Text

Submittal Core Operating Limits Report for Cycle 16 Operation
	ML16015A289
Person / Time
Site:	Browns Ferry
Issue date:	03/01/2013
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
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ML16015A283	List: ML13108A122; ML16015A289;
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U U

EDMS L32 130303 804 QA Document N P G

Pages Affected: All" BFE-3238, Revision 2 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF3CI16 Revision 2 (Final)

(Revision Log, Page v)

March 2013 Prepared:

Verified:

Approved:

Reviewed T. W. ichenberg, Sr. Spe~ialist B. C. Mitchell, Engineer G. C. Storey, Managier, B*/IR Fuel Enginee Date:

/**-

,2/*

Date:~

A

/3-Date:

3/(/) 3 ering Date:

3*- V-3

ng Date:

- /

W. R. Hayes, M~anag

, Reactor Engineeri Approved.

//-**

Chairman, PORC Approved:

EDMS: L32 130303 804

~Nuclear Fuel Engineering - BWRFE NPG 1101 Market Street, Chattanooga TN 37402 Date: March 1, 2013 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......................................................................................... 1 1.1 Purpose........................................................................................ 1 1.2 Scope...........................................................................................

1.3 Fuel Loading................................................................................... 1 1.4 Acceptability................................................................................... 2 2

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

3 2.2 Off-Rated Power Dependent Limit: APLHGRp'...................................

3 2.2.1 Startup without Feedwater Heaters.................................................... 3 2.3 Off-Rated Flow Dependent Limit: APLHGRF............................................... 3 2.4 Single Loop Operation Limit: APLHGRsLo.................................................. 3 2.5 Equipment Out-Of-Service Corrections..................................................... 5 3

LHGR Limits........................................................................................ 6 3.1 Rated Power and Flow Limit: LHGRRATED.................................................. 6 3.2 Off-Rated Power Dependent Limit: LHGRP................................................. 6 3.2.1 Startup without Feedwater Heaters.................................................... 6 3.3 Off-Rated Flow Dependent Limit: LHGRF.................................................. 7 3.4 Equipment Out-Of-Service Corrections..................................................... 7 4

OLMCPR Limits.................................................................................. 13 4.1 Flow Dependent MCPR Limit: MCPRF.................................................... 13 4.2 Power Dependent MCPR Limit: 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 Limits.......................................................... 14 4.2.4 Equipment Out-Of-Service (EOOS) Options........................................ 1!5 4.2.5 Single-Loop-Operation (SLO) Limits................................................. 15 4.2.6 Below Pbypass Limits................................................................. 15 5

Oscillation Power Range Monitor (OPRM) Setpoint.......................................... 24 6

APRM Fiow Biased Rod Block Trip Settings................................................... 25 7

Rod Block Monitor (RBM) Trip Setpoints and Operability..................................... 26 8

Shutdown Margin Limit.........................................

................................. 28 Br~ns Ferry Unit 3 Cyde 16 Page ii Core Operatng Umils Report, (105% OLTP)

V-ORB3Ievio2(Fn)

Page ii TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 N GNuclear Fuel Engineering - BWRFEDaeMrc1,23 N G1101 Market Street, Chattanooga TN 37402 Dt:Mrh121 List of Tables Nuclear Fuel Types...................................................................................... 2 Startup Feedwater Temperature Basis................................................................. 6 Nominal Scram Time 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 OPRM Setpoint Range................................................................................. 24 OPRM Successive Confirmation Count Setpoint.................................................... 24 Analytical RBM Trip Setpoints.......................................................................... 26 RBM Setpoint Applicability............................................................................. 26 Control Rod Withdrawal Error Results................................................................ 27 Browns FerryUnit 3Cycle 16 Core Operating Umits Report, (105% OLTP)

Page iii TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 Nuclear Fuel Engineering - BWRFEDaeMrc1,23 N PG

~ ~~1101 Market Street, Chattanooga TN 37402 Dt:Mrh121 List of Figures APLHGRRATED for ATRIUM-I10 Fuel.................................................................... 4 LHGRRATED forATRIUM-10 Fuel......................................................................... 8 Base Operation LHGRFACp for ATRIUM-10 Fuel..............................................

