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| issue date = 04/09/2012
| issue date = 04/09/2012
| title = Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation
| title = Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation
| author name = Shea J W
| author name = Shea J
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 9, 2012 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296  
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 9, 2012 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296


==Subject:==
==Subject:==
Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 3 Cycle 16, Core Operating Limits Report (COLR), Revision 0. This Unit 3 COLR was issued as an interim measure to include Shutdown Margin Limit in support of fuel loading for Cycle 16 (Mode 5 operation).
Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 3 Cycle 16, Core Operating Limits Report (COLR), Revision 0. This Unit 3 COLR was issued as an interim measure to include Shutdown Margin Limit in support of fuel loading for Cycle 16 (Mode 5 operation). A revision to the COLR will be issued prior to Cycle 16 startup covering all licensed power levels of operation (Modes 1 through 5).
A revision to the COLR will be issued prior to Cycle 16 startup covering all licensed power levels of operation (Modes 1 through 5).There are no new commitments contained in this letter. If you have any questions please contact Tom Hess at (423) 751-3487.JRes e ully, J. .Shea M ager, Corporate Nuclear Licensing  
There are no new commitments contained in this letter. If you have any questions please contact Tom Hess at (423) 751-3487.
JRes e               ully, J.       . Shea M         ager, Corporate Nuclear Licensing


==Enclosure:==
==Enclosure:==
Core Operating Limits Report, (105% OLTP), for Cycle 16 Operation TVA-COLR-BF3C16, Revision 0 cc: See Page 2 Printed on r.cycled paper


Core Operating Limits Report, (105% OLTP), for Cycle 16 Operation TVA-COLR-BF3C16, Revision 0 cc: See Page 2 Printed on r.cycled paper U.S. Nuclear Regulatory Commission Page 2 April 9, 2012 cc: (w/ Enclosure)
U.S. Nuclear Regulatory Commission Page 2 April 9, 2012 cc: (w/ Enclosure)
NRC Regional Administrator  
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
-Region II NRC Senior Resident Inspector  
 
-Browns Ferry Nuclear Plant Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 16 Operation TVA-COLR-BF3CI6, Revision 0 (See Attached)
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 16 Operation TVA-COLR-BF3CI6, Revision 0 (See Attached)
U U EDMS L32 120321 804 QA Document Pages Affected:
 
All BFE-3238, Revision 0 EMNPG Nuclear Fuel Engineering  
U                                                                                                               U EDMS L32 120321 804 QA Document Pages Affected: All BFE-3238, Revision 0 EMNPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)
-BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)TVA-COLR-BF3CI 6 Revision 0 (Final)(Revision Log, Page v)March 2012 Prepared: 6"1T..W. Eichenberg, Sr. Spe~list Verified: B. chell, Engineer Date: I z -t "-.t-L Date: 3/22 12-Date: 32-i-12-ering Approved: ( "/7 V v /G. C. Storey, Manager, B /R Fuel Enginei Reviewed:
TVA-COLR-BF3CI 6                       Revision 0 (Final)
Dii C'c ;.Fre/ rA PLC Date: W. R. Hayes, Manager, Reactor Engineering Approved:  
(Revision Log, Page v)
ý ýSL Chairman, PORC Approved:
March 2012 Prepared:6"1T..W. Eichenberg, Sr. Spe~list                     Date: I         z - t "-.t-L Verified:                                                      Date:     3/22       12-B.        chell, Engineer Approved:                   ( "/ 7 V v /                       Date:    32-i                                  G. C. Storey, Manager, B /R Fuel Engineiering Reviewed:                                 D*AY.f, Dii C'c ;.Fre/ rA PLC Date:
1 9._Plant Manager Date: Z L7, Date: "1-l "311 i U U EDMS: L32 120321 804 Nuclear Fuel Engineering  
W. R. Hayes, Manager, Reactor Engineering Approved:         ý               ýSL                         Date:          Z      L7, Chairman, PORC Approved:                                       1         9._  Date:   "1-l"311 i Plant Manager U                                                                                                               U
-BWRFE Date: March 21, 2012 N PG 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 12 (including review cover sheet)L is t o f T a b le s .................................................................................................................................................
 
