ML12102A141

Core Operating Limits Report to Support Fuel Loading for Cycle 16 Operation

ML12102A141
Person / Time
Site:	Browns Ferry
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)

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)