9 LHGRFACF for ATRIUM-10 Fuel................

...................................................... 10 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 1.......... 11 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 2.......... 12 MCPRF for ATRIUM-10 Fuel........................................................................... 16 Browns Ferny Unit 3 Cyde 16 Core Operating Umits Report, (105% OLTP)

Page iv TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 E2 NPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Revision Log Number IPageI Description Added SER annotation to Reference 20 methodology update per TS-1 -R2 ix 429. Added Reference 28 in support of TS-429 OPRM setpoint relocation.

Section 1.2, added editorial clarification in RED text echoing Technical 2-R2 1-2 Specification Mode applicability. The impact on page 2 is that Section 1.4 now appears after Table i-1.

Implemented TS-429 requirement to locate OPRM Setpoint to COLR.

3-R2 24-28 Section 5 is added on Page 24(in conjunction with change 3-R2).

Previous Sections 5-7 are now Section 6-8.

4-2 Rev 1 Appendix A removed. Table A-i information now appears as Table 5.1 28-29 per change noted in 2-R2 above.

1-Ri All Revised to support all modes of operation.

0-R0 All New document.

Browns Ferny Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)

Page v TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 Ei~NPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Nomenclature APLHGR APRM AREVA NP BOC BSP BWR CAVEX CD CMSS COLR CPR CRWE CSDM DIVOM EOC EOOS FFTR FFWTR FHOOS ft 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 Equipment 00S Final Feedwater Temperature Reduction Final Feedwater Temperature Reduction Feedwater Heaters OOS Foot: English unit of measure for length Giga Watt Day High TSP Interim Corrective Action Increased Core Flow (beyond rated)

I n-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 MAPLHGR multiplier (Power or Flow dependent)

Minimum CPR Moisture Separator Reheater Valve kW LCO LFWH LHGRFAC LPRM LRNB MAPFAC MCPR MSRV Bre~ns Feny unt 3 Cyde 16 Page vi Core Operating Limits Report, (105% OLTP)

TACL-Fc6 eiin2(nl Page vi TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 Nuclear Fuel Engineering - BWRFEDaeMrc1,23 N

IPG

~~1101 Market Street, Chattanooga TN 37402 Dt:Mrh121 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 00S 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 3 Cyde 16 Core Operating Uimits Report, (105% OLTP)

Page vii TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 i*Nuclear Fuel Engineering - BWRFE Date: March 1,2013 NPG 1101 Market Street, Chattanooga TN 37402

< References

1.

ANP-3068, Revision 0, Browns Ferry Unit 3 Cycle 16 Reload Safety Analysis, AREVA NP, Inc.; February, 2012.

2.

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.

3.

ANP-2838(P) Revision 0, Mechanical Design Report for Browns Ferry Unit 3 Reload BFE3-15 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., August 2009.

4.

ANP-2628(P), Rev. 0, Mechanical Design Report for Browns Ferry Unit 3 Reload BFE3-14 ATRIUM-10 Fuel Assemblies, ARE VA NP, Inc., May 2007.

5.

ANP-2991(P) Revision 0, Browns Ferry Unit 3 Cycle 16 Plant Parameters Document, ARE VA NP, Inc., June 2011.

6.

BFE-3253, Revision 0, Browns Ferry Unit 3 Cycle 16 Calculation File: Unit 3 Reload 15 Shuffle, Tennessee Valley Authority, March 21, 2012.

Methodoloay 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-80-1 9(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 3 Cydle 16 Page viii Core Operating Umits Report, (105% OLTP)

TVA-COLR-BF3C1 6, Revision 2 (Final)

EDMS: L32 130303 804

~Nuclear Fuel Engineering - BWRFE N G1101 Market Street, Chattanooga TN 37402 Date:

March 1, 2013

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-1358(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, ATRIUM TM -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, 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.

Brown~sFeIj Unit3 Cyde 16 CoreOperlngUrnits Report, (105% OLTP)

Page ix TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 S N GNuclear Fuel Engineering - BWRFE Date:

March 1, 2013 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 will discuss the following areas:

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

Applicability: Mode 1, > 25% RTP (Technical Specifications definition of RTP)

SLinear 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)

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

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

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

Applicability: Mode 1, > (as specified in Technical Requirements 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 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.