iii L is t o f F ig u re s ...........................................................  
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE                                               Date:       March 21, 2012 N PG                                 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 12                               (including review cover sheet)
....................................................................................
Lis t of T a b le s .................................................................................................................................................             iii Lis t of F igu re s ...........................................................           .................................................................................... iv R e v is io n Lo g ...................................................................................................................................                             v Nom e n c la tu re ................................................................................................................................................               vi R e fe re n c e s ..................................................................................................................................................             v iii 1         Intro d u c tio n ..........................................................................................................................                             1 1 .1         Pu rp os e .........................................................................................................................                               1 1 .2       S c o pe ............................................................................................................................                               1 1 .3         F u e l Lo ad ing ..................................................................................................................                               1 1 .4       Ac ce pta b ility ..................................................................................................................                               1 2         Shutdown Margin Limit .................................................................................................                                                   3 Page ii Browns Ferry unit Unit 3 CyR(e 16 3 C~yde   16                                                                                                                                               Page ii Core Operating Limits Report, (105% OLTP)                                                                                                 TVA-COLR-BF3C16, Revision 0 (Final)
iv R e v is io n L o g ...................................................................................................................................
 
v N o m e n c la tu re ................................................................................................................................................
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE IM        NPG                    1101 Market Street, Chattanooga TN 37402 Date:      March 21, 2012 List of Tables Nuclear Fuel Types .......................................................................................................................         2 Browns Ferry Unit 3 Cycle 16                                                                                                                 Page iii Core Operatng Limits Report (105% OLTP)                                                                       TVA-COLR-BF3C16, Revision 0 (Final)
v i R e fe re n c e s ..................................................................................................................................................
 
v iii 1 In tro d u c tio n ..........................................................................................................................
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date:  March 21, 2012
1 1 .1 P u rp o s e .........................................................................................................................
[M NPG                          1101 Market Street, Chattanooga TN 37402 List of Figures None Browns Ferry Unit 3 Cycle 16                                                                               Page iv Core Operatlng Limits Report, (105% OLTP)                                         TVA-COLR-BF3C16, Revision 0 (Final)
1 1 .2 S c o p e ............................................................................................................................
 
1 1 .3 F u e l L o a d in g ..................................................................................................................
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date:  March 21, 2012 UT NPG                            1101 Market Street, Chattanooga TN 37402 Revision Log Number I           Page                                     Description 0-RO             All       New document Page v Ferry Unit Browns Fernm Unit 3 3 Cycle 16 Cyde 16                                                                                      Page v Core Operating Limits Report, (1105% OLTP)                                           TVA-COLR-BF3C1 6, Revision 0 (Final)
1 1 .4 A c ce p ta b ility ..................................................................................................................
 
1 2 Shutdown Margin Limit .................................................................................................
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 UT NPG                           1101 Market Street, Chattanooga TN 37402 Nomenclature               )
3 Browns Ferry unit 3 C~yde 16 Page ii Browns Ferry Unit 3 CyR(e 16 Core Operating Limits Report, (105% OLTP)Page ii TVA-COLR-BF3C16, Revision 0 (Final)
APLHGR               Average Planar LHGR APRM                  Average Power Range Monitor AREVA NP              Vendor (Framatome, Siemens)
EDMS: L32 120321 804 Date: March 21, 2012 IM NPG Nuclear Fuel Engineering  
BOG                    Beginning of Cycle BSP                    Backup Stability Protection BWR                    Boiling Water Reactor CAVEX                  Core Average Exposure CD                    Coast Down CMSS                  Core Monitoring System Software COLR                  Core Operating Limits Report CPR                    Critical Power Ratio CRWE                  Control Rod Withdrawal Error CSDM                  Cold SDM DIVOM                  Delta CPR over Initial CPR vs. Oscillation Magnitude EOC                    End of Cycle EOOS                  Equipment OOS FFTR                  Final Feedwater Temperature Reduction FFWTR                  Final Feedwater Temperature Reduction FHOOS                  Feedwater Heaters OOS ft                    Foot: english unit of measure for length GWd                    Giga Watt Day HTSP                  High TSP ICA                    Interim Corrective Action ICF                    Increased Core Flow (beyond rated)
-BWRFE 1101 Market Street, Chattanooga TN 37402 List of Tables Nuclear Fuel Types .......................................................................................................................
IS                    In-Service kW                     kilo watt: SI unit of measure for power.
2 Browns Ferry Unit 3 Cycle 16 Core Operatng Limits Report (105% OLTP)Page iii TVA-COLR-BF3C16, Revision 0 (Final)
LCO                   License Condition of Operation LFWH                  Loss of Feedwater Heating LHGRFAC                LHGR Multiplier (Power or Flow dependent)
EDMS: L32 120321 804[M NPG Nuclear Fuel Engineering  
LPRM                  Low Power Range Monitor LRNB                  Generator Load Reject, No Bypass MAPFAC                MAPLHGR multiplier (Power or Flow dependent)
-BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 21, 2012 List of Figures None Browns Ferry Unit 3 Cycle 16 Core Operatlng Limits Report, (105% OLTP)Page iv TVA-COLR-BF3C16, Revision 0 (Final)
MCPR                  Minimum CPR MSRV                  Moisture Separator Reheater Valve Browns Ferry Unit 3 Cyde 16                                                                                   Page vi Core Operating Limits Report, (105% OLTP)                                           TVA-COLR-BF3C16, Revision 0 (Final)
EDMS: L32 120321 804 UT NPG Nuclear Fuel Engineering  
 
-BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 21, 2012 Revision Log Number I Page Description 0-RO All New document Browns Ferry Unit 3 Cyde 16 Page v Browns Fernm Unit 3 Cycle 16 Core Operating Limits Report, (1105% OLTP)Page v TVA-COLR-BF3C1 6, Revision 0 (Final)
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE           Date: March 21, 2012 N                 1101 Market Street, Chattanooga TN 37402 MSRVOOS               MSRV OOS MTU                   Metric Ton Uranium MWd/MTU               Mega Watt Day per Metric Ton Uranium NEOC                   Near EOC NRC                   United States Nuclear Regulatory Commission NSS                   Nominal Scram Speed NTSP                   Nominal TSP OLMCPR                 MCPR Operating Limit OOS                   Out-Of-Service OPRM                   Oscillation Power Range Monitor OSS                   Optimum Scram Speed PBDA                   Period Based Detection Algorithm Pbypass               Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed PLU                   Power Load Unbalance PLUOOS                 PLU OOS PRNM                   Power Range Neutron Monitor RBM                   Rod Block Monitor RPS                   Reactor Protection System RPT                   Recirculation Pump Trip RPTOOS                 RPT OOS SDM                   Shutdown Margin SLMCPR                 MCPR Safety Limit SLO                   Single Loop Operation TBV                   Turbine Bypass Valve TBVIS                 TBV IS TBVOOS                 Turbine Bypass Valves OOS TIP                   Transversing In-core Probe TIPOOS                 TIP OOS TLO                   Two Loop Operation TSP                   Trip Setpoint TSSS                   Technical Specification Scram Speed TVA                   Tennessee Valley Authority Browns Ferry Unit 3 cycle 16                                                                               Page vii Core Operating Limits Report, (105% OLTP)                                         TVA-COLR-BF3C16, Revision 0 (Final)
EDMS: L32 120321 804 Date: March 21, 2012 UT NPG Nuclear Fuel Engineering
 
-BWRFE 1101 Market Street, Chattanooga TN 37402 Nomenclature
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE           Date: March 21, 2012 TN 37402 1101 Market Street, Chattanooga References
)APLHGR APRM AREVA NP BOG 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 OOS 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)In-Service kW kilo watt: SI unit of measure for power.LCO LFWH LHGRFAC LPRM LRNB MAPFAC MCPR MSRV License Condition of Operation Loss of Feedwater Heating LHGR Multiplier (Power or Flow dependent)
: 1.       BFE-3253, Revision 0, Browns Ferry Unit 3 Reload 15 Cycle 16 InCore Shuffle, Calculation File, Tennessee Valley Authority, February 2012.
Low Power Range Monitor Generator Load Reject, No Bypass MAPLHGR multiplier (Power or Flow dependent)
Methodology References
Minimum CPR Moisture Separator Reheater Valve Browns Ferry Unit 3 Cyde 16 Core Operating Limits Report, (105% OLTP)Page vi TVA-COLR-BF3C16, Revision 0 (Final)
: 2.       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.
EDMS: L32 120321 804 Nuclear Fuel Engineering  
: 3.       XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.
-BWRFE Date: March 21, 2012 N 1101 Market Street, Chattanooga TN 37402 MSRVOOS MSRV OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit OOS Out-Of-Service OPRM Oscillation Power Range Monitor OSS Optimum Scram Speed PBDA Period Based Detection Algorithm Pbypass Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed PLU Power Load Unbalance PLUOOS PLU OOS PRNM Power Range Neutron Monitor RBM Rod Block Monitor RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority Browns Ferry Unit 3 cycle 16 Page vii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)
: 4.       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.
EDMS: L32 120321 804 Nuclear Fuel Engineering  
: 5.       ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
-BWRFE Date: March 21, 2012 1101 Market Street, Chattanooga TN 37402 References
: 6.       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.
: 1. BFE-3253, Revision 0, Browns Ferry Unit 3 Reload 15 Cycle 16 InCore Shuffle, Calculation File, Tennessee Valley Authority, February 2012.Methodology References
: 7.       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.
: 2. XN-NF-81-58(P)(A)
: 8.       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.
Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.3. XN-NF-85-67(P)(A)
: 9.       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.
Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.4. EMF-85-74(P)
: 10.       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.
Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.5. ANF-89-98(P)(A)
: 11.       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.
Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.6. XN-NF-80-19(P)(A)
: 12.       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.
Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors -Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.7. XN-NF-80-19(P)(A)
: 13.       ANF-1358(P)(A) Revision 1, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.
Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors:
Browns Ferry Unit 3 Cycle 16                                                                               Page viii Core Operating Limits Report, (105% OLTP)                                         TVA-COLR-BF3C16, Revision 0 (Final)
Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.8. EMF-2158(P)(A)
 
Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date:  March 21, 2012
Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.9. XN-NF-80-19(P)(A)
[M NPG                        1101 Market Street, Chattanooga TN 37402
Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.10. XN-NF-84-105(P)(A)
: 14.       EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, Siemens Power Corporation, September 2009.
Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T:
: 15.       EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001.
A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.11. ANF-524(P)(A)
: 16.       EMF-2292(P)(A) Revision 0, ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.12. ANF-913(P)(A)
: 17.       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.
Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2:
: 18.       BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, Framatome ANP, Inc., May, 2008.
A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.13. ANF-1358(P)(A)
Page ix Bru~nsFenyUnit3Cyde16 Browns Ferry Unit 3 Cycle 16                                                                                 Page ix Core Operating Limits Report, 0105% OLTP)
Revision 1, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)Page viii TVA-COLR-BF3C16, Revision 0 (Final)
TVA-COLR-BF3C16, Re\Asion 0 (Final)
EDMS: L32 120321 804[M NPG Nuclear Fuel Engineering  
 
-BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 21, 2012 14. EMF-2209(P)(A)
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 EIM!lNPG                       1101 Market Street, Chattanooga TN 37402 1     Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.
Revision 3, SPCB Critical Power Correlation, Siemens Power Corporation, September 2009.15. EMF-2361(P)(A)
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.
Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001.16. EMF-2292(P)(A)
1.2     Scope This version of the COLR is specifically intended to support the refueling outage. Consequently, this document only covers MODE 5 operation of the unit. Operation outside MODE 5 will be addressed in a future COLR revision. This document will discuss the following areas:
Revision 0, ATRIUMTM-10:
    >     Shutdown Margin (SDM) Limit (Technical Specification 3.1.1) 1.3 Fuel Loading The core will contain all AREVA NP, Inc., ATRIUM-10 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented in Reference 1.
Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.17. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis:
1.4     Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 2 through 18.
Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.18. BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, Framatome ANP, Inc., May, 2008.Bru~nsFenyUnit3Cyde16 Page ix Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, 0105% OLTP)Page ix TVA-COLR-BF3C16, Re\Asion 0 (Final)
Page 1 Browns Feny Browns      Unit 3 Ferry Unit   cyRle 16 3 Cyde 16                                                                                 Page 1 Core operating Limits Report, (105% OLTP)
EDMS: L32 120321 804 Date: March 21, 2012 EIM!lNPG Nuclear Fuel Engineering
TVA-C0LR-BF3C16, Revision 0 (Final)
-BWRFE 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 version of the COLR is specifically intended to support the refueling outage. Consequently, this document only covers MODE 5 operation of the unit. Operation outside MODE 5 will be addressed in a future COLR revision.
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date:    March 21, 2012 IM        NPG                          1101 Market Street, Chattanooga TN 37402 Table 1.1       Nuclear Fuel Types Nuclear Original       Number of           Fuel Type             Fuel Names Fuel Description                               Cycle         Assemblies             (NFT)               (Range)
This document will discuss the following areas:> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)1.3 Fuel Loading The core will contain all AREVA NP, Inc., ATRIUM-10 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented in Reference 1.1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 2 through 18.Browns Feny Unit 3 Cyde 16 Page 1 Browns Ferry Unit 3 cyRle 16 Core operating Limits Report, (105% OLTP)Page 1 TVA-C0LR-BF3C16, Revision 0 (Final)
ATRIUM-10 A10-4218B-15GV80-FCC                                       14               108               4             FCC001-FCC216 ATRIUM-10 A10-4218B-13GV80-FCC                                       14               72                 5             FCC219-FCC290 ATRIUM-10 A10-3831B-15GV80-FCD                                       15               200                 6             FCDO01-FCD200 ATRIUM-10 A10-3403B-9GV80-FCD                                         15               20                 7             FCD257-FCB276 ATRIUM-10 A10-3392B-10GV80-FCD                                       15               34                 8             FCD221-FCB256 ATRIUM-10 A104218B-15GV80-FCC                                         15                 2                 9             FCC217-FCC218 ATRIUM-10 AIO-4218B-13GV80-FCC                                       15                 4                 10             FCC307-FCC310 ATRIUM-10 A10-3757B-10GV80-FCC                                       15               40                 11             FCC335-FCC374 ATRIUM-10 A10-3440B-11GV80-FCE                                       16               144               12             FCE001-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 The table identifies the expected fuel type breakdown inanticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified inthis document.
EDMS: L32 120321 804 IM NPG Nuclear Fuel Engineering  
Browns Feny Unit 3 Cyde 16                                                                                                               Page 2 Core Operating Limits Report, (105% OLTP)                                                                   TVA-COLR-BF3C16, Revision 0 (Final)
-BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 21, 2012 Table 1.1 Nuclear Fuel Types Nuclear Original Number of Fuel Type Fuel Names Fuel Description Cycle Assemblies (NFT) (Range)ATRIUM-10 A10-4218B-15GV80-FCC 14 108 4 FCC001-FCC216 ATRIUM-10 A10-4218B-13GV80-FCC 14 72 5 FCC219-FCC290 ATRIUM-10 A10-3831B-15GV80-FCD 15 200 6 FCDO01-FCD200 ATRIUM-10 A10-3403B-9GV80-FCD 15 20 7 FCD257-FCB276 ATRIUM-10 A10-3392B-10GV80-FCD 15 34 8 FCD221-FCB256 ATRIUM-10 A104218B-15GV80-FCC 15 2 9 FCC217-FCC218 ATRIUM-10 AIO-4218B-13GV80-FCC 15 4 10 FCC307-FCC310 ATRIUM-10 A10-3757B-10GV80-FCC 15 40 11 FCC335-FCC374 ATRIUM-10 A10-3440B-11GV80-FCE 16 144 12 FCE001-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 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 Feny Unit 3 Cyde 16 Core Operating Limits Report, (105% OLTP)Page 2 TVA-COLR-BF3C16, Revision 0 (Final)
EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date:  March 21, 2012 1101 Market Street, Chattanooga TN 37402 2     Shutdown Margin Limit (Technical Specification 3.1.1)
EDMS: L32 120321 804 Nuclear Fuel Engineering  
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:
-BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 21, 2012 2 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 Fern'y Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)Page 3 TVA-COLR-BF3C16, Revision 0 (Final)}}
SDM     > 0.38% dk/k Browns Fern'y Unit 3 Cycle 16                                                                               Page 3 Core Operating Limits Report, (105% OLTP)                                         TVA-COLR-BF3C16, Revision 0 (Final)}}

