ML13080A075

Core Operating Limits Report for Cycle 18 Operation

ML13080A075
Person / Time
Site:	Browns Ferry
Issue date:	03/18/2013
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13080A075 (39)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 March 18, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

Browns Ferry Nuclear Plant, Unit 2 Core Operating Limits Report for Cycle 18 Operation In accordance with the requirements of Technical Specification (TS) 5.6.5.d, Tennessee Valley Authority is submitting Browns Ferry Nuclear Plant (BFN), Unit 2, Cycle 18, Core Operating Limits Report (COLR), Revision 0. Revision 0 of BFN, Unit 2, Cycle 18, COLR includes all modes of operation (Modes 1 through 5). The BFN, Unit 2, Cycle 18, COLR reference to the AREVA Loss of Coolant Accident methodology has been revised to reflect the changes made to TS 5.6.5.b as part of TS License Amendment Number 309.

Additionally, BFN, Unit 2, Cycle 18, COLR includes the oscillation power range monitor setpoint limits which were approved by Amendment Number 309.

There are no new commitments contained in this letter. If you have any questions please contact Ed Schrull at (423) 751-3850.

Respe

Ily, J

hea ice resident, Nuclear Licensing

Enclosure:

Core Operating Limits Report, (105% OLTP), for Cycle 18 Operation TVA-COLR-BF2C18, Revision 0 cc: (w/ Enclosure)

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

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 Core Operating Limits Report, (105% OLTP), for Cycle 18 Operation TVA-COLR-BF2CI8, Revision 0 (See Attached)

EDMS L32 130301 800 QA Document Pages Affected: Aill BFE-3447. Revision 0.

Reactor Engineering and Fuels - BWRFE 1101 Market Street. Chattanooga, TN 37402 Browns Ferry Unit 2 Cycle 18 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF2CI 8 Revision 0 (Final)

(Revision Log. Page v)

March 2013 T. W, Eichenberg, Sr. S-ecialist Verified:

B. C'"Mitchell, Engineer Approved:

A G. C. Storey. Manag~r, 8WR Fuel EngineE Date: /AIfs4. /

/3r Date:

3//

L Date:

311 13

• ring Date:

-'0f-(3 ng Date:

.. T -45_ 13 Date:

31 g 1.:_

Reviewed:

W. R. Hayes, Manag6u, Reactor Engineeri Approved >

Approved:

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 N PG 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 37 (including review cover sheet)

List of Tables.................................................................................................................................................

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

iv Revision Log...................................................................................................................................

v Nomenclature................................................................................................................................................

vi References..................................................................................................................................................

viii 1

Introduction........................................................................................................................

10 1.1 Purpose.......................................................................................................................

10 1.2 Scope..........................................................................................................................

10 1.3 Fuel Loading...........................................................................................................

10 1.4 Acceptability...........................................................................................................

11 2

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

12 2.1 Rated Power and Flow Lim it: APLHGRRATED..........................................................

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 Out-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: LHGRp............................................................

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 M CPR Lim it: M CPRF...................................................................

22 4.2 Power Dependent M CPR Lim it: M CPRp..............................................................

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 (EOOS) O ptions...................................................

24 4.2.5 Single-Loop-O peration (SLO ) Lim its..............................................................

24 4.2.6 Below Pbypass Lim its...................................................................................

24 5

Oscillation Power Range M onitor (O PRM ) Setpoint.....................................................

33 6

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

34 7

Rod Block M onitor (RBM ) Trip Setpoints and O perability..............................................

35 8

Shutdow n M argin Lim it..................................................................................................

37 Browns Ferry Unit 2 Cyde 18 Page ii Core Operating LUnits Report, (105% OLTP)

TVA-COLR-BF2C18, Revision 0 (Fwd)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 N P G 1101 Market Street, Chattanooga TN 37402 List of Tables N uclear Fuel Types.....................................................................................................................