Browns Ferry Unit 3 Cycle 16 Page 1 Core Operating Limits Report, (105% OLTP)

TVA-coLR-BF3C16, Revision 2 (Fwnal)

EDMS: L32 130303 804 E~NPG Nuclear Fuel Engineering - 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 (NET)

(Rangle)

ATRIUM-10 A10-4218B-15GV80-FCC 14 108 4

FCC006-FCC216 ATRIUM-10 A10-4218B-13GV80-FCC 14 72 5

FCC219-FCC290 ATRIUM-10 A10-3831B-15GV80-FCD 15 200 6

FCD001-FCD200 ATRIUM-10 A10-3403B-9GV80-FCD 15 20 7

FCD257-FCD276 ATRIUM-10 AbO-3392B-1OGVS0-FCD 15 34 8

FCD221-FCD256 ATRIUM-10 A10-4218B-15GV80-FCC 15 2

9 FCC217-FCC218 ATRIUM-10 A10-4218B-13GV80-FCC 15 4

10 FCC3O7-FCC310 ATRIUM-10 A10-3757B-b0GV80-FCC 15 40 11 FCC335-FCC374 ATRIUM-10 A10-3440B-11GV80-FCE 16 144 12 FCEOO1-FCE144 ATRIUM-10 A10-3826B-13GV80-FCE 16 44 13 FCE145-FCE188 ATRIUM-10 A10-4075B-13GV80-FCE 16 48 14 FCE189-FCE236 ATRIUM-10 A10-4081B-12GV80-FCE 16 48 15 FCE237-FCE284 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.

BrowinsFerryUnit 3Cyde 16 Core Operating Umits Report, (105% OLTP)

