ML14247A309

TVA-COLR-BF2C18, Rev. 1, Browns Ferry Unit 2 Cycle 18 Core Operating Limits Report

ML14247A309
Person / Time
Site:	Browns Ferry
Issue date:	08/29/2014
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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References
TVA-COLR-BF2C18, Rev 1
Download: ML14247A309 (39)

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EDMS L32 140820 800 QA Document Pages Affected All BFE-3447 Revision 1 Reactor Engineering and Fuels - BWRFE 1101 Market Street Chattanooga TN 37402 Browns Ferry Unit 2 Cycle 18 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF2CI8 Revision 1 (Final)

Revision Log Page v)

August 2014

Prepared, Verified I.--

T W Eichenberg, Sr. Spec**ist a.e7itchell, Engineer Approved G. C Storey, M

~nage'WR Fuel Enginei Revieww**

Date:

A!O//:i, Date-F]

/5 Date:

/Zoi_4 ering Date: -

______/

ng Date:

Date:

zA4-D D Coffey, Manager, Reactor Engineeri Approved Chairman, PORC Approved PlAnt Man ige Umom

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 N PG 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 38 (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................................................................................................................................................

iv R e v is io 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 c tio n........................................................................................................................

1 0 1.1 P u rp o s e.......................................................................................................................

1 0 1.2 S c o p e..........................................................................................................................

1 0 1.3 Fuel Loading...........................................................................................................

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

11 2

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

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

12 2.2 Off-Rated Power Dependent Lim it: APLHGRp.......................................................

12 2.2.1 Startup without Feedwater Heaters................................................................

12 2.3 Off-Rated Flow Dependent Lim it: APLHG RF.........................................................

12 2.4 Single Loop O peration Lim it: APLHG RSLO..............................................................

12 2.5 Equipm ent O ut-Of-Service Corrections...................................................................

14 3

LHG R Lim its.......................................................................................................................

15 3.1 Rated Power and Flow Lim it: LHGRRATED................................................................... 15 3.2 Off-Rated Power Dependent Lim it: LHGRp............................................................

15 3.2.1 Startup without Feedwater Heaters................................................................

15 3.3 Off-Rated Flow Dependent Lim it: LHG RF..............................................................

16 3.4 Equipm ent O ut-Of-Service Corrections...................................................................

16 4

O LM CPR Lim its.................................................................................................................

22 4.1 Flow Dependent M CPR Lim it: M CPRF.......................................................................

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

22 4.2.1 Startup without Feedwater Heaters................................................................

22 4.2.2 Scram Speed Dependent Limits (TSSS vs. NSS vs. OSS)............................

23 4.2.3 Exposure Dependent Lim its............................................................................

23 4.2.4 Equipm ent O ut-Of-Service (EOOS) O ptions.......................................................

24 4.2.5 Single-Loop-Operation (SLO) Lim its.............................................................

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

24 5

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

34 6

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

35 7

Rod Block M onitor (RBM ) Trip Setpoints and Operability..................................................

36 8

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

38 Brwns Ferry Unit 2 Cycie 18 Page ii Core Operating Units Report (105% OLTP)

TVA-COLR-BF2C18, Revision 1 (Fia)

EDMS: L32 140820 800 Date: August 20, 2014

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 List of Tables Nuclear Fuel Types.....................................................................................................................

11 Startup Feedwater Tem perature Basis...................................................................................

15 Nom inal Scram Tim e Basis....................................................................................................

23 M CPRp Lim its for O ptim um Scram Tim e Basis.....................................................................

26 M CPRp Lim its for Nom inal Scram Time Basis.......................................................................

27 M CPRp Lim its for Technical Specification Scram Tim e Basis....................................................

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

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

32 M CPRp Lim its for Single Loop O peration for All Scram Tim es...................................................

33 O PRM Setpoint Range..........................................................................................................

34 O PRM Successive Confirm ation Count Setpoint............................................................

34 Analytical RBM Trip Setpoints..............................................................................................

36 RBM Setpoint Applicability..........................................................................................................

36 Control Rod W ithdrawal Error Results...................................................................................

37 B1rowts Ferry Unit 2 Cycle 18 Core Opra Lmits Report, (105% OLTP)

Page iii TVA-COLR-BF2C18, Revision I (F-nal)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 SN PG 1101 Market Street, Chattanooga TN 37402 List of Figures APLHG RRATED for ATRIUM -10 Fuel.......................................................................................

13 LHG R RATED for ATR IUM -10 Fuel............................................................................................

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

18 LH G R FA C F for A T R IU M -10 Fuel................................................................................................

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

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

21 M C P R F for A T R IU M -10 Fuel..................................................................................................

25 Brwns Ferry Unit 2 Cyde 18 Core Operating LiUtts Report (105% OLTP)

Page iv TVA-COLR-8F2C18, Revision 1 (Fral)

EDMS: L32 140820 800 Date: August 20, 2014 IM ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Revision Log Number Page I

Description 1-R1 vii Added RCP and RCPOOS to the list.

Updated Reference 1. This revised reference provides explicit MCPRp 2-R1 viii results for single loop operation (RCPOOS). No other results are impacted.

3-Ri 24 Revised Section 4.2.5 wording to be consistent with the Reference 1 revision. Includes a new footnote.

Removed footnote information regarding the addition of a 0.02 adder to 4-Ri 26-32 the safety limit for constructing single loop operating limits. The foot note is still true, but not relevant to the document as the revised Reference 1 provides explicit limits.

Provided new Table 4.7, and footnotes, showing the explicit MCPRp limits for single loop operation (RCPOOS) 0-RO All New document.

Browns Fery Unit 2 Cycle 18 Core OpenaM Limits Report (105% OLTP)

Page v TVA-COLR-BF2C18, Revision 1 (Find)

EDMS: L32 140820 800 Date: August 20, 2014 LUNPG 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)

Bmwns Feny Unit 2 Cyde 18 Page vi mrmow Ferry Unrit 2 Cycle 18 Core Opera LrrftS RepoL~x (105% OLTP)

Page vi TVA-C0LR-BF2C18, Revisim 1 (Final)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 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 RCP Recirculation Pump RCPOOS RCP OOS RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS RTP Rated Thermal Power, 3458 MW.

SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority B~mr. Ferny Unit 2 Cyde 18 Page vii Core OperanLiits Report (105% OLTP)

TVA-COLR-BF2C18, Revision 1 (Fnal)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 M

N PG 1101 Market Street, Chattanooga TN 37402 References

1.

ANP-3183, Revision 2, Browns Ferry Unit 2 Cycle 18 Reload Safety Analysis, AREVA NP, Inc., July 2014.

2.

ANP-2755(P) Revision 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-16 ATRIUM TM -10 Fuel Assemblies, AREVA NP, Inc., November 2008.

3.

ANP-2939(P), Rev. 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-17 ATRIUM-10 Fuel Assemblies, AREVA NP, Inc., July 2010.

4.

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

5.

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

6.

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

Methodology References

7.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

8.

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

9.

EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

10.

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

11.

XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

12.

XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

13.

EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

14.

XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

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

Page viii

[VA-COLR-BF2C18, Revision 1 (Fnal)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 D NPG 1101 Market Street, Chattanooga TN 37402

15.

XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

16.

ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

17.

ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

18.

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

19.

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

September 2009.

20.

EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001, as supplemented by the site specific approval in NRC safety evaluation dated February 15, 2013.

21.

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

22.

EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

23.

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

PRNM Setpoint References

24.

Filtered Setpoints - EDE-28-0990 Rev. 3 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.

25.

Unfiltered Setpoints - EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition]

for Tennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.

26.

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

27.

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

28.

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

Browns Ferry Unit 2 Cycle 18 Page ix Core Opeating Limits Report (105% OLTP)

TVA-COLR-BF2C18, Revision 1 (F'ral)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 M NPG 1101 Market Street, Chattanooga TN 37402 1

Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

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

1.2 Scope This document addresses the following areas:

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

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

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

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

>' Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

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

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

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

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

Applicability: Mode 1, > (as specified in Technical Requirements Manuals Table 3.3.4-1)

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

Applicability: Mode 1, > % RTP as specified in Table 3.3.2.1-1 (TS definition of RTP)

> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

Applicability: All Modes 1.3 Fuel Loading The core will contain previously exposed and fresh AREVA NP, Inc., ATRIUM-10 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented in Reference 6.

Bwns Ferry Unit 2 cycle 18 Core Operating Limits Report (105% OLTP)

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

EDMS: L32 140820 800 Date: August 20, 2014 BIMNPG 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)

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

FCC291-FCC306 ATRIUM-10 A10-3757B-10GV80-FCC 16 16 7

FCC311-FCC334 ATRIUM-10 A10-4019B-14GV80-FBC 16 105 8

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

FBC569-FBC644 ATRIUM-10 A10-3799B-14GV80-FBD 17 136 10 FBDO01-FBD136 ATRIUM-10 A10-4004B-15GV80-FBD 17 135 11 FBD137-FBD272 ATRIUM-10 A10-4165B-15GV75-FBE 18 176 12 FBE001-FBE176 ATRIUM-10 A10-4107B-13GV75-FBE 18 68 13 FBE177-FBE244 ATRIUM-10 A10-4176B-10GV75-FBE 18 72 14 FBE245-FBE316 1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 7 through 23.

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

BDowns Ferry Unit 2 Cycle 18 Core Operan Limrits Report (105% OLTP)

Page 11 TVA-COLR-BF2C18, Revision 1 (F'na)

EDMS: L32 140820 800 Date: August 20, 2014 EID iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2 APLHGR Limits (Technical Specifications 3.2.1 & 3.7.5)

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

APLHGR limit = MIN (APLHGRp, APLHGRF, APLHGRsLo) where:

APLHGRp APLHGRF APLHGRSLO off-rated power APLHGR limit off-rated flow APLHGR limit SLO APLHGR limit

[APLHGRRATED

• MAPFACp]

[APLHGRRATED

• MAPFACF]

[APLHGRRATED

• SLO Multiplier]

2.1 Rated Power and Flow Limit: APLHGRRATED The rated conditions APLHGR for ATRIUM-10 fuel is identified in Reference 1 and shown in Figure 2.1.

2.2 Off-Rated Power Dependent Limit: APLHGRP Reference 1, for 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 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.

Bowns Ferry Unit 2 Cycle 18 Core Operating Urds Report (105% OLTP)

Page 12 TVA-COLR-BF2C18, Revision 1 (Fina)

EDMS: L32 140820 800 Date: August 20, 2014 ELD NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 15 12 X

C, 9

6 3

0 0

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

Planar Avg.

APLHGR Exposure Limit (GVd/MTU)

(kW/ft 0.0 12.5 15.0 12.5 67.0 7.3 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Browns Ferny Urtt 2 Cycle 18 Core Operat Lits Report (105% OLTP)

Page 13 TVA-COLR-BF2C18, Revision 1 (F-nI)

EDMS: L32 140820 800 Date: August 20, 2014 ELM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2.5 Equipment Out-Of-Service Corrections The limits shown in Figure 2.1 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.

In-Service RPTOOS TBVOOS PLUOOS FHOOS (or FFWTR)

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

• All equipment service conditions assume 1 SRVOOS.

Blrois Ferry Unit 2 Cyce 18 Core Operating Units Report (105% OLTP)

Page 14 TVA-COLR-BF2C18, Revision 1 (FfI*)

EDMS: L32 140820 800 Date: August 20, 2014 IM ~NPG 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 off-rated power LHGR limit off-rated flow LHGR limit

[LHGRRATED

• LHGRFACp]

[LHGRRATED

• LHGRFACF]

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

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

3.2.1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional limits are shown in Figure 3.4 and Figure 3.5, based on temperature conditions identified in Table 3.1.

Table 3.1 Startup Feedwater Temperature Basis Temperature Power Range 1 Range 2

(%Rated)

ME)

(F) 25 160.0 155.0 30 165.0 160.0 40 175.0 170.0 50 185.0 180.0 Browns Ferny Unit 2 Cycle 18 Cor Opeang Lirkt Report (105% OLTP)

Page 15 rVA-COLR-BF2C18, Revision 1 (Fwiai)

EDMS: L32 140820 800 Date: August 20, 2014 EID NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 3.3 Off-Rated Flow Dependent Limit: LHGRF The LHGR limit is adjusted for off-rated flow conditions using the LHGRFACF multiplier provided in Reference 1. The multiplier are shown in Figure 3.3.

3.4 Equipment Out-Of-Service Corrections The limit shown in Figure 3.1 is applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.

In-Service RPTOOS TBVOOS PLUOOS FHOOS (or FFWTR)

SLO All equipment In-Service EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Power Load Unbalance Out-Of-Service Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction Single Loop Operation, One Recirculation Pump Out--Of-Service Off-rated power corrections shown in Figure 3.2 are dependent on operation of the Turbine Bypass Valve system. For this reason, separate limits are to be applied for TBVIS or TBVOOS operation. The limits have no dependency on RPTOOS, PLUOOS, FHOOS/FFWTR, or SLO.

Off-rated flow corrections shown in Figure 3.3 are bounding for all EOOS conditions.

Off-rated power corrections shown in Figure 3.4 and Figure 3.5 are also dependent on operation of the Turbine Bypass Valve system. In this case, limits support FHOOS operation during startup. These limits have no dependency on RPTOOS, PLUOOS, or SLO.

. All equipment service conditions assume 1 SRVOOS.

Browns Ferry Unit 2 Cycle 18 Core prang Limits Report (105% OLTP)

Page 16 TVA-COLR-BF2C18. Revision 1 (Fkrk)

EDMS: L32 140820 800 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 15 12

-9 36 3

0 0

20 40 60 Pellet Exposure (GWd/MTU) 80 Pellet Exposure (GN~dMMJ 0.0 18.9 74.4 LHGR Limit (kWflt) 13.4 13.4 7.1 Figure 3.1 LHGRRATED for ATRIUM-10 Fuel Browns Ferry Unit 2 Cyde 18 Core Opeating ULnits Report (105% OLTP)

Page 17 TVA-COLR-BF2C18, Revision 1 (Fnal)

EDMS: L32 140820 800 Date: August 20, 2014 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 14.

CC,

,U-

-J 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine Bypass Valve In-Service. TBVIS Turbine Bypass Valve Out-of-Service, TBVOOS TBVIS, < 50% Core.Flow TBVOOS, !550% 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

(%

hted) 100.0 1.00 30.0 0.61 Core Flow> 50%Rated 30.0 0.53 25.0 0.49 Core Flow 50%Rated 30.0 0.57 25.0 0.55 Turbine Bypass Out-of-Service Core Power LHGRFACp

(% Rated) 100.0 0.92 30.0 0.61 Core Flow > 50% Rated

30. 0 I

0.45 25.0 0.41 Core Flow S 50% Rated 30.0

[

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

I I

Brns Ferry Unit 2 Cyde 18 Core Operating Lits Repot, (105% OLTP)

Page 18 IVA-COLR-BF2C18, Revision 1 (Fnal)

EDMS: L32 140820 800 Date: August 20, 2014

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

0.95 0.90 0.85 0.80 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow LHGRFACF (0/ Rated) 30.0 0.98 35.5 1

107.0 1

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

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

Browns Fery Unit 2 Cyyde 18 Core Operating Lrimts Report (105% OLTP)

Page 19 TVA-COLR-BF2C18, Revision 1 (Final)

EDMS: L32 140820 800 Date: August 20, 2014 ELM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 0.

C.,

U-r CI 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30

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

Turbine Bypass In-Service Core Power LHGRFACp

(%Rated) 100.0 1.00 30.0 0.60 Core Row > 50% Rated 30.0 j

0.49 25.0 0_45 Core Flow S 50% Rated 30.0 0.54 25.0 0.48 Turbine Bypass Out-of-Service Core Power LHGRFACp

(%Rated) 1000 0.92 30.0 0.60 Core Row > 50% Rated 30.0 0.43 25.0 0.38 Core Row 5 50% Rated 30.0 0.51 25.0 0.45 Figure 3.4 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

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

Bmow's Ferry Unit 2 Cycle 18 Core Opeatirg Limits Report (105% OLTP)

Page 20 TVA-COLR-BF2C18, Revision 1 (Fi)

EDMS: L32 140820 800 Date: August 20, 2014 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 a.

C.,

IL 0=-J 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 Turbine Bypass Valve In-Service, TBVIS Turbine Bypass Valve Out-of-Serwice, TBVOOS rBVIS, ! 50% Core Flow TBVOOS, s 50% Core Flow TBV IS, > 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 1.00 30.0 0.60 Core Flow > 50% Rated 30.0 J

0.49 25.0 0.44 Core Row S 50% Rated 30.0 0.53 25.0 0.48 Turbine Bypass Out-of-Service Core Power LHGRFACp

(%Rated) 100.0 0.92 30.0 0.60 Core Row > 50% Rated 30.0 1

0.43 25.0 0.38 Core Row S 50% Rated 30.0 1

0.51 25.0 0.43 Figure 3.5 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

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

Biu~ns Ferry Unit 2 Cyde 18 Page 21 Breopn Ferny Unit 2 Cyc(e 18 Core Operating Umits Report, (105% OLTP)

Page 21 TVA-C0LR-BF2C18, Revision 1 Final)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 NPG 1101 Market Street, Chattanooga TN 37402 4 OLMCPR Limits (Technical Specification 3.2.2, 3.3.4.1, & 3.7.5)

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

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

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

" Core Power Level (% of Rated)

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

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

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

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

4.2. 1 Startup without Feedwater Heaters There is a range of operation during startup when the feedwater heaters are not placed into service until after the unit has reached a significant operating power level. Additional power dependent limits are shown in Table 4.5 and Table 4.6, based on temperature conditions identified in Table 3.1.

B&mns Ferry Unit 2 Cyce 18 Page 22 Core Operating Units Report, (105% OLTP)

TVA-COLR-BF2C18, Revision 1 (Frkal)

EDMS: L32 140820 800 Date: August 20, 2014 ELM NPG 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 29,748.8 MWd / MTU 31,635.1 MWd / MTU 33,056.4 MWd I MTU NEOC refers to a Near EOC exposure point.

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

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

Bmons Feny Uit 2 Cyc 18 Core Operating Limits Report (105% OLTP)

Page 23 TVA-COLR-BF2C18, Revision 1 (Final)

EDMS: L32 140820 800 Date: August 20, 2014 IM 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 Equipment Out-Of-Service (EOOS) Options EOOS options* covered by MCPRp limits are given by the following:

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

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 Sin-gle-Loop-Operation (SLO) Limits When operating in RCPOOS conditions, MCPRp limits are constructed differently from the normal operating RCP conditions. The limiting event for RCPOOS is a pump seizure scenario, which sets the upper bound for allowed core power and flowt. This event is not impacted by scram time assumptions. Specific MCPRp limits are shown in Table 4.7.

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.

t RCPOOS limits are only valid up to 50% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlbm/hr.

Bowns Ferry Unit 2 Cyce 18 Core Operating Lknits Report (105% OLTP)

Page 24 "VA-COLR-BF2C18, Revision I (Friat)

EDMS: L32 140820 800 Date: August 20, 2014

~IDNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2.00 1.80 1.60 I-U E

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

(% Rated) 30.0 1.61 78.0 1.28 107.0 1.28 Figure 4.1 MCPRF for ATRIUM-10 Fuel (Values bound all EOOS conditions)

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

B&mwms Fery Unit 2 Cyde 18 Core Oper Limits Report (105% OLTP)

Page 25 TVACOLR-BF2C18, Revision 1 (Fial)

EDMS: L32 140820 800 Date: August 20, 2014

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.2 MCPRP Limits for Optimum Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.40 1.41 1.43 75 1.50 1.51 1.53 65 1.57 1.58 1.61 50 1.73 1.73 1.80 50 1.80 1.81 1.82 Base Case 40 1.92 1.92 2.00 30 2.18 2.18 2.28 30 at > 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at s; 50%F 2.58 2.58 2.67 25 at 9 50%F 2.81 2.81 2.93 100 1.42 1.43 75 1.52 1.53 65 1.61 1.61 50 1.80 1.80 50 1.81 1.82 FHOOS 40 2.00 2.00 30 2.28 2.28 30 at > 50%F 2.75 2.75 25 at> 50%F 3.04 3.04 30 at - 50%F 2.67 2.67 25 at t 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.

FFWTRIFHOOS is supported for the BOC to End of Coast limits.

I Brovis Feny Unit 2 Cycle 18 Core Operating Li.its Report (105% OLTP)

Page 26 TVA-COLR-BF2C18, Revision 1 (FInal)

EDMS: L32 140820 800

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 Table 4.3 MCPRp Limits for Nominal Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.41 1.43 1.44 75 1.54 1.54 1.55 65 1.60 1.60 1.64 50 1.75 1.75 1.82 50 1.81 1.82 1.83 Base Case 40 1.94 1.94 2.02 30 2.20 2.20 2.31 30 at > 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at z* 50%F 2.58 2.58 2.67 25 at i 50%F 2.81 2.81 2.93 100 1.45 1.46 1.47 75 1.55 1.56 1.58 65 1.64 1.64 1.67 50 1.76 1.76 50 1.81 1.82 1.83 TBVOOS 40 1.95 1.95 2.03 30 2.20 2.20 2.31 30 at > 50%F 3.06 3.06 3.20 25 at > 50%F 3.47 3.47 3.61 30 at t 50%F 2.70 2.70 2.83 25 at r 50%F 3.10 3.10 3.25 100 1.44 1.44 75 1.54 1.55 65 1.64 1.64 50 1.82 50 1.82 1.83 FHOOS 40 2.02 2.02 30 2.31 2.31 30 at > 50%F 2.75 2.75 25 at, 50%F 3.04 3.04 30 at : 50%F 2.67 2.67 25 at ; 50%F 2.93 2.93 100 1.41 1.43 1.44 75 1.54 1.54 1.55 65 1.73 1.75 1.75 50 50 1.82 1.82 1.83 PLUOOS 40 1.94 1.94 2.02 30 2.20 2.20 2.31 30 at > 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at t 50%F 2.58 2.58 2.67 25 at t 50%F 2.81 2.81 2.93 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of I MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

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 :5 50%, the LRNB event is the same with, or without PLUOOS.

Brw=ns Fefry Unit 2 Cycle 18 Cor OpeatgLrnis Report (105% OLTP)

Page 27 TVA-COLR-BF2C18, Revision 1 (F*I)

EDMS: L32 140820 800 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 Table 4.3 MCPRp Limits for Nominal Scram Time Basis (continued)*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.47 1.47 75 1.58 1.58 65 1.67 1.67 50 TBVOOS 50 1.83 1.83 FHOOS 40 2.03 2.03 30 2.31 2.31 30 at> 50%F 3.20 3.20 25 at > 50%F 3.61 3.61 30 at z 50%F 2.83 2.83 25 at z 50%F 3.25 3.25 100 1.45 1.46 1.47 75 1.55 1.56 1.58 65 1,73 1.75 1.75 50 TBVOOS 50 1.82 1.82 1.83 PUOOS 40 1.95 1.95 2.03 30 2.20 2.20 2.31 30 at> 50%F 3.06 3.06 3.20 25 at >, 50%F 3.47 3.47 3.61 30 at S 50%F 2.70 2.70 2.83 25 at ý; 50%F 3.10 3.10 3.25 100 1.44 1.44 75 1.54 1.55 65 1.73 1.75 50 FHOOS 50 1.82 1.83 PUOOS 40 2.02 2.02 30 2.31 2.31 30 at > 50%F 2.75 2.75 25 at > 50%F 3.04 3.04 30 at t 50%F 2.67 2.67 25 at r 50%F 2.93 2.93 100 1.47 1.47 75 1.58 1.58 65 1.73 1.75 50 TBVOOS 50 1.83 1.83 FHOOS 40 2.03 2.03 PLUOOS 30 2.31 2.31 30 at > 50%F 3.20 3.20 25 at >, 50%F 3.61 3.61 30 at s 50%F 2.83 2.83 25 at s 50%F 3.25 3.25 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

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 eadier exposure applicability windows.

A 50% power step change for PLUOOS limits is not supported. When core power is :5 50%, the LRNB event is the same with, or without PLUOOS.

Brons Ferry Urnt 2 Cycle 18 Core Operating Units Report, (105% OLTP)

Page 28 TVA-COLR-BF2C18, Revision 1 (Final)

EDMS: L32 140820 800 ED INPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.43 1.43 1.45 75 1.54 1.54 1.57 65 1.62 1.62 1.66 50 1.77 1.77 1.84 50 1.82 1.84 1.85 Base Case 40 1.96 1.96 2.04 30 2.22 2.22 2.33 30 at > 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at r 50%F 2.58 2.58 2.67 25 at g 50%F 2.81 2.81 2.93 100 1.46 1.47 1.48 75 1.57 1.58 1.61 65 1.66 1.66 1 69 50 1.79 1.79 50 1.82 1.84 1.85 TBVOOS 40 1.97 1.97 2.05 30 2.23 2.23 2.33 30 at > 50%F 3.06 3.06 3.20 25 at > 50%F 3.47 3.47 3.61 30 at i; 50%F 2.70 2.70 2.83 25 at. 50%F 3.10 3.10 3.25 100 1.45 1.45 75 1.57 1.57 65 1.66 1.66 50 50 1.84 1.84 FHOOS 40 2.04 2.04 30 2.33 2.33 30 at > 50%F 2.75 2.75 25 at ý, 50%F 3.04 3.04 30 at s 50%F 2.67 2.67 25 at S 50%F 2.93 2.93 100 1.43 1.43 1.45 75 1.54 1.54 1.57 65 1.74 1.77 1.77 50 50 1.83 1.84 1.85 PLUOOS 40 1.96 1.96 204 30 2.22 2.22 2.33 30 at > 50%F 2.64 2.64 2.75 25 at > 50%F 2.91 2.91 3.04 30 at 9 50%F 2.58 2.58 2.67 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.

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

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

Browns Ferry Unit 2 Cycle 18 Core Opeating Lt Report (105% OLTP)

Page 29 TVA-COLR-BF2CI18, Revision 1 (Final)

EDMS: L32 140820 800 Date: August 20, 2014 IM ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.4 MCPRp Limits for Technical Specification Scram Time Basis (continued)*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.48 1.48 75 1 60 1.61 65 1.69 1.69 50 TBVOOS 50 1.85 1.85 FHOOS 40 2.05 2.05 30 2.33 2.33 30 at > 50%F 3.20 3,20 25 at > 50%F 3.61 3.61 30 at

• 50%F 2.83 2.83 25 at

• 50%F 3.25 3.25 100 1.46 1.47 1.48 75 1.57 1.58 1 61 65 1.74 1.77 1.77 50 TBVOOS 50 1.83 1.84 1.85 PtUOOS 40 1.97 197 2.05 30 2.23 2.23 2.33 30 at> 50%F 3.06 3.06 3.20 25 at > 50%F 3.47 3.47 3.61 30 at I 50%F 2.70 2.70 2.83 25 at 9 50%F 3.10 3.10 3.25 100 1.45 1.45 75 1.57 1.57 65 1.74 1.77 50 FHOOS 50 1.84 1.84 PtUGos 40 2.04 2.04 30 2.33 2.33 30 at> 50%F 2.75 2.75 25 at > 50%F 3.04 3.04 30 at < 50%F 2.67 2.67 25 at!; 50%F 2.93 2.93 100 1.48 1.48 75 1.60 1.61 65 1.74 1.77 50 TBVOOS 50 1.85 1.85 FHOOS 40 2.05 2.05 PLUOOS 30 2.33 2.33 30 at > 50%F 3.20 3.20 25 at>* 50%F 3.61 3.61 30 at f 50%F 2.83 2.83 25 at i 50%F 3.25 3.25 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

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 Fery Unit 2 Cyde 18 Core eaing Linits Report, (105% OLTP)

Page 30 TVANCOLR-BF2C18, Revision 1 (Frial)

EDMS: L32 140820 800 Date: August 20, 2014 BIMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.5 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:

Technical Specification Scram Time Basis BOC BOC BOC Operating Power to to to End of Condition

(% of rated)

NEOC EOCLB Coast 100 1.45 1.45 1.45 75 1.57 1.57 1.57 65 1.74 1177 1.77 50 1.84 1.84 1.84 50 1.99 1.99 1.99 TBVIS 40 2.24 2.24 224 30 2.58 2.58 2.58 30 at> 50%F 3.00 3.00 3.00 25 at> 50%F 3.37 3.37 3.37 30 at f 50%F 2.90 2.90 2.90 25 at s 50%F 3.23 3.23 3.23 100 1.48 1.48 1.48 75 1.60 1.61 1.61 65 1.74 1.77 1.77 50 1.85 1.85 1.85 50 2.00 2.00 2.00 TBVOOS 40 2.24 2.24 2.24 30 2.58 2.58 2.58 30 at > 50%F 3.41 3.41 3.41 25 at>* 50%F 3.85 3.85 3.85 30 at z 50%F 3.02 3.02 3.02 25 at ! 50%F 3.51 3.51 3.51 Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

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

Blrows Ferry Unit 2 Cycle 18 Core Operang Umits Report (105% OLTP)

Page 31 rVA-COLR-BF2C18, Revision 1 (Fhal)

EDMS: L32 140820 800 Date: August 20, 2014 EL! NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.6 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Technical Specification Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.45 1.45 1.45 75 1.57 1.57 1.57 65 1.74 1.77 1.77 50 1.84 1.84 1.84 50 2.00 2.00 2.00 TBVIS 40 2.25 2.25 2.25 30 2.60 2.60 2.60 30 at > 50%F 3.01 3.01 3.01 25 at > 50%F 3.39 3.39 3.39 30 at s 50%F 2.91 2.91 2.91 25 at f. 50%F 3.25 3.25 3.25 100 1.48 1.48 1.48 75 1.60 1.61 1.61 65 1.74 1.77 1.77 50 1.85 1.85 1.85 50 2.00 2.00 2.00 TBVOOS 40 2.25 2.25 2.25 30 2.60 2.60 2.60 30 at> 50%F 3.42 3.42 3.42 25 at > 50%F 3.87 3.87 3.87 30 at g 50%F 3.04 3.04 3.04 25 at g 50%F 3.53 3.53 3.53 Limits support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

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

Browns Ferry Unit 2 Cycle 18 Core Operating Urrits Repot (105% OLTP)

Page 32 TVA-COLR-BF2C18, Revision 1 (Fina)

EDMS: L32 140820 800 EIMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 Table 4.7 MCPRp Limits for Single Loop Operation for All Scram Times BOC to Operating Pow er End of Condition

(% of rated)

Coast 100 1.92 50 1.92 40 2.06 RCPOOS 30 2.35 FHOOS 30 at > 50%F 2.77 25 at > 50%F 3.06 30 at < 50%F 2.69 25 at S 50%F 2.95 100 1.92 50 1.92 RCPOOS 40 2.07 TBVOOS 30 2.35 PLUOOS 30 at > 50%F 3.22 FHOOS 25 at > 50%F 3.63 30 at5 <50%F 2.85 25 at < 50%F 3.27 100 2.02 50 2.02 RCPOOS 40 2.26 30 2.60 TBOOSI 30 at > 50%F 3.43 FHOOS 1 25 at > 50%F 3.87 30 at: <50%F 3.04 25 at<50%F 3.53 100 2.02 50 2.02 40 2.27 30 2.62 TVOOS2 30 at > 50%F 3.44 FHOOS2 25 at > 50%F 3.89 30 at: <50%F 3.06 25 at<50%F 3.55 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.

FFWTR and FHOOS assume the same value of temperature drop.

RCPOOS limits are only valid up to 50% rated core power, 50% rated core flow, and an active recirculation drive flow of 17.73 Mlb,,/hr.

Brons Fery Unit 2 Cycle 18 Core Operating Umits Report (105% OLTP)

Page 33

[VA-COLR-BF2C18, Revision 1 (Fnal)

EDMS: L32 140820 800 DIMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 5

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

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

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

The resulting stability based OLMCPR's are reported in Reference 1. The OPRM setpoint (sometimes referred to as the Amplitude Trip, Sp) is selected, such that required margin to the SLMCPR is provided without stability being a limiting event. Analyses are based on cycle specific DIVOM analyses performed per Reference 23. The calculated OLMCPR's are shown in Table 5.1. Review of results shown in COLR Table 4.2 indicates an OPRM setpoint of 1.14 may be used. The successive confirmation count (sometimes referred to as Np) is provided in Table 5.2, per Reference 28.

Table 5.1 OPRM Setpoint Range*

OPRM OLMCPR OLMCPR Setpoint (SS)

(2PT) 1.05 1.17 1.12 1.06 1.19 1.14 1.07 1.21 1.16 1.08 1.23 1.18 1.09 1.25 1.19 1.10 1.27 1.21 1.11 1.29 1.23 1.12 1.31 1.25 1.13 1.33 1,27 1.14 1.35 1.29 1.15 1.37 1.32 Table 5.2 OPRM Successive Confirmation Count Setpoint Count OPRM Setpolnt 6

> 1.04 8

> 1.05 10

> 1.07 12

> 1.09 14 2 1.11 16 a 1.14 18

> 1.18 20

> 1.24

• Extrapolation beyond a setpoint of 1.15 is not allowed Browns Fery Unit 2 Cycle 18 Core Operaing Lirmits Report (105% OLTP)

Page 34 TVA-COLR-BF2C18, Revision 1 (F'wa*)

EDMS: L32 140820 800 Date: August 20, 2014 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 6 APRM Flow Biased Rod Block Trip Settings (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

The APRM rod block trip setting is based upon References 24 & 25, and is defined by the following:

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

SRB < (0.66(W-AW) + 59%)

Allowable Value 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%).

EBowns Ferry Urnt 2 Cycle 18 Core Opetig LrniAs Report (105% OLTP)

Page 35 TVA-COLR-BF2C18, Revision 1 (Firn)

EDMS: L32 140820 800 IM !iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: August 20, 2014 7

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

The RBM trip setpoints and applicable power ranges, based on References 24 & 25, are shown in Table 7.1. Setpoints are based on an HTSP, unfiltered analytical limit of 114%. Unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds; filtered setpoints are consistent with a nominal RBM filter setting less than 0.5 seconds. Cycle specific CRWE analyses of OLMCPR are documented in Reference 1, superseding values reported in References 24, 25, and 27.

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

- filtered Allowable Value (AV) 27%

62%

82%

121.7%

120.7%

Nominal Trip Setpoint (NTSP) 25%

60%

80%

120.0%

119.0%

ITSP

- unfiltered

- filtered HTSP - unfiltered

- filtered 116.7%

115.7%

111.7%

110.9%

90%

115.0%

114.0%

110.0%

109.2%

92%

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

Table 7.2 RBM Setpoint Applicability Thermal Power Applicable Notes from

(% Rated)

MCPRt Table 3.3.2.1-1 Comment

< 1.72 (a), (b), (f), (h) two loop operation

> 27% and < 90%

< 1.75 (a), (b), (f), (h) single loop operation a 90%

< 1.42 (g) two loop operationt Values are considered maximums. Using lower values, due to RBM system hardware/software limitations, is conservative, and acceptable.

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

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

Browns Feny Unit 2 Cycle 18 Core OperatgmLkits Report (105% OLTP)

Page 36 TVA-COLR-BF2018, Revision I (Fna)

EDMS: L32 140820 800 Date: August 20, 2014 IM ~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 1.24 111 1.31 114 1.34 117 1.36 Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 114% unblocked).

Brows Ferry Unit 2 Cycle 18 Core OpeigVkrits Report, (105% OLTP)

Page 37 TVA-COLR-BF2C18, Revision 1 (FaOl)

EDMS: L32 140820 800 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 M

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% dklk Brovma Ferry Unit 2 Cyde 18 Core Operating Limits Report (105% OLTP)

Page 38 TVA-COLR-BF2C18, Revision I (FiaI)

Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 17 Operation TVA-COLR-BF3CI7, Revision I (See Attached)