Latest revision as of 06:08, 12 November 2019

Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation
ML12102A141
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 04/09/2012
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF3C16
Download: ML12102A141 (15)
v • d • e


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 April 9, 2012 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 3 Cycle 16, Core Operating Limits Report (COLR), Revision 0. This Unit 3 COLR was issued as an interim measure to include Shutdown Margin Limit in support of fuel loading for Cycle 16 (Mode 5 operation). A revision to the COLR will be issued prior to Cycle 16 startup covering all licensed power levels of operation (Modes 1 through 5).

There are no new commitments contained in this letter. If you have any questions please contact Tom Hess at (423) 751-3487.

JRes e ully, J. . Shea M ager, Corporate Nuclear Licensing

Enclosure:

Core Operating Limits Report, (105% OLTP), for Cycle 16 Operation TVA-COLR-BF3C16, Revision 0 cc: See Page 2 Printed on r.cycled paper

U.S. Nuclear Regulatory Commission Page 2 April 9, 2012 cc: (w/ Enclosure)

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

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 16 Operation TVA-COLR-BF3CI6, Revision 0 (See Attached)

U U EDMS L32 120321 804 QA Document Pages Affected: All BFE-3238, Revision 0 EMNPG Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 16 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF3CI 6 Revision 0 (Final)

(Revision Log, Page v)

March 2012 Prepared:6"1T..W. Eichenberg, Sr. Spe~list Date: I z - t "-.t-L Verified: Date: 3/22 12-B. chell, Engineer Approved: ( "/ 7 V v / Date: 32-i G. C. Storey, Manager, B /R Fuel Engineiering Reviewed: D*AY.f, Dii C'c ;.Fre/ rA PLC Date:

W. R. Hayes, Manager, Reactor Engineering Approved: ý ýSL Date: Z L7, Chairman, PORC Approved: 1 9._ Date: "1-l"311 i Plant Manager U U

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 N PG 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 12 (including review cover sheet)

Lis t of T a b le s ................................................................................................................................................. iii Lis t of F igu re s ........................................................... .................................................................................... iv R e v is io n Lo g ................................................................................................................................... v Nom e n c la tu re ................................................................................................................................................ vi R e fe re n c e s .................................................................................................................................................. v iii 1 Intro d u c tio n .......................................................................................................................... 1 1 .1 Pu rp os e ......................................................................................................................... 1 1 .2 S c o pe ............................................................................................................................ 1 1 .3 F u e l Lo ad ing .................................................................................................................. 1 1 .4 Ac ce pta b ility .................................................................................................................. 1 2 Shutdown Margin Limit ................................................................................................. 3 Page ii Browns Ferry unit Unit 3 CyR(e 16 3 C~yde 16 Page ii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE IM NPG 1101 Market Street, Chattanooga TN 37402 Date: March 21, 2012 List of Tables Nuclear Fuel Types ....................................................................................................................... 2 Browns Ferry Unit 3 Cycle 16 Page iii Core Operatng Limits Report (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012

[M NPG 1101 Market Street, Chattanooga TN 37402 List of Figures None Browns Ferry Unit 3 Cycle 16 Page iv Core Operatlng Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 UT NPG 1101 Market Street, Chattanooga TN 37402 Revision Log Number I Page Description 0-RO All New document Page v Ferry Unit Browns Fernm Unit 3 3 Cycle 16 Cyde 16 Page v Core Operating Limits Report, (1105% OLTP) TVA-COLR-BF3C1 6, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 UT NPG 1101 Market Street, Chattanooga TN 37402 Nomenclature )

APLHGR Average Planar LHGR APRM Average Power Range Monitor AREVA NP Vendor (Framatome, Siemens)

BOG Beginning of Cycle BSP Backup Stability Protection BWR Boiling Water Reactor CAVEX Core Average Exposure CD Coast Down CMSS Core Monitoring System Software COLR Core Operating Limits Report CPR Critical Power Ratio CRWE Control Rod Withdrawal Error CSDM Cold SDM DIVOM Delta CPR over Initial CPR vs. Oscillation Magnitude EOC End of Cycle EOOS Equipment OOS FFTR Final Feedwater Temperature Reduction FFWTR Final Feedwater Temperature Reduction FHOOS Feedwater Heaters OOS ft Foot: english unit of measure for length GWd Giga Watt Day HTSP High TSP ICA Interim Corrective Action ICF Increased Core Flow (beyond rated)

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

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

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

MCPR Minimum CPR MSRV Moisture Separator Reheater Valve Browns Ferry Unit 3 Cyde 16 Page vi Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 N 1101 Market Street, Chattanooga TN 37402 MSRVOOS MSRV OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit OOS Out-Of-Service OPRM Oscillation Power Range Monitor OSS Optimum Scram Speed PBDA Period Based Detection Algorithm Pbypass Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed PLU Power Load Unbalance PLUOOS PLU OOS PRNM Power Range Neutron Monitor RBM Rod Block Monitor RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority Browns Ferry Unit 3 cycle 16 Page vii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 TN 37402 1101 Market Street, Chattanooga References

1. BFE-3253, Revision 0, Browns Ferry Unit 3 Reload 15 Cycle 16 InCore Shuffle, Calculation File, Tennessee Valley Authority, February 2012.

Methodology References

2. 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.
3. XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.
4. 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.
5. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
6. 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.
7. 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.
8. 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.
9. 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.
10. 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.
11. 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.
12. 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.
13. ANF-1358(P)(A) Revision 1, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.

Browns Ferry Unit 3 Cycle 16 Page viii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012

[M NPG 1101 Market Street, Chattanooga TN 37402

14. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, Siemens Power Corporation, September 2009.
15. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001.
16. EMF-2292(P)(A) Revision 0, ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
17. 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.
18. BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, Framatome ANP, Inc., May, 2008.

Page ix Bru~nsFenyUnit3Cyde16 Browns Ferry Unit 3 Cycle 16 Page ix Core Operating Limits Report, 0105% OLTP)

TVA-COLR-BF3C16, Re\Asion 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 EIM!lNPG 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 version of the COLR is specifically intended to support the refueling outage. Consequently, this document only covers MODE 5 operation of the unit. Operation outside MODE 5 will be addressed in a future COLR revision. This document will discuss the following areas:

> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1) 1.3 Fuel Loading The core will contain all AREVA NP, Inc., ATRIUM-10 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented in Reference 1.

1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 2 through 18.

Page 1 Browns Feny Browns Unit 3 Ferry Unit cyRle 16 3 Cyde 16 Page 1 Core operating Limits Report, (105% OLTP)

TVA-C0LR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 IM NPG 1101 Market Street, Chattanooga TN 37402 Table 1.1 Nuclear Fuel Types Nuclear Original Number of Fuel Type Fuel Names Fuel Description Cycle Assemblies (NFT) (Range)

ATRIUM-10 A10-4218B-15GV80-FCC 14 108 4 FCC001-FCC216 ATRIUM-10 A10-4218B-13GV80-FCC 14 72 5 FCC219-FCC290 ATRIUM-10 A10-3831B-15GV80-FCD 15 200 6 FCDO01-FCD200 ATRIUM-10 A10-3403B-9GV80-FCD 15 20 7 FCD257-FCB276 ATRIUM-10 A10-3392B-10GV80-FCD 15 34 8 FCD221-FCB256 ATRIUM-10 A104218B-15GV80-FCC 15 2 9 FCC217-FCC218 ATRIUM-10 AIO-4218B-13GV80-FCC 15 4 10 FCC307-FCC310 ATRIUM-10 A10-3757B-10GV80-FCC 15 40 11 FCC335-FCC374 ATRIUM-10 A10-3440B-11GV80-FCE 16 144 12 FCE001-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 The table identifies the expected fuel type breakdown inanticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified inthis document.

Browns Feny Unit 3 Cyde 16 Page 2 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

EDMS: L32 120321 804 Nuclear Fuel Engineering - BWRFE Date: March 21, 2012 1101 Market Street, Chattanooga TN 37402 2 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 Fern'y Unit 3 Cycle 16 Page 3 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF3C16, Revision 0 (Final)

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