11 Startup Feedwater Temperature Basis.................................................................................

15 Nominal Scram Time 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 cram T im e B asis.......................................................................................................................

31 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2: Technical Specification S cram T im e B asis.......................................................................................................................

32 OPRM Setpoint Range..........................................................................................................

33 OPRM Successive Confirmation Count Setpoint............................................................

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

35 RBM Setpoint Applicability....................................................................................................

35 Control Rod Withdrawal Error Results...................................................................................

36 Brciwis Ferry Unit2 Cyde 18 Core operat nLimb tRqxx4 (105% OLTP)

Page iii TVA-COLR-8F2C18, Revision 0 (Final)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 NPG 1101 Market Street, Chattanooga TN 37402 List of Figures APLHGRRATED for ATRIUM-10 Fuel.......................................................................................

13 LHG RRATED for ATRIUM -1 0 Fuel............................................................................................

17 Base Operation LHGRFACp for ATRIUM-1 0 Fuel................................................................

18 LHG RFACF for ATRIUM -10 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 M CPRF for ATRIUM -1 0 Fuel.................................................................................................

25 Browns Ferry Unit 2 Cyce 18 Core Operating Likt Report (105% OLTP)

Page iv TVA-COLR-BF2C18, Revision 0 (Final)

EDMS: L32 130301 800

[M ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 Revision Log INumber I Page Description 0-RO All New document.

Browns Ferry Unit 2 Cyde 18 Core Operatig Lrnts Report (105% OLTP)

Page v "VA-COLR-BF2C18, Revision 0 (Frnal)

EDMS: L32 130301 800

[M ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 1

-1 Nomenclature APLHGR APRM AREVA NP BOC BSP BWR CAVEX CD CMSS COLR CPR CRWE CSDM DIVOM EOC EOCLB EOOS FFTR FFWTR FHOOS ft GNF GWd HTSP ICA ICF IS Average Planar LHGR Average Power Range Monitor Vendor (Framatome, Siemens)

Beginning of Cycle Backup Stability Protection Boiling Water Reactor Core Average Exposure Coast Down Core Monitoring System Software Core Operating Limits Report Critical Power Ratio Control Rod Withdrawal Error Cold SDM Delta CPR over Initial CPR vs. Oscillation Magnitude End of Cycle End-of-Cycle Licensing Basis Equipment OOS Final Feedwater Temperature Reduction Final Feedwater Temperature Reduction Feedwater Heaters OOS Foot: english unit of measure for length Vendor (General Electric, Global Nuclear Fuels)

Giga Watt Day High TSP Interim Corrective Action Increased Core Flow (beyond rated)

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

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

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

Browns Ferry Unit 2 Cycle 18 Core Openeting Linib Report (105% OLTP)

Page vi TVA-COLR-BF2C18, Revision 0 (Final)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 1101 Market Street, Chattanooga TN 37402 MCPR Minimum CPR 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 RTP Rated Thermal Power, 3458 MW.

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 Broom sFerryUnit 2 Cyde18 Core Olwetuing Linis Report, (105% OLTP)

Page vii TVACO.R-8F2C18, RPevwion 0 (Final)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 N PG 1101 Market Street, Chattanooga TN 37402 References

1.

ANP-3183, Revision 0, Browns Ferry Unit 2 Cycle 18 Reload Safety Report, AREVA NP, Inc., January, 2013.

2.

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.

3.

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.

4.

ANP-3031 P, Revision 0, Mechanical Design Report for Browns Ferry Units 1, 2, and 3 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., October 2011.

5.

ANP-3107(P) Revision 1, Browns Ferry Unit 2 Cycle 18 Plant Parameters Document, AREVA NP, Inc., June 2012.

6.

BFE-3454, Revision 0, Verification for Unit 2 Reload 17 Incore Shuffle, Tennessee Valley Authority, February 20, 2013.

Methodology 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.

