59 1.60 1.6065 1.83 1.83 1.8350 1.94 1.94 1.9450 1.97 1.97 1.9740 2.23 2.23 2.2330 2.60 2.60 2.6030 at > 50%F 3.45 3.45 3.4525 at > 50%F 3.86 3.86 3.8630 at < 50%F 3.12 3.12 3.1225 at < 50%F 3.56 3.56 3.56* Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number ofTIP channels),

and up to 50% of the LPRMs out-of-service.

For single-loop operation, MCPRp limits will be 0.02 higher.Limits are applicable for all other EOOS scenarios, apart from TBV.Browns Ferry Unit 3 Cycle 17Core Operating Limits Report (105% OLTP)Page 34TVA-COLR-BF3C17, Revision 0 (Final) 1U NPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374025 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 isperformed for each reload core to determine allowable OLMCPR's as a function of OPRMsetpoint.

Analyses consider both steady state startup operation, and the case of a tworecirculation pump trip from rated power.The resulting stability based OLMCPR's are reported in Reference

1. The OPRM setpoint(sometimes referred to as the Amplitude Trip, Sp) is selected, such that required margin to the SLMCPRis provided without stability being a limiting event. Analyses are based on cycle specificDIVOM analyses performed per Reference

22. The calculated OLMCPR's are shown in Table5.1. Review of results shown in Table 4.2 indicates an OPRM setpoint of 1.14 may be used.The successive confirmation count (sometimes referred to as Np) is provided in Table 5.2, perReference 27.Table 5.1 OPRM Setpoint Range*OPRM OLMCPR OLMCPRSetpoint (SS) (2PT)1.05 1.18 1.191.06 1.20 1.211.07 1.22 1.231.08 1.24 1.251.09 1.26 1.271.10 1.28 1.291.11 1.30 1.311.12 1.32 1.331.13 1.34 1.361.14 1.36 1.381.15 1.39 1.40Table 5.2 OPRM Successive Confirmation Count SetpointCount OPRMSetpoint6 >1.048 >1.0510 1.0712 > 1.0914 > 1.1116 > 1.1418 > 1.1820 > 1.24"Extrapolation beyond a setpoint of 1.15 is not allowedIBivwns Ferry Unit 3 Cyde 17Core Operating Limits Report, (105% OLTP)Page 35TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 2014[PG 1101 Market Street, Chattanooga TN 374026 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 23 & 24, and is defined by thefollowing:

SRB _ (0.66(W-AW)

+ 61%) Allowable ValueSRB _ (0.66(W-AW)

+ 59%) Nominal Trip Setpoint (NTSP)where:SRB = Rod Block setting in percent of rated thermal power (3458 MWt)W = Loop recirculation flow rate in percent of ratedAW = Difference between two-loop and single-loop effective recirculation flowat the same core flow (AW=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%).Browns Ferry Unit 3 Cycle 17Core Operating ULmits Report, (105% OLTP)Page 36TVA-COLR-BF3C17, Revision 0 (Final)

[M NPGEDMS: L32 140123 801Date: January 23, 2014Reactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 374027 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 23 & 24, are shownin Table 7.1. 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 areconsistent with a nominal RBM filter setting less than 0.5 seconds.

Cycle specific CRWEanalyses of OLMCPR are documented in Reference 1, superseding values reported inReferences 23, 24, and 26.Table 7.1 Analytical RBM Trip Setpoints*

RBMTrip SetpointLPSPIPSPHPSPLTSP -unfiltered

-filteredAllowable Value(AV)27%62%82%121.7%120.7%Nominal TripSetpoint(NTSP)25%60%80%120.0%119.0%ITSP -unfiltered

-filteredHTSP -unfiltered

-filtered116.7%115.7%111.7%110.9%90%115.0%114.0%110.0%109.2%92%DTSPAs a result of cycle specific CRWE analyses, RBM setpoints in Technical Specification Table3.3.2.1-1 are applicable as shown in Table 7.2. Cycle specific setpoint analysis results areshown in Table 7.3, per Reference 1.Table 7.2 RBM Setpoint Applicability Thermal Power Applicable Notes from(% Rated) MCPRt Table 3.3.2.1-1 Comment< 1.74 (a), (b), (f), (h) two loop operation

> 27% and < 90%< 1.77 (a), (b), (f), (h) single loop operation

> 90% < 1.43 (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.t Greater than 90% rated power is not attainable in single loop operation.

Browns Ferry Unit 3 Cycle 17Core Operating Limits Report (105% OLTP)Page 37TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Date: January 23, 2014EIM iNPGReactor Engineering and Fuels -BWRFE1101 Market Street, Chattanooga TN 37402Table 7.3 Control Rod Withdrawal Error ResultsRBM CRWEHTSP Analytical Limit OLMCPRUnfiltered 107 1.28111 1.31114 1.33117 1.35Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPRremains protected for RBM inoperable conditions (i.e., 114% unblocked).

Browns Fery Unit 3 Cycle 17Core Operatng Limits Report, (105% OLTP)Page 38TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801Reactor Engineering and Fuels -BWRFE Date: January 23, 20141101 Market Street, Chattanooga TN 374028 Shutdown Margin Limit(Technical Specification 3.1.1)Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLEcontrol blades are fully inserted, the core shall be sub-critical and meet the following minimumshutdown margin:SDM > 0.38% dk/kir -1Browns Ferry Unit 3 Cycle 17Core operating Umits Report, (105% OLTP)Page 39"VA-COLR-BF3C17, Revision 0 (Final)