ML14247A310

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TVA-COLR-BF3C17, Rev. 1, Browns Ferry Unit 3 Cycle 17 Core Operating Limits Report
ML14247A310
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 08/29/2014
From: Eichenberg T
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
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References
TVA-COLR-BF3C17, Rev 1
Download: ML14247A310 (40)
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U EDMS L32 140820 801 QA Document PPages Affected All gBFE-303 Retseon 1 Reactor Engineering and Fuels - BWRFE 1101 Market Street. Chattanooga TN 37402 Browns Ferry Unit 3 Cycle 17 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF3C17 Revision I (Final)

(Revision Log Page v)

August 2014 Prepared:* *-!

r z

T W Eichenberg, Sr Specialist Verified:

Date:

qv5-

.,(

Dateý fll;?o MI Verified-f itchell, Engineer Approved G, C Storey. Mana er, (2~/(4 Date BWR Fuel Engineering Reviewed&

Date:

_121_//y D D Coffey. Manager. Reactor Engineering Approved Date:

_?__

I Date:

Approved U

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 N PG 1101 Market Street, Chattanooga TN 37402 Table of Contents Total Number of Pages = 40 (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 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 Operation Limit: APLHGRSLO.................................

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 Limit: LHGRF.............................

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..........................................................

36 6

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

37 7

Rod Block M onitor (RBM ) Trip Setpoints and O perability..................................................

38 8

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

40 Brovn s Ferry Unit 3 Cyce 17 Page ii Core Operating Umits Report (105% OLTP)

TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 ELM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 List of Tables Nuclear Fuel Types.....................................................................................................................

11 Startup Feedw ater Tem perature Basis...................................................................................

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

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

26 M CPRp Lim its for Nom inal Scram Tim e 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 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1: Nominal Scram Time B a s is...........................................................................................................................................

3 3 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2: Nominal Scram Time B a s is...........................................................................................................................................

3 4 M CPRp Lim its for Single Loop Operation for All Scram Tim es...................................................

35 O PRM Setpoint Range...............................................................................................................

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

36 Analytical RBM Trip Setpoints..............................................................................................

38 RBM Setpoint Applicability..........................................................................................................

38 Control Rod W ithdrawal Error Results...................................................................................

39 Bmns Ferry Unit 3 Cyde 17 Core Operatig Liits Report (105% OLTP)

Page iii TVA-COLR-BF3C17, Revision 1 (F-rr)

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 N PG 1101 Market Street, Chattanooga TN 37402 List of Figures APLHG RRATED for ATRIUM -1 0 Fuel.......................................................................................

13 LHG R RATED for ATR IU M -10 Fuel............................................................................................

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

18 LHG R FAC F for ATR 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 AT R IUM -10 Fuel..................................................................................................

25 Bmwns Feny Unit 3 Cyde 17 Core Opera" Inits Report (105% OLTP)

Page iv TVA-COLR-8F3C17, Revision 1 (Fina

EDMS: L32 140820 801 Date: August 20, 2014 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Revision Log Number Page 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.

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-R1 26-34 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 4.9, and footnotes, showing the explicit MCPRp limits for single loop operation (RCPOOS) 0-RO All New document.

Brmns Femj Unit 3 Cyde 17 Core Operating LkTts Report, (105% OLTP)

Page v TVA-COLR-BF3C17, Revision 1 (Fnal)

EDMS: L32 140820 801 Date: August 20, 2014

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Nomenclature APLHGR APRM AREVA NP ARTS Average Planar LHGR Average Power Range Monitor Vendor (Framatome, Siemens)

APRM/RBM Technical Specification Improvement BOC BWR Beginning of Cycle Boiling Water Reactor CAVEX CD CMSS COLR CPR CRWE CSDM DIVOM ECCS 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 Emergency Core Cooling System 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 Linear Heat Generation Rate LHGR Multiplier (Power or Flow dependent)

Low Power Range Monitor Generator Load Reject, No Bypass LCO LFWH LHGR LHGRFAC LPRM LRNB Biuws Ferry U 3 Cycle 17 CoeOp~era"~LkTIts Report (105% OLIP)

Page vi TVA-COLR-BF3C17, Revision 1 (Firl)

EDMS: L32 140820 801 Date: August 20, 2014 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 MAPFAC MCPR MELL MSRV MSRVOOS MTU MWd/MTU NEOC NRC NSS NTSP OLMCPR OOS OPRM OSS PBDA Pbypass PLU PLUOOS PRNM RBM RCP RCPOOS RPS RPT RPTOOS SDM SLMCPR SLO SRV SRVOOS TBV TBVIS TBVOOS TIP TIPOOS TLO TSP TSSS TVA MAPLHGR multiplier (Power or Flow dependent)

Minimum CPR Maximum Extended Load Line Moisture Separator Reheater Valve MSRV OOS Metric Ton Uranium Mega Watt Day per Metric Ton Uranium Near EOC United States Nuclear Regulatory Commission Nominal Scram Speed Nominal TSP MCPR Operating Limit Out-Of-Service Oscillation Power Range Monitor Optimum Scram Speed Period Based Detection Algorithm Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed Power Load Unbalance PLU OOS Power Range Neutron Monitor Rod Block Monitor Recirculation Pump RCP OOS Reactor Protection System Recirculation Pump Trip RPT OOS Shutdown Margin MCPR Safety Limit Single Loop Operation Safety Relief Valve SRV OOS Turbine Bypass Valve TBV IS TBV OOS Transversing In-core Probe TIP OOS Two Loop Operation Trip Setpoint Technical Specification Scram Speed Tennessee Valley Authority Brwns Ferry Unit 3 Cycle 17 Core Operat UT& Report (105% OLTP)

Page vii TVA-COLR-BF3C17, Revison 1 (Fr.)

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 M NPG 1101 Market Street, Chattanooga TN 37402 References

1.

ANP-3264, Revision 2, Browns Ferry Unit 3 Cycle 17 Reload Safety Analysis, AREVA NP, Inc., July 2014.

2.

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

3.

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

4.

ANP-3222(P) Revision 0, Browns Ferry Unit 3 Cycle 17 Plant Parameters Document, AREVA NP, Inc., May 2013.

5.

BFE-3600, Revision 0, Browns Ferry Unit 3 Cycle 17 Incore Shuffle, Tennessee Valley Authority, January, 2014.

Methodology References

6.

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.

7.

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

8.

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.

9.

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

10.

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.

11.

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.

12.

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.

13.

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.

14.

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.

l~rmm Ferry Unit 3Cycle17 Core OpeatingUits Report (105% OLTP)

Page viii TVA-COLR-BF3C17, Revsion 1 (F-n*)

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 M NPG 1101 Market Street, Chattanooga TN 37402

15.

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.

16.

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.

17.

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

18.

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

September 2009.

19.

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.

20.

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

21.

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.

22.

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

PRNM Setpoint References

23.

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.

24.

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.

25.

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

26.

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.

27.

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

Bro s Ferry Unit 3 Cyce 17 Page ix Core Operatng LUrnts Repat (105% OLTP)

TVA-COLR-BF3C17, Revision 1 (F-ial)

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 N PG 1101 Market Street, Chattanooga TN 37402 1 Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

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

1.2 Scope This document will discuss the following areas:

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

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

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

Applicability: Mode 1, 2 25% RTP (Technical Specifications definition of RTP)

> Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

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

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

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

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

Applicability: Mode 1, 2: (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, Ž: % RTP as specified in Table 33.21-1 (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 5.

Brons Ferry Unit 3 Cycle 17 Page 10 Core Operatng Limits Report (105% OLTP)

TVA-COLR-BF3C17, Revision 1 (Firas)

EDMS: L32 140820 801 Date: August 20, 2014 EIMNPG 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 A10-3831B-15GV80-FCD 15 120 6

FCDO01-FCD200 ATRIUM-10 A10-3403B-9GV80-FCD 15 20 7

FCD257-FCD276 ATRIUM-10 A10-3392B-10GV80-FCD 15 7

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

9 FCC217-FCC218 ATRIUM-10 Al0-4218B-13GV80-FCC 15 4

10 FCC307-FCC310 ATRIUM-10 Al0-3757B-10GV80-FCC 15 40 11 FCC335-FCC374 ATRIUM-10 Al0-3440B-1 1 GV80-FCE 16 144 12 FCE001-FCE144 ATRIUM-10 Al0-3826B-13GV80-FCE 16 44 13 FCE145-FCE188 ATRI UM-10 Al0-4075B-13GV80-FCE 16 47 14 FCE189-FCE236 ATRIUM-10 A10-4081B-12GV80-FCE 16 48 15 FCE237-FCE284 ATRIUM-10 A10-3849B-13GV80-FCF 17 176 16 FCF301-FCF476 ATRIUM-10 A10-3882B-1OGV70-FCF 17 40 17 FCF477-FCF516 ATRIUM-10 A10-4116B-12GV70-FCF 17 72 18 FCF517-FCF588 1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 6 through 22.

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.

Bwrs Ferry Unit3 Cycle 17 Core Operang Limt Report (105% OLTP)

Page 11 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 IM NPG 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 off-rated power APLHGR limit APLHGRF off-rated flow APLHGR limit APLHGRsLO 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-1 0 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-10 fuel is 0.85, per Reference 1.

Brons Ferry Unit 3 Cyde 17 Core OWatin Urrits Report (105% OLTP)

Page 12 TVA-COUR-BF3C17, Revision 1 (F-aDl)

EDMS: L32 140820 801 Date: August 20, 2014 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 15 V

Y 12 0

9 6

3 0

0 20 40 60 80 Planar Average Exposure (GWd/MTU)

Planar Avg.

APLHGR Exposure Limit (GWd/fTU" (kW/ft) 0.0 12.5 15.0 12.5 67.0 73 Figure 2.1 APLHGRRATED for ATRIUM-10 Fuel Brwns Feffy Unit 3 Cyde 17 Core p atimg its Report (105% OLTP)

Page 13 TVA-COLR-BF3C17, Revision 1 (Fral)

EDMS: L32 140820 801 Date: August 20, 2014 IM ~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.

Browns Fery Unit 3 Cyde 17 Core pg Lits Report (105% OLTP)

Page 14 TVA-COLR-BF3C17, Revision 1 (lFina)

EDMS: L32 140820 801 Date: August 20, 2014 EIU 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 and 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. 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 I Range 2

(% Rated)

(*F)

(OF) 25 160.0 155.0 30 165.0 160.0 40 175.0 170.0 50 185.0 180.0 B&mmo Fery Unit 3 Cyde 17 Core Operating Lh Report (105% OLTP)

Page 15 TVA-COLR-BF3C17, Revision 1 (Ffrf )

EDMS: L32 140820 801 Date: August 20, 2014 IM INPG 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 3 Cycle 17 Core Operal Lits Report (105% OLTP)

Page 16 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 IM ~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 15 12

-9 C)

IX 3

0 0

20 40 60 80 Pellet Exposure (GWd/MTU)

Pellet Exposure (dGTLU 0.0 18.9 74.4 t LHGR Limit (kWIft) 13.4 13.4 7.1 Figure 3.1 LHGRRATED for ATRIUM-10 Fuel

&mm Ferry Unit 3 Cyde 17 CoeOperatkng Lirrs Repotr (105% OLTP)

Page 17 TVA-COLR-BF3C17, Revision 1 (FrIn)

EDMS: L32 140820 801 Date: August 20, 2014

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 0~

C-)

U-0z-J 1.10 1.00 0.90 Turbine Bypass Valve In-Service, TBVIS 0.80 Turbine Bypass Valve Out-of-Service, TBVOOS 0.70 0.60 TBVIS, s 50% Core Flow 0.50 TBVIS, > 50% Core Flow TBVOOS,, 50% Core Row TBVOOS, > 50% Core Flow 0.40 0.30

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

Turbine Bypass In-Service Core Power LHGRFACp

(%Rated)1 100.0 1.00 30.0 0.61 Core Flow > 50% Rated 30.0 0.48 25.0 0.43 Core Flow < 50% Rated 30.0 I

0.50 25.0 0.45 Turbine Bypass Core Out-of-Service Power LHGRFACP

(% Rated)I 100.0 0.95 30.0 0.61 Core Flow > 50% Rated 30.0 1

0.43 25.0 0.41 Core Flow:5 500% Rated 30.0 I

0.48 25.0 0.41 Figure 3.2 Base Operation LHGRFACp for ATRIUM-10 Fuel (Independent of other EOOS conditions)

Brovmm Ferry Unit 3 Cyde 17 Core Oeat Limnits Report (105% OLTP)

Page 18 TVA-COLR-BF3C17, Revision I (Final)

EDMS: L32 140820 801 Date: August 20, 2014 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 I

I 1.10 1.05 1.00 U.

U.

0.95 0.90 0.85 0.80 0

10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow LHGRFACF

(% Rated) 0.0 0.93 30.0 0.93 46.4 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 Ferry Unit 3 Cyde 17 Core Operating Limits Repot (105% OLTP)

Page 19 TVA-COLR-BF3C17, Revision 1 (Ft)

EDMS: L32 140820 801 Date: August 20, 2014 IM ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 C.,

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 Turbin Bypass Valve Out-of-Service, TBVOOS T*BI0 0ey s

eOoFwow TBVIS, !5 50% Core Flow

TBVOOS, 50% Core Flow TBVIS, > 50% Core Flow "BVOOS, > 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 0.56 Core Flow > 50% Rated 30.0 J

0.42 25.0 0.37 Core Row < 50% Rated 30.0 J

0.45 25.0 0.39 Turbine Bypass Out-of-Service Core Power LI-IGRFACp

(%Rated) 100.0 0.95 30.0 0.56 Core Fow > 50% Rated 30.0 1

0.38 25.0 0.33 Core Flow < 50%Rated 30.0 1

0.43 25.0 J

0.36 Figure 3.4 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

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

Browns Ferry Unit 3 Cyde 17 Core Operating LInits Report, (105% OLTP)

Page 20 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 EIMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 a.CL U-1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 n in Turbine Bypass Valve In-Service, TBVIS Turbine Bypass Valve Out-of-Service, TBVOOS "BVIS, s50%CoreFlow TBVOOS, S 50% Core Flow TBVIS, > 50% Core Flow I

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 0.56 Core Row > 50% Rated 30.0 f

0.42 25.0 0.37 Core Flow S 50% Rated 30.0 0.44 25.0 0.39 Turbine Bypass Out-of-Service Core Power LHGRFACp

(%RateMd) J 100.0 0.95 30.0 0.56 Core Row > 50% Rated 30.0 0.37 25.0 0.33 Core Row < 50% Rated 30.0 0.43 25.0 0.36 Figure 3.5 Startup Operation LHGRFACp for ATRIUM-10 Fuel:

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

Brons Ferry Unit 3 Cycle 17 Core Operating Lirmts Report (105% OLTP)

Page 21 TVA-COLR-BF3C17, Revision 1 (F'iai)

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 M

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, consistent with 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 through Table 4.8, based on temperature conditions identified in Table 3.1.

Brons Ferry Unit 3 Cycle 17 Page 22 Core Operating Units Report (105% OLTP)

TVA-COLR-BF3C17, Revision 1 (Finail)

EDMS: L32 140820 801 Date: August 20, 2014 EIMNPG 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 DeDendent 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 27,393.0 MWd / MTU 31,304.9 MWd / MTU 32,724.6 MWd / MTU NEOC refers to a Near EOC exposure point.

Reference 1 analysis results are based on information identified in Reference 4.

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

Brons Ferry Unit 3 Cycle 17 Core Operatig inits Report (105% OLTP)

Page 23 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 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 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-Looo-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 4.9.

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.

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.

Browns FerryUnit 3Cyle 17 Core Ota"Lkfit Report (105% OLTP)

Page 24 TVA-COLR-8F3C17, Revision I (Final)

EDMS: L32 140820 801 Date: August 20, 2014 ELM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2.00 1.80 1.60 I-IL 1.40 1.20 1.00 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow MCPRF

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

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

Brons Ferry Unit 3 Cyde 17 Core Operating Units Report, (105% OLTP)

Page 25 IVA-COLR-8F3C17, Revision 1 (Final)

EDMS: L32 140820 801 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 1.38 1.41 1.43 75 1.51 1.51 1.55 65 1.57 1.57 1.61 50 1.70 1.70 1.76 50 1.93 1.93 1.93 Base Case 40 2.03 2.03 2.03 30 2.19 2.19 2.30 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at : 50%F 2.45 2.45 2.52 25 at < 50%F 2.68 2.68 2.80 100 1.40 1.43 75 1.55 1.55 65 1.61 1.61 50 1.76 1.76 50 1.93 1.93 FH-OOS 40 2.03 2.03 30 2.30 2.30 30 at > 50%F 2.63 2.63 25 at > 50%F 2.89 2.89 30 at < 50%F 2.52 2.52 25 at: <50%F 2.80 2.80

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

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

I Browns Feny Unit 3 Cycle 17 Core Operating tiri Report (105% OLTP)

Page 26 rVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 IM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 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 1.40 1,42 1.43 75 1.53 1.53 1.56 65 1,59 1.59 1.62 50 1.72 172 179 50 1.93 1.93 1.94 Base Case 40 2.04 2.04 2.04 30 2.22 2.22 2.33 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 289 30 at < 50%F 2.45 2.45 2.52 25 at5 50%F 2.68 2.68 2.80 100 1.44 1.46 147 75 1,57 1.57 1.60 65 1.62 1.63 1.66 50 1.75 1.75 1.81 50 1.93 1,93 1.94 TBVOOS 40 2.04 2.04 2.04 30 2.23 2.23 2,34 30 at > 50%F 3.14 3.14 3,26 25 at > 50%F 3.53 3.53 3.64 30 at5 50%F 2.74 2.74 2.88 25 ats

<50%F 3.17 3.17 3.32 100 1.43 1.43 75 1.55 1,56 65 1.62 1.62 50 1.79 1.79 50 1.94 1.94 FHOOS 40 2.04 2.04 30 2.33 2.33 30 at > 50%F 2.63 2.63 25 at > 50%F 2.89 2.89 30 at <50%F 2.52 2.52 25 at5 50%F 2.80 2.80 100 1.40 1.42 1.43 75 1.53 1.53 1.56 65 1.82 1.82 1.83 50 50 1.94 1,94 1.94 PLUOOS 40 2.04 2.04 2,04 30 2.22 2.22 2.33 30 at > 50%F 2.53 2.53 2ý63 25 at > 50%F 2.77 2.77 2.89 30 at 5 50%F 2.45 2.45 2.52 25 at 5 50%F 2.68 2.68 2.80 All limits, including "Base Case," support RPTOOS operation; operation is supported for any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service, 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 I

Bro&M Feny Unit 3 Cycle 17 Core Opeating Lits Report (105% OLTP)

Page 27 TVA-COLR-BF3C17, Revision 1 (Fuial)

EDMS: L32 140820 801 Date: August 20, 2014 IM ?iNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 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 1.46 1.47 75 1.59 1.60 65 1.66 1.66 50 1.81 1.81 TBVOOS 50 1.94 1.94 EHOOS 40 2.04 2.04 30 2.34 2.34 30 at > 50%F 3.26 3.26 25 at > 50%F 3.64 3.64 30 at !5 50%F 2.88 2.88 25 at 5 50%F 3.32 3,32 100 1.44 1.46 1.47 75 1.57 1.57 1.60 65 1.82 1,82 1.83 50 mVOOS 50 1.94 1.94 1.94 40 2.04 2.04 2.04 30 223 2.23 2.34 30 at >50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at < 50%F 2.74 2.74 2.88 25 at! <50%F 3.17 3.17 3.32 100 1.43 1.43 75 1.55 1.56 65 1,83 1.83 50 FHOOS 50 1.94 1.94 PUOOS 40 2.04 2,04 30 2.33 2.33 30 at > 50%F 2.63 2.63 25 at > 50%F 2.89 2.89 30 at5 <50%F 2.52 2.52 25 atr

<50%F 2.80 2.80 100 1.46 1.47 75 1.59 1.60 65 1.83 1,83 50 TBVOOS 50 1.94 1.94 FHOOS 40 2.04 2.04 PLUOOS 30 2.34 2.34 30 at > 50%F 3.26 3,26 25 at > 50%F 3.64 3.64 30 at! <50%F 2.88 2.88 25 atS 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.

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.

Brwns Ferry Unit 3 Cycle 17 Core OpeatigLiits Report (105% OLTP)

Page 28 TVA-COLR-BF3C17, Revision 1 (Fra)

EDMS: L32 140820 801 Date: August 20, 2014 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 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 1.42 1.43 1.44 75 1.55 1.55 1.57 65 1.60 1.60 1.64 50 1.75 1.75 1.82 50 1.94 1.94 1.95 Base Case 40 2.05 2.05 2.05 30 2.24 2.24 2.36 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at: ;50%F 2.45 2.45 2.52 25 at < 50%F 2.68 2.68 2.80 100 1.46 1.47 1.48 75 1.59 1.59 1.61 65 1.64 1.64 1.68 50 1.77 1.77 1.83 50 1.94 1.94 1.95 TBVOOS 40 2.05 2.05 2.07 30 2.26 2.26 2.37 30 at >50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at <50%F 2.74 2.74 2.88 25 at5

<50%F 3.17 3.17 3.32 100 1.44 1.44 75 1.57 1.57 65 1.64 1.64 50 1.82 1.82 50 1.95 1.95 FHOOS 40 2.05 2.05 30 2.36 2.36 30 at > 50%F 2.63 2.63 25 at > 50%F 2.89 2.89 30 at! <50%F 2.52 2.52 25 at < 50%F 2.80 2.80 100 1.42 1.43 1,44 75 1.55 1.55 1.57 65 1.83 1.83 1.84 50 50 1.95 1.95 1.95 PLUOOS 40 2.05 2.05 2.05 30 2.24 2.24 2.36 30 at > 50%F 2.53 2.53 2.63 25 at > 50%F 2.77 2.77 2.89 30 at s 50%F 2.45 2.45 2.52 25 at < 50%F 2.68 2.68 2.80

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

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.

I Browns Ferry Unit 3 Cycle 17 Core Opera Lits Report (105% OLTP)

Page 29

[VA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 EIM 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 BOG Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.48 1.48 75 1.61 1.61 65 1.68 1.68 50 1.83 1ý83 TBVOOS 50 1.95 195 FHOOS 40 2.07 2.07 30 2.37 2.37 30 at > 50%F 3.26 3.26 25 at > 50%F 3.64 3.64 30 at!< 50%F 2.88 2.88 25 at 5 50%F 3.32 3.32 100 1.46 1,47 1.48 75 1.59 1.59 1.61 65 1.83 1.83 1,84 50 mVOOS 50 1.95 1.95 1.95 PtUOOS 40 2.05 2.05 2.07 30 2.26 2,26 2.37 30 at >50%F 3.14 3.14 3.26 25 at > 50%F 3.53 3.53 3.64 30 at S 50%F 2.74 2.74 2.88 25 at S 50%F 3.17 3.17 3.32 100 1.44 1.44 75 1.57 1.57 65 1.84 1.84 50 FHOOS 50 1.95 1.95 40 2.05 2.05 30 2.36 2.36 30 at > 50%F 2.63 2.63 25 at > 50%F 2.89 2.89 30 at < 50%F 2.52 2.52 25 at< 50%F 2.80 2.80 100 1.48 1.48 75 1.61 1.61 65 1.84 1.84 50 TBVOOS 50 1.95 1.95 FHOOS 40 2.07 2.07 PLUOOS 30 2.37 2.37 30 at > 50%F 3.26 3.26 25 at > 50%F 3.64 3.64 30 at S 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.

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

Browns Ferry Unit 3 Cycle 17 Core Operating LUrits Report (105% OLTP)

Page 30 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 I!NPG 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 Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.44 1.44 1.44 75 1.57 1.57 1.57 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 1.99 1.99 1.99 TBVIS 40 2.24 2.24 2.24 30 2.61 2.61 2.61 30 at > 50%F 2.88 2.88 2.88 25 at > 50%F 3.21 3.21 3.21 30 at s 50%F 2.79 2.79 2.79 25 at < 50%F 3.07 3.07 3.07 100 1.48 1.48 1.48 75 1.61 1.61 1.61 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 1.99 1.99 1.99 TBVOOS 40 2.25 2.25 2.25 30 2.61 2.61 2.61 30 at > 50%F 3.44 3.44 3.44 25 at > 50%F 3.85 3.85 3.85 30 at S 50%F 3.10 3.10 3.10 25 at s 50%F 3.54 3.54 3.54

  • 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.

Brow0s Ferry Unit 3 Cycle 17 Core Operating Limits Report (105% OLTP)

Page 31 TVA-COLR-BF3C17, Revision I (Final)

EDMS: L32 140820 801 Date: August 20, 2014 IMNPG 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 Operating Power to to to End of Condition

(% of rated)

NEWC EOCLB Coast 100 1.44 1.44 1.44 75 1.57 1.57 1.57 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 2.00 2.00 2.00 TBVIS 40 2.26 2.26 2.26 30 2.63 2.63 2.63 30 at > 50%F 2.90 2.90 2.90 25 at > 50%F 3.23 3.23 3.23 30 at S 50%F 2.80 2.80 2.80 25 at S 50%F 3.09 3.09 3.09 100 1.48 1.48 1.48 75 1.61 1.61 1.61 65 1.84 1.84 1.84 50 1.95 1.95 1.95 50 2.00 2.00 2.00 TBVOOS 40 2.26 2.26 2.26 30 2.63 2.63 2.63 30 at > 50%F 3.45 3.45 3.45 25 at > 50%F 3.86 3.86 3.86 30 at S 50%F 3.12 3.12 3.12 25 at < 50%F 3.56 3.56 3.56

  • 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 3 Cycle 17 Core O g Limrits Report (105% OLTP)

Page 32 TVA-COLR-BF3C17, Revision 1 (Fhl)

EDMS: L32 140820 801 Date: August 20, 2014 IM

~NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.7 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 1:

Nominal Scram Time Basis BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.43 1.43 1.43 75 1.55 1.56 1.56 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.96 1.96 1.96 TBVIS 40 2.22 2.22 2.22 30 2.58 2.58 2.58 30 at > 50%F 2.88 2.88 2.88 25 at > 50%F 3.21 3.21 3.21 30 at < 50%F 2.79 2.79 2.79 25 at < 50%F 3.07 3.07 3.07 100 1.46 1.47 1.47 75 1.59 1.60 1.60 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.96 1.96 1.96 TBVOOS 40 2.22 2.22 2.22 30 2.58 2.58 2.58 30 at > 50%F 3.44 3.44 3.44 25 at > 50%F 3.85 3.85 3.85 30 ats 50%F 3.10 3.10 3.10 25 at < 50%F 3.54 3.54 3.54 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.

B1rwns Ferry Unit 3 Cyle 17 Core Operating Lrmits Report (105% OLTP)

Page 33 TVA-COLR-BF3C17, Revision 1 (FfI)

EDMS: L32 140820 801 Date: August 20, 2014

~IMNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.8 Startup Operation MCPRp Limits for Table 3.1 Temperature Range 2:

Nominal Scram Time Basis*

BOC BOC BOC Power to to to End of Operating Condition

(% of rated)

NEOC EOCLB Coast 100 1.43 1.43 1.43 75 1.55 1.56 1.56 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.97 1.97 1.97 TBVIS 40 2.23 2.23 2.23 30 2.60 2.60 2.60 30 at > 50%F 2.90 2.90 2.90 25 at > 50%F 3.23 3.23 3.23 30 at < 50%F 2.80 2.80 2.80 25 at S 50%F 3.09 3.09 3.09 100 1.46 1.47 1.47 75 1.59 1.60 1.60 65 1.83 1.83 1.83 50 1.94 1.94 1.94 50 1.97 1.97 1.97 TBVOOS 40 2.23 2.23 2.23 30 2.60 2.60 2.60 30 at > 50%F 3.45 3.45 3.45 25 at > 50%F 3.86 3.86 3.86 30 at 5 50%F 3.12 3.12 3.12 25 at % 50%F 3.56 3.56 3.56 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.

Brons Ferry Unit3 Cyle 17 CoeOperaingLk~t Report (105% OLTP)

Page 34 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 EIM NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table 4.9 MCPRP Limits for Single Loop Operation for All Scram Times BOC to Power End of Operating Condition

(% of rated)

Coast 100 2.00 50 2.00 40 2.07 RCPOOS 30 2.38 FHOOS 30 at > 50%F 2.65 25 at > 50%F 2.91 30 at <50%F 2.54 25 at < 50%F 2.82 100 2.00 50 2.00 RCPOOS 40 2.09 TBVOOS 30 2.39 PLUOOS 30 at > 50%F 3.28 FHOOS 25 at > 50%F 3.66 30 at! <50%F 2.90 25 at s 50%F 3.34 100 2.01 50 2.01 40 2.27 Bvoos 30 2.63 FTBOOS1 30 at > 50%F 3.46 25 at > 50%F 3.87 30 at5 <50%F 3.12 25 at! <50%F 3.56 100 2.02 50 2.02 RCPOOS 40 2.28 TBVOOS 30 2.65 30 at > 50%F 3.47 25 at > 50%F 3.88 30 atS 50%F 3.14 25 at < 50%F 3.58

  • 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 Mlbm/hr.

Bro"is Feny Unit 3 Cycle 17 Core Operating Umits Report, (105% OLTP)

Page 35 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014 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 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 22. The calculated OLMCPR's are shown in Table 5.1. Review of results shown in 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 27.

Table 5.1 OPRM Setpoint Range*

OPRM OLMCPR OLMCPR Setolint (SS)

(2PT) 1.05 1.18 1.19 1.06 1.20 1.21 1.07 1.22 1.23 1.08 1.24 1.25 1.09 1.26 1.27 1.10 1.28 1.29 1.11 1.30 1.31 1.12 1.32 1.33 1.13 1.34 1.36 1.14 1.36 1.38 1.15 1.39 1.40 Table 5.2 OPRM Successive Confirmation Count Setpoint Count OPRM s_ pont 6

>1.04 8

Ž1.05 10

> 1.07 12

> 1.09 14

Ž1.11 16

>1.14 18

> 1.18 20

Ž 1.24

  • Extrapolation beyond a setpoint of 1.15 is not allowed Bowns Ferry Unit 3 Cyde 17 Core Openg Unts Report (105% OLTP)

Page 36 rVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Reactor Engineering and Fuels - BWRFE Date: August 20, 2014 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 23 & 24, 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%).

Brons Ferry Unit 3 Cycle 17 Core Operating Linits Report (105% OLTP)

Page 37 TVA-COLR-BF3C17, Revision 1 (Final)

EDMS: L32 140820 801 Date: August 20, 2014

~IMNPG 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 23 & 24, 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 23, 24, and 26.

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

- filtered ITSP - unfiltered

- filtered HTSP - unfiltered

- filtered Allowable Value (AV) 27%

62%

82%

121.7%

120.7%

116.7%

115.7%

111.7%

110.9%

90%

Nominal Trip Setpoint (NTSP) 25%

60%

80%

120.0%

119.0%

115.0%

114.0%

110.0%

109.2%

92%

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

Table 7.2 RBM Setpoint Applicability Thermal Power Applicable Notes from

(% Rated)

MCPRt Table 3.3.2.1-1 Comment

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

> 27% and < 90%

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

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

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

Boensm Ferry U1%t 3 Cycle 17 Core Oprtn Liit Report, (105% OLTP)

Page 38 TVA-0ý-BFK 17, Rew" 1 Fffl*

EDMS: L32 140820 801 Date: August 20, 2014 BIMNPG 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 Uknftred 107 1.28 111 1.31 114 1.33 117 1.35 Results, compared against the base case OLMCPR results of Table 4.2, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., 114% unblocked).

Bromns Ferry Unit 3 Cycle 17 Core Operatg Lits Report, (105% OLTP)

Page 39 TVA-COUR-BF3C17, Reision 1 (Frial)

EDMS: L32 140820 801 Date: August 20, 2014 U IfNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 8 Shutdown Margin Limit (Technical Specification 3.1.1)

Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLE control blades are fully inserted, the core shall be sub-critical and meet the following minimum shutdown margin:

SDM

> 0.38% dk/k Browns Ferry Unit 3 Cyde 17 Core Oerating Limits Report, (105% OLTP)

Page 40 TVA-COLR-BF3C17, Revision I (Frkal)

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