Page 2 TVA.-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 SNuclear Fuel Engineering - BWRFEDaeMrc1,23 N PG

~~~1101 Market Street, Chattanooga TN 37402DaeMrc1,23 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-I10 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-i10 fuel, does not specify a flow dependent APLHGR. Therefore, MAPEACF is set to a value of 1.0.

2.4 Single Loop Operation Limit: APLHGRsLo The single loop operation multiplier for ATRIUM-i10 fuel is 0.85, per Reference 1.

Browns Ferr Unit 3 Cydle 16 Core Opera~ng Limits Report, (105% OLTP)

Page 3 "TVA-COLR-BF3C16, Revision 2 (Final)

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-J-01 9

6 3

0 0

20 40 60 Planar Average Exposure (GWd/MTU) 80 Planar Avg.

Exposure APLHGR Limit i'(GWdIMTU)0.

(kW/ft)12, 05.0 I

12.5 67.0 7.3 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Browns Ferry Unit 3 Cyde 16 Core Operating Umit Report, (105% OLTP)

Page ;4 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 EI!?iINPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March1, 2013 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 RPTOOS TBVOOS PLUOOS EHOOS (or FFWTR)

All equipment In-Service (includes 1 SRVOOS)

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.

Browns Ferry Unit 3 Cydle 16 Core Operating Limits Report, (105% OLTP)

Page 5 TVA-COLR-BF3Cl16, Revision 2 (Final)

EDMS: L32 130303 804 Ei!?i~NPG Nuclear Fuel Engineering - 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: LHGRPATED 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-i10 fuel, LHGR limits are adjusted for off-ratedl 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 Te mpe ratu re Power Range I 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 Fenry Unit 3 Cydle 16 Core Operating Limits Report, (105% OLTP)

Page 6 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 E.iIPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March1, 2013 3.3 Off-Rated Flow Dependent Limit: LHGRF The ATRIUM-l0 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 RPTOOS TBVOOS PLUOOS EHOOS (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/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, orSLO.

"All equipment service conditions assume 1 SRVOOS.

Brow'nsFerryUnit 3Cycde 16 Core Operating Umits Report, (105% OLTP)

Page 7 TVA-COLR-BF3C16, Revision 2 (Final)

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.L~IPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1,2013 15 12 9

-'6 0

20 40 60 Pellet Exposure (GWd/MTU) 80 Pellet Exposure LHGR Limit (GWc/MTU)

(kWIft) 0.0 13.4 18.9 13.4 74.4 7.1 Figure 3.1 LHGRRATEO for ATRIUM-10 Fuel Buowns Ferry Unit 3 Cyde 16 Core Operating Limit Report, (105% OLTP)

Page 8 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 E~INPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1, 2013 a.

U u-1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine Bypass Valve In-Service, TBVIS TbieBypass Valve Out-of-Service, TBVOOS TBVIS, <50% Core FlIow TBI,>50% Core Flow 7 TBVOOS,

50% Core Flow JTBVOOS, >50% Core Flow i==

2i i

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

Turbine Bypass In-Service Core Power LHGRFACp Cor Floate 0%date Core Flow > 50% Rated

30.

5s

.5 Turbine Bypass Out-of-Service Core Power LHGRFACp

(% Rated)100 09 30.0 I

0.61 Core Flow > 50% Rated Core Flow < 50% Rated Figure 3.2 Base Operation LHGRFACp for ATRIUM-i10 Fuel (Independent of other EOOS conditions)

Browns Ferry Unit 3Cycele6 Core Operating Urnits Report, (105% OLTP)

Page 9 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 Ei~NPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1,2013 1.10 1.05 1.00 U-

..I 0.95

//..

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

Core Flow LHGRFACF

(% Rated) 30.0 0.94 42.5 1

107.0 1

Figure 3.3 LHGRFACF for ATRIUM-10 Fuel (Values bound all EOOS conditions)

(10 7.0% maximum core flow line is used to support 105% rated flow operation, ICE)

