ML14052A217

Core Operating Limits Report for Cycle 17 Operation

ML14052A217
Person / Time
Site:	Browns Ferry
Issue date:	02/18/2014
From:	Polson K 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, 2014 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report for Cycle 17 Operation 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 3, Cycle 17, Core Operating Limits Report (COLR), Revision 0. Revision 0 of the BFN, 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 please contact Jamie L. Paul at (256) 729-2636.

Respectfully, K. J. Poison Vice President

Enclosure:

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

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

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

NRC Project Manager - Browns Ferry Nuclear Plant G. C. Storey, LP 4G-C EDMS, WT CA-K bcc: (w/o enclosure)

S. M. Bono, POB 2C-BFN D. M. Czufin, LP 3R-C S. M. Douglas, LP 3R-C K. J. Poison, NAB 2A-BFN C. S. Putnam, SAB 2A-BFN E. D. Schrull, LP 4B-C J. W. Shea, LP 3D-C P. B. Summers, NAB 1A-BFN S. A. Vance, W'T 6A-K P. R. Wilson, LP 4B-C NSRB Support, LP 5M-C S:\Licensing\LIC\EVERYONE\2014\Submittals\U3C17 COLR

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 17 Operation TVA-COLR-BF3C17, Revision 0 (See Attached)

K EDMS L32 140123 801 CA Document Pages Affected: All BFE-3603, Revision 0 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 17 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF3CI 7 Revision 0 (Final)

(Revision Log, Page v)

January 2014 Prepared:

I c - 'iýz /-,/

T. W. Eichenberg, Sr. Specialist Date: ,Ij4.-,. =23 ,2d/V Verified: Date: / /23 // -Y B. C etitel, Engineer Approved: Date:

G. C. Storey, Manager, WR Fuel Eng ineering

÷ - /

Reviewed: Date: _/__q__

D. D. Co--fey, Manager, Reactor Engineerirng Approved: Date: 1""o" --

Approved: Date: 31/4-m

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 N PG 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 39 (including review cover sheet)

L ist o f T a b le s ................................................................................................................................................. iii L ist o f F ig u re s ................................................................................................................................................ iv Re v is ion Lo g ................................................................................................................................... v N om e n c la tu re ................................................................................................................................................ vi R e fe re n ce s .................................................................................................................................................. v iii 1 Introduction ........................................................................................................................ 10 1.1 Purpose ....................................................................................................................... 10 1 .2 S c o p e .......................................................................................................................... 10 1.3 Fuel Loading ................................................................................................................ 10 1.4 Acceptability ................................................................................................................ 11 2 APLHG R Lim its .................................................................................................................. 12 2.1 Rated Power and Flow Lim it: APLHG RRATED ......................................................... 12 2.2 Off-Rated Power Dependent Lim it: APLHG Rp ....................................................... 12 2.2.1 Startup without Feedwater Heaters ................................................................ 12 2.3 Off-Rated Flow Dependent Lim it: APLHG RF ......................................................... 12 2.4 Single Loop O peration Lim it: APLHG RSLO .............................................................. 12 2.5 Equipm ent O ut-Of-Service Corrections ................................................................... 14 3 LHG R Lim its ....................................................................................................................... 15 3.1 Rated Power and Flow Lim it: LHG RRATED ................................................................... 15 3.2 Off-Rated Power Dependent Lim it: LHG Rp ............................................................ 15 3.2.1 Startup without Feedwater Heaters ................................................................ 15 3.3 Off-Rated Flow Dependent Lim it: LHG RF .............................................................. 16 3.4 Equipm ent O ut-Of-Service Corrections ................................................................... 16 4 O LM CPR Lim its ................................................................................................................. 22 4.1 Flow Dependent MCPR Lim it: MCPRF ................................................................... 22 4.2 Power Dependent MCPR Lim it: MCPRp ................................................................ 22 4.2.1 Startup without Feedwater Heaters ................................................................ 22 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS) ............................. 23 4.2.3 Exposure Dependent Lim its ............................................................................ 23 4.2.4 Equipm ent O ut-Of-Service (EO OS) Options .................................................. 24 4.2.5 Single-Loop-Operation (SLO ) Lim its .............................................................. 24 4.2.6 Below Pbypass Lim its ..................................................................................... 24 5 Oscillation Power Range Monitor (O PRM ) Setpoint .................................................... 35 6 APRM Flow Biased Rod Block Trip Settings ................................................................. 36 7 Rod Block Monitor (RBM ) Trip Setpoints and O perability .............................................. 37 8 Shutdown Margin Lim it................................................................................................. 39 Browns Ferry Unit 3 Cycle 17 Page ii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 MNP G 1101 Market Street, Chattanooga TN 37402 List of Tables Nu cle a r F ue l Ty pe s ..................................................................................................................... 11 Startup Feedwater Temperature Basis ................................................................................... 15 Nom inal Scram Tim e Basis .................................................................................................... 23 MCPRp Limits for Optimum Scram Time Basis ..................................................................... 26 MCPRp Limits for Nominal Scram Time Basis ....................................................................... 27 MCPRP Limits for Technical Specification Scram Time Basis ................................................ 29 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1: Technical Specification S cra m T im e B as is ....................................................................................................................... 31 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2: Technical Specification S cra m T im e B as is ....................................................................................................................... 32 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1: Nominal Scram Time B a s is ........................................................................................................................................... 33 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2: Nominal Scram Time B a s is ........................................................................................................................................... 34 O P RM S etpoint R ange .......................................................................................................... 35 OPRM Successive Confirmation Count Setpoint ................................................................... 35 Analytical RBM Trip Setpoints .............................................................................................. 37 R BM S etpoint Applicability .................................................................................................... . . 37 Control Rod Withdrawal Error Results ................................................................................... 38 Browns Ferry Unit 3 Cyde 17 Page iii Core Operating ULmits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 TN 37402 1101 Market Street, Chattanooga List of Figures APLHG RRATED for ATRIUM -10 Fuel ....................................................................................... 13 LHG RpATED for ATR IUM-10 Fuel ............................................................................................ 17 Base Operation LHGRFACp for ATRIUM-10 Fuel ................................................................ 18 LHG RFACF for ATR IUM -1 0 Fuel ........................................................................................... 19 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 1 ....... 20 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 2 ...... 21 MC PR Ffor ATR IUM-10 Fuel ............................................................................................... .25 Browns Ferry Unit 3 Cycle 17 Page iv Core Operating Limits Report (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 EIMNPG 1101 Market Street, Chattanooga TN 37402 Revision Log INumber I Page Description O-RO All New document.

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

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 NPG 1101 Market Street, Chattanooga TN 37402 Nomenclature APLHGR Average Planar LHGR APRM Average Power Range Monitor AREVA NP Vendor (Framatome, Siemens)

ARTS APRM/RBM Technical Specification Improvement BOC Beginning of Cycle BWR Boiling Water Reactor CAVEX Core Average Exposure CD Coast Down CMSS Core Monitoring System Software COLR Core Operating Limits Report CPR Critical Power Ratio CRWE Control Rod Withdrawal Error CSDM Cold SDM DIVOM Delta CPR over Initial CPR vs. Oscillation Magnitude ECCS Emergency Core Cooling System EOC End of Cycle EOCLB 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 LHGR Linear Heat Generation Rate LHGRFAC LHGR Multiplier (Power or Flow dependent)

LPRM Low Power Range Monitor LRNB Generator Load Reject, No Bypass Browns Feny Unit 3 Cycle 17 Page vi Core operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Finad)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 0 !~NPG 1101 Market Street, Chattanooga TN 37402 MAPFAC MAPLHGR multiplier (Power or Flow dependent)

MCPR Minimum CPR MELL Maximum Extended Load Line MSRV Moisture Separator Reheater Valve MSRVOOS MSRV OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit 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 RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation SRV Safety Relief Valve SRVOOS SRV OOS TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS TBV OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority Page vii Ferry un~

Browns Feriy Browns Cycle 17 3 Cyde Unit 3 17 Page vii Core operating Limits Report, (105% OLTP)

TVA-C0LR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 TN 37402 1101 Market Street, Chattanooga References

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 3 Reload 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 Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

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

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

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

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

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

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

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

14. 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.

Browns Ferry Unit 3 CyRee 17 Page viii Core operating Limits Report, (105% OLTP) TVA-C0LR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 I,,1NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Dt:Jnay321 Date: January 23, 2014

15. ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology 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 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. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001, as supplemented by the site specific approval in NRC safety evaluation dated February 15, 2013.

20. EMF-2292(P)(A) Revision 0, ATRIUM TM-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), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP Inc., Inc., May, 2008.

PRNM Setpoint References

23. Filtered Setpoints - EDE-28-0990 Rev. 3 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.

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 Setpoint Clarification - 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 Nuclear Energy, April 1995.

27. NEDO-32465-A, Licensing Topical Report - Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, GE Nuclear Energy, August 1996.

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

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 NPG TN 37402 Jnay3 1101 Market Street, Chattanooga 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, > 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 Modes 1.3 Fuel Loading The core will contain previously exposed and fresh AREVA NP, Inc., ATRIUM-10 fuel. 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 in Reference 5.

Browns Ferry Unit 3 Cycle 17 Page 10 Core Operang Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 IM NPG 1101 Market Street, Chattanooga TN 37402 Table 1.1 Nuclear Fuel Types*

Nuclear Original Number of Fuel Type Fuel Names Fuel 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 per References 6 through 22.

The table identifies the expected fuel type breakdown inanticipation 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 inthis document.

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

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 PG M 1101 Market Street, Chattanooga TN 37402 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 (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 in Figure 2.1.

2.2 Off-Rated Power Dependent Limit: APLHGRp Reference 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 FeedwaterHeaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. No Additional power dependent limitation is required.

2.3 Off-Rated Flow Dependent Limit: APLHGRF Reference 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.

I Browns Ferry Unit 3 Cyde 17 Page 12 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[MIiNPG 1101 Market Street, Chattanooga TN 37402 15 12 9

CL 4 6 3

0 0 20 40 60 80 PlanarAverage Exposure (GWdlMTU)

Planar Avg. APLHGR Exposure Limit (G1 (kWft) 0.0 12.5 15.0 12.5 67.0 7.3 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Browns FerryUnk3 Cycle 17 Page 13 Core Operfing LimblsReport (105% OLTP) TVA-COLR-BF3C17, Revision 0 (F'wil)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[M NPG 1101 Market Street, Chattanooga TN 37402 2.5 Equipment Out-Of-Service Corrections The limits shown in Figure 2.1 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 Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to the rated APLHGR limits as described previously.

• All equipment service conditions assume 1SRVOOS.

Browns FerryUnit 3Cycle 17 Page 14 Core OeakinqLkir~t Report, (105% OLTP) "VA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[MliNPG 1101 Market Street, Chattanooga TN 37402 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 (LHGRp, LHGRF) where:

LHGRp off-rated power LHGR limit [LHGRRATED

• LHGRFACp]

LHGRF off-rated flow LHGR limit [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 Figure 3.1. The LHGR limit is consistent with References 2 and 3.

3.2 Off-Rated Power Dependent Limit: LHGRp LHGR limits are adjusted for off-rated power conditions using the LHGRFACp multiplier provided in Reference 1. The multiplier is split into two sub cases: turbine bypass valves in and out-of-service. The multipliers are shown in Figure 3.2.

3.2.1 Startup without FeedwaterHeaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional limits are shown in Figure 3.4 and Figure 3.5, based on temperature conditions identified in Table 3.1.

Table 3.1 Startup Feedwater Temperature Basis Temperature Power Range 1 Range 2 25 160.0 155.0 30 165.0 160.0 40 175.0 170.0 50 185.0 180.0 Page 15 BownsFenyunt3cydel7 Browis Ferry Unit 3 Cycle 17 Page 15 Core OPM*alV Lhft# Report (105% OLTP) TVA-C0LR-BF3C17, Reh3bn 0 (Fiffial)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 EIMiNPG 1101 Market Street, Chattanooga TN 37402 3.3 Off-Rated Flow Dependent Limit: LHGRF The LHGR limit is adjusted for off-rated flow conditions using the LHGRFACF multiplier provided in 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 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 SLO Single Loop Operation, One Recirculation Pump Out--Of-Service Off-rated power corrections shown in Figure 3.2 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 3.3 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 during startup. These limits have no dependency on RPTOOS, PLUOOS, or SLO.

. All equipment service conditions assumfe 1SRVOOS.

Page 16 Bit~ns Fetry Unit 3C~de 17 Page 16 CoreOetlig Units Report (105% OLTP) 1ACL-FC7 Revisim TVA-C0LR-BF3C17, eso 0 Frd)

F~

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 23, 2014

[M NPG 15 12 9

0

-j 6 3

0 0 20 40 60 80 Pellet Exposure (GWd/MTU)

Pellet LHGR Exposure Limit 0.0 13.4 18.9 13.4 74.4 7.1 Figure 3.1 LHGRRATED for ATRIUM-10 Fuel Broaws Ferry Unit 3 Cyde 17 Page 17 Core LimitrReport, (105% OLTP) TVA-COUR-F3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[M ~NPG 1101 Market Street, Chattanooga TN 37402 1.10 1.00 0.90 Turbine BypassValve In-Service, TBVIS 0.80 L-Turbine Bypass Valve Out-of-Service, TBVOOS II

.U-0.70 C,,

0.60 TBVIS, < 50% Core Flow 0.50 TBVIS, >50% Core Flow TBVOOS, 5 50% Core Flow 0.40 j

TBVOOS, > 50% Core Flow 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Core Power LHGRFACp Power LHGRFACp 100.0 1.00 100.0 0.95 30.0 0.61 30.0 0.61 Core Flow > 50% Rated Core Flow > 50% Rated F

30.0 0.48 30.0 0.43 25.0 0.43 25.0 0.41 Core Flow < 500/6 Rated Core Flow S 50% Rated 30.0 0.50 30.0 0.48 25.0 0.45 25.0 0.41 Figure 3.2 Base Operation LHGRFACp for ATRIUM-10 Fuel (Independent of other EOOS conditions)

Browns Ferry Unit 3 Cye17 Page 18 CoreOeraling Units Report~ (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[MJiNPG 1101 Market Street, Chattanooga TN 37402 1.10 1.05 1.00 IL U

4 0.95 0

-J 0.90 0.85 0.80 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow LHGRFACF 6 IRated) 0.0 0.93 30.0 0.93 46.4 1 107.0 1 Figure 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 17 Page 19 Core Operating Limits Report (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 REi NPG 1101 Market Street, Chattanooga TN 37402 1.10 1.00 0.90 Turbine Bypass Valve In-Service, TBVIS 0.80 0.

IL Turbine Bypass Valve Out-of-Service, TBVOOS 0.70 LJ

-J-0.60 T 0I 0.50 TBVIS, S 50% Core Flow TBVooS>50%Core Flow 0.40 .;7 TBVIS, > 50% Core Flow TBVOOS, > 50% Core Flow 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Core Power LHGRFACp Power LHGRFACp

(% Rated) _ (%Rated) (

100.0 f 1.00 100.0 0.95 30.0 0.56 30.0 0.56 Core Row > 50% Rated Core Row > 50% Rated 30.0 j 0.42 30.0 0.38 25.0 0.37 25.0 0.33 Core Flow < 50% Rated Core Row $ 50% Rated 30.0 0.45 30.0 0.43 25.0 1 0.39 25.0 1 0.36 Figure 3.4 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

Table 3.1 Temperature Range 1 (no Feedwaterheating during startup)

Browns Ferry Unit 3 Cycle 17 Page 20 Core Operatirg Lits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 RE ~iNPG 1101 Market Street, Chattanooga TN 37402 1.10 1.00 0.90 Turbine Bypass Valve In-Service, TBVIS 0.80 ILL Turbine Bypas Valve Out-of-Service, TBV0OS 0.70 0

-J 0.60 0.50 TBVIS, s 50% Core Flow TBVOOS, S50% Core Flow 0.40 TBVIS, > 50% Core Flow O 5 I TBVOOS, > 50% Core Flow 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Core Power LHGRFACp Power LHGRFACp

(%Rated) _ (% Rated) ______

100.0 1.00 100.0 0.95 30.0 0.56 30.0 0.56 Core Fow > 50% Rated Core Fow > 50% Rated 30.0 0.42 30.0 0.37 25.0 0.37 25.0 0.33 Core Flow < 50% Rated Core Flow < 50% Rated 30.0 0.44 30.0 0.43 25.0 I 0.39 25.0 0.36 Figure 3.5 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

Table 3.1 Temperature Range 2 (no Feedwaterheating during startup)

Page 21 Bn~wns Ferry Brows Cyde 17 Unit 33 Cycle Ferry Unit 17 Page 21 Core opera"n Lirnts Report, (105% OLTP)

TVA-C0LR-l3F3C17, ReArjon 0 (Frial)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 TN 37402 1101 Market Street, Chattanooga 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 ( MCPRF, MCPRp) where:

MCPRF core flow-dependent MCPR limit MCPRp power-dependent MCPR limit 4.1 Flow Dependent MCPR Limit: MCPRF MCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated or Increased Core Flow, ICF). MCPRF limits are shown in Figure 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: MCPRP MCPRp limits are dependent upon:

" Core Power Level (% of Rated)

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

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

" Equipment Out-Of-Service Options

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

The MCPRp limits are provided in the following tables, where each table contains the limits for all fuel types and EOOS options (for a specified scram speed and exposure range). The CMSS determines MCPRp limits, from these tables, based on linear interpolation between the specified powers.

4.2.1 Startup without FeedwaterHeaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional power dependent limits are shown in Table 4.5 through Table 4.8, based on temperature conditions identified in Table 3.1.

Brovm FerryUnk 3 Cycle17 Page 22 Core peraing Li~t Report (105% OLTP) TVACOLAR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[M1iNPG 1101 Market Street, Chattanooga TN 37402 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)

MCPRp limits are provided for three different sets of assumed scram speeds. The Technical Specification Scram Speed (TSSS) MCPRp limits are applicable at all times, as long as the scram time surveillance demonstrates the times in Technical Specification Table 3.1.4-1 are met. Both Nominal Scram Speeds (NSS) and/or Optimum Scram Speeds (OSS) may be used, as long as the scram time surveillance demonstrates Table 4.1 times are applicable.*t Table 4.1 Nominal Scram Time Basis Notch Nominal Optimum Position Scram Timing Scram Timing (index) (seconds) (seconds) 46 0.420 0.380 36 0.980 0.875 26 1.600 1.465 6 2.900 2.900 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 demonstrated, TSSS based MCPRp limits are applied.

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

4.2.3 Exposure Dependent Limits Exposures 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 Average Exposure up to the ending exposure. Per Reference 1, MCPRp limits are provided for the following exposure ranges:

BOC to NEOC NEOC corresponds to 27,393.0 MWd / MTU BOC to EOCLB EOCLB corresponds to 31,304.9 MWd / MTU BOC to End of Coast End of Coast 32,724.6 MWd I MTU NEOC refers to a Near EOC exposure point.

. Reference 1 analysis results are based on information identified inReference 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 17 Page 23 Core OpertfiM Limits Report (105% OLTP) "VA-COLR-BF3C17, Revision 0 (Fwral)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 EI!MNPG 1101 Market Street, Chattanooga TN 37402 The EOCLB exposure point is not the true End-Of-Cycle exposure. Instead it corresponds to a licensing exposure window exceeding expected end-of-full-power-life.

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 MCPRp limits are given by the following:

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

For exposure ranges up to NEOC and EOCLB, additional combinations of MCPRp limits are also provided including FHOOS. The coast down exposure range assumes application of FFWTR. FHOOS based MCPRp limits for the coast down exposure are redundant because the temperature setdown assumption is identical with FFWTR.

4.2.5 Sin-gle-Loop-Operation(SLO) Limits MCPRp limits are increased by 0.02 to support SLO, per Reference 1.

4.2.6 Below Pbypass Limits Below Pbypass (30% rated power), MCPRp limits depend upon core flow. One set of MCPRp 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 1SRVOOS.

Page 24 Brow.ns Ferry Unit 3 Cycle 17 BEo~sFenyUnit3Cyde 17 Page 24 Core Opwafing Limits Repot (105% OLTP) TVA-C0LR-l3F3C17, Revision 0 (Finad)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 EIMNPG 1101 Market Street, Chattanooga TN 37402 2.00 1.80 1.60 I.

1.40 1.20 1.00 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow MCPRF

(%Rated) 30.0 1.61 78.0 1.28 107.0 1.28 Figure 4.1 MCPRF for ATRIUM-10 Fuel (Values bound all EOOS conditions)

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

Browns Fery Unit 3 Cycle 17 Page 25 Core Operaling LUit Repot (105% OLTP) "VA-COLR-BF3C17, Revisio 0 (Finl)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BBWRFE Date: January 23, 2014 EIM NPG 110 1 Market Street, Chattanooga TN 37402 Table 4.2 MCPRp Limits for Optimum Scram Time Basis*

BOC BOC BOC Operating Fower to to to End of Condition (% of rated) NEOC EOCLB Coast 100 1.38 1.41 1.43 75 1.51 1.51 1.55 65 1.57 1.57 1.61 50 1.70 1.70 1.76 50 1.93 1.93 1.93 Base Case 40 2.03 2.03 2.03 30 2.19 2.19 2.30 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at < 50%F 2.45 2.45 2.52 25 at 5 50%F 2.68 2.68 2.80 100 1.40 1.43 ---

75 1.55 1.55 65 1.61 1.61 50 1.76 1.76 50 1.93 1.93 FHOOS 40 2.03 2.03 30 2.30 2.30 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

• 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 0.02 higher.

FFWTRIFHOOS is supported for the BOC to End of Coast limits.

Browns Ferry Unit 3 Cycle 17 Page 26 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 23, 2014 IM NPG Table 4.3 MCPRp Limits for Nominal Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition (% of rated) NBOC BOCLB Coast 100 1.40 1.42 1.43 75 1.53 1.53 1.56 65 1.59 1.59 1.62 50 1.72 1.72 1.79 50 1.93 1.93 1.94 Base Case 40 2.04 2.04 2.04 30 2.22 2.22 2.33 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at  : 50%F 2.45 2.45 2.52 25 at < 50%F 2.68 2.68 2.80 100 1.44 1.46 1.47 75 1.57 1.57 1.60 65 1.62 1.63 1.66 50 1.75 1.75 1.81 50 1.93 1.93 1.94 TBVOOS 40 2.04 2.04 2.04 30 2.23 2.23 2.34 30 at > 50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at < 50%F 2.74 2.74 2.88 25 at! <50%F 3.17 3.17 3.32 100 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 1.43 75 1.53 1.53 1.56 65 1.82 1.82 1.83 50 ... ... ...

50 1.94 1.94 1.94 PLUOOS 40 2.04 2.04 2.04 30 2.22 2.22 2.33 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at < 50%F 2.45 2.45 2.52 25 at < 50%F 2.68 2.68 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 0.02 higher.

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.

A 50% power step change for PLUOOS limits is not supported. When core power is< 50%, the LRNB event isthe same with, or without PLUOOS.

Browns Ferry Unit 3 Cycle 17 Page 27 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 U@INPG 1101 Market Street, Chattanooga TN 37402 Table 4.3 MCPRp Limits for Nominal Scram Time Basis (continued)*

BOC BOC BOC Operating Power to to to End of Condition (% of rated) NEOC E0CLB Coast 100 1.46 1.47 ---

75 1.59 1.60 --

65 1.66 1.66 ---

50 1.81 1.81 ---

1.94 1.94 --

50 40 2.04 2.04 ---

EHOOS 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 1.47 75 1.57 1.57 1.60 65 1.82 1.82 1.83 50 ... ... ...

50 1.94 1.94 1.94

-BVOOS PtuOOS 40 2.04 2.04 2.04 30 2.23 2.23 2.34 30 at > 50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at5<50%F 2.74 2.74 2.88 25 at < 50%F 3.17 3.17 3.32 100 1.43 1.43 ---

75 1.55 1.56 ---

65 1.83 1.83 ---

50 ... ... ...

50 1.94 1.94 ---

A-OS 40 2.04 2.04 ---

PtUOOS 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 1.47 75 1.59 1.60 65 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 0.02 higher.

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.

A 50% power step change for PLUOOS limits is not supported. When core power is < 50%, the LRNB event is the same with, or without PLUOOS.

Browns Ferry Unit 3 Cycle 17 Page 28 Core Operating Urmits Report (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 23, 2014

[M NPG Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition (% of rated) NEOC EOCLB Coast 100 1.42 1.43 1.44 75 1.55 1.55 1.57 65 1.60 1.60 1.64 50 1.75 1.75 1.82 50 1.94 1.94 1.95 Base Case 40 2.05 2.05 2.05 30 2.24 2.24 2.36 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at < 50%F 2.45 2.45 2.52 25 at ! 50%F 2.68 2.68 2.80 100 1.46 1.47 1.48 75 1.59 1.59 1.61 65 1.64 1.64 1.68 50 1.77 1.77 1.83 50 1.94 1.94 1.95 TBVOOS 40 2.05 2.05 2.07 30 2.26 2.26 2.37 30 at > 50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at < 50%F 2.74 2.74 2.88 25 at5<50%F 3.17 3.17 3.32 100 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 1.44 75 1.55 1.55 1.57 65 1.83 1.83 1.84 50 ... ... ...

50 1.95 1.95 1.95 PLLUOOS 40 2.05 2.05 2.05 30 2.24 2.24 2.36 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at < 50%F 2.45 2.45 2.52 25 at < 50%F 2.68 2.68 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 0.02 higher.

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.

A 50% power step change for PLUOOS limits is not supported. When core power is < 50%, the LRNB event is the same with, or without PLUOOS.

Browns Ferry Unit 3 Cycle 17 Page 29 Core Operating Limit Report, (105% OLTP) TVA-COLR-BF3C1 7, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[M ~NPG 1101 Market Street, Chattanooga TN 37402 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis (continued)*

BOC BOC BOG Pow er to to to End of Operating Condition (% of rated) NEOC EOCLB Coast 100 1.48 1.48 ---

75 1.61 1.61 65 1.68 1.68 ---

50 1.83 1.83 ---

50 1.95 1.95 TBVOOS 40 2.07 2.07 ---

FHOOS 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 1.48 75 1.59 1.59 1.61 65 1.83 1.83 1.84 50 ... ... ...

TBVOOS 50 1.95 1.95 1.95 40 2.05 2.05 2.07 P..uoos 30 2.26 2.26 2.37 30 at > 50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at < 50%F 2.74 2.74 2.88 25 at:<50%F 3.17 3.17 3.32 100 1.44 1.44 75 1.57 1.57 ---

65 1.84 1.84 ---

50 ... ... ...

50 1.95 1.95 ---

40 2.05 2.05 ---

mUOOS 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 1.48 1.48 ---

75 1.61 1.61 65 1.84 1.84 50 --- .-..

TBVOOS 50 1.95 1.95 FHOOS 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 0.02 higher.

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.

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 without PLUOOS.

Browns Ferry Unit 3 Cyde 17 Page 30 Core Operating ULmits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Fnal)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[M NPG 1101 Market Street, Chattanooga TN 37402 Table 4.5 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:

Technical Specification Scram Time Basis*

BOC BOC BOC Pow er to to to End of Operating Condition (% of rated) NEOC EOCLB Coast 100 1.44 1.44 1.44 75 1.57 1.57 1.57 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 1.99 1.99 1.99 TBVIS 40 2.24 2.24 2.24 30 2.61 2.61 2.61 30 at > 50%F 2.88 2.88 2.88 25 at > 50%F 3.21 3.21 3.21 30 at < 50%F 2.79 2.79 2.79 25 at < 50%F 3.07 3.07 3.07 100 1.48 1.48 1.48 75 1.61 1.61 1.61 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 1.99 1.99 1.99 TBVOOS 40 2.25 2.25 2.25 30 2.61 2.61 2.61 30 at > 50%F 3.44 3.44 3.44 25 at > 50%F 3.85 3.85 3.85 30 at 5 50%F 3.10 3.10 3.10 25 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 of TIP 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 17 Page 31 Core Operating Limits Report, (1105% OLTP) TVA-COLR-BF3C1 7, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 V ~NPG 1101 Market Street, Chattanooga TN 37402 Table 4.6 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Technical Specification Scram Time Basis*

BOC BOC BOC Pow er to to to End of Operating Condition (% of rated) NEOC EOCLB Coast 100 1.44 1.44 1.44 75 1.57 1.57 1.57 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 2.00 2.00 2.00 TBVIS 40 2.26 2.26 2.26 30 2.63 2.63 2.63 30 at > 50%F 2.90 2.90 2.90 25 at > 50%F 3.23 3.23 3.23 30 at < 50%F 2.80 2.80 2.80 25 at < 50%F 3.09 3.09 3.09 100 1.48 1.48 1.48 75 1.61 1.61 1.61 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 2.00 2.00 2.00 TBVOOS 40 2.26 2.26 2.26 30 2.63 2.63 2.63 30 at > 50%F 3.45 3.45 3.45 25 at > 50%F 3.86 3.86 3.86 30 atS 50%F 3.12 3.12 3.12 25 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 of TIP 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 Unit3 Cy(le 17 Page 32 Core Operating Limits Report, (105% OLTP) TVA-C0LR-I3F3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 IM NPG 1101 Market Street, Chattanooga TN 37402 Table 4.7 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:

Nominal Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition (% of rated) NEOC EOCLB Coast 100 1.43 1.43 1.43 75 1.55 1.56 1.56 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.96 1.96 1.96 TBVIS 40 2.22 2.22 2.22 30 2.58 2.58 2.58 30 at > 50%F 2.88 2.88 2.88 25 at > 50%F 3.21 3.21 3.21 30 at < 50%F 2.79 2.79 2.79 25 at 5 50%F 3.07 3.07 3.07 100 1.46 1.47 1.47 75 1.59 1.60 1.60 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.96 1.96 1.96 TBVOOS 40 2.22 2.22 2.22 30 2.58 2.58 2.58 30 at > 50%F 3.44 3.44 3.44 25 at > 50%F 3.85 3.85 3.85 30 ats 50%F 3.10 3.10 3.10 25 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 of TIP 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 17 Page 33 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE IM NPG Date: January 23, 2014 1101 Market Street, Chattanooga TN 37402 Table 4.8 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Nominal Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition (% of rated) NEOC EOCLB Coast 100 1.43 1.43 1.43 75 1.55 1.56 1.56 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.97 1.97 1.97 TBVIS 40 2.23 2.23 2.23 30 2.60 2.60 2.60 30 at > 50%F 2.90 2.90 2.90 25 at > 50%F 3.23 3.23 3.23 30 at < 50%F 2.80 2.80 2.80 25 at < 50%F 3.09 3.09 3.09 4

100 1.46 1.47 1.47 75 1.59 1.60 1.60 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.97 1.97 1.97 TBVOOS 40 2.23 2.23 2.23 30 2.60 2.60 2.60 30 at > 50%F 3.45 3.45 3.45 25 at > 50%F 3.86 3.86 3.86 30 at < 50%F 3.12 3.12 3.12 25 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 of TIP 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 17 Page 34 Core Operating Limits Report (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 1U NPG 1101 Market Street, Chattanooga TN 37402 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 setpoint (sometimes referred to as the Amplitude Trip, Sp) 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 Table 4.2 indicates an OPRM setpoint of 1.14 may be used.

The successive confirmation count (sometimes referredto as Np) is provided in Table 5.2, per Reference 27.

Table 5.1 OPRM Setpoint Range* Table 5.2 OPRM Successive Confirmation Count Setpoint OPRM OLMCPR OLMCPR Count OPRM Setpoint (SS) (2PT)

Setpoint 1.05 1.18 1.19 6 >1.04 1.06 1.20 1.21 1.07 1.22 1.23 8 >1.05 1.08 1.24 1.25 10

• 1.07 1.09 1.26 1.27 12 > 1.09 1.10 1.28 1.29 1.11 1.30 1.31 14 > 1.11 1.12 1.32 1.33 16 > 1.14 1.13 1.34 1.36 18 > 1.18 1.14 1.36 1.38 1.15 1.39 1.40 20 > 1.24 "Extrapolation beyond a setpoint of 1.15 is not allowed I

Bivwns Ferry Unit 3 Cyde 17 Page 35 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[PG 1101 Market Street, Chattanooga TN 37402 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 23 & 24, and is defined by the following:

SRB _ (0.66(W-AW) + 61%) Allowable Value SRB _ (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 rated AW = Difference between two-loop and single-loop effective recirculation flow at 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 17 Page 36 Core Operating ULmits Report, (105% OLTP) TVA-COLR-BF3C17, Revision 0 (Final)

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014

[M NPG 1101 Market Street, Chattanooga TN 37402 7 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 shown in 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 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 23, 24, and 26.

Table 7.1 Analytical RBM Trip Setpoints*

Allowable Nominal Trip RBM Value Setpoint Trip Setpoint (AV) (NTSP)

LPSP 27% 25%

IPSP 62% 60%

HPSP 82% 80%

LTSP - unfiltered 121.7% 120.0%

- filtered 120.7% 119.0%

ITSP - unfiltered 116.7% 115.0%

- filtered 115.7% 114.0%

HTSP - unfiltered 111.7% 110.0%

- filtered 110.9% 109.2%

DTSP 90% 92%

As a result of cycle specific CRWE analyses, RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable as shown in Table 7.2. Cycle specific setpoint analysis results are shown 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 insingle loop operation.

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

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 EIM iNPG 1101 Market Street, Chattanooga TN 37402 Table 7.3 Control Rod Withdrawal Error Results RBM CRWE HTSP Analytical Limit OLMCPR Unfiltered 107 1.28 111 1.31 114 1.33 117 1.35 Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 114% unblocked).

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

EDMS: L32 140123 801 Reactor Engineering and Fuels - BWRFE Date: January 23, 2014 TN 37402 1101 Market Street, Chattanooga 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 ir -1 Browns Ferry Unit 3 Cycle 17 Page 39 Core operating Umits Report, (105% OLTP) "VA-COLR-BF3C17, Revision 0 (Final)