Enclosure TVA-COLR-BF1C9, Revision 0, dated October 2010 · 2012-12-04 · Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice

Tennessee Valley Authority1101 Market Street, LP 3RChattanooga, Tennessee 37402-2801

R. M. KrichVice PresidentNuclear Licensing

November 17, 2010

10 CFR 50.4

ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001

Browns Ferry Nuclear Plant, Unit 1Facility Operating License No. DPR-33NRC Docket No. 50-259

Subject: Browns Ferry Nuclear Plant, Unit 1, Core Operating Limits Report forCycle 9 Operation

In accordance with the requirements of Technical Specification 5.6.5.d, the TennesseeValley Authority is submitting the Browns Ferry Nuclear Plant, Unit 1, Cycle 9, CoreOperating Limits Report (COLR). The Unit 1, Cycle 9, COLR includes all modes ofoperation (Modes 1 through 5).

There are no new commitments contained in this letter. If you have any questions,please contact Tom Matthews at (423) 751-2687.

Respectfully,

R. M. Krich

Enclosure: Core Operating Limits Report, (105% OLTP), for Cycle 9 OperationTVA-COLR-BF1 C9, Revision 0, dated October 2010

cc (Enclosure):NRC Regional Administrator - Region IINRC Senior Resident Inspector - Browns Ferry Nuclear Plant

printed on recycled paper (U-

Enclosure

Tennessee Valley AuthorityBrowns Ferry Nuclear Plant

Unit I

Core Operating Limits Report, (105% OLTP), for Cycle 9 OperationTVA-COLR-BF1C9, Revision 0, dated October 2010

j

------ -------

ENO;' L-52 16016t 801QA oumentPagm Affmcf§d; Allh•flt--•30(1, Ivi•lfn 0

LINPGNuclear Fuel Engineering - BWRFE1101 Mrtker tret SUM attanooga, TN 37402

Browns Ferry Unit I Cycle 9Core Operating Limits Report, (105% OLTP)

TVA-COLR-BFIC9 Revision o (Finai)(OVtobe 010, P§00 V

October 2010

Prepared:, ;W.-, 9r _ ý i- Date:

Date: 0,,•-ii'ý ýohefl, E~ngineerVerified,

6,(. .....itApproved: / .Date,

BWR Fuel EngineeringG. C, Storey, Mai

36ek, Manager, Reator EngineeringDate; / Aozo/O_

Approved:

U

Nuclear Fuel Engineering - BWRFE

NPG Date: October 15, 2010

1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801

Table of ContentsTotal Number of Pages = 38 (including review cover sheet)

L is t o f T a b le s . ................................................................................................................................................ iiiL ist o f F ig u re s ................................................................................................................................................ iv

R e v is io n L o g ................................................................................................................................... vN o m e n c la tu re ................................................................................................................................................ v iReferences .................................................................................................... ................... ...... ....... viii

1 In tro d u c tio n ........................................................................................................................... 11 .1 P u rp o s e ......................................................................................................................... 11 .2 S c o p e ............................................................................................................................ 11.3 Fuel Loading .................................................................................................................. 11.4 Acceptability .................................................................................................................. 1

2 APLHG R Lim its .................................................................................................................... 32.1 Rated Power and Flow Lim it: APLHG RRATED ........................................................... 32.2 Off-Rated Power Dependent Lim it: APLHG Rp ......................................................... 32.3 Off-Rated Flow Dependent Lim it: APLHGRF ........................................................... 32.4 Single Loop O peration Lim it: APLHG RSLO ............................................................... 32.5 Equipment Out-Of-Service Corrections .................................. 5

3 LHG R Lim its ......................................................................................................................... 63.1 Rated Power and Flow Lim it: LHGRRATED ................................................................ 63.2 Off-Rated Power Dependent Lim it: LHG Rp ............................................................. 63.3 Off-Rated Flow Dependent Lim it: LHG RF ................................................................ 63.4 Single Loop O peration Lim it: LHG RSLO ........................................................................ 63.5 Equipm ent O ut-Of-Service Corrections .................................................................... 6

4 O LM CPR Lim its ................................................................................................................. 144.1 Rated Power and Flow Lim it: M CPRRATED ............................................................. 14

4.1.1 Scram Tim ing Dependence ............................................................................ 144.1.2 Equipment O ut-Of-Service (EOOS) Options .................................................. 154.1.3 Exposure Dependent Lim its ............................................................................ 15

4.2 Flow Dependent M CPR Lim it: M CPRF .................................................................. 164.3 Single Loop O peration Lim it: M CPRSLO .................................................................. 164.4 Power Dependent M CPR Lim it: M CPRp ............................................................... 16

5 APRM Flow Biased Rod Block Trip Settings .................................................................. 246 Rod Block M onitor (RBM ) Trip Setpoints and Operability ........................ ......................... 257 Shutdown Margin Lim it .................................................................................................. 27

Appendix A: Therm al-Hydraulic Stability ............................................................................. 28

Browns Feny Unit I Cycle 9 Page iiCore Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

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Date: October 15, 2010

EDM&S L32 101015 801

List of Tables

Nuclear Fuel Types ............................................................... I ....................................................... 2Analytical RBM Trip Setpoints .............................................................................................. 25RBM Setpoint Applicability .................................................................................................... 25

Control Rod W ithdrawal Error Results ................................................................................... 26

O PRM Setpoints ........................................................................................................................ 30

Browns Ferry Unit 1 Cyde 9Core Operating Limits Report, (105% OLTP)

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List of Figures

APLHGRRATED ............................................................................................................................... 4LHGRRATED for GE14 U0 2 Fuel ............................................................................................... 8LHGRFACp for All EIS or RPTOOS Conditions ........................................................................ 9LHGRFACp for TBVOOS Conditions ..................................................................................... 10LHGRFACp for PLUOOS Conditions ..................................................................................... 11LHGRFACP for RPTOOS, TBVOOS, and PLUOOS Conditions ............................................ 12L H G R F A C F ................................................................................................................................. 1 3M C P R F ........................................................................................................................................ 1 7MCPRRaed: BOC to MOC Exposure ..................................................................................... 18MCPRRated: BOC to EOC Exposure ....................................................................................... 19Kp M ultiplier and MCPRp for All Equipment In Service or RPTOOS ...................................... 20Kp M ultiplier and MCPRp for TBVOOS .................................................................................. 21Kp M ultiplier and M CPRp for PLUOOS .................................................................................. 22Kp Multiplier and MCPRp for RPTOOS, TBVOOS, and PLUOOS ......................................... 23

Browns Ferry Unit 1 Cycle 9Core Operating Limits Report, (105% OLTP)

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Revision Log

Number I Page Description

1 -RO All New document, per NFTP-1 11, Section 3.3, Item Q.

Browns Feny Unit 1 Cyde 9 Page v

Browns Ferry Unit R Cycle 9Core Operating Limits Report, (105% OLTP)

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<Nomenclature

APLHGRAPRMAREVA NP

BOCBSPBWR

CAVEXCDCMSSCOLRCPRCRWECSDM

DIVOM

EOCEOOS

FFTRFFWTRFHOOSft

GWd

HTSP

ICAICFIS

Average Planar LHGRAverage Power Range MonitorVendor (Framatome, Siemens)

Beginning of CycleBackup Stability ProtectionBoiling Water Reactor

Core Average ExposureCoast DownCore Monitoring System SoftwareCore Operating Limits ReportCritical Power RatioControl Rod Withdrawal ErrorCold SDM

Delta CPR over Initial CPR vs. Oscillation Magnitude

End of CycleEquipment OOS

Final Feedwater Temperature ReductionFinal Feedwater Temperature ReductionFeedwater Heaters OOSFoot: english unit of measure for length

Giga Watt Day

.High TSP

Interim Corrective ActionIncreased Core Flow (beyond rated)In-Service

kilo watt: SI unit of measure for power.

License Condition of OperationLoss of Feedwater HeatingLHGR Multiplier (Power or Flow dependent)Low Power Range MonitorGenerator Load Reject, No Bypass

kW

LCOLFWHLHGRFACLPRMLRNB

MAPFAC MAPLHGR multiplier (Power or Flow dependent)MCPR Minimum CPR


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MSRVMSRVOOSMTUMWd/MTU

NEOCNRCNSSNTSP

OLMCPROOSOPRM

PBDAPbypassPLUPLUOOSPRNM

RBMRPSRPTRPTOOS

SDMSLMCPRSLO

TBVTBVISTBVOOSTIPTIPOOSTLOTSPTSSSTVA

Moisture Separator Reheater ValveMSRV OOSMetric Ton UraniumMega Watt Day per Metric Ton Uranium

Near EOCUnited States Nuclear Regulatory CommissionNominal Scram SpeedNominal TSP

MCPR Operating LimitOut-Of-ServiceOscillation Power Range Monitor

Period Based Detection AlgorithmPower, below which TSV Position and TCV Fast Closure Scrams are BypassedPower Load UnbalancePLU OOSPower Range Neutron Monitor

Rod Block MonitorReactor Protection SystemRecirculation Pump TripRPT OOS

Shutdown MarginMCPR Safety LimitSingle Loop Operation

Turbine Bypass ValveTurbine Bypass Valve ISTurbine Bypass Valves OOSTransversing In-core ProbeTransversing In-core Probe OOSTwo Loop OperationTrip SetpointTechnical Specification Scram SpeedTennessee Valley Authority

Browns Ferry Unit 1 Cycle 9Core Operating Umits Report, (105% OLTP)

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References

1. 0000-01 13-6833-SRLR, Revision 0, Supplemental Reload Licensing Report BrownsFerry 1 Reload 8 Cycle 9, Global Nuclear Fuels, Inc., September 2010.

2. 0000-0077-8380-SRLR, Revision 0, Supplemental Reload Licensing Report BrownsFerry 1 Reload 7 Cycle 8, Global Nuclear Fuels, Inc., August 2008.

3. 0000-0044-1520-SRLR, Revision 0, Supplemental Reload Licensing Report BrownsFerry 1 Reload 6 Cycle 7, Global Nuclear Fuels, Inc., January 2007.

4. 0000-0113-6833-FBIR, Revision 0, Fuel Bundle Information Report Browns Ferry I

Reload 8 Cycle 9, Global Nuclear Fuels, Inc., September 2010.

Methodoloqy References

5. NEDE-24011-P-A-16, General Electric Standard Application for Reactor Fuel,October 2007.

6. NEDE 724011-P-A-16-US, General Electric Standard Application for Reactor Fuel(Supplement for United States), October 2007.

PRNM Setpoint References

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

8. Unfiltered Setpoints - EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, RBM, andRFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] forTennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.

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

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


Page viiiTVA-COLR-BF1C9, Revision 0 (Final)



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I IntroductionIn 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 technicalspecification section 5.6.5. This document may be provided, upon final approval, to the NRC.

1.2 Scope

This document will discuss the following areas:

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

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

> Minimum Critical Power Ratio Operating Limit (OLMCPR)(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

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

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

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

1.3 Fuel Loading

The core will contain all Global Nuclear Fuels, Inc., GE14 fuel. Nuclear fuel types used in thecore loading are shown in Table 1.1. The core shuffle and final loading were assessed todetermine Reference 1 applicability relative to minor loading changes.

1.4 Acceptability

Limits discussed in this document were generated based on NRC approved methodologies perReferences 5 through 6.

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Table 1.1 Nuclear Fuel Types

NuclearOriginal Number of Fuel Type Fuel Names

Fuel Description Cycle Assemblies (NFT) (Range)

GE 1 4-P1 ODNAB1 57-NOG-1 OOT-1 50-T6-2889 7 1 4 JLX209-JLX432

GE14-P1ODNAB377-16GZ-1OOT-150-T6-2890 7 37 5 JLX433-JLX528

GE 1 4-P1 ODNAB402-16GZ-1 OOT-1 50-T6-2891 7 31 6 JLX529-JLX560

GE 14-PI ODNAB350-16GZ-1 00T-1 50-T6-2892 7 20 7 JLX561-JLX592

GE1 4-P1 ODNAB419-16GZ-1 OOT-1 50-T6-2894 7 32 9 JLX613-JLX644

GE1 4-PI ODNAB368-15GZ-1 OOT-1 50-T6-2895 7 32 10 JLX645-JLX716

GE14-P1ODNAB402-19GZ-100T-150-T6-2896 7 24 11 JLX717-JLX740

GE 1 4-P1 ODNAB377-17GZ-1 OOT-1 50-T6-2897 7 8 13 JLX741-JLX772

GE14-PI ODNAB406-16GZ-1 OOT-1 50-T6-3078 8 48 14 JYE101-JYE148

GE 1 4-P1 ODNAB406-15GZ-1 OT-1 50-T6-3079 8 63 16 JYE245-JYE308

GE1 4-P1 ODNAB418-16GZ-1 OOT-1 50-T6-3080 8 72 18 JYE357-JYE428

GE 1 4-P1 ODNAB400-17GZ-1 OOT-1 50-T6-3081 8 96 15 JYE149-JYE244

GE 1 4-P1 ODNAB417-16GZ-1 OOT-1 50-T6-3082 8 48 17 JYE309-JYE356

GE 1 4-P1 ODNAB408-16GZ-1 OOT-1 50-T6-3363 9 180 1 JYP101-JYP280

GE1 4-P1 ODNAB412-16GZ-1 OOT-1 50-T6-3364 9 40 2 JYP281-JYP320

GE1 4-P1 ODNAB404-15GZ-1 OOT-1 50-T6-3365 9 16 8 JYP321 -JYP336

GE 1 4-P1 ODNAB408-17GZ-1 OOT-1 50-T6-3366 9 16 19 JYP337-JYP352

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


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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 the different fuel types, are identified in References 1, 2, & 3,and are shown in Figure 2.1.

2.2 Off-Rated Power Dependent Limit: APLHGRp

References 1 & 6 for GE14 fuel do not specify a power dependent APLHGR. Therefore,MAPFACp is set to a value of 1.0.

2.3 Off-Rated Flow Dependent Limit: APLHGRF

References 1 & 6 for GE14 fuel do 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 is 0.93, per Reference 1.


Page 3TVA-COLR-BF1 C9, Revision 0 (Final)

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15

12

6

< 6

3

00 20 40 60

Planar Average Exposure (GWd/MTU)

Planar Avg. Planar Avg. APLHGRExposure Exposure Limit

(GWd/MTU), (GWd/ST) (kW/ft)0.00 0.00 12.82

21.09 19.13 12.8263.50 57.61 8.0070.00 63.50 5.00

80

Figure 2.1 APLHGRRATED



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2.5 Equipment Out-Of-Service CorrectionsThe limit shown in Figure 2.1 is applicable for operation with all equipment In-Service as well asthe following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*

In-ServiceRPTOOSTBVOOS

PLUOOSFHOOS (or FFWTR)

All equipment In-ServiceEOC-Recirculation Pump Trip Out-Of-ServiceTurbine Bypass Valve(s) Out-Of-ServicePower Load Unbalance Out-Of-ServiceFeedwater Heaters Out-Of-Service or Final FeedwaterTemperature Reduction

Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to therated APLHGR limits as described previously.

All equipment service conditions assume 1 SRVOOS.


Page 5TVA-COLR-BFIC9, Revision 0 (Final)




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 off-rated power LHGR limit [LHGRRATED * LHGRFACp]

LHGRF off-rated flow LHGR limit [LHGRRATED* LHGRFACF]LHGRSLO SLO LHGR limit [LHGRRATED * SLO Multiplier]

3.1 Rated Power and Flow Limit: LHGRRATED

The rated conditions LHGR is identified in Reference 4, and shown in Figure 3.1 for U0 2 fuel.

Separate, concentration dependent limits apply for rods containing Gadolinium; LHGR limits are

provided in Reference 4.

3.2 Off-Rated Power Dependent Limit: LHGRp

LHGR limits are adjusted for off-rated power conditions using the LHGRFACp multiplierprovided in Reference 1. The multiplier is dependent on EOOS conditions. Consequently, themultipliers are shown in Figure 3.2 thru Figure 3.5, for various EOOS conditions/combinations.

3.3 Off-Rated Flow Dependent Limit: LHGRF

LHGR limits are adjusted for off-rated flow conditions using the LHGRFACF multiplier providedin Reference 1. There are no EOOS dependencies for the multiplier. The multiplier is shown in

Figure 3.6.

3.4 Single Loop Operation Limit: LHGRSLO

The single loop operation multiplier is 0.93, per Reference 1.

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

In-Service All equipment In-Service

RPTOOS EOC-Recirculation Pump Trip Out-Of-Service

TBVOOS Turbine Bypass Valve(s) Out-Of-Service

All equipment service conditions assume 1 SRVOOS.

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I



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PLUOOSFHOOS (or FFWTR)

SLO

Power Load Unbalance Out-Of-Service

Feedwater Heaters Out-Of-Service or Final FeedwaterTemperature ReductionSingle Loop Operation,One Recirculation Pump Out--Of-Service

Off-rated power corrections shown in Figure 3.2 thru Figure 3.5 cover various EOOS scenarios.

The limits have no dependency on FHOOS/FFWTR.

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Page 7TVA-COLR-BF1C9, Revision 0 (Final)




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15

12

C,=-J

9

6

3

00 20 40 60

Pellet Exposure (GWd/MTU)

Pellet Pellet LHGRExposure Exposure Limit

(GWd/MTU) (GWd/ST) (kW/ft)0.00 0.00 13.40

16.00' 14.51 13.4055.50 50.35 8.8063.50 57.61 7.1070.00 63.50 5.00

Figure 3.1 LHGRRATED for GE14 U0 2 Fuel

80






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1.10

1.00

0.90

0.80

C.

0.70

,-J

0.60

0.50

0.40

0.30

SCore Flow 4 80%

. ..-- -

..- 0

20 30 40 50 60 70 80

Core Power (% Rated)

90 100 110

CorePower LHGRFACp

(% Rated)100.0 1.00050.0 0.73950.0 0.68830.0 0.614

Core Flow > 50% Rated

30.0 0.46025.0 0.428

Core Flow <= 50% Rated

30.0 0.53825.0 0.533

Figure 3.2 LHGRFACp for All EIS or RPTOOS Conditions(with and without FHOOS)



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Nuclear Fuel Engineering - BWRFEt


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1.10

1.00

0.90

0.80

0.70C.)

-- I

0.60

0.50

0.40

0.30

20 30 40 50 60 70


80 90 100 110

CorePower LHGRFACp

(% Rated) _

100.0 1.00050.0 0.73950.0 0.68830.0 0.614


30.0 0.37125.0 0.315

Core Flow <= 50% Rated30.0 0.54925.0 0.473

Figure 3.3 LHGRFACp for TBVOOS Conditions(with and without FHOOS)


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I ,nJ

1.10

1.00

0.90

0.80

0.70

0.60

0.50

0.40'

0.30

20 30 40 50 60 70


80 90 100 110

CorePower LHGRFACp

(% Rated)100.0 1.000

70.0 0.84360.0 0.72530.0 0.614


30.0 0.46025.0 0.428

Core Flow <= 50% Rated30. 0 .[ 0.538

25.0 0.533

Figure 3.4 LHGRFACp for PLUOOS Conditions(with and without FHOOS)






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1.10

1.00

0.90

0.800.

• 0.70

"-J

0.60

0.50

0.40

0.30

20 30 40 50 60 70 80


90 100 110

CorePower LHGRFACp

(%Rated)100.0 1.000

70.0 0.84360.0 0.72530.0 0.614


30.0 0.37125.0 0.315

Core Flow <= 50% Rated30.0 " 0.54 925.0 0.473

Figure 3.5 LHGRFACp for RPTOOS, TBVOOS, and(with and without FHOOS)

PLUOOS Conditions



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1.10

1.00

0.90U.

U-

_10.80

0.70

0.60

30 40 50 60 70 80 90 100

Core Flow (% Rated)

110

CoreFlow LHGRFACF

(% Rated)30.0 0.6680.3 1

110.0 1

Figure 3.6 LHGRFACF(Values bound all EOOS conditions)

(110.0% maximum core flow line is used to support 105% rated flow operation, ICF)






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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:MCPRp

MCPRFMCPRSLO

off-rated power MCPR limitoff-rated flow MCPR limitSLO MCPR limit

[MCPRRATED * KpJ

[MCPRp + SLO Adder]

4.1 Rated Power and Flow Limit: MCPRRATED

The rated conditions MCPR is identified in Reference 1. The rated power and flow limits forvarious cycle exposure windows, and EOOS scenarios, are shown in Figure 4.2 & Figure 4.3.

OLMCPR is calculated to be the most limiting of the flow or power dependent values.

4.1.1 Scram Timing Dependence

The MCPRRATED has a scram timing dependence which is assessed after control blade timingshortly after startup, and is discussed as follows:

T = 0.0 or,

T ave r TBwhichever is greater

TA- TB

where: TA = 1.096 sec (analytical Option A scram time limitbased on dropout time for notch position 36)

Tave

TB

n~

n

-t I+1.65 * cy* N]ý

Browns Ferry Unit 1 Cycle 9Core Operating Ulmits Report, (105% OLTP)





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where: = 0.830 sec (mean scram time used in transient analysisbased on dropout time for notch position 36)

(Y = 0.019 sec (standard deviation of pt)

N = Total number of active rods measured in Technical SpecificationSurveillance Requirement SR 3.1.4.1

n = Number of surveillance rod tests performed to date in cycle

1= Scram time (dropout time) from fully withdrawn to notch position36 for the ith rod

For reactor startup, Option A limits (T=1.0) shall be used prior to the determination of T inaccordance with SR 3.1.4.1.

4.1.2 Equipment Out-Of-Service (EOOS) Options

All equipment service conditions support 1 SRVOOS. EOOS options, including combinations,covered by MCPRp limits are given by the following:

In-ServiceRPTOOSTBVOOSPLUOOSFHOOS (or FFWTR)

All equipment In-ServiceEOC-Recirculation Pump Trip Out-Of-ServiceTurbine Bypass Valve(s) Out-Of-ServicePower Load Unbalance Out-Of-ServiceFeedwater Heaters Out-Of-Service (or FinalFeedwater Temperature Reduction)

4.1.3 Exposure Dependent Limits

Exposures are tracked on a cycle exposure basis. Higher exposure limits are always morelimiting, and may be used for any cycle exposure up to the ending exposure. Cycle ExposureRanges are defined as follows:

BOC to MOC: where MOC corresponds to EOR* - 3208 MWd/MTU (2910 MWd/ST).BOC to EOC

EOC exposure includes cycle extension options such as final feedwater reduction (FFTR) andpower coastdown.

EOR is defined as the end of rated power capability for rated core flow and nominal feedwater temperature conditions.



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4.2 Flow Dependent MCPR Limit: MCPRF

MCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated orIncreased Core Flow, ICF). MCPRF limits are shown in Figure 4.1, per Reference 1. Limits arevalid for all EOOS combinations. No adjustment is required for SLO conditions.

4.3 Single Loop Operation Limit: MCPRSLO

The single loop operation adder is 0.02, per Reference 1.

4.4 Power Dependent MCPR Limit: MCPRp

MCPRp limits are dependent upon core power level (% of Rated) and EOOS conditions. KpMultipliers and/or MCPRp values are provided in Figure 4.4 thru Figure 4.7. Determination ofpower dependent MCPR is differentiated relative to Pbypass (30% Rated Power) as follows:

P > 30% (above Pbypass):P < 30% (below Pbypass):

MCPRP = [MCPRRATED* Kp]MCPRp = MCPRp






EDMS: L32 101015 801

2.00

1.80

1.60

Li.

1.40

1.20

1.00

30 40 50 60 70 80 90 100

Core Flow (% Rated)

110

CoreFlow MCPRF

(% Rated)30.0 1.5571.9 1.30

110.0 1.30

Figure 4.1 MCPRF(Values bound all EOOS, and SLO conditions)

(110.0% maximum core flow line is used to support 105% rated flow operation, ICF)






EDMS: L32 101015 801

1.60

1.55

1.50

a.0o1.45

1.40

1.35

1.30

0.00 0.20 0.40 0.60 0.80

Tau

1.00

Option A Option BOut-of-Service Condition Tau = 1.0 Tau = 0.0

All Equipment In-Service 1.41 1.38

RPTOOS 1.52 1.41

TBVOOS 1.47 1.44

PLUOOS 1.52 1.41

Combined RPTOOS, TBVOOS, & PLUOOS 1.57 1.46

Figure 4.2 MCPRRated : BOC to MOC Exposure(Values support ISRVOOS & FHOOS/FFTR conditions)






EDMS: L32 101015 801

a,

C.)

1.75

1.70

1.65

1.60

1.55

1.50

1.45

1.40

1.35

Combined RPTOOS, TBVOOS, & PLUOOS .I

TRPTOOS

All EquPLUOOS

• • All EquipmentlIn-Service

0.00 0.20 0.40 0.60 0.80 1.00

Tau

Option A Option BOut-of-Service Condition Tau = 1.0 Tau = 0.0

All Equipment In-Service 1.46 1.43

RPTOOS 1.62 1.45

TBVOOS 1.51 1.48

PLUOOS 1.62 1.45

Combined RPTOOS, 'TBVOOS, & PLUOOS 1.69 '1.52

Figure 4.3 MCPRRated: BOC to EOC Exposure(Values support ISRVOOS & FHOOS/FFTR conditions)

Browns Ferry Unit 1 Cycle 9Core Operating Umnits Report, (105% OLTP)





EDMS: L32 101015 801

5.00

4.50

4.00

3.50

3.00

C_ MCPR for Core Flow >50%o2.50

:•. ~~MCIR fo Cor r u2.00

1.50

1.00

Kp Multiplier

0.50

0.00

20 30 40 50 60 70 80

Core Power (% Rated)90 100 110

CorePower Kp

(% Rated) -

100.0 1.00060.0 1.15050.0 1.23750.0 1.38430.0 1.552


MCPRp30.0 2.640

25.0 2.820


MCPRp30.0 2.150

25.0 2.200

Figure 4.4 Kp Multiplier and MCPRp for All Equipment In Service or RPTOOS(Values support ISRVOOS & FHOOS/FFTR conditions)






EDMS: L32 101015 801

5.00

4.50

4.00

3.50

3.00

lk2.50

2.00

1.50

1.00

0.50

0.00

\MCPRp for Core Flow >50%

CPRpfor Co r Flow y-O%

Kp Multiplier

20 30 40 50 60 70 80


90 100 110

CorePower Kp

(% Rated) _

100.0 1.000

60.0 1.15050.0 1.237

50.0 1.38430.0 1.552


MCPRp30.0 3.55025.0 4.290


MCPRp

30.0 2.63025.0 3.060

Figure 4.5 Kp Multiplier and MCPRp for TBVOOS(Values support 1SRVOOS & FHOOS/FFTR conditions)

Browns Ferry Unit 1 Cyde 9Core Operating Umits Report, (105% OLTP)


SNPG1101 Market Sbreet Chattanooga, TN 37402



-- EDMS: L32 101015 801

5.00

4.50

4.00

3.50

3.00

&4S" • MCPRp for Core Flow p50%(LL