B~uAns Feny Unit 3 C~ie 16 Page 10 Core Operating Limits Report, (105% OLTP)1VCLRB36,evso2(Fi)

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.PG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1, 2013 a1.

-J-1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 A '*n TurbineByp0 sValveIn-ervce, TBVIS j

Turie Byp *'s Valve Out-of-Service, TBVOOS TBVIS,

50% Core Flow TBVIS, > 50% Core Flow TBVOOS, <50% Core Flow I

I STBVOOS, >50% Core Flow V, *=#V 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Sevilce Core Power L HGRF-

..- A C p

(% =Rated) I______

100.0 j

1.00 30.0 j

0.61 Core Flow > 50% Rated Core Flow < 50% Rated Turbine Bypass Out-of-Service Core Power LHGRFACp

(% Rated) 100.0 0.93 30.0 0.61 Core Flow > 50% Rated 30.0 j

0.44 25.0 j

0.41 Core Flow < 50% Rated Figure 3.4 Startup Operation LHGRFACP for ATRIUM-10 Fuel:

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

Biv~ns Fenyunit3Cyde 16 Page 11 Core Operating Umitsi Report, (105% OLTP)1V-ORBC6,evso2(Fal Page 11 TVA-COLR-BF3C16, Revision 2 (Fr*l)

EDMS: L32 130303 804 LLIPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1,2013 a.

C-U-

C, 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine Bypass Valve In-Service, TBVIS Turbine Bypass Valve Out-of-Service, TBVOOS TBVIS, < 50% Core Flow STBVIS, > 50% Core Flow STBVOOS,< 550% Core Flow STBVOOS, > 50% Core Flow 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Core Power LHGRFACp

(% Rated) J______

100.0 j

1.00 30.0 J

0.61 Core Flow > 50% Rated Core FRow < 50% Rated

30.

I

.5 Turbine Bypass Out-aof-S ervice Core Power LHGRFACp

(%Rated) 100.0 0.93 30.0 0.61 Core Flow >50% Rated 30.0 0.44 25.0 j

0.41 Core Flow < 50% Rated Figure 3.5 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

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

Brons Ferry Unit 3 Cyde 16 CoreOpeang Urnits Report, (105% OLTP)

Page 12 TVA-COLR-BF3C16, Revision 2 (Final)

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~

~~1101 Market Street, Chattanooga TN 37402 Dt:Mrh121 40OLMCPR 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 dependernt upon core flow (% of Rated), and the max core flow limit, (Rated or Increased Core Flow, ICE). 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.

BrowvnsFerryUnit 3Cycde16 Page 13 Core Operating Units Report, (105% OLTP)

TVA-COLR-BF3C16, Revision 2 (FinaI)

EDMS: L32 130303 804 ENPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1,2013 4.2.2 Scram Speed Depen dent 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 Depen dent 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 EOC BOC to End of Coast NEOC corresponds to EOC corresponds to End of Coast 28,822.0 MWd / MTU 31,128.6 MWd / MTU 32,100.7 MWd / MTU NEOC refers to a Near EOC exposure point.

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

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

Browns Ferry Unit 3 Cycde 16 CoeOperatng Umits Report, (105% OLTP)

Page 14 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 E!i.PG NuclearFuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date:

March 1,2013 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 (EQOOS) 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 EHOOS (or FFWTR)

Al! 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 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 Singl~e-Loop-Operation (SLO) Limits MCPRp limits are increased by 0.02 to support SLO, per Reference 1.

4.2.6 Below Pbvp3ass Limits Below Pbypass (30% rated power), MCPRp limits depend upon core flow. One set of MCPRp limits applies for core flow above 50% of rated; a second set applies if the core flow is less than or equal to 50% rated.

All equipment service conditions assume 1 SRV00S.

Browns Feny Unit 3 Cydle 16 Core Operating Umits Report, (105% OLTP)

Page 15 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 LL!l~INPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 2.00 1.80 1.60 a.