Browins Ferryunit2 CyAe 18 Core Opeft tki nbt Reort~ (105% OLTP)

Page viii TVA-COLR-8F2C18, Revision 0 (Final)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 N PG 1101 Market Street, Chattanooga TN 37402

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 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 2005.

19.

EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP Inc.,

September 2009.

20.

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.

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-1 0255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP Inc., 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.

28.

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

Bmrons Ferry Unit 2 Cyde 18 CorOpeiatigl imilReport, (105% OLTP)

Page ix TVA-COLR-BF2C18, Revision 0 (Final)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 NPG 1101 Market Street, Chattanooga TN 37402 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 addresses the following areas:

> Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specifications 3.2.1 and 3.7.5)

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

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

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 6.

Browns Ferry Unt 2 Cyde 18 Core Operating UTnt Report (105% OLTP)

Page 10 TVA-COLR-BF2C18, Revision 0 (Final)

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[M !iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Table 1.1 Nuclear Fuel Types*

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

(Range)

ATRIUM-10 A10-4218B-13GV80-FCC 16 16 6

FCC291-FCC306 ATRIUM-10 Al0-3757B-10GV80-FCC 16 16 7

FCC31 1 -FCC334 ATRIUM-10 A10-4019B-14GV80-FBC 16 105 8

FBC401-FBC568 ATRIUM-10 A10-3841B-14GV80-FBC 16 40 9

FBC569-FBC644 ATRIUM-10 A10-3799B-14GV80-FBD 17 136 10 FBD001-FBD136 ATRIUM-10 A10-4004B-15GV80-FBD 17 135 11 FBD137-FBD272 ATRIUM-10 A10-4165B-15GV75-FBE 18 176 12 FBE001-FBE176 ATRIUM-10 A10-4107B-13GV75-FBE 18 68 13 FBE177-FBE244 ATRIUM-10 A10-4176B-10GV75-FBE 18 72 14 FBE245-FBE316 1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 7 through 23.

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

Browns Ferry Unit 2 Cycle 18 Corn Operetng Lirils Report, (105% OLTP)

Page 11 VA-CO C18, Revision 0 (Fir)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 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-1 0 fuel is identified in Reference 1 and shown in Figure 2.1.

2.2 Off-Rated Power Dependent Limit: APLHGRp Reference 1, for ATRIUM-1 0 fuel, does not specify a power dependent APLHGR. Therefore, MAPFACp is set to a value of 1.0.

2.2.1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has 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.

Bowns Feny Unit 2 Cyde 18 Core Opereting Limts Report, (105% OLTP)

Page 12 "VA-COLR-BF2C18, Revision 0 (Firel)

EDMS: L32 130301 800 IM ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 1

-1 15 12 C0

-J 9

6 3

0 0

20 40 60 80 PlanarAverage Exposure (GWdlMTU)

Planar Avg.

APLHGR Exposure Limit 0.0 12.5 15.0 12.5 67.0 7.3 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Browns Fery Unit 2 Cyde 18 Core OpeaWsng Lirnts Report (105% OLTP)

Page 13 TVA-COR-BF2C18, Revision 0 (Firal)

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[M liNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 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 RPTOOS TBVOOS PLUOOS FHOOS (or FFWTR)

All equipment In-Service*

EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Power Load Unbalance Out-Of-Service Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to the rated APLHGR limits as described previously.

• All equipment service conditions assume 1 SRVOOS.

Browns Ferry Unit 2 Cycle 18 Core Operating Limbd Report, (105% OLTP)

Page 14 TVA-COLR-BF2C18, Revision 0 (Final)

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[M iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 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 LHGRF off-rated power LHGR limit off-rated flow LHGR limit

[LHGRRATED

• LHGRFACp]

[LHGRRATED

• LHGRFACF]

3.1 Rated Power and Flow Limit: LHGRRATED The rated conditions LHGR for all fuel types, is identified in Reference 1 and shown in Figure 3.1. The LHGR limit is consistent with References 2, 3, and 4.

