ML12299A252

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Core Operating Limits Report for Cycle 10 Operation
ML12299A252
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 10/22/2012
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12299A252 (53)
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Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 October 22, 2012 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259

Subject:

Browns Ferry Nuclear Plant, Unit I Core Operating Limits Report for Cycle 10 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 1 Cycle 10, Core Operating Limits Report (COLR), Revision 0. Revision 0 of the Unit 1, Cycle 10, COLR includes all modes of operation (Modes 1 through 5).

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

Respec y,

J.

.Shea President, Nuclear Licensing

Enclosure:

Core Operating Limits Report, (105% OLTP), for Cycle 10 Operation TVA-COLR-BF1C10, Revision 0 cc: (w/ Enclosure)

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

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit I Core Operating Limits Report, (105% OLTP), for Cycle 10 Operation TVA-COLR-BFlCl0, Revision 0 (See Attached)

EDMS L32 121004 800 QA Document Pages Affected: All BFE-3355, Revision 0 92NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 1 Cycle 10 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BFICIO Revision 0 (Final)

(Revision Log, Page v)

October 2012 Prepared:

~9 T. W. Eichenberg, Sr."pecialist B. C. Mitchell, Engineer Verified:

Approved:

Date:

/0)3

/

Date: /'*//2 Date:.

m G. C. Storey, M, Reviewed:_

W. R. Hayes, Manger, Reactor Engineeri Approved:

Date:

/O-!*(t ng Date:

\\ © Date:

M/19 I'

z h*

n ORC Approved:

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 N PG.

1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 51 (including review cover sheet)

L is t o f T a b le s.................................................................................................................................................

iii L ist o f F ig u re s................................................................................................................................................

iv R e v isio n L o g...................................................................................................................................

v N o m e n c la tu re................................................................................................................................................

v i R e fe re n c e s..................................................................................................................................................

v iii 1

In tro d u ctio n........................................................................................................................

1 1 1.1 P u rp o s e.......................................................................................................................

1 1 1.2 S c o p e..........................................................................................................................

1 1 1.3 F u e l L o a d in g................................................................................................................

1 1 1.4 A cce p ta b ility................................................................................................................

1 1 2

APLHGR Limits..................................................................................................................

13 2.1 Rated Power and Flow Limit: APLHGRRATED.........................................................

13 2.2 Off-Rated Power Dependent Limit: APLHGRp.......................................................

13 2.2.1 Startup without Feedwater Heaters................................................................

13 2.3 Off-Rated Flow Dependent Limit: APLHGRF.........................................................

13 2.4 Single Loop Operation Limit: APLHGRSLO..............................................................

13 2.5 Equipment Out-Of-Service Corrections..................................................................

16 3

L H G R L im its.......................................................................................................................

1 7 3.1 Rated Power and Flow Limit: LHGRRATEO..............................................................

17 3.2 Off-Rated Power Dependent Limit: LHGRp............................................................

17 3.2.1 Startup without Feedwater Heaters................................................................

17 3.3 Off-Rated Flow Dependent Limit: LHGRF..............................................................

18 3.4 Single Loop Operation Limit: LHGRSLO..................................................................

18 3.5 Equipment Out-Of-Service Corrections..................................................................

18 4

OLMCPR Limits.................................................................................................................

29 4.1 Flow Dependent MCPR Limit: MCPRF....................................

29 4.2 Power Dependent MCPR Limit: MCPRp................................................................

29 4.2.1 Startup without Feedwater Heaters................................................................

29 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)............................ 30 4.2.3 Exposure Dependent Limits...........................................................................

30 4.2.4 Equipment Out-Of-Service (EOOS) Options..................................................

31 4.2.5 Single-Loop-Operation (SLO) Limits.............................................................

31 4.2.6 Below Pbypass Limits....................................................................................

31 5

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

47 6

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

48 7

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

49 8

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

51 BrewnsO Ferrn Unit 1 CyRoe 10 Core operating Limits Report, (105% OLTP)

Page ii TVA-COLR-BFI C10, ReAsion 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 N PG 1101 Market Street, Chattanooga TN 37402 List of Tables N ucle a r F ue l T ype s.....................................................................................................................

12 Startup Feedwater Temperature Basis..................................................................................

17 N om inal Scram Tim e Basis....................................................................................................

30 MCPRp Limits for Optimum Scram Time Basis: ATRIUM-10................................................

33 MCPRp Limits for Optimum Scram Time Basis: GE 14............................

34 MCPRp Limits for ATRIUM-10: Nominal Scram Time Basis................................................

35 MCPRp Limits for GE 14: Nominal Scram Time Basis.........................................................

37 MCPRp Limits for ATRIUM-10: Technical Specification Scram Time Basis......................... 39 MCPRp Limits for GE 14: Technical Specification Scram Time Basis...................................

41 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1 for ATRIUM-10: Technical Specification Scram Tim e Basis.............................................................................................

43 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1 for GE 14: Technical Specification Scram Tim e Basis.............................................................................................

44 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2 for ATRIUM-10: Technical Specification Scram Tim e Basis.............................................................................................

45 Startup Operation MCPRp Limits for Table 3.1 Temperature Range :2 for GE 14: Technical Specification Scram Tim e Basis.............................................................................................

46 O P R M S etpoint R ange...............................................................................................................

4 7 A nalytical R BM Trip Setpoints...............................................................................................

49 R BM Setpoint A pplicability....................................................................................................

49 Control Rod Withdrawal Error Results....................................................................................

50 Browns Ferry Unit 1 Cycle 10 Core Operating Limits Report, (105% OLTP)

Page iii TVA-COLR-BF1 C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 N PG 1101 Market Street, Chattanooga TN 37402 List of Figures APLHG RRATED for ATR IUM -10 Fuel........................................................................................

14 A PLH G RR ATED for G E 14 Fuel.................................................................................................

15 LHG RRATED for ATR IUM -10 Fuel............................................................................................

19 LH G R RATED for G E14 U 0 2 Fuel...............................................................................................

20 Base Operation LHGRFACp for ATRIUM-10 Fuel..................................................................

21 Base Operation LHGRFACp for GE 14 Fuel...........................................................................

22 LHG RFACF for ATR IUM -10 Fuel..........................................................................................

23 LH G R FA CF for G E 14 Fuel....................................................................................................

24 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 1......

25 Startup Operation LHGRFACp for ATRIUM-10 Fuel: Table 3.1 Temperature Range 2......

26 Startup Operation LHGRFACp for GE 14 Fuel:

Table 3.1 Temperature Range 1.............. 27 Startup Operation LHGRFACp for GE 14 Fuel:

Table 3.1 Temperature Range 2........

28 M CPRF for G E 14 and ATRIUM-10 Fuel................................................................................

32 Browns Ferry Unit 1 Cycle 10 Core Operating Umits Report (105% OLTP)

Page iv TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Revision Log Number I Page Description O-RO All New document.

Browns Ferry Unit 1 Cycle 10 Core Operating Limits Report, (105% OLTP)

Page v "VA-COLR-BF1CI0, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIM iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Nomenclature APLHGR APRM AREVA NP Average Planar LHGR Average Power Range Monitor Vendor (Framatome, Siemens)

Beginning of Cycle, Backup Stability Protection Boiling Water Reactor BOC BSP BWR CAVEX CD CMSS COLR CPR CRWE CSDM DIVOM EOC EOCLB EOOS FFTR FFWTR FHOOS ft GNF GWd HTSP ICA ICF IS kW Core Average Exposure Coast Down Core Monitoring System Software Core Operating Limits Report Critical Power Ratio Control Rod Withdrawal Error Cold SDM Delta CPR over Initial CPR vs. Oscillation Magnitude End of Cycle End-of-Cycle Licensing Basis Equipment OOS Final Feedwater Temperature Reduction Final Feedwater Temperature Reduction Feedwater Heaters OOS Foot: english unit of measure for length Vendor (General Electric, Global Nuclear Fuels)

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

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

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

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

Browns Fery Unit 1 Cycle 10 Core operating Limits Report, (105% OLTP)

Page vi TVA-COLR-BF1CIO, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 NPG 1101 Market Street, Chattanooga TN 37402 MCPR Minimum CPR MSRV Moisture Separator Reheater Valve MSRVOOS MSRV OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit OOS Out-Of-Service OPRM Oscillation Power Range Monitor OSS Optimum Scram Speed PBDA Period Based Detection Algorithm Pbypass Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed PLU Power Load Unbalance PLUOOS PLU OOS PRNM Power Range Neutron Monitor RBM Rod Block Monitor RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS 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 Bmwns Ferry Unit 1 Cyde 10 Page vii Browns Ferry Unit 1 cycle 10 Core operating Limits Report, (105% OLTP)

Page A TVA-COLR-BF1 C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 a PG 1101 Market Street, Chattanooga TN 37402 References

1.

ANP-3123, Revision 0, Browns Ferry Unit I Cycle 10 Reload Safety Report, AREVA NP, Inc., August, 2012.

2.

0000-0113-6833-SRLR, Revision 1, Supplemental Reload Licensing Report Browns Ferry 1 Reload 8 Cycle 9, Global Nuclear Fuels, Inc., November 2010.

3.

0000-0113-6833-FBIR, Revision 0, Fuel Bundle Information Report Browns Ferry 1Reload 8 Cycle 9, Global Nuclear Fuels, Inc., September 2010.

4.

ANP-2628(P), Rev. 0, Mechanical Design Report for Browns Ferry Units 1, 2, and 3 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., October 2011.

5.

ANP-3064(P) Revision 0, Browns Ferry Unit 1 Cycle 10 Plant Parameters Document, AREVA NP, Inc., June 2012.

6.

BFE-3352, Revision 0, Browns Ferry Unit 1 Cycle 10 Calculation File: Unit 1 Reload 9 Shuffle, Tennessee Valley Authority, September 05, 2012.

Methodology References

7.

NEDE-2401 1-P-A-1 6, General Electric Standard Application for Reactor Fuel, October 2007.

8.

NEDE-2401 1-P-A-1 6-US, General Electric Standard Application for Reactor Fuel (Supplement for United States), October 2007.

9.

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.

10.

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

11.

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.

12.

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

13.

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.

14.

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.

15.

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.

Browns Ferry Una 1 Cycle 10 Core operating Limits Report (105% OLTP)

Page viii TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 1101 Market Street, Chattanooga TN 37402

16.

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.

17.

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.

18.

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.

19.

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.

20.

ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 2005.

21.

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

September 2009.

22.

EMF-2245(P)(A) Revision 0 Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.

23.

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 April 27, 2012.

24.

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

25.

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.

26.

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

PRNM Setpoint References

27.

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.

28.

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.

29.

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

Brona s Feny Unit 1 Cycle 10 Page ix Core Operating Umits Report (105% OLTP)

[VA-COLR-BFlCl0, Revision 0 (Final)

EDMS: L32 121004 800 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012

30.

NEDC-32433P, Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3, GE Nuclear Energy, April 1995.

Browns Fery Unit 1 Cyde 10 Core Operating Limits Report, (105% OLTP)

Page x TVA-COLR-BF1CIO, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 NPG 1101 Market Street, Chattanooga TN 37402 1 Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

1.1 Purpose The primary purpose of this document is to satisfy requirements identified by unit technical specification section 5.6.5. This document may be provided, upon final approval, to the NRC.

1.2 Scope This document will discuss the following areas:

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

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

> Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

> Oscillation Power Range Monitor (OPRM) Setpoint (Technical Specification Table 3.3.1.1)

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

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

> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1) 1.3 Fuel Loading The core will contain previously exposed GNF GE14 fuel, and fresh AREVA NP, Inc., ATRIUM-10 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented in Reference 6.

1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 7 through 26.

BrownsFenyUnitl CydelO Page 11 Browns Ferrn Unit I CycCe 10 Core operating Lrimb Report, (105%* OLTP )

Page 11 TVA-C0LR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIM NPG Reactor Engineering and Fuels - BWRFE 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)

GE14-PI0DNAB406-16GZ-10OT-150-T6-3078 8

40 14 JYE101-JYE148 GE14-P1ODNAB400-17GZ-10OT-150-T6-3081 8

64 15 JYE149-JYE244 GE14-P10DNAB406-15GZ-10OT-150-T6-3079 8

49 16 JYE245-JYE308 GE14-P10DNAB417-16GZ-10OT-150-T6-3082 8

32 17 JYE309-JYE356 GE14-PIODNAB418-16GZ-I0OT-150-T6-3080 8

48 18 JYE357-JYE428 GE14-Pi0DNAB408-16GZ-10OT-150-T6-3363 9

179 1

JYPl01-JYP280 GE14-P10DNAB412-16GZ-10OT-150-T6-3364 9

40 2

JYP281 -JYP320 GE1 4-P10DNAB404-15GZ-1 GOT-1 50-T6-3365 9

16 8

JYP321 -JYP336 GE1 4-P1 0DNAB408-17GZ-1 0OT-1 50-T6-3366 9

16 19 JYP337-JYP352 ATRIUM-10 A10-3562B-14GV80-FAA 10 168 20 FAA001-FAA168 ATRIUM-10 A10-3676B-10GV80-FAA 10 24 21 FAA169-FAA192 ATRIUM-10 A10-4111 B-15GV80-FAA 10 88 22 FAA193-FAA280 The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified in this document.

Browns Ferry Unit 1 Cycle 10 Core Operating ULmits Report (105% OLTP)

Page 12 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 1101 Market Street, Chattanooga TN 37402 2 APLHGR Limits (Technical Specifications 3.2.1 & 3.7.5)

The APLHGR limit is determined by adjusting the rated power APLHIGR 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

  • MAPFACpJ APLHGRF off-rated flow APLHGR limit

[APLHGRPATED* MAPFACF]

APLHGRSLO SLO APLHGR limit

[APLHGRRATED* SLO Multiplier]

2.1 Rated Power and Flow Limit: APLHGRRATED The rated conditions APLHGR for ATRIUM-1 0 fuel is identified in Reference 1 and shown in Figure 2.1; for GE 14 fuel is identified in Reference 2, and shown in Figure 2.2.

2.2 Off-Rated Power Dependent Limit: APLHGRp Reference 1, for both GE14 and ATRIUM-10 fuel, does not specify a power dependent APLHGR. Therefore, MAPFACp is set to a value of 1.0.

2.2.1 Startup without 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 GE14 and ATRIUM-10 fuel, does not specify a flow dependent APLHGR.

Therefore, MAPFACF is set to a value of 1.0.

2.4 Single Loop Operation Limit: APLHGRSLO The single loop operation multiplier for ATRIUM-1 0 fuel is 0.85, per Reference 1; for GE 14 fuel the multiplier is 0.93 per Reference 2.

Browns Ferry Unit 1 Cyyde 10 Core Operating Umrits Report (105% OLTP)

Page 13 TVA-COLR-BF1 C10, Revision 0 (Final)

EDMS: L32 121004 800

~IUNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 15 12 C,

0.,*6 3

0 0

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

APLHGR Exposure Limit (GVidIMTtU)

(kWA) 0.0 12.5 15.0 12.5 67.0 7.3 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Browns Ferry Unit 1 Cycle 10 Core Operating Umits Report, (105% OLTP)

Page 14 TVA-COLR-BF1 Cl0, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012

~IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 15 12 I9 C,

<J a.,<6 3

0 0

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

APLHGR Exposure Limit

-(GWdIMTU)

(kWIft) 0.00 12.82 21.09 12.82 63.50 8.00 70.00 5.00 Figure 2.2 APLHGRRATEDfor GE 14 Fuel Browns Ferry Unit 1 Cycle 10 Core Operating Limits Report, (105% OLTP)

Page 15 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800

[M NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 2.5 Equipment Out-Of-Service Corrections The limits shown in Figure 2.1 and Figure 2.2 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.

In-Service RPTOOS TBVOOS PLUOOS FHOOS (or FFWTR)

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

All equipment service conditions assume 1 SRVOOS.

Browns Ferry Unit 1 Cyde 10 Core Operating Umits Report (105% OLTP)

Page 16 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 flMINPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 3

LHGR Limits (Technical Specification 3.2.3, 3.3.4.1, & 3.7.5)

The LHGR limit is determined by adjusting the rated power LHGR limit for off-rated power and off-rated flow conditions. The most limiting of these is then used as follows:

LHGR limit = MIN (LHGRp, LHGRF) where:

LHGRp LHGRF LHGRSLO off-rated power LHGR limit off-rated flow LHGR limit SLO LHGR limit

[LHGRRATED

  • LHGRFACp]

[LHGRRATED

  • LHGRFACF]

[LHGRpATED

  • SLO Multiplier]

3.1 Rated Power and Flow Limit: LHGRRATED The rated conditions LHGR for ATRIUM-10 fuel is identified in Reference 1 and shown in Figure 3.1 ;r for GE 14 fuel, is identified in Reference 3, and shown in Figure 3.2 for U02 fuel. Separate, concentration dependent limits apply for rods containing Gadolinium; LHGR limits are provided in Reference 3.

3.2 Off-Rated Power Dependent Limit: LHGRp LHGR limits are adjusted for off-rated power conditions using the LHGRFACp multiplier provided in Reference 1, for both ATRIUM-10 and GE 14 fuel. The multiplier is split into two sub cases: turbine bypass valves in and out-of-service. The multipliers are shown in Figure 3.3 and Figure 3.4.

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 3.7 and Figure 3.8, based on temperature conditions identified in Table 3.1.

Table 3.1 Startup Feedwater Temperature Basis Temperature 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 Ferry Unit 1 Cycle 10 Core Operating Umits Report, (105% OLTP)

Page 17 TVA-COLR-BFI CIO, Revision 0 (Final)

EDMS: L32 121004 800

[D NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 3.3 Off-Rated Flow Dependent Limit: LHGRF LHGR limits are adjusted for off-rated flow conditions using the LHGRFACF multiplier provided in Reference 1, for both ATRIUM-10 and GE 14 fuel. Multiplier are shown in Figure 3.5 and Figure 3.6.

3.4 Single Loop Operation Limit: LHGRSLO The single loop operation multiplier is 0.93, per Reference 2 for GE 14 fuel. There is no single loop operation restriction for ATRIUM-1 0; therefore the multiplier is 1.0.

3.5 Equipment Out-Of-Service Corrections The limits shown in Figure 3.1 and Figure 3.2 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*

In-Service RPTOOS TBVOOS PLUOOS FHOOS (or FFWTR)

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 3.3 and Figure 3.4 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 flow corrections shown in Figure 3.5 and Figure 3.6 are bounding for all EOOS conditions.

Off-rated power corrections shown in Figure 3.7 through Figure 3.10 are also dependent on operation of the Turbine Bypass Valve system. In this case, limits support FHOOS operation during startup. These limits have no dependency on RPTOOS, PLUOOS, or SLO.

All equipment service conditions assume 1 SRVOOS.

Brownm Fey Unit 1 Cycle 10 Core Operating Limits Report. (105% OLTP)

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[U ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 15 12

-9 C,.

-j6 3

0 0

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

(W_.t 0.0 13.4 18.9 13.4 74.4 7.1 Figure 3.1 LHGRRATED for ATRIUM-10 Fuel Browns Ferry Unit 1 Cycle 10 Cote Operating Limits Report, (105% OLTP)

Page 19 TVA-COLR-BF1C10, Revision 0 (Final)

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[M IiNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 15 12

-9

-j 6 3

0 0

20 40 60 80 Pellet Exposure (GWd/MTU)

Pellet LHGR Exposure Limit (GWdiMTU)

(kW/ft) 0.00 13.40 16.00 13.40 55.50 8.80 63.50 7.10 70.00 5.00 Figure 3.2 LHGRRATED for GE14 U0 2 Fuel Browns Ferry Unit 1 Cyde 10 Core Operating Umits Report, (105% OLTP)

Page 20 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 0.

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

Turbine Bypass In-Service Core Power LHGRFACp

(% Rated) 100.0 100 65.0 0.77 30.0 0.61 Core Flow > 50% Rated 30.0

[

0.48 25.0

[

044 Core Flow _ 50% Rated 30.0

[

0.51 25.0 0.47 Turbine Bypass Out-af-Service Core Power LHGRFACp

(% Rated) 100.0 0.88 65.0 0.73 30.0 0.61 Core Flow > 50% Rated 30.0 0.41 25.0 0.36 Core Flow!_ 5N% Rated 30.0 0.49 25.0 0.43 Figure 3.3 Base Operation LHGRFACp for ATRIUM-10 Fuel (Independent of other EOOS conditions)

Bivwns Feny Unit 1 Cyde 10 Page 21 Browns Ferry Unit I Cycle 10 Core operating Limits Report, (105% OLTP)

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~ImNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 a.

C.,

"-J 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine Bypas Valve In-Service, TBVIS Turbine Bypass Valve Out-of-Service, TBVOOS TBVIS, < 50% Core Flow I

I TBVOOS,

  • 50% Core Flow I

I A

TBVOOS, > 50% Core Flow

-L I

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

Turbine Bypass In-Service Core Power LHGRFACp

(% fited) 100.0 0.99 75.0 0.78 30.0 0.54 Core Flow > 50% Rated 30.0 T 0.43 25.0 0.40 Core Flow!; 50% Rated 30.0 I

0.7 25.0 0.43 Turbine Bypass Out-of-Service Core Power LHGRFACp j% Rated) 100.0 0.96 75.0 0.76 30.0 0.54 Core Flow > 50% Rated 30.0 0.37 25.0 0.31 Core Flow!; 50% Rated 3M T-0.46 25.0 0.39 Figure 3.4 Base Operation LHGRFACp for GE 14 Fuel (Independent of other EOOS conditions)

Browns Ferry Unit I Cycle 10 Core Operating Umits Report, (105% OLTP)

Page 22 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012

[U iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 1.10 1.05 1.00 U.

0

-j 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 0.87 55.4 1

107.0 1

Figure 3.5 LHGRFACF for ATRIUM-10 Fuel (Values bound all EOOS conditions)

(107. 0% maximum core flow line is used to support 105% rated flow operation, ICF)

Browns Ferry Unit 1 Cyde 10 Core Operating Limits Report (105% OLTP)

Page 23 "VA-COLR-BF1C10, Revision 0 (Final)

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[U ~iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 1.10 1.00 0.90 U.

0.

0.80 0.70 0.60 0.50 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow LHGRFACF

(% Rated) 30.0 0.59 81.8 1

107.0 1

Figure 3.6 LHGRFACF for GE 14 Fuel (Values bound all EOOS conditions)

(107.0% maximum core flow line is used to support 105% rated flow operation, /CF)

Browns Feny Unit 1 Cyce 10 Core Operatlng Umits Report (105% OLTP)

Page 24 TVA-COLR-BF1 Cl0, Revision 0 (Final)

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[U ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 10.

(.)

U-r

-I 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine Bypas Valve In-Service, TBVIS

-" --Turbine Bypas Valve Out-of-Service, TBVOOS TBVIS, : 50% Core Flow TBVOOS,,__ 50% Core Flow TBVIS, >50% Core Flow TBVOOS, >50% Core Flow 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Core Power LHGRFACp

(% Ra*ted) 100.0 1.00 65.0 0.77 50.0 070 50.0 0.68 30.0 0.54 Core Flow > 50% Rated 30.0 0.43 25.0 0.39 Core Flow _ 50% Rated 30.0 0A46 25.0 0-41 Turbine Bypass Out-of-Service Core Power LHGRFACp 1% Rated) 100.0 0.88 65.0 0.73 50.0 0.67 50.0 0.66 30.0 0.54 Core Flow > 50% Rated 30.0 0.38 25.0 0.34 Core Flow _ 50% Rated 30..0 T

0.45 2.5-0 0.39 Figure 3.7 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

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

BrcwnsFerryUnitl CydelO Page 25 Browns Fern Unit I CyRte 10 Core operating Umnits Report, (105% OILTP)

Page 25 TVA-COLR-BF1 C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 a.

I.I

(.)

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

Turbine Bypass In-Service Core Power L.HGRFACp

(%ýiRated) 100.0 1.00 65.0 0-77 50.0 0-70 50.0 0.68 30.0 0.52 Core Flow > 50% Rated 30.0 0.43 25-0 038 Core Flow 5 50% Rated 30.0 0-45 25-0 0.41 Turbine Bypass Outnof-Service Core Power LH!GRFACjp

(% Rated) 10H.0 0.88 65.0 073 50.0 067 50.0

  • 0.66 30.0 0.52 Core Flow > 50W Rated 30.0 0.38 25.0 0-34 Core Flow!5 50% Rated 30-0 0.45 25.0 0.38 Figure 3.8 Startup Operation LHGRFACp for ATRIUM-1 0 Fuel:

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

Browns Ferry Unit 1 Cyde 10 Core Operating Umits Report, (105% OLTP)

Page 26 TVA-COLR-BFC1l0, Revision 0 (Final)

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~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 0.

<C

-J-1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 0.20 Turbine BypassValve In-Service, TBVIS UrTurbine Bypass Valve Out-of-Service, TBVOOS TBVIS, -- 5.0% Core Flow

  • TBVOOS,:
  • 50% Coreý Flow

-7ý0TBVIS, >50% Core Flow TBVOOS, > 50% Core Flow 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Turbine Bypass In-Service Core Power LHGRFACp

(% Rated) 100.0 0.99 75 0 0.78 30.0 0.46 Core Flow > 50% Rated 30.0 T

0.39 25.0 0.35 Core Flow _ 50% Rated

! 30.0

{

0.2 i

25.0 U.8 Turbine Bypass Out of-Service Core Power LHIGRFACp 1000 0.96 75.0 0.76 30.0 0.46 Core Flow > 50% Rated 30.0 0.35 25.0 0.31 Core Flow < 50% Rated 30.0 0.42 25.0 0 036 Figure 3.9 Startup Operation LHGRFACp for GE 14 Fuel:

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

Browns Feny Unit 1 Cycle 10 Page 27 Browns Ferry Unit R

Cycle 10 Core Operating Limits Report, (105% OLTP)

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C.)

U--

..J 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 0.20 Turbine Bypas Valve In-Service,TBVIS Turbine BypassValve Out-of-Service, TBVOOS TBVIS, 550% Core Flow TBVOOS, : 50% Core Flow TBVIS, > 50% Core Flow TBVOOS, > 50% Core Flow L --

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

Turbine Bypass In-Service Turbine Bypass Out.of-Service Core Power Core Power LHGRFACp LHGRFACp MRatedi)

S 100.0 0.99 i

75.0 0.78 30.0 0.46 Core Flow > 50% Rated 30.0 0.39 25.0 0.35 Core Flow

%5O% Rated 30.0 0.42 25.0 j

0.38 f% Rated) 100.0 0.96 75.0 0.76 30.0 0.46 Core Flow > 50% Rated 30.0 0.35 25.0 0.31 Core Flow _ 50% Rated 30.0 0.42 25.0 0.36 Figure 3.10 Startup Operation LHGRFACp for GE 14 Fuel:

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

Browns Feny Unit 1 Cycle 10 Core Operating Umits Report (105% OLTP)

Page 28 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 NPG 1101 Market Street, Chattanooga TN 37402 4 OLMCPR Limits (Technical Specification 3.2.2, 3.3.4.1, & 3.7.5)

OLMCPR is calculated to be the most limiting of the flow or power dependent values OLMCPR limit = MAX ( MCPRF, MCPRp) where:

MCPRF core flow-dependent MCPR limit MCPRp power-dependent MCPR limit 4.1 Flow Dependent MCPR Limit: MCPRF MCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated or Increased Core Flow, ICF). MCPRF limits are shown in Figure 4.1, per Reference 1. Limits are valid for all EOOS combinations. No adjustment is required for SLO conditions.

4.2 Power Dependent MCPR Limit: MCPRp MCPRp limits are dependent upon:

" Core Power Level (% of Rated)

" Technical Specification Scram Speed (TSSS), Nominal Scram Speed (NSS), or Optimum Scram Speed (OSS)

Cycle Operating Exposure (NEOC, EOC, and CD - as defined in this section)

Equipment Out-Of-Service Options Two or Single recirculation Loop Operation (TLO vs. SLO)

The MCPRp limits are provided in the following tables, where each table contains the limits for all fuel types and EOOS options (for a specified scram speed and exposure range). The CMSS determines MCPRp limits, from these tables, based on linear interpolation between the specified powers.

4.2.1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional power dependent limits are shown in Table 4.8, Table 4.9, Table 4.10, and Table 4.11, based on temperature conditions identified in Table 3.1.

Browns Feny Unit 1 Cyde 10 Page 29 Core Operating Limits Report, (105% OLTP)

"VA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EiUiNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)

MCPRp limits are provided for three different sets of assumed scram speeds. The Technical Specification Scram Speed (TSSS) MCPRp limits are applicable at all times, as long as the scram time surveillance demonstrates the times in Technical Specification Table 3.1.4-1 are met. Both Nominal Scram Speeds (NSS) and/or Optimum Scram Speeds (OSS) may be used, as long as the scram time surveillance demonstrates Table 4.1 times are applicable.*t Table 4.1 Nominal Scram Time Basis Notch Nominal Optimum Position Scram Timing Scram Timing (index)

(seconds)

(seconds) 46 0.420 0.380 36 0.980 0.875 26 1.600 1.465 6

2.900 2.900 In demonstrating compliance with the NSS and/or OSS scram time basis, surveillance requirements from Technical Specification 3.1.4 apply; accepting the definition of SLOW rods should conform to scram speeds shown in Table 4.1. If conformance is not demonstrated, TSSS based MCPRp limits are applied.

On initial cycle startup, TSSS limits are used until the successful completion of scram timing confirms NSS and/or OSS based limits are applicable.

4.2.3 Exposure Dependent Limits Exposures are tracked on a Core Average Exposure basis (CAVEX, not Cycle Exposure).

Higher exposure MCPRp limits are always more limiting and may be used for any Core Average Exposure up to the ending exposure. Per Reference 1, MCPRp limits are provided for the following exposure ranges:

BOC to NEOC BOC to EOCLB BOC to End of Coast NEOC corresponds to EOCLB corresponds to End of Coast 29,932.4 MWd I MTU 32,824.7 MWd I MTU 314,132.4 MWd I MTU NEOC refers to a Near EOC exposure point.

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

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

BrDwns Ferry Unit 1 Cyde 10 Page 30 Browns Ferry Unit 1 cycle 10 Core operating Limits Report, (105% OLTP)

Page 30 TVA-COLR-BFIC10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 The EOCLB exposure point is not the true End-Of-Cycle exposure. Instead it corresponds to a licensing exposure window exceeding expected end-of-full-power-life.

The End of Coast exposure point represents a licensing exposure point exceeding the expected end-of-cycle exposure including cycle extension options.

4.2.4 Eauipment Out-Of-Service (EOOS) Options EOOS options* covered by MCPRp limits are given by the following:

In-Service RPTOOS TBVOOS RPTOOS+TBVOOS PLUOOS PLUOOS+RPTOOS PLUOOS+TBVOOS PLUOOS+TBVOOS+RPTOOS FHOOS (or FFWTR)

All equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Combined RPTOOS and TBVOOS Power Load Unbalance Out-Of-Service Combined PLUOOS and RPTOOS Combined PLUOOS and TBVOOS Combined PLUOOS, RPTOOS, and TBVOOS Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction)

For exposure ranges up to NEOC and EOCLB, additional combinations of MCPRp limits are also provided including FHOOS. The coast down exposure range assumes application of FFWTR. FHOOS based MCPRp limits for the coast down exposure are redundant because the temperature setdown assumption is identical with FFWTR.

4.2.5. Single-Loop-Operation (SLO) Limits MCPRp limits, for both ATRIUM-10 and GE 14, are increased by 0.02 to support SLO, per Reference 1.

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

  • All equipment service conditions assume 1 SRVOOS.

Browns Ferry Unit 1 Cyde 10 Core Operating Lmits Report (105% OLTP)

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EDMS: L32 121004 800 Date: October 3, 2012

[M ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2.00 1.80 1.60 I.

1.40 1.20 1.00 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow MCPRF (0.Ratectd) 7 30.0 1.61 78.0 1.28 107.0 1.28 Figure 4.1 MCPRF for GE 14 and ATRIUM-10 Fuel (Values bound all EOOS conditions)

(107. 0% maximum core flow line is used to support 105% rated flow operation, ICF)

Browns Ferry Un~ 1 Cyde 10 Page 32 Browns Ferry Unit 1 CyRe 10 Core Operating Limits Report, (105% OLTP)

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[M NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.2 MCPRp Limits for Optimum Scram Time Basis: ATRIUM-1O BOC BOC BOC Power to to to End of Operating o

g

(% of rated)

NEOC EOCLB Coast 100 1.44 1.46 1.48 75 1.57 1.57 1.60 65 1.67 1.67 1.71 50 1.79 1.79 1.84 50 1.89 1.90 1.91 Base Case 40 1.98 1.98 2.04 30 2.21 2.21 2.32 30 at > 50%F 2.70 2.70 2.80 25 at > 50%F 2.96 2.96 3.09 30 at i 50%F 2.56 2.56 2.65 25 at 25ac 50%F 2.81 2.81 2.93 100 1.47 1.48 75 1.59 1.60 65 1.71 1.71 50 1.84 1.84 50 1.89 1.91 FHOOS 40 2.04 2.04 30 2.32 2.32 30 at > 50%F 2.80 2.80 25 at > 50%F 3.09

3.09 30 at 50%F 2.65 2.65 25 at
  • 50%F 2.93 2.93

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

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

Browns Ferry Unit R

Cycle 10 Core Operating Umits Report, (105% 0OLTP)

Page 33 TVA-C0lR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 iMiNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.3 MCPRp Limits for Optimum Scram Time Basis: GE 14*

BOC BOC BOC Power to to to End of Operating Condton

(% of rated)

NEOC EOCLB Coast 100 1.45 1.47 1.49 75 1.58 1.58 1.61 65 1.68 1.68 1.72 50 1.84 1.84 50 1.90 1.9D 1.92 Base Case 40 2.05 2.05 2.15 30 2.36 2.36 2.48 30 at > 50%F 2.89 2.89 3.02 25 at > 50%F 3.21 321 3.37 30 at

  • 50%F 2.83 2.83 2.94 25 at s;50%F 3.11 3.11 3.26 100 1.48 1.49 75 1.61 1.61 65 1.72 1.72 50 50 1.92 1.92 FHOOS 40 2.15 2.15 30 2.48 2.48 30 at > 50%F 3.02 3.02 25 at > 50%F 3.37 3.37 30 at 29 50%F 2.94 294 25 at ' 5f%F 3.26 3.26
  • All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

Browns Ferry Unit 1 Cycle 10 Core Operating Umits Report (105% OLTP)

Page 34 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 E!U1NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.4 MCPRp Limits for ATRIUM-I 0: Nominal Scram Time Basis BOC 8OC 130C Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.46 1.48 1.49 75 1.61 1.61 1.64 65 1.69 1.69 1.73 50 1.80 1.80 1.86 50 1.90 1.92 1.92 Base Case 40 1.98 1.99 2.06 30 2.23 2.23 2.35 30 at > 50%F 2.70 2.70 2.80 25 at > 50%F 2.96 2.96 3.09 30 at g 50%F 2.56 2.56 2.65 25 at 50o%F 2.81 2.81 2.93 10'0 1.E50 1.52 1.53 75 1.65 1.65 1.66 65 1.74 1.74 1.77 50 1.85 1.85 1.80 50 1.90 1.92 1.92

'TBVOOS 40 1.99 1.99 2.07 30 2.24 2.24 2.35 30 at > 50%F 3.25 3.25 3.39 25 at > 50%f 3.68 3.68 3.82 30 at g 50%F 2.75 2.75 2.88 25 at j 50%F 3.16 3.16 3.32 100 1.49 1.49 75 1.62 1.64 65 1.73 1.73 50 1.86 1.86 50 1.90 1.92 FHOOS 40 2.06 2.06 30 2.35 2.35 30 at > 50%F 2.80 2.80 25 at > 50%F 3.09 3.09 30 at 9 50%F 2.65 2.65 25 at 2; 50%F 2.93 2.93 100 1.46 1.48 1.49 75 1.61 1.61 1.64 65 1.81 1.84 1.84 so 50 1.90 1.92 1.92 PLUOOS 40 1.98 1.99 2.06 30 2.23 2.23 2.35 30 at > 50%f 2.70 2.70 2.80 25 at > 50%F 2.96 2.96 3.09 30 at 50%F 2.56 2.56 2.65 25 at 5 504%F 2.81 2.81 2.93 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

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

Browns Ferry Unit 1 Cyde 10 Core Operating limits Report, (105% OLTP)

Page 35 TVA-COLR-BF1C1O, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.4 MCPRp Limits for ATRIUM-10: Nominal Scram Time Basis (continued)

BOC BOC BOC Power to to to End of Operating Condon of rated)

NEOC EOCLB Clast 100 1.52 1.53 75 1.65 1.66 65 1.77 1.77 50 1.901 50 1.90 1.92

.TBVOOS 40 2.07 2.07

.FHOOS 30 2.35 2.35 30 at > 50%F 3.39 3.39 25 at > 50%F 3.82 3.82 30 at 5 50%F 2.88 2.88 25at < 5D%F 3.32 3.32 100 1.50 1.52 1.53 75 1.65 1.65 1.66 65 1.81 1.84 1.84 50 50 1.90 1.92 1.92 T8VOOS 40 1.99 1.99 2.07

  • LU OOS 30 2.24 2.24 2.35
30 at > 50%.F 3.25 3.25 3.39 25 at > 50%F 3.68 3.68 3.82 30 at e 50%F 2.75 2.75 2.88 25 at g 50%F 3.16 3.16 3.32 100 1.49 1.49 75 1.62 1.64 65 1.81 1.84 50 F S50 1.90 1.92 FHOOS i~iwOS 40 2.06 2.06 30 2.35 2.35 30 at > 50%F 2.80 2.80 25 at > 50%F 3.09 3.09 30 at
  • 50%F 2.65 2.65 25 at
  • 50%F 2.93 2.93 100 1.52 1.53 75 1.65 1.66 65 1.81 1.84 ITBVOOS 50 1.90 1.92 FHOOS 40 2.07 2.07 PLUOOS 30 2.35 2.35
3) at > 50%F 3.39 3.39 25 at > 50%F 3.82 3.82 30 at
  • 50%F 2.88 2.88 25 at 50%F 3.32 3.32 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

A 50% power step change for PLUOOS limits is not supported. When core power is _ 50%, the LRNB event is the same with, or without PLUOOS.

Browns Ferry Unit 1 Cyde 10 Core Operating Umits Report, (105% OLTP)

Page 36 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800

[M NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 Table 4.5 MCPRp Limits for GE 14: Nominal Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition of rated)

NEOC EOCLB Coast 100 1.48 1.48 1.51 75 1.61 1.61 1.64 65 1.71 1.71 1.75 50 1.87 1.87 50 1.91 1.91 1.95 Base Case 40 2.08 2.08 2.18 30 2.39 2.39 2.51 30 at > 50%F 2.89 2.89 3.02 25 at > 50%F 3.21 3.21 3.37 30 at !ý 50%F 2.83 2.83 2.94 25 at 4 50%f 3.11 3.11 3.26 10G 1.52 1.52 1.54 75 1.65 1.65 1.67 65 1.76 1.76 1.79 50 1.88 1.88 50 1.91 1.91 1.96 TBVOOS 40 2.09 2.09 2.18 30 2.39 2.39 2.51

30 at > 50%F 3.31 3.31 3.47 25 at > 50%F 3.76 3.76 3.91
30 atg 50%F 2.98 2.98 3.15 25 at -ý 50%F 3.45 3.45 3.64 10 1.51 1.51 75 1.64 1.64 65 1.75 1.75 50 50 1.95 1.95 FHOOS 40 2.18 2.18 30 2.51 2.51 30 at > 50%F 3.02 3.02 25 at > 50%F 3.37 3.37 30 at s 50%F 2.94 2.94 25 at 2r 50%F 3.26 3.26 100 1.48 1.48 1.51 75 1.61 1.61 1.64 65 1.82 1.83 1.83 50

-s 50 1.91 1.91 1.95 PLUOOS 40 2.08 2.08 2.18 30 2.39 2.39 2.51 30 at > 50%F 2.89 2.89 3.02 25 at > 50%F 3.21 3.21 3.37 30 at i 50%F 2.83 2.83 2.94 25 at e50%F 3.11 3.11 3.26

  • All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02
higher, FFWTR and FHOOS assume the same value of temperature drop. Consequently, FHOOS limits are not provided for BOC to End of COAST due to redundancy. Thermal limits for the "BOC to End of COAST" exposure applicability window are developed to Conservatively bound FHOOS limits for earlier exposure applicability windows.

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

Browns Ferry Unit 1 Cycle 10 Core Operating Umits Report (105% OLTP)

Page 37 TVA-COLR-BF1ClO, Revision 0 (Final)

EDMS: L32 121004 800 5T /~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 Table 4.5 MCPRp Limits for GE 14: Nominal Scram Time, Basis (continued)*

BOC BOC BOC Power to to to End of Operating Condition (h% of rated)

NEOC EOCLB Coast 100 1.54 1.54 75 1.67 1.67 65 1.79 1.79

,50 50 1.96 1.96

TBVOOS 40 2.18 2.18
FHOOS 30 2.51 2.51 30 at > 50%F 3.47 3.47 25 at > 50%F 3.91 3.91 30 at* 50%F 3.15 3.15 25 at i 50%F 3.64 3.64 100 1.52 1.52 1.54 75 1.65 1.65 1.67 65 1.82 1.83 1.83 50 50 1.91 1.91 1.96 PLUODS 40 2.09 2.09 2'.18 30 2.39 2.39 2.51 3O at > 50%F 3.31 3.31 3.47 25 at > 50%F 3.76 3.76 3.91 30 at 9 50%f 2.98 2.98 3.15 25 at g 50%F 3.45 3.45 3.64 100 1.51 1.51 75 1.64 1.64 65 1.82 1.83 50 50 1.95 1.95
  • FH OOS 40 2.18 2.18 30 2.51 2.51 30 at > 50%F 3.02 3.02 25 at > 500%F 3.37 3.37 30 at *; 50%F 2.94 2.94 25 at f. 50%F 3.26 3.26 100 1.54 1.54 75 1.67 1.67 65 1.82 1.83 50

.TBVOOS 50 1.96 1.96 0FHOOS 40 2.18 2.18

.PLUOOS 30 2.51 2.51 30 at > 50%F 3.47 3.47 25 at > 50%F 3.91 3.91 30 at i 50%F 3.15 3.15 25 at ; 50%f 3.64 3.64 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

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

Browns Ferry Unit 1 Cycle 10 Core Operating Umits Report (105% OLTP)

Page 38 TVA-COLR-8F1 CIO, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 U !NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.6 MCPRp Limits for ATRIUM-I 0: Technical Specification Scram Time Basis*

BOC 8OC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.49 1.5t 1.52 75 1.62 1.63 1.65 65 1.71 1.71 1.75 50 1.82 1.82 1.87 50 1.91 1.93 1.93 Base Case 40 1.99 2.00 2.08 30 2.26 2.26 2.37 30 at > 50%F 2.70 2.70 2.80 25 at > 50%F 2.96 2.96 3.09 30 at *; 50%F 2.56 2.56 2.65 25 at I 50%F 2.81 2.81 2.93 100 1.53 1.54 1.56 75 1.66 1.67 1.69 65 1.76 1.76 1.79 50 1.87 1.87 1.92 50 1.91 1.93 1.93 TBVOOS 40 2.01 2.01 2.10 30 2.27 2.27 2.38

30 at > S0%f 3.25
3.25 3.39 25 at > 50%F 3.68 3.68 3.82 30 at ' 50%F 2.75 2.75 2.88 25 at 2950%F 3.16 3.16 3.32 100 1.52 1.52 75 1.65 1.65 65 1.75 1.75 50 1.87 1.87 50 1.91 1.93 IFHOOS 40 2.08 2.08 30 2.37 2.37 30 at > 50%F 2.80 2.80 25 at > 50%F 3.09 3.09 30 at I 50%F 2.65 2.65 25 at
  • 50%F 2.93 2.93 100 1.49 1.50 1.52 75 1.62 1.63 1.65 65 1.82 1.86 1.86 50 1.91 1.93 1.93 PLUOOS 40 1.99 2.00 2.08 30 2.26 2.26 2.37 30 at > 50%F 2.70 2.70 2.80 25 at> 50%F 2.96 2.96 3.09 30 at ý 50%f 2.56 2.56 2.65 25 at 9 50%F 2.81 2.81 2.93
  • All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

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

Browns Ferny Unit 1 Cyde 10 Core Operating Umits Report, (105% OLTP)

Page 39 TVA-COLR-BF1 ClO, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 IImliNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.6 MCPRp Limits for ATRIUM-l0: Technical Specification Scram Time Basis (continued)*

BOC 6OC BOC Power to to to End of Operating Conditon

(% of rated)

NEOC EOCLB Coast 106 1.55 1.56 75 1.68 1.69 65 1.79 1.79 50 1.92 50 1.92 1.93 "rBVOOS 40 2.10 2.10

FHOOS 30 2.38 2.38 30 at > 50%F 3.39 3.39 25 at > 50%F 3.82 3.82 30 at
  • 50%F 2.88 2.88 25 at 50%F 3.32 3.32 100 1.53 1.54 1.56 75 1.66 1.67 1.69 65 182 1.86 1.86 50 1.91 1.93 1.93 iTBVOOS 40 2.01 2.01 2.10 i PLUOOS 30 2.27 2.27 2.38
30 at > 50%F 3.25 3.25 3.39 25 at > 50%F 3.68 3.68 3.82
30 at z 50%F 2.75 2.75 2.88 25 at < 50%F 3.16 3.16 3.32 100 1.52 1.52 75 1.65 1.65 65 1.82 1.86 50 50 1.91 1.93
FHOOS 40 2.08 2.08 PLUOOS 30 2.37 2.37 30 at > 50%F 2.80 2.80 25 at > 50%F 3.0) 3.09 30 at f 50%F 2.65 2.65 25 atr <50%F 2.93 2.93 1-00 1.55 1.56 75 1.68 1.69 65 1.82 1.86 50 ITBVOOS 50 1.92 1.93 FHOOS 40 2.10 2.10 PLUOOS 30 2.38 2.38 30 at > 50%f 3.39 3.39 25 at > 50%F 3.82 3.82 30 at < 50%F 2.88 2.88 25 at - 50%F 3.32 3.32 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

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

Browns Ferry Unit 1 Cyde 10 Core Operating Limits Report (105% OLTP)

Page 40 TVA-COLR-BF1C1O, Revision 0 (Final)

EDMS: L32 121004 800 E!UINPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 Table 4.7 MCPRp Limits for GE 14: Technical Specification Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 1O0 1.50 1.50 1.54 75 1.65 1.65 1.67 65 1.73 1.73 1.76 50 1.89 1.89 50 1.92 1.92 1.97 Base Case 40 2.11 2.11 2.20 30 2.41 2.41 2.54 30 at > 50%F 2.89 2.89 3.02 25 at > 50%F 3.21 3.21 3.37 30 at

  • 50%F 2.83 2.83 2.94 25 at -_

__t50%F 3.11 3.11 3.26 100 1.54 1.55 1.57 75 1.69 1.69 1.70 65 1-78 1.78 1.81 50 1.91 1.91 50 1.92 1.92 1.99 TBVOOS 40 2.12 2.12 2.21 30 2.41 2.41 2.54 30 at > 50%F 3.31 3.31 3.47 25 at > 50%F 3.76 3.76 3.91 30 at 1 50%f 2.98 2.98 3.15 25 at ! 50%F 3.45 3.45 3.64 100 1.54 1.54 75 1.67 1.67 65 1.76 1.76 50 50 1.97 1.97 FHOOS 40 2.20 2.20 30 2.54 2.54 30 at > 50%F 3.02 3.02 25 at > 50%F 3.37 3.37 30 at

  • 50%F 2.94 2.94 25 at r 50%F 3.26 3.26 100 1.50 1.50 1.54 75 1.65 1.65 1.67 65 1.83 1.85 1.85 50 1.92 1.92 1.97 PLUOOS 40 2.11 2.11 2.20 30 2.41 2.41 2.54 30 at > 50%F 2.89 2.89 3.02 25 at > 50%F 3.21 3.21 3.37 30 at i 50%F 2.83 2.83 2:.94 25 ats 50%f 3.11 3.11 3.26
  • All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

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

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

Browns Ferry Unit 1 cycle 10 Core Operating Umits Report, (105% OLTP)

Page 41 "VA-COLR-BF1C1O, Revision 0 (Final)

EDMS: L32 121004 800

[U INPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 Table 4.7 MCPRp Limits for GE 14: Technical Specification Scram Time Basis (continued)

B3C BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLS Coast 100 1.57 1.57 75 1.70 1.70 65 1.81 1.81 50 50 1.99 1.99 40

  • 2.21 2.21 FHOOS 30 2.54 2.54 30 at > 50%F 3.47 3.47 25 at > 50%F 3.91 3.91 30 at 50%F 3.15 3.15 25 at 50%F 3.64 3.64 100 1.54 1.55 1.57 75 1.69 1.69 1.70 65 1.83 1.85 1.85 50 50 1.92 1.92 1.99 TBVOOS 40 2.12 2.12 2.21 30 2.41 2.41 2.54
30 at > 50%F 3.31 3.31 3.47 25 at > 5O%F 3.76 3.76 3.91 30 at 50%F 2.98 2.98 3.15 25 at
  • 50%F 3.45 3.45 3.64 100 1.54 1.54 75 1.67 1.67 65 1.83 1.85 50 FHOOS 50 1.97 1.97 PiUoos 40 2.20 2.20 30 2.54 2.54 30 at > 50%f 3.02 3.02 25 at > 50%F 3.37 3.37 30 at 50%F 2.94 2.94 25 at 50%F 3.26 3.26 100 1.57 1.57 75 1.70 1.70 65 1.83 1.85 s0

.TBVOOS 50 1.99 1.99 FHOOS 40 2.21 2.21 PLUOOS 30 2.54 2.54 30 at> 50%F 3.47 3.47 25 at > 50%F 3.91 3.91 30at s 50%F 3.15 3.15 25 at

  • 50%F 3.64 3.64 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.

Br=

sey=i1Cd 1

ae4 Browns Ferrn Unit 1 Cycle 10 Core Operating Limits Report, (105% OLTP)

Page 42 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800

[U ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: October 3, 2012 Table 4.8 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1 for ATRIUM-10: Technical Specification Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.52 1.52 1.52 75 1.65 1.65 1.65 65 1.82 1.86 1.86 50 50 2.02 2.02 2.02 TBVIS 40 2.30 2.30 2.30 30 2.64 2.64 2.64 30 at > 50%F 3.07 3.07 3.07 25 at > 50%F 3.42 3.42 3.42 30 atg 50%F 2.88 2.88 2.88 25 at ý 50%F 3.23 3.23 3.23 100 1.55 1.56 1.56 75 1.68 1.69 1.69 65 1.82 1.86 1.86 50 50 2.03 2.03 2.03 TBVOOS 40 2.31 2.31 2.31 30 2.63 2.63 2.63 30 at > 50%F 3.61 3.61 3.61 25 at > 50%F 4.06 4.06 4.06 30 at A 50%F 3.07 3.07 3.07 25 at g 50%F 3.57 3.57 3.57 Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Browns Ferrn Unit I Cycle 10 Core operating Limits Report, (105% OLTP)

Page 43 TVA-COLR-BF1 C1 0, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIn iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.9 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1 for GE 14: Technical Specification Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.54 1.54 1.54 75 1.67 1.67 1.67 65 1.83 1.85 1.85 5D 50 2.16 2.16 2.16 TBVIS 40 2.44 2.44 2.44 30 2.83 2.83 2.83 30 at > 50%F 3.32 3.32 3.32 25 at > 50%F 3.75 3.75 3.75 30 at

  • 50%F 3.21
3.21 3.21 25 at ; 50%F 3.61 3.61 3.61 100 1.57 1.57 1.57 75 1.70 1.70 1.70 65 1.83 1.85 1.85 50 50 2.17 2.17 2.17 TBVOOS 40 2.44 2.44 2.44 30 2.80 2.80 2.80 30 at > 50%F 3.72 3.72 3.72 25 at > 50%F 4.21 4.21 4.21 30 at *; 50%F 3.37 3.37 3.37 25 at r 50%F 3.94 3.94 3.94
  • Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Browns Ferry Unit I Cyde 10 Core Operating Umits Report, (105% OLTP)

Page 44 TVA-COLR-BF1C1O, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIUNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.10 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2 for ATRIUM-10: Technical Specification Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.52 1.52 1.52 75 1.65 1.65 1.65 65 1.82 1.86 1.86 50 2.03 2.03 2.03 TBVts 40 2.31 2.31 2.31 30 2.66 2.66 2.65 30 at > 50%F 3.09 3.09 3.09 25 at > 50%F 3.44 3.44 3.44 30 at g 50%F 2.91 2.91 2.91 25 at r 50%F 3.25 3.25 3.25 100 1.55 1.56 1.56 75 1.68 1.69 1.69 65 1.82 1.86 1.86 50 50 2.04.

2.04 2.04 TBVOOS 40 2.32 2.32 2.32 30 2.65 2.65 2.65 30 at > 50%F 3.62 3.62 3.62.

25 at > 50%F 4.08 4.08 4.08 30 at A 50%F 3.09 3.09 3.09 25 at I 50%F 3.58 3.58 3.58 Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Browns Ferry Unit 1 Cycle 10 Core Operating Limits Report, (105% OLTP)

Page 45 "VA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 EIU NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.11 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2 for GE 14: Technical Specification Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.54 1.54 1.54 75 1.67 1.67 1.67 65 1.83 1.85 1.85 50 50 2.17 2.17 2.17 T8VIS 40 2.46 2.46 2.46 30 2.85 2.85 2.85 30 at > 50%F 3.34 3.34 3.34 25 at > 50%F 3.77 3.77 3.77 30 at

  • 50%F 3.23 3.23 3.23 25 at
  • 50%F 3.63 3.63 3.63 100 1.57 1.57 1.57 75 1.70 1.70 1.70 65 1.83 1.85 1.85 5(0....-

50 2.18 2.18 2.18 TBVOOS 40 2.45 2.45 2.45 30 2.82 2.82 2.82

30 at > 50%F 3.73 3.73 3.73 25 at > 50%F 4.23 4.23 4.23 30 at e 50%F 3.39 3.39 3.39 25 at I 50%F 3.96 3.96 3.96 Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.

Limits are applicable for all other EOOS scenarios, apart from TBV.

Browns Ferry Unit 1 Cycle 10 Core Operating Umims Report (105% OLTP)

Page 46 TVA-COLR-BF1CIO, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 5

Oscillation Power Range Monitor (OPRM) Setpoint (Technical Specification 3.3.1.1)

Technical Specification Table 3.3.1.1-1, Function 2f, identifies the OPRM upscale function.

Instrument setpoints are established, such that the reactor will be tripped before an oscillation can grow to the point where the SLMCPR is exceeded. An Option III stability analysis is performed for each reload core to determine allowable OLMCPR's as a function of OPRM setpoint. Analyses consider both steady state startup operation, and the case of a two recirculation pump trip from rated power.

The resulting stability based OIMCPR's are reported in Reference 1. The OPRM setpoint (sometimes referred toas 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 26. The calculated OLMCPR's are shown in Table 5.1. Review of results shown in COLR Table 4.2 and Table 4.3 indicates an OPRM setpoint of 1.15 may be used.

Table 5.1 OPRM Setpoint Range OPRM OLMCPR OLM(,PR Setpoint (SS)

(2P1r) 1.05 1.18 1.14 1.06 1.20 1.16 1.07 1.22 1.17 1.08 1.24 1.19 1.09 1.26 1.21 1.10 1.28 1.23 1.11 1.30 1.25 1.12 1.32 1.27 1.13 1.34 1.29 1.14 1.36 1.31 1.15 1.39 1.34

' Extrapolation beyond a setpoint of 1.15 is not allowed Brt~ns Ferry Unit 1 (Jyde 10 Page 47 Browns Feran Unit 1 Cycle 10 Core operating Limits Report, (105% OLTP)

Page 47 TVA-COLR-BF1 C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 M NPG 1101 Market Street, Chattanooga TN 37402 6 APRM Flow Biased Rod Block Trip Settings (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

The APRM rod block trip setting is based upon References 27 & 28, and is defined by the following:

SRB _ (0.66(W-AW) + 61%)

Allowable Value SRB _ (0.66(W-AW) + 59%)

Nominal Trip Setpoint (NTSP) where:

SRB

=

Rod Block setting in percent of rated thermal power (3458 MWt)

W

=

Loop recirculation flow rate in percent of rated AW

=

Difference between two-loop and single-loop effective recirculation flow at the same core flow (AW=0.0 for two-loop operation)

The APRM rod block trip setting is clamped at a maximum allowable value of 115%

(corresponding to a NTSP of 113%).

Browns Ferry Unit 1 Cycle 10 Core Operating Urmits Report (105% OLTP)

Page 48 "VA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012

[M ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 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 27 & 28, are shown in Table 7.1. Setpoints are based on an HTSP, unfiltered analytical limit of 117%. 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 27, 28, and 30.

Table 7.1 Analytical RBM Trip Setpoints" IRBM Trip Setpoint LPSP IPSP HPSP LTSP - unfiltered

- filtered ITSP

- unfiltered

- filtered Allowable Value (AV) 27%

62%

82%

124.7%

123.5%

119.7%

118.7%

Nominal Trip Setpoint (NTSP) 25%

60%

80%

123.0%

121.8%

118.0%

117.0%

HTSP - unfiltered 114.7%

113.0%

- filtered 113.7%

112.0%

DTSP 90%

92%

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

Table 7.2 RBM Setpoint Applicability Thermal Power Applicable Notes from

(% Rated)

MCPRt Table 3.3.2.1-1 Comment

> 27% and < 90%

< 1.70 (a), (b), (f), (h) two loop operation

< 1.74 (a), (b), (f), (h) single loop operation

> 90%

< 1.43 (g) two loop operationt Values are considered maximums. using lower values, due to RBM system hardware/software limitations, is conservative, and acceptable.

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

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

Browns Ferry Unit 1 Cycle 10 Core Operating Umits Report (105% OLTP)

Page 49 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Date: October 3, 2012

[U ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 7.3 Control Rod Withdrawal Error Results RBM CRWE HTSP Analytical Limit OLMCPR Unfiltered 107 1.30 111 1.34 114 1.38 117 1.40 Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 117% unblocked).

Browns Ferry Unit 1 Cyde 10 Core Operating Limits Report (105% OLTP)

Page 50 TVA-COLR-BF1C10, Revision 0 (Final)

EDMS: L32 121004 800 Reactor Engineering and Fuels - BWRFE Date: October 3, 2012 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 1 Cyde 10 Page 51 Browns Ferry Unit 1 Cylde 10 Core operating Urnits Report, (105% OLTP)

Page 51

-I'VA-COI-R-BF1C10, RevisionO (Final)

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