U 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)

(10 7.0% maximum core flow line is used to support 105% rated flow operation, ICF)

Browns Ferry Unit 3 Cycde 16 Core Operating Urnit Report, (105% OLTP)

Page 16 TVA-COLR-BF3C16, Revision 2 (Anal)

EDMS: L32 130303 804 EINPG Table4.2 Nuclear Fuelt Engineeringm Sca TimeBai Date: March 1, 2013 Table 4.2 MCPR~ Limits for Optimum Scram Time Basis BOC BOC BOC Power to to to Eidof Operating Condition

(% of rated)

NEOC EOC Coast 100 1.39 1.41 1.42 75 1.51 1.51 1.54 65 1.58 1.58 1.64 50 1.78 1.78 1.85 50 1.92 1.92 1.92 Base Case 40 2.01 2.01 2.05 30 2.22 2.22 2.33 30 at > 50%F 2.54 2.54 2.64 25 at > 50%F 2.75 2.75 2.88 30 at

50%F 2.52 2.52 2.60 25 at < 50%F 2.69 2.69 2.80 10O0 1.41 1.42 75 1.54 1.54 65 1.64 1.64 50 1.85 1.85 50 1.92 1.92 FHOOS 40 2.05 2.05 30 2.33 2.33 30Oat >50%F 2.64 2.64 25 at > 50%F 2.88 2.88 30Oat*<50%F 2.60 2.60 25 at *;50%F 2.80 2.80

All limits, including 'Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRP limits will be 0.02 higher.

FFWNTPIFHOOS is supported for the BOG to End of Coast limits.

CoreOperating Umi* Report, (105% OLTP)

A-ORB31,Rvso2(Fnl Page 17 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 EI~NPG Nuclear Fuel Engineering -BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 table 4.3 MCPRp Limits for Nominal Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Conditon

(% of rated)

NEOC EOC Coast 100 1.41 1.42 1.43 75 1.54 1.54 1.58 65 1.62 1.62 1.67 50 1.80 1.80 1.87 50 1.92 1.92 1.93 Base Case 40 2.02 2.02 2.07 30 2.24 2.24 2.36 30 at > 50%F 2.54 2.54 2.64 25 at > 50%F 2.75 2.75 2.88 30 at

50%F 2.52 2.52 2.60 25 at < 50%F 2.69 2.69 2.80 100 1.45 1.46 1.47 75 1.58 1.58

1.60 65 1.64 1.64 1.69

50 1.82 1.82 1.89 50 1.92 1.92 1.93 TBVOOS 40 2.02 2.02 2.08 30 2.25 2.25 2.36 30Oat >50%F 3.06 3.06 3.18 25 at > 50%F 3.35 3.35 3.46 30 at < 50%F 2.86 2.86 2.99 25 at S 50%F 3.24 3.24 3.39 100 1.43 1.43 75 1.58 1.58 65 1.67 1.67 50 1.87 1.87 50 1.93 1.93 FHCOS 40 2.07 2.07 30 2.36 2.36 30Oat >50%F 2.64 2.64 25 at > 50%F 2.88 2.88 30 at S 50%F 2.60 2.60 25 at S 5O%F 2.80 2.80 10O0 1.41 1.42 1.43 75 1.54 1.54 1.58 65 1.82 1.82 1.82 50.....

50 1.92 1.92 1.93 PLUOOS 40 2.02 2.02 2.07 30 2.24 2.24 2.36 30 at > 50%F 2.54 2.54' 2.64 25 at > 50%F 2.75 2.75 2.88 30 at < 50%F 2.52 2.52 2.60 25 at S; 50%F 2.69 2.69 2.80 SAll limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of I 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 eventjs the same with, or without PLUOOS.

Browns Ferry Unit 3 Cydle 16 Core Operating Umits Report, (105% OLTP)

Page 18 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 NPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Table 4.3 MCPRp Limits for Nominal Scram Time Basis (continued)*

BOC BOC BCC OprtogFw er to to to End of Condition

(% of rated)

NEOC ECO Coast 10O0 1.46 1.47 75 1.60 1.60 65 1.69 1.69 50 1.89 1.89

- vos50 1.93 1.93 FOS40 2.08 2.08 30 2.36 2.36 30Oat >50%F 3.18 3.18 25 at > 50%F 3.46 3.46 30 at

50%F 2.99 2.99 25 at

50%F 3.39 3.39 100 1.45 1.46 1.47 75 1.58 1.58 1.60 65 1.82 1.82 1.82 50.....

50 1.92 1.92 1.93 i~~os40 2.02 2.02 2.08 30 2.25 2.25 2.36 30 at > 50%F 3.06 3.06 3.18 25 at > 50%F 3.35 3.35 3.46.

30 at S 50%F 2.86 2.86 2.99

_______25 at S 50%F 3.24 3.24 3.39 100 1.43 1.43 75 1.58 1.58 65 1.82 1.82 50.....

50 1.93 1.93 i~os40 2.07 2.07 30 2.36 2.36 30 at > 50%F 2.64 2.64 25 at > 50%F 2.88 2.88 30 at S 50%F 2.60 2.60 25 at < 50%F 2.80 2.80 100 1.46 1.47 75 1.60 1.60 65 1.82 1.82 50.....

"IBVOOS 50 1.93 1.93 FE-OOS 40 2.08 2.08 FLUOOS 30 2.36 2.36 30Oat >50%F 3.18 3.18 25 at > 50%F 3.46 3.46.

30 at S 50%F 2.99 2.99 25 at S 50%F 3.39 3.39

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.

BrowvnsFerryUnit 3OCyce16 Core Operating limits Report, (105% OLTP)

Page 19 TVA-COLR-8F3C16, Revision 2 (Final)

EDMS: L32 130303 804