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 Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional limits are shown in Figure 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 I Range 2 25 160.0 155.0 30 165.0 160.0 40 175.0 170.0 50 185.0 180.0 Brmons Fery Unit 2 Cycle 18 Core Opealing Umits Report, (105% OLTP)

Page 15 TVA-COLR-BF2C18, Revision 0 (Final)

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[M liNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 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 RPTOOS TBVOOS PLUOOS FHOOS (or FFWTR)

SLO All equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Power Load Unbalance Out-Of-Service Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction Single 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/FFVVTR, 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 assume 1 SRVOOS.

Browns Feny Unit 2 Cyde 18 Core opering LimbitsRepoit, (105% OLTP)

Page 16 TVA-COLR-BF2C18, Revision 0 (Final)

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[M 1iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 15 12 9

6 3

0 0

20 40 60 Pellet Exposure (GWdlMTU)

Pellet LHGR Exposure Limit 0.0 13.4 18.9 13.4 74.4 7.1 Figure 3.1 LHGRRATED for ATRIUM-10 Fuel 80 Browns Feny Unit 2 Cyde 18 Core Operting Lmits Report, (105% OLTP)

Page 17 "VA-COLR-BF2C18, Revision 0 (F-ial)

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[M ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 a.

C.,

U-C, z

-J 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine IypassValveIn-Service,n T

Turbine Bypas Valve Out-of-Service, TBVOOS 0

TBVIS, <50%CoreFtlow TBVOOS1 < 50% Core Flow TBVIS > 50% Core Flow TBVOOS, > 50% Core Flow i

20 30 40 50 60 70 80 Core Power (% Rated) 90 100 110 Turbine Bypass In-Service Core Power LHGRFACp 100.0 I

1.00 30.0 0.61 Core Flow > 50% Rated 30.0 T 0.53 25.0 0.49 Core Flow S 50% Rated 30.0

).57 25.0 0.55 Turbine Bypass Out-of-Seivice Core Power LHGRFACp 100.0 0.92 30.0 0.61 Core Flow > 50% Rated 30.0 t0.45 25.0 0.41 CoeFlow 5 50%Rated 30.0 1

0.54 25.0 0.48 Figure 3.2 Base Operation LHGRFACp for ATRIUM-10 Fuel (Independent of other EOOS conditions)

Brwns Feny Unit 2 Cyde 18 Corn Opeitig Linif Report, (105% OLTP)

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[M !iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 1.10 1.05 1.00

-i-I Y1YY U.

C..

C,

-j 0.95 0.90 0.85 0.80 4

1 4

4 1

4.

I

4.

I t

4.

I 4.

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

Core Flow LHGRFACF 30.0 0.98 35.5 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)

I I

Brons Ferry Unit 2 Cyde 18 Core Operaing Lkiif Rport, (105% OLTP)

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[M iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 x

1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Core Power LHGRFACp 100.0 1.00 30.0 0.60 Core Fow 50% Rated 30.0 1

0.49 25.0 J

0.45 Core Raw S 50% Rated 30.0 1

0.54 25.0 0.48 Turbine Bypass Out-of-Service Core Power LHGRFACp 100.0 0.92 30.0 7

0.60 Core Flow > 50% Rated 30.0 0.43 25.0 0.38 Core How S 50% Rated 30.0 i

0.51 25.0 0.45 Figure 3.4 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

Table 3.1 Temperature Range 1 (no Feedwater heating during startup)

Browns Fery Unit 2 Cyde 18 Core Opeang Uiits Report, (105% OLTP)

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[M ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 U-

.J 1.10 1.00 0.90 00 Turbine Bypas Valve In-Service TBVIS 0.80

_--"00" Turbin BypassValve Out-of-Service. TBVOS 0.70 0.60 TBVIS, < 50% Core Flow 0.50 TBVOS,,> 50% Core Flow TBVOOS, >50% Core Flow 0.40 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Core Power LHGRFACp 100.0 1.00 30.0 0.60 Core Row :, 50% Rated 30.0 0.49 25.0 0.44 Core Row S 50%Rted 30.0 J

0.53 25.0 0.48 Turbine Bypass Out-of-Service Core Power LHGRFACp 100.0 0.92 30.0 0.60 Core How > 50% Rated 30.0 0.43 25.0 0.38 Core Row S 50% Rated 30.0 0.51 25.0 0.A3 Figure 3.5 Startup Operation LHGRFACp for ATRIUM-1 0 Fuel:

Table 3.1 Temperature Range 2 (no Feedwater heating during startup)

Brwns Feny Unit 2 Cyde 18 Core Openg Lint Report (105% OLTP)

Page 21 TVA-COLR-BF2C18, Revison 0 (Frial)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 0 NPG 1101 Market Street, Chattanooga TN 37402 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 Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional power dependent limits are shown in Table 4.5 and Table 4.6, based on temperature conditions identified in Table 3.1.

F--

I Bewris FerryUnit 2 Cycl 18 Core Oimaftin LhinI Repast, (105% OLTP)

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EDMS: L32 130301 800 BIMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 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 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 BOC to EOCLB BOC to End of Coast NEOC corresponds to EOCLB corresponds to End of Coast 29,748.8 MWd I MTU 31,635.1 MWd I MTU 33,056.4 MWd I MTU NEOC refers to a Near EOC exposure point.

" Reference 1 analysis results are based on information identified in Reference 5.

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

Browns Ferry Unit 2 Cycle 18 Corn Operating Limits Report, (105% OLTP)

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[M !iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 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 RPTOOS TBVOOS RPTOOS+TBVOOS PLUOOS PLUOOS+RPTOOS PLUOOS+TBVOOS PLUOOS+TBVOOS+RPTOOS FHOOS (or FFWTR)

All equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Combined RPTOOS and TBVOOS Power Load Unbalance Out-Of-Service Combined PLUOOS and RPTOOS Combined PLUOOS and TBVOOS Combined PLUOOS, RPTOOS, and TBVOOS 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 Single-Loop-Operation (SLO) Limits MCPRp limits are increased by 0.02 to support SLO, per Reference 1.

4.2.6 Below Pbvoass 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.

SAll equipment service conditions assume 1 SRVOOS.

Bro~wis Feny Unit 2 Cycle 18 Page 24 Browns Ferry Unit 2 Cye1e 18 Core Operating Lklfts Report, (105% OLTP)

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[M ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 2.00 1.80 1.60 a-IL 1.40 1.20 1.00 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow MCPRF 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)

I Browns Feny Unit 2 Cyde 18 Core Operating Units Report (105% OLTP)

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[M liNPG Reactor Engineering and Fuels -

B iWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1; 2013 Table 4.2 MCPRp Limits for Optimum Scram Time Basis*

SOC SOC SOC Power to to to End of Codboan

(% of rated)

NEOC EOCLB Coast 100 1.40 1.41 1.43 75 1.50 1.51 1.53 65 1.57 1.58 1.61 50 1.73 1.73 1D80 50 1.80 1181 1.82 ase Coae 40 1.92 1.92 2.00 30 2.18 2.18 2.28 30 at > 5D0 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at 50%F 2.58 2.58 2.67 25 at t 50%F 2.81 2.81 2.93 100 1.42 1.43 75 1.52 1.53 65 1.61 1.61 50 1.80 1.80 50 1.81 1.82 FuMos 40 2.00 2.00 30 2.28 228 30 at > 50%F 2.75 2.75 25 at > 50%F 3.04 3.04 30 att 50%F 2.67 2.67 25 at, t50%F 2-93 2.93

• 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 Cyde 18 Core Operstig Limits Report (105% OLTP)

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[M ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Table 4.3 MCPRp Limits for Nominal Scram Time Basis*

BOC 50C BOC Power to to to End of Condibn

(% of rated)

NEOC EOCLB Coast 100 1.41 1.43 1.44 75 1.54 1.54 1.55 65 1.60 1.60 1.64 50 1.75 1.75 1.82 50 1.81 1.82 1.83 Base Case 40 1.94 1.94 2.02 30 2.20 2.20 2.31 30 at 50%F 2.64 2.64 2.75 25 at 50%f 2.91 2.91 3.04 30atM50%F 2.58 2.58 2.67 25 ats 50%F 2.81 2.81 2.93 100 1.45 1.46 1.47 75 1.55 1.56 1.58 65 1.64 1.64 1.67 50 1.76 1.76 50 1.81 1.82 1.83 TBVOOS 40 1.95 1.95 2.03 30 2.20 2.20 2.31 30 at > 50%

3.06 3.06 3.20 25 at o 50%F 3.47 3.47 3.61 30 at s 50%F 2.70 2.70 2.83 25 at% 50%F 3.10 3.10 3.25 100 1.44 1.44 75 1.54 1.55 65 1.64 1.64 50 1.82 50 1.82 1.83 FHOOS 40 2.02 2.02 30 2.31 2.31 30 at > 50%F 2.75 2.75 25 at > S0%F 3.04 3.04 30 at I 50%F 2.67 2.67 25 at s 50%F 2.93 2.93 100 1.41 1.43 1.44 75 1.54 1.54 1.55 65 1.73 1.75 1.75 50 50 1.82 1.82 1.83 PLUCOS 40 1.94 1.94 2.02 30 2.20 2.20 2.31 30 at), 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at, 50/%F 2.58 2.58 2.67 25 at i 50%1 2.81 2.81 2.93

• 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 COAS' 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 Fery Unit 2 Cycle 18 Core Operating Umits Report, (105% OLTP)

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[M iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Table 4.3 MCPRp Limits for Nominal Scram Time Basis (continued)*

BOC BOC 8OC Power to to to End of operatkig Conditin

(% of rated)

NEOC EOCLB Coast 100 1.47 1.47 75 1.58 1.58 65 1.67 1.67 so 50 1.83 1.83 FHOOS 40 2.03 2.03 30 2.31 2.31 30 at > 50%F 3.20 3.20 25 at ) 50%F 3.61 3.61 30 at s 50%F 2.83 2.83 25at 5%F 3.25 325 100 1.45 1.46 1.47 75 1.55 1.56 1.58 65 1.73 1.75 1.75 50 50 1.82 1.82 1.83 40 1.95 1.95 2.03 30 2.20 2.20 2.31 30 at > 50%F 3.06 3.06 3.20 25 at > 50%F 3.47 3.47 3.61 30 at l 50%F 2.70 2.70 283 25 at %50%F 3.10 3.10 3.25 100 1.44 1.44 75 1.54 1.55 65 1.73 1.75 50 50 1.82 1.83 FHOOS 40 2.02 202 30 2.31 2.31 30 at > 50%F 2.75 2.75 25 at > 50%F 3.04 3.04 30 at 9 50%F 2.67 2.67 25 at s 50%F 2.93 2.93 100 1.47 1.47 75 1.58 1.58 65 1.73 1.75 50 TBVOOS 50 1.83 1.83 FHOOS 40 2.03 2.03

.PLU0OS 30 2.31 2.31 30at,50%F 3.20 3.20 25 at > 50%F 3.61 3.61 30 at I50%F 2.83 2.83 25 at t 50%F 3.25 3.25

" 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 18 Core Operating Liits Report, (105% OLTP)

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[M liNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis' BOC BOC BOC Power to to to End of Condition

(% of rated)

NEOC EOCLB Coast 100 1.43 1.43 1.45 75 1.54 1.54 1.57 65 1.62 1.62 1.66 50 1.77 177 1.84 50 1.82 1.84 1.85 Base Case 40 1.96 196 2.04 30 2.22 2.22 2.33 30 at > 50%F 2.64 2.64 2.75 25 at 3 50%F 2.91 2.91 3.04 30 at I50%F 2.58 2.58 2.67 25 at % 50%F 2.81 2.81 2.93 100 1.46 1.47 1.48 75 1.57 1ý58 1.61 65 1.66 1.66 1.69 50 1.79 1.79 50 1.82 1.84 1.85 TBVOOS 40 1.97 1.97 2.05 30 2.23 223 2.33 30 at > 50%F 3.06 3.06 3.20 25 at3 50%F 3.47 3.47 3.61 30 at r. 50%F 2.70 2.70 2.83 25 at 50%F 3.10 3.10 3.25 100 1.45 1.45 75 1.57 1.57 65 1.66 1.66 so 50 1,84 184 FHOOS 40 2.04 2.04 30 2.33 2.33 30 at > 50%F 2.75 275 25 at > 50%F 3.04 3.04 30 at I 50%F 2.67 2.67 25 at s 50%F 2.93 2.93 100 1.43 1.43 1.45 75 1.54 1.54 1.57 65 1.74 1.77 1.77 50 50 1.83 1.84 1.85 PLUOOS 40 1.96 1.96 2.04 30 2.22 2.22 2.33 30 at > 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at' 50%F 2.58 2.58 2.67 25 at r 50%F 2.81 2.81 2.93

• 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.

B&wns Feny Unit 2 Cyde 18 Core OpWaing Linm Report, (105% OLTP)

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[M liNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 Table 4.4 MCPRP Limits for Technical Specification Scram Time Basis (continued)*

BOC BOC BOC Power to to to End of Conditin

(% of rated)

NEOC EOCLB Coast 100 1.48 1.48 75 1.60 1,61 65 1.69 1.69 50 50 1.85 1.85 ravos 40 2.05 2.05 30 2.33

.33 30 at >50%F 3.20 3.20 25 at 50%F 3.61 3.61 30 at i 50%F 2.83 2.83 25 at 50%F 325 3.25 100 1.46 1.47 1.48 75 1.57 1.58 1.61 65 1.74 1.77 1.77 50 mV0oS 50 1.83 1.84 1.865 40 1.97 1.97 2.05 30 2.23 2.23 2.33 30 at > 50%F 3.06 3.06 3.20 25 at > 50%F 3.47 3.47 3.61 30 at I 50%F 2.70 2.70 2.83 25 at S 50%F 3.10 3.10 3.25 100 1.45 1.45 75 1.57 1.57 65 1.74 177 so 50 1.84 1.84 FHOOS 40 2.04 2.04 30 2.33 2.33 30 at > 50%F 2.75 2.75 25 at > 50%F 3.04 3.04 30 at! 50%F 2.67 2.67 25 at g 50%F 2.93 2.93 100 1.48 1.48 75 1.60 1 61 65 1.74 1.77 50 TBVOOS 50 1.85 1.85 FHOOS 40 2.05 2.05 PLUOOS 30 2.33 2.33 30 at > 50%F 3.20 3.20 25 at > 50%F 3.61 3.61 30 at6 50%F 2.83 2.83 1

25 at z 50%F 3.25 3.25 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 18 Core Operatlng Umits Report (105% OLTP)

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[M ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Table 4.5 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:

Technical Specification Scram Time Basis BOC BOC 1OC operating Power to to to End of

(% of rated)

NEOC EOCLB Coast 100 1.45 1.45 1.45 75 1.57 1.57 1.57 65 1.74 1.77 1.77 50 1.84 1.84 1.84 50 1.99 1.99 1.99 TBVIS 40 2.24 2.24 2.24 30 2.58 2.58 2.58 30 at > 50%F 3.00 3.00 3.00 25 at > 50%F 3.37 337 3.37 30 at r 50%F 2.90 2.90 2.90 25 at i 50%F 3.23 3.23 3.23 100 1.48 1.48 1.48 75 1.60 1.61 1.61 65 1.74 1.77 1.77 50 1.85 1.85 1.85 50 2.00 200 2.00 TBVOOS 40 2.24 2.24 2.24 30 2.58 2.58 2.58 30 at > 50%F 3.41 3.41 3.41 25 at > 50%F 3.85 3.85 3.85 30 ats 50%F 3.02 3.02 3.02 25 at i 50%F 3.51 3.51 3.51

" 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 Fery Unit 2 Cycle 18 Core Operating Limit Report (105% OLTP)

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[M liNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 Table 4.6 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Technical Specification Scram Time Basis*

BOC BOC BOC Power to to to End of Condiion

(% of rated)

NEOC EOCLB Coast 100 1.45 1.45 1.45 75 1.57 1.57 1.57 65 1.74 1.77 1.77 50 1.84 1.84 1.84 50 2.00 2.00 2.00 TBVIS 40 2.25 2.25 2.25 30 2.60 2.60 2.60 30 at > 50%F 3.01 3.01 3.01 25 at > 50%F 3.39 3.39 3.39 30 at 50%F 2.91 2.91 2.91 25 att 50%F 3.25 3.25 3.25 100 1.48 1.48 1.48 75 18A0 1.61 1.61 65 1.74 1.77 1.77 50 1.85 1.85 1.85 50 2.00 2.00 2.00 TBVOOS 40 2.25 2.25 2.25 30 2.60 2.60 2.60 30 at > 50%1 3.42 3.42 3.42 25 at > 50%F 3.87 3.87 3.87 30 at i 50%F 3.04 3.04 3.04 25 at i 50%F 3.53 3.53 3.53

• 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 2 Cyde 18 Core Operatng Linm Report (105% OLTP)

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[M liNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 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 23. The calculated OLMCPR's are shown in Table 5.1. Review of results shown in COLR Table 4.2 indicates an OPRM setpoint of 1.14 may be used. The successive confirmation count (sometimes referred to as Np) is provided in Table 5.2, per Reference 28.

Table 5.1 OPRM Setpoint Range' OPRM OLMCPR OLMCPR 1.05 1.06 1.07 1.08 1.09 1.10 1.11 1.12 1.13 1.14 1.15 1.17 1.19 1.21 1.23 1.25 1.27 1.29 1.31 1.33 1.35 1.37 1.12 1.14 1.16 1.18 1.19 1.21 1.23 1.25 1.27 1.29 1.32 Table 5.2 OPRM Successive Confirmation Count Setpoint Count OPRM 6

> 1.04 8

> 1.05 10

> 1.07 12

>1.09 14

Ž1.11 16

>1.14 18

> 1.18 20

>1.24 "Extrapolation beyond a setpoint of 1.15 is not allowed I

Browns Fery Unit 2 Cyde 18 CouOpeMraing 1tReport (105% OLTP)

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[M NPG 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 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 Cyle 18 CorpeaWig LUnits Repolt (105% OLTP)

Page 34 TVACO.R-BF2C18, ReWn 0 (Fh-W)

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~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 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 24 & 25, 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 24, 25, and 27.

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

> 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 operationt

' 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 in Reference 1.

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

Browns Fenry Unit 2 Cycle 18 Core Opereft Uimts Report, (105% OLTP)

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[M NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 Table 7.3 Control Rod Withdrawal Error Results RBM CRWE HTSP Analytical Limit OLMCPR 107 1.24 111 1.31 114 1.34 117 1.36 Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 114% unblocked).

Brumrs FerryUnit 2Cyde 18 CoreOmfetgLh* Report~ (105% OLTP)

Page 36 TVA-COLR-BF2C18, Revion 0 (Fin)

EDMS: L32 130301 800 Reactor Engineering and Fuels - BWRFE Date: March 1, 2013 NPG 1101 Market Street, Chattanooga TN 37402 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 Browns Ferry Unit 2 Cyde 18 Core Operating Ln Report, (105% OLTP)

Page 37 TVA-COLR-BF2C18, Reision 0 (Fia)