ML110670225

Core Operating Limits Report for Cycle 17 Operation

ML110670225
Person / Time
Site:	Browns Ferry
Issue date:	03/02/2011
From:	Krich R, Eichenberg T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF2C17, Rev. 0
Download: ML110670225 (41)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing March 2, 2011 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

Browns Ferry Nuclear Plant, Unit 2 Core Operating Limits Report for Cycle 17 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 2, Cycle 17, Core Operating Limits Report (COLR). The Unit 2, 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 Tom Matthews at (423) 751-2687.

Respectfully, R. M. Krich

Enclosure:

Core Operating Limits Report, (105% OLTP), for Cycle 17 Operation TVA-COLR-BF2C17, Revision 0 cc: (Enclosure)

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant printed on recycled paper

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 Core Operating Limits Report, (105% OLTP), for Cycle 17 Operation TVA-COLR-BF2CI7, Revision 0 (See Attached)

- U----

EDMS L32 110204 801 QA Document Pages Affected: All 0

Revision BFE-3086, Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 2 Cycle 17 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF2C17 Revision 0 (Final)

(Revision Log, Page v)

February 2011 P re pare8ýý-*,ý"I/_,J!-t Date: .. //

--- I'. W. Eichenberg, Sr. VJecialist Verified: Date: I c)//zO W. B. Bird, Engineer Approved: - _' Date: 2/4-1!

G. C. Storey, Ma ager, B R Fuel EngineEering Reviewed: Date: 2-P?', J. M. Keck, Manager, Reactor Engineering W-1 7e-3 Approved: C b//a,',#) Date:

Chairman, PORC U

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE N PG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 Table of Contents Total Number of Pages = 39 (including review cover sheet)

L ist of T a b le s ................................................................................................................................................. iii Lst of Figure s ................................................................................................................................................ iv Revision Log ................................................................................................................................... v No m e n c la tu re ................................................................................................................................................ vi Re fe re n ce s ....................... .......................................................................................................................... v iii 1 Introduction .......................................................................................................................... 1 1.1 Purpose ......................................................................................................................... 1 1.2 Scope ............................................................................................................................ 1 1.3 Fuel Loading .................................................................................................................. 1 1.4 Acceptability ......................................................................................................... 1 2 APLHG R Lim its ............................................................................................................ 3 2.1 Rated Power and Flow Lim it: APLHG RRATED ............................................................ 3 2.2 Off-Rated Power Dependent Lim it: APLHG Rp ....................................................... 3 2.2.1 Startup without Feedwater Heaters ................................................................... 3 2.3 Off-Rated Flow Dependent Lim it: APLHG RF ............................................................ 3 2.4 Single Loop O peration Lim it: APLHG RSLO .............................................................. 3 2.5 Equipm ent O ut-Of-Service Corrections ..................................................................... 5 3 LHG R Lim its .......................................................................................................................... 6 3.1 Rated Power and Flow Lim it: LHG RRATED ..................................................................... 6 3.2 Off-Rated Power Dependent Lim it: LHGRp ............................................................ 6 3.2.1 Startup without Feedwater Heaters ................................................................... 6 3.3 Off-Rated Flow Dependent Lim it: LHG RF ................................................................. 7 3.4 Equipm ent O ut-Of-Service Corrections ................................................................... 7 4 O LM CPR Lim its ................................................................................................................. 13 4.1 Flow Dependent MCPR Lim it: MCPRF ................................................................... 13 4.2 Power Dependent MCPR Lim it: MCPRp ................................................................ 13 4.2.1 Startup without Feedwater Heaters ............................................................... 13 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS) ............................. 14 4.2.3 Exposure Dependent Lim its ............................................................................ 14 4.2.4 Equipm ent O ut-Of-Service (EOOS) O ptions .................................................. 15 4.2.5 Single-Loop-O peration (SLO ) Lim its .............................................................. 15 4.2.6 Below Pbypass Lim its ..................................................................................... 15 5 APRM Flow Biased Rod Block Trip Settings ................................................................. 24 6 Rod Block Monitor (RBM ) Trip Setpoints and Operability .............................................. 25 7 Shutdow n Margin Lim it.................................................................................................. 27 Appendix A: Therm al-Hydraulic Stability ............................................................................. 28 Browns Ferry Unit 2 Cycle 17 Page ii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE N PG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 List of Tables Nuclear Fuel Types ......................................................................................... .. ................... 2 Startup Feedwater Temperature Basis .................................................................................. 6 Nom inal Scram Tim e Basis .................................................................................................... 14 MCPRp Limits for Optimum Scram Time Basis ..................................................................... 17 MCPRp Limits for Nominal Scram Time Basis ....................................................................... 18 MCPRp Limits for Technical Specification Scram Time Basis ............................................... 20 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:

Technical Specification Scram Time Basis ................................... 22 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Technical Specification Scram Time Basis ............................................................................ 23 A nalytical RBM Trip Setpoints .............................................................................................. 25 R BM Setpoint A pplicability ...................................................................................................... 25 Control Rod Withdrawal Error Results ................................................................................... 26 O P RM S etpo ints ......................................................................................................................... 30 Browns Ferry Unt 2 Cyle 17 Page iii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 N PG List of Figures APLHG RRATED for ATRIUM -1 0 Fuel ........................................................................................ 4 LHG RRATED for ATRIUM -10 Fuel ............................................................................................ .8 Base Operation LHGRFACp for ATRIUM-1 0 Fuel .................................................................. 9 LHG RFACF for ATRIUM -10 Fuel ............................................................................................ 10 Startup Operation LHGRFACp for ATRIUM-1 0 Fuel: Table 3.1 Temperature Range 1 .............. 11 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 2 ....... 12 MC PRF for ATR IUM-10 Fuel ................................................................................................... 16 Browns Ferry Unit 2 Cyde 17 Page iv Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 V INPG 1101 Market Street, Chattanooga TN 37402 Revision Log I Number I Page Description I O-RO All New document Browns Ferry Unit 2 Cyde 17 Page v Core Operafing Limits Report, (105% OLTP) "VA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 U NPG 1101 Market Street, Chattanooga TN 37402 Nomenclature APLHGR Average Planar LHGR APRM Average Power Range Monitor AREVA NP Vendor (Framatome, Siemens)

BOC Beginning of Cycle BSP Backup Stability Protection BWR Boiling Water Reactor CAVEX Core Average Exposure 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 EOC End of Cycle 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 GWd Giga Watt Day HTSP High TSP ICA Interim Corrective Action ICF Increased Core Flow (beyond rated)

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

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

LPRM Low Power Range Monitor LRNB Generator Load Reject, No Bypass MAPFAC MAPLHGR multiplier (Power or Flow dependent)

MCPR Minimum CPR MSRV Moisture Separator Reheater Valve Browns Ferry Unit 2 Cycle 17 Page vi Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 NPG 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 TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority Browns Ferry Unit 2 Cycle 17 Page vii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 NPG References

1. ANP-2964, Revision 0, Browns Ferry Unit 2 Cycle 17 Reload Safety Analysis, AREVA NP, Inc., December, 2010.

2. ANP-2537(P) Revision 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-15 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., May 2006.

3. ANP-2755(P) Revision 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-16 ATRIUMTM-10 Fuel Assemblies, AREVA NP, Inc., November 2008.

4. ANP-2939(P), Rev. 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-17 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., July 2010.

5. ANP-2913(P) Revision 1, Browns Ferry Unit 2 Cycle 17 Plant Parameters Document, AREVA NP, Inc., November 2010.

6. BFE-3083, Revision 0, Verification of Browns Ferry Unit 2 Reload 16 Cycle 17 InCore Shuffle, Calculation File, Tennessee Valley Authority, February 2011.

Methodolo-y References

7. 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.

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

9. 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.

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

11. 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.

12. 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.

13. 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.

14. 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.

Browns Ferry Unit 2 Cyde 17 Page viii Core Operating Limts Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 NPG

15. 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.

16. 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.

17. 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.

18. ANF-1 358(P)(A) Revision 1, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.

19. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, Siemens Power Corporation, September 2009.

20. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001.

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

22. 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.

23. BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, Framatome ANP, Inc., May, 2008.

PRNM Setpoint References

24. 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.

25. 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.

26. GE Letter LB#: 262-97-133, Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information, September 12, 1997.

27. 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.

Browns Ferry Unit 2 Cycle 17 Page ix Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 NPG I 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)

> Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.2.3, 3.3.4.1, and 3.7.5)

>' Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

> Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

>' Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1) 1.3 Fuel Loading The core will contain all 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 6.

1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 7 through 23.

Browns Ferry Unit 2 cycle 17 Page 1 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011

[MIiNPG 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 A10-4227B-15GV80-FBB 15 112 2 FBB001-FBB206 ATRIUM-10 A10-4239B-15GV80-FBB 15 81 3 FBB207-FBB317 ATRIUM-10 A10-3552B-10GV80-FBB 15 16 4 FBB319-FBB374 ATRIUM-10 A10-4218B-13GV80-FCC 16 16 6 FCC291-FCC306 ATRIUM-10 A10-3757B-10GV80-FCC 16 24 7 FCC311-FCC334 ATRIUM-10 A10-4019B-14GV80-FBC 16 167 8 FBC401-FBC568 ATRIUM-10 A10-3841B-14GV80-FBC 16 76 9 FBC569-FBC644 ATRIUM-10 A10-3799B-14GV80-FBD 17 136 10 FBD001-FBD136 ATRIUM-10 A10-4004B-15GV80-FBD 17 136 11 FBD137-FBD272

• 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 2 Cycle 17 Page 2 Core Operating Limits ReporL (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 NPG 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 all fuel types, 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 reach 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-1 0 fuel is 0.85, per Reference 1.

Browns Ferry Unit 2 Cycle 17 Page 3 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 UT?iNPG 1101 Market Street, Chattanooga TN 37402 15 12 q

-J 0.6 3

0 0 20 40 60 80 Planar Average Exposure (GWdlMTU)

Planar Avg. APLHGR Exposure Limit 1"

(GWd/MTU) (kW/ft) 0.0 12.5 15.0 12.5 67.0 7.3 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Browns Ferry Unit 2 Cyde 17 Page 4 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 UT INPG 1101 Market Street, Chattanooga TN 37402 2.5 Equipment Out-Of-Service Corrections The limit shown in Figure 2.1 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 (includes 1 SRVOOS)

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.

Page 5 Browns Browns Ferry Unit 22Cy Ferry Unit 17 C~yde 17 5Re Page 5 Core Operating Limits Report, (105% OLTP) TVA-C0LR-BF2C17, Rexýision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011

[MiNPG 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, 3, and 4.

3.2 Off-Rated Power Dependent Limit: LHGRp The ATRIUM-10 fuel, 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 reach 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

(%Rated) (oF) (oF) 25 160.0 155.0 30 165.0 160.0 40 175.0 170.0 50 185.0 180.0 Browns Ferry Unit2 Cyde 17 Page 6 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 EIM!JNPG 1101 Market Street, Chattanooga TN 37402 3.3 Off-Rated Flow Dependent Limit: LHGRF The ATRIUM-10 fuel, LHGR limits are adjusted for off-rated flow conditions using the LHGRFACF multiplier provided in Reference 1. The multiplier is 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 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 assume 1SRVOOS.

Browns Ferry Unit 2 Cycle 17 Page 7 Core Operating Limits Report (105% OLTP) TVA-CoLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011

[M NPG 1101 Market Street, Chattanooga TN 37402 15 12 9

C,

=

~1 6 3 4 4 4 0

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

Pellet LHGR Exposure Limit (GWd/MTU) (kW/f 0.0 13.4 18.9 13.4 74.4 7.1 Figure 3.1 LHGRRATED for ATRIUM-10 Fuel Browns Ferry Unit 2 Cyde 17 Page 8 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011

[M NPG 1101 Market Street, Chattanooga TN 37402 1.10 1.00 0.90 0.80 0.

(.)

IL 0.70 C,

z

-J 0.60 0.50 0.40 0.30 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Core Power LHGRFACp Power LHGRFACp 100.0 I 0.92 30.0 0.60 30.0 0.60 Core Flow > 50% Rated Core Flow>50%Rated 30.0 0.48 30.0---T --7.42 25.0 0.45 25.0 0.38 Core Flow 5 50% Rated CoreFlowSS50% Rated 30.0 0.49 30.0--i7 i.49 25.0 1 0.46 25.0 0.43 Figure 3.2 Base Operation LHGRFACp for ATRIUM-10 Fuel (Independent of other EOOS conditions)

Bramns Ferry Unit 2Cyde 17 Page 9 Core Opeffhin Lini Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (FhWi)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE

[M!iNPG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 1.10 1.05 1.00 Ii-L-

0.95 0,

0.90 0.85 0.80 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow LHGRFACF

(%Rated) 30.0 0.9 52.0 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)

Browns Ferry Unit 2 Cyde 17 Page 10 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011

[MiNPG 1101 Market Street, Chattanooga TN 37402 1.10 1.00 0.90 TurbineO ypasValve n-Service, TBVIS 0.80 4 Turbine Bypass Valve Out-of-Service, TBVOOS

=. 0.70 IL 0.60 0.50 TBVIS. :5 50% Core Flow

_ TBVOOS,.: 50% Core Flow TBVIS, > 50% Core Flow 0.40 TBVOOS, > 50% Core Flow l I ______

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

Turbine Bypass In-Service Turbie Bypass Out-of-Service Core Core Power LHGRFA Power IHORFA 100.0 1.00 100.0 0.92 50.0 0.71 50.0 0.69 Corte 50.0Rw 0Rae0.68 50.0 0.68 30.0 0.57 30.0 0.55 Core Row > 50% Rated Core Raw > 50% Rated 30.0 0.42 30.0 0.40 25.0 I 0.39 25.0 0.36 Core Rlow < 50% Rated Core RaowS 50% Rated 30.0 0.43 30.0 7 0.43 25.0 0.40 25.0 0.39 Figure 3.4 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

Table 3.1 Temperature Range 1 (no Feedwaterheating during startup)

Page 11 Bi~wnsFenyUnt2Cyde17 Browns Ferry Unit 2 Cycle 17 Page 11 Core operating Limits Report, (105% OLTP) TVA-C0LR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 EIM NPG 1101 Market Street, Chattanooga TN 37402 1.10 1.00 0.90 0.80 a.

C.,

IL 0.70 C,

-J 0.60 0.50 0.40 0.30 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Turbine Bypass In-Service Turbine Bypass Out-of-Service Core Core Power UIGRFA Power HORýFAC 100.0 1.00 100.0 0.92 50.0 0.71 50.0 0.69 50.0 0.68 50.0 0.68 30.0 0.55 30.0 0.55 Core Raw > 50%Rated Core Row > 50% Rated 30.0 1 0.42 30.0 0.39 25.0 0.39 25.0 0.35 Core Row S 50% Rated Core Row S 50% Rated 30.0 0.43 30.0 0.43 25.0 0.39 25.0 0.39 Figure 3.5 Startup Operation LHGRFACp for ATRIUM-1 0 Fuel:

Table 3.1 Temperature Range 2 (no Feedwaterheating during startup)

Browns Fery Uni 2 Cyde 17 Page 12 Core Operaing Umts Report, (105% OLTP) TVA-COLR-BF2C17, Revisio 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February7, 2011 NPG 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, per 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 reach a significant operating power level. Additional power dependent limits are shown in Table 4.5 and Table 4.6, based on temperature conditions identified in Table 3.1.

Browns Ferry Unit 2 Cyde 17 Page 13 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE EIM iNPG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 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 29,179.5 MWd / MTU BOC to EOC EOC corresponds to 31,822.1 MWd / MTU BOC to End of Coast End of Coast 32,730.9 MWd / MTU NEOC refers to a Near EOC exposure point.

Reference 1 analysis results are based on information identified inReference 5.

t Assumption basis is consistent with method used to perform actual timing measurements, (i.e., including pickup/dropout effects).

Browns Ferry Unit 2 Cyde 17 Page 14 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011

[MIiNPG 1101 Market Street, Chattanooga TN 37402 The EOC 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 EOC, 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 ifthe core flow is less than or equal to 50% rated.

All equipment service conditions assume 1 SRVOOS.

Page 15 Browns Feny UnLi Browns Ferry 17 cycle 17 Unt22 Cycle Page 15 Core operating Limits Report, (1105% OLTP) TVA-C0LR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE EL NPG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 2.00 1.80 1.60 0~

U E

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% rated flow operation, ICF)

Browns Ferry Unit 2 Cycle 17 Page 16 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BBWRFE Date: February 7, 2011

[M!iNPG 110 1 Market Street, Chattanooga TN 37402 Table 4.2 MCPRp Limits for Optimum Scram Time Basis*

BOC BOC BOC Operating Pow er to to to End of Condition (% of rated) NEOC EOC Coast 100 1.38 1.41 1.44 75 1.51 1.51 1.56 65 1.60 1.61 1.68 50 1.78 1.78 50 1.85 1.85 1.90 Base Case 40 2.00 2.00 2.13 30 2.29 2.29 2.44 30 at > 50%F 2.79 2.79 2.90 25 at > 50%F 3.08 3.08 3.22 30 at : 50%F 2.72 2.72 2.82 25 at* 50%F 2.97 2.97 3.10

• 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/FHOOS is supported for the BOC to End of Coast limits.

Browns Ferry Unit 2 Cycle 17 Page 17 Core Operating Limits Report, (105% OLTP) rVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 U ~NPG 1101 Market Street, Chattanooga TN 37402 Table 4.3 MCPRp Limits for Nominal Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition (% of rated) NEOC EOC Coast 100 1.41 1.42 1.44 75 1.52 1.53 1.56 65 1.62 1.62 1.68 50 1.82 1.82 ---

50 1.86 1.86 1.90 Base Case 40 2.03 2.03 2.13 30 2.32 2.32 2.44 30 at > 50%F 2.79 2.79 2.90 25 at > 50%F 3.08 3.08 3.22 30 at 5 50%F 2.72 2.72 2.82 25 at 5 50%F 2.97 2.97 3.10 100 1.44 1.46 1.47 75 1.57 1.57 1.60 65 1.66 1.67 1.70 50 1.83 1.83 ---

50 1.86 1.86 1.90 TBVOOS 40 2.04 2.04 2.13 30 2.32 2.32 2.44 30 at > 50%F 3.26 3.26 3.40 25 at > 50%F 3.70 3.70 3.85 30 at < 50%F 2.85 2.85 3.00 25 at < 50%F 3.29 3.29 3.47 100 1.43 1.44 ---

75 1.55 1.56 ---

65 1.68 1.68 ---

50 ... ... ...

50 1.90 1.90 ---

FHOOS 40 2.13 2.13 ---

30 2.44 2.44 30 at > 50%F 2.90 2.90 ---

25 at > 50%F 3.22 3.22 ---

30 at < 50%F 2.82 2.82 ---

25 at 5 50%F 3.10 3.10 ---

100 1.41 1.42 1.44 75 1.52 1.53 1.56 65 1.76 1.77 1.77 50 ... ... ...

50 1.86 1.86 1.90 PLUOOS 40 2.03 2.03 2.13 30 2.32 2.32 2.44 30 at > 50%F 2.79 2.79 2.90 25 At > 50%F 3.08 3.08 3.22 30 at < 50%F 2.72 2.72 2.82 1 25 at5<50%F 2.97 2.97 3.10 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.

A50% 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 2 Cycle 17 Page 18 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 U ?iNPG 1101 Market Street, Chattanooga TN 37402 Table 4.3 MCPRp Limits for Nominal Scram Time Basis (continued)*

BOC BOC BOC Operating Pbw er to to to End of Condition (% of rated) NEOC EOC Coast 100 1.46 1.47 ---

75 1.58 1.59 ---

65 1.70 1.70 ---

50 ... ... ...

50 1.90 1.90 ---

TBVOCG 40 2.13 2.13 ---

FHOOS 30 2.44 2.44 ---

30 at > 50%F 3.40 3.40 ---

25 at > 50%F 3.85 3.85 ---

30 at < 50%F 3.00 3.00 ---

25 at < 50%F 3.47 3.47 ---

100 1.44 1.46 1.47 75 1.57 1.57 1.60 65 1.76 1.77 1.77 50 ... ... ...

50 1.86 1.86 1.90 TBVOOS 40 2.04 2.04 2.13 30 2.32 2.32 2.44 30 at > 50%F 3.26 3.26 3.40 25 at > 50%F 3.70 3.70 3.85 30 at < 50%F 2.85 2.85 3.00 25 at < 50%F 3.29 3.29 3.47 100 1.43 1.44 ---

75 1.55 1.56 ---

65 1.76 1.77 ---

50 ... ... ...

50 1.90 1.90 ---

FHOOS 40 2.13 2.13 ---

PUOOS 30 2.44 2.44 ---

30 at > 50%F 2.90 2.90 ---

25 at > 50%F 3.22 3.22 ---

30 at < 50%F 2.82 2.82 ---

25 at 5 50%F 3.10 3.10 ---

100 1.46 1.47 ---

75 1.58 1.59 ---

65 1.76 1.77 --

50 ... ... ...

TBVOOS 50 1.90 1.90 ---

FHOOS 40 2.13 2.13 ---

PLUOOS 30 2.44 2.44 ---

30 at > 50%F 3.40 3.40 ---

25 at > 50%F 3.85 3.85 ---

30 at <50%F 3.00 3.00 ---

1 25 at <50%F 3.47 3.47 ---

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 2 Cycle 17 Page 19 Core Operating Limbt Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 ET NPG 1101 Market Street, Chattanooga TN 37402 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 EOC Coast 100 1.43 1.43 1.45 75 1.54 1.54 1.58 65 1.65 1.65 1.72 50 1.85 1.85 ---

50 1.87 1.87 1.93 Base Case 40 2.06 2.06 2.16 30 2.36 2.36 2.47 30 at > 50%F 2.79 2.79 2.90 25 at > 50%F 3.08 3.08 3.22 30 at < 50%F 2.72 2.72 2.82 25 at5 50%F 2.97 2.97 3.10 100 1.46 1.47 1.48 75 1.58 1.58 1.61 65 1.69 1.69 1.73 50 1.86 1.86 ---

50 1.87 1.87 1.94 TBVOOS 40 2.07 2.07 2.16 30 2.36 2.36 2.47 30 at > 50%F 3.26 3.26 3.40 25 at > 50%F 3.70 3.70 3.85 30 at 5 50%F 2.85 2.85 3.00 25 at < 50%F 3.29 3.29 3.47 100 1.45 1.45 ---

75 1.58 1.58 ---

65 1.72 1.72 ---

50 ... ... ...

50 1.93 1.93 ---

FHOOS 40 2.16 2.16 ---

30 2.47 2.47 ---

30 at > 50%F 2.90 2.90 ---

25 at > 50%F 3.22 3.22 ---

30 at < 50%F 2.82 2.82 ---

25 at5 50%F 3.10 3.10 ---

100 1.43 1.43 1.45 75 1.54 1.54 1.58 65 1.77 1.78 1.79 50 ... ... ...

50 1.87 1.87 1.93 PLUOOS 40 2.06 2.06 2.16 30 2.36 2.36 2.47 30 at > 50%F 2.79 2.79 2.90 25 at > 50%F 3.08 3.08 3.22 30 at < 50%F 2.72 2.72 2.82 25 at - 50%F 2.97 2.97 3.10 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 2 Cycle 17 Page 20 Core Operating Limits Report, (105% OLTP) "VA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 IMNPG 1101 Market Street, Chattanooga TN 37402 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis (continued)*

BOC BOC BOC Pbwer to to to End of Operating Condition (% of rated) NEOC EOC Coast 100 1.48 1.48 ---

75 1.61 1.61 ---

65 1.73 1.73 ---

50 ... ... ...

50 1.94 1.94 ---

TBVOOS 40 2.16 2.16 ---

FHOOS 30 2.47 2.47 ---

30 at > 50%F 3.40 3.40 ---

25 at > 50%F 3.85 3.85 ---

30 at < 50%F 3.00 3.00 ---

25 at s 50%F 3.47 3.47 ---

100 1.46 1.47 1.48 75 1.58 1.58 1.61 65 1.77 1.78 1.79 50 --- ...---

50 1.87 1.87 1.94 PBVOOS 40 2.07 2.07 2.16 PL-UOOS 30 2.36 2.36 2.47 30 at > 50%F 3.26 3.26 3.40 25 at > 50%F 3.70 3.70 3.85 30 at < 50%F 2.85 2.85 3.00 25 at 5 50%F 3.29 3.29 3.47 100 1.45 1.45 --

75 1.58 1.58 ---

65 1.77 1.78 ---

50 ... ... ...

50 1.93 1.93 ---

FHOOS 40 2.16 2.16 ---

PiuooS 30 2.47 2.47 ---

30 at > 50%F 2.90 2.90 ---

25 at > 50%F 3.22 3.22 ---

30 at < 50%F 2.82 2.82 ---

25 at5 50%F 3.10 3.10 100 1.48 1.48 ---

75 1.61 1.61 ---

65 1.77 1.78 ---

50 ... ... ...

TBVOOS 50 1.94 1.94 ---

FHOOS 40 2.16 2.16 ---

PLUOOS 30 2.47 2.47 ---

30 at > 50%F 3.40 3.40 ---

25 at > 50%F 3.85 3.85 ---

30 at <50%F 3.00 3.00 ---

25 at <50%F 3.47 3.47 ---

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 2 Cycle 17 Page 21 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 LEIM 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 Operating Rower to to to End of Condition (% of rated) NEOC EOC Coast 100 1.45 1.45 1.45 75 1.58 1.58 1.58 65 1.72 1.72 1.72 50 1.93 1.93 1.93 50 2.11 2.11 2.11 TBVIS 40 2.38 2.38 2.38 30 2.76 2.76 2.76 30 at > 50%F 3.18 3.18 3.18 25 at > 50%F 3.57 3.57 3.57 30 at < 50%F 3.07 3.07 3.07 25 at 5 50%F 3.44 3.44 3.44 100 1.48 1.48 1.48 75 1.61 1.61 1.61 65 1.73 1.73 1.73 50 1.94 1.94 1.94 50 2.11 2.11 2.11 TBVOOS 40 2.38 2.38 2.38 30 2.76 2.76 2.76 30 at > 50%F 3.64 3.64 3.64 25 at > 50%F 4.12 4.12 4.12 30 at < 50%F 3.23 3.23 3.23 25 at < 50%F 3.76 3.76 3.76 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 non-PLUOOS EOOS scenarios. PLU is inoperable for powers less than 50% rated power, therefore at these powers itcan be considered a base case.

Browns Ferry Unit 2 Cycle 17 Page 22 Core Operiting Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE

[M NPG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 Table 4.6 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Technical Specification Scram Time Basis*

BOC BOC BOC tow er to to to End of Operating Condition (% of rated) NEOC EOC Coast 100 1.45 1.45 1.45 75 1.58 1.58 1.58 65 1.72 1.72 1.72 50 1.93 1.93 1.93 50 2.12 2.12 2.12 TBVIS 40 2.40 2.40 2.40 30 2.78 2.78 2.78 30 at > 50%F 3.19 3.19 3.19 25 at > 50%F 3.60 3.60 3.60 30 at < 50%F 3.11 3.11 3.11 25 at < 50%F 3.46 3.46 3.46 100 1.48 1.48 1.48 75 1.61 1.61 1.61 65 1.73 1.73 1.73 50 1.94 1.94 1.94 50 2.12 2.12 2.12 TBVOOS 40 2.40 2.40 2.40 30 2.78 2.78 2.78 30 at > 50%F 3.65 3.65 3.65 25 at > 50%F 4.13 4.13 4.13 30 at < 50%F 3.24 3.24 3.24 25 at < 50%F 3.78 3.78 3.78 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 non-PLUOOS EOOS scenarios. PLU is inoperable for powers less than 50% rated power, therefore at these powers it can be considered a base case.

Browns Feny Unit 2 Cycle 17 Page 23 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 NPG 5 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 24 & 25, 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 2 Cyde 17 Page 24 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2Cl7, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 UT NPG 1101 Market Street, Chattanooga TN 37402 6 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 24 & 25, are shown in Table 6.1. 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, superceding values reported in References 24, 25, and 27.

Table 6.1 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 6.2. Cycle specific setpoint analysis results are shown in Table 6.3, per Reference 1.

Table 6.2 RBM Setpoint Applicability Thermal Power Applicable Notes from

(% Rated) MCPRt Table 3.3.2.1-1 Comment

> 27% and < 90% < 1.72 (a), (b), (f), (h) two loop operation

< 1.75 (a), (b), (f), (h) single loop operation

>90% < 1.42 (g) two loop operation*

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

t MCPR values shown correspond with, (support), SLMPCR values identified inReference 1.

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

Browns Ferry Unit 2 Cycle 17 Page 25 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 EIMNPG 1101 Market Street, Chattanooga TN 37402 Table 6.3 Control Rod Withdrawal Error Results RBM CRWE HTSP Analytical Limit OLMCPR Unfiltered 107 1.31 111 1.35 114 1.36 117 1.39 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 Ferry Unit 2 cycle 17 Page 26 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 UTJiNPG 1101 Market Street, Chattanooga TN 37402 7 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 Browns Ferry Unit 2 Cyde 17 Page 27 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: February 7, 2011 IM ~NPG 1101 Market Street, Chattanooga TN 37402 Appendix A: Thermal-Hydraulic Stability Browins Ferry Unit 2 Cyde 17 Page 28 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE Date: 2011 1101 Market Street, Chattanooga TN 37402 February7, NPG RPS Instrumentation (Technical Specification 3.3.1.1)

Technical Specification Section 3.3.1.1, LCO 3.3.1.1 states:

The RPS instrumentationfor each Function in Table 3.3.1.1-1 shall be OPERABLE.

Table 3.3.1.1-1, Function 2f, identifies the OPRM upscale function. This function must be operable in conjunction with the following surveillance requirements:

SR 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.17

Background

Browns Ferry uses the Option III stability Detect and Suppress solution as part of the PRNM system. The Option III system is based upon combining groups of local LPRM's into cells known as OPRM's. The OPRM's generate a combined LPRM signal that is examined for the characteristics of a reactor instability event, and if detected, a reactor trip is generated.

The PBDA is the licensing basis portion of the Option III system, requiring a cycle-specific calculation to determine the amplitude setpoint to generate a reactor trip in time to protect the fuel from exceeding the SLMCPR.

The OPRM Upscale Trip function is required to be operable when the plant is in a region of power-flow operation where actual thermal-hydraulic oscillations might occur (T.S. enabled region --

greater than 25% rated thermal power and less than 60% recirculation drive flow).

Setpoints 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 23. The calculated OLMCPR's are shown in Browns Ferry Unit 2 Cycle 17 Page 29 Core Operating Limits Report (105% OLTP) TVA-COLR-BF2C17, Revision 0 (Final)

EDMS: L32 110204 801 Nuclear Fuel Engineering - BWRFE 1U NPG 1101 Market Street, Chattanooga TN 37402 Date: February 7, 2011 Table A.1. Review of results, relative to the base case operation shown in COLR Table 4.2 indicates an OPRM setpoint of 1.14 can be supported. Extrapolation beyond a setpoint of 1.15 is not allowed.

Table A.1 OPRM Setpoints OPRM OLMCPR OLMCPR Setpoint (SS) (2PT) 1.05 1.17 1.19 1.06 1.19 1.21 1.07 1.21 1.22 1.08 1.23 1.24 1.09 1.25 1.26 1.10 1.27 1.28 1.11 1.29 1.30 1.12 1.31 1.33 1.13 1.33 1.35 1.14 1.35 1.37 1.15 1.37 1.39 Backup Stability Should the Option III system be declared inoperable, alternate methods/procedures (i.e.,

stability ICA's) are incorporated restricting plant operation in the high power, low core flow region of the power/flow map. ICA's contain specific operator actions, providing clear instructions (depending upon the plant type) for operator response to a reactor inadvertently (or under controlled conditions) entering any of the defined regions. ICA's provide appropriate guidance to reduce the likelihood of hydraulic instability, and enhance early detection in the very unlikely event a stability threshold is exceeded in spite of the ICA guidelines.

In July 2002, GE recommended the original ICAs, established generically in 1994, be re-evaluated to assure adequate conservatism, given the trend to higher energy cores and more aggressive fuel management strategies. The recommended replacement regions and the associated calculational procedure are referred to as BSP, and need to be confirmed on a plant/cycle specific basis. The vendor has performed an ICA/BSP confirmation calculation using the NRC approved method in Reference 22.

Based upon the above discussion, appropriate stability analyses and evaluations have been performed to satisfy licensing requirements.

Browns Ferry Unit 2 CyRee 17 Page 30 Core operating Limits Report, (1105% OLTP) TVA-C0LR-BF2C17, Revision 0 (Final)