.L~PG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 1,2013 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis*

BOC BOO BOO Opraon wer to to to End of Condition

(% of rated)

NEOC EOO Coast 10O0 1.43 1.43 1.44 75 1.56 1.56 1.61 65 1.64 1.64 1.70 50 1.83 1.83 1.90 50 1.93 1.93 1*.93 Base Case 40 2.03 2.03 2.09 30 2.26 2.26 2.38 30 at > 50%F 2.54 2.54 2.64 25 at > 50%F 2.75 2.75 2.88 30 at < 50%F 2.52 2.52 2.60 25 at < 50%F 2.69 2.69 2.80 100 1.47 1.47 1.49 75 1.60 1.60 1.63 65 1.67 1.67 1.72 50 1.85 1.85 1.91 50 1.93 1.93 1.93 "TBVOOS 40 2.03 -

2.03 2.11 30 2.27 2.27 2.38 K

30Oat >50%F 3.06 3.06 3.18 25 at > 50%F 3.35 3.35 3.46 30 at < 50%F 2.86 2.86 2.99 25 at < 50%F 3.24 3.24 3.39 10O0 1.44 1.44 75 1.61 1.61 65 1.70 1.70 50 1.90 1.90 50 1.93 1.93 FHOS 40 2.09 2.09 30 2.38 2.38 30 at > 50%F 2.64 2.64 25 at > 50%F 2.88 2.88 30 at < 50%F 2.60 2.60 7

25 at < 50%F 2.80 2.80 10O0 1.43 1.43 1.44 75 1.56 1.56 1.61 65 1.83 1.83 1.83 50.....

50 1.93 1.93 1.*93 PLUOOS 40 2.03 2.03 2.09 30 2.26 2.26 2.38 30 at > 50%F 2.54 2.54 2.64 25 at > 50%F 2.75 2.75 2.88 30 at < 50%F 2.52 2.52 2.60 25 at < 50%F 2.69 2.69 2.80

All limits, including 'Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for BOC to End of COAST due to redundancy. Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to conservatively bound FHOOS limits for earlier exposure applicability windows.

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

Browns Ferry Unit 3 Cydle 16 Core Operal~ng Umits Report, (105% OLTP)

Page 20 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 E.IPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: Marchl1,2013 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis '(continued)*

BOO BOO BOO Ppoan w er to to to End of Condition

(% of rated)

NEOC EOC Coast 10O0 1.48 1.48 75 1.63 1.63 65 1.72 1.72 50 1.91 1.91 50 1.93 1.93 F-OS40 2.11 2.11 30 2.38 2.38 30Oat >50%F 3.18 3.18 25 at >50%F 3.46 3.46 30 at < 50%F 2.99 2.99 25 at < 50%F 3.39 3.39 10O0 1.47 1.47 1.49 75 1.60 1.60 1.63 65 1.83 1.83 1.83 50.....

ieos50 1.93 1.93 1.93 iuos40 2.03 2.03 2.11 30 2.27 2.27 2.38 30 at > 50%F 3.06 3.06 3.18 25 at > 50%F 3.35 3.35 3.46 30 at < 50%F 2.86 2.86 2.99

_______25 at < 50%F 3.24 3.24 3.39 10O0 1.44 1.44 75 1.61 1.61 65 1.83 1.83 50.....

FOS50 1.93 1.93 FLQS40 2.09 2.09 30 2.38 2.38 30 at > 50%F 2.64 2.64 25 at > 50%F 2.88 2.88 30 at < 50%F 2.60 2.60 25 at < 50%F 2.80 2.80 100o 1.48 1.48 75 1.63 1.63 65 1.83 1.83 50....

TBVOOS 50 1.93 1.93 FHOOS 40 2.11!

2.11 RLUOOS 30 2.3"8 2.38.

30Oat >50%F 3.18 3.18 25 at > 50%F 3.46 3.46 30 at S 50%F 2.99 2.99 25 at < 50%F 3.39 3.39 "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.

Brow'ns FerryUnit 3Cydele6 Core Operating Umits Report, (105% OLTP)

Page 21 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 EI!

PG Nuclear Fuel Engineering - 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*

BOO BOO BOC Power to to to Endof Operating Condition

(% of rated)

NEOC EOC Coast 100 1.44 1.44 1.44 75 1.61 1.61 1.61 65 1.83 1.83 1.83 50 1.93 1.93 1.93 50 2.05 2.05 2.05 TBVIS 40 2.30 2.30 2.30 30 2.63 2.63 2.63 30 at > 50%F 2.88 2.88 2.88 25 at >50%F 3.18 3.18 3.18 30 at < 50%F 2.85 2.85 2.85 25 at <50%F 3.11 3.11 3.11 100 1.48 1.48 1.49 75 1.63 1.63 1.63 65 1.83 1.83 1.83 50 1.93 1.93 1.93 50 2.05 2.05 2.05

-rBVOOS 40 2.30 2.30 2.30 30 2.63 2.63 2.63 30 at > 50%F 3.36 3.36 3.36 25 at > 50%F 3.64 3.64 3.64 30 at *; 50%F 3.20

.3.20 3.20 25 at < 50%F 3.64 3.64 3.64

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 E0OS scenarios. PLU is inoperable for powers less than 50% rated power, therefore at these powers it can be considered a base case.

Browns Ferry Unit 3 Cydle 16 Core Operating Limits Report, (105% OLTP)

Page 22 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 II!?~NPG Nuclear Fuel Engineering - 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 OprtogFw er to to to End of Condition

(% of rated)

NEOC EOC Coast 100 1.44 1.44 1.44 75 1.61

.1.61 1.61 65 1.83 1.83 1.83 50 1.93 1.93 1.93 50 2.06

.2.06 2.06 TBVlS 40 2.31 2.31 2.31 30 2.65 2.65 2.65 30 at > 50%F 2.90 2.90 2.90 25 at > 50%F 3.20 3.20 3.20 30 at S 50%F 2.86 2.86 2.86 25 at**50%F 3.13 3.13 3.13 100 1.48 1.48 1.49 75 1.63 1.63 1.83 65 1.83 1.83 1.83 50 1.93 1.93 1.93 50 2.06 2.06 2.06 "FBVOOS 40 2.31 2.31 2.31 30 2.65 2.65 2.65 30 at > 50%F 3.36 3.36 3.36 25 at > 50%F 3.66 3.66 3.66 30 at S 50%F 3.21 3.21 3.21 25 at < 50%F 3.66 3.66 3.66 "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 Ferry Unit 3 Cyde 16 Core Operaflng Umts Report, (105% OLTP)

Page 23 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 EI.PG Nuclear Fuel Engineering - 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 Ill 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 5.10OPRM Setpoint Range*

OPRM OLMCPR OLMCPR Setpoint (SS)

(2PT) 1.05 1.18 1.13 1.06 1.20 1.14 1.07 1.22 1.16 1.08 1.24 1.18 1.09 1.26 1.20 1.10 1.28 1.22 1.11 1.30 1.24 1.12 1.32 1.26 1.13 1.34 1.28 1.14 1.36 1.30 1.15 1.39 1.32 Table 5.20OPRM Successive Confirmation Count Setpoint Count OPRM

~Setpoint 6

>_1.04 8

> 1.05 10

> 1.07 12

> 1.09 14

>_ 1.11 16

> 1.14 18

> 1.18 20

>_1.24 "Extrapolation beyond a setpoint of 1.15 is not allowed Browns Feny un~ 3 cyde 16 Page 24 Core Operating LUmits Report, (105% OLTP)TvcoRBc1,eisn2(Fal Page 24 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 Nuclear Fuel Engineering - BWRFE Date: March 1, 2013 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=O.O 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%).

Br~ns Feny Unit 3 cyde 16 Page 25 Core Operating Limits Report, (105% OLTP)Tv-oRB cIeisn2(Fa)Page 25 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 EI.PG Nuclear Fuel Engineering - 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*

RBM Trip Setpoint LPSP IPSP HPSP LTSP - unfiltered

- filtered ITSP

- unfiltered

- filtered HTSP - unfiltered

- filtered Allowable Value (AV) 27%

62%

82%

121.7%

120.7%

116.7%

115.7%

111.7%

110.9%

90%

Nominal Trip Setpoint (NTSP)

'25%

60%

80%

120.0%

119.0%

115.0%

114.0%

110.0%

109.2%

92%

DTSP As a result of cycle specific CRWE analyses, RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable as shown in Table 7.2. Cycle specific setpoint analysis results are shown in Table 7.3, per Reference 1.

Table 7.2 RBM Setpoint Applicability Thermal Power

(% Rated)

> 27% and < 90%

Applicable MCPRt

< 1.74 Notes from Table 3.3.2.1 -1 (a), (b), (f), (h)

Comment two loop operation

< 1.77 (a), (b), (f), (h) single loop operation

> 90%

< 1.43 (g) two loop operation*:

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

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

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

Browns FerryUnit 3 Cycele Core Operating Limits Report, (105% OLTP)

Page 26 TVA-COLR-BF3C16, Revision 2 (FRnal)

U, EDMS: L32 130303 804 E!iNPG Nuclear Fuel Engineering - 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 Unfiltered 107 1.31 111 1.32 114 1.35 117 1.40 Results, compared against the base case OLMCPR res'ults of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 114% unblocked).

Browns Fenry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)

Page 27 TVA-COLR-BF3C16, Revision 2 (Final)

EDMS: L32 130303 804 Nuclear Fuel Engineering - 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 3 Cycle 16 Core Operating Umnits Report, (105% OLTP)

Page 28 TVA-COLR-BF3C16, Revision 2 (Final)

U U

EDMS L32 130303 804 QA Document N P G

Pages Affected: All" BFE-3238, Revision 2 Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF3CI16 Revision 2 (Final)

(Revision Log, Page v)

March 2013 Prepared:

Verified:

Approved:

Reviewed T. W. ichenberg, Sr. Spe~ialist B. C. Mitchell, Engineer G. C. Storey, Managier, B*/IR Fuel Enginee Date:

/**-

,2/*

Date:~

A

/3-Date:

3/(/) 3 ering Date:

3*- V-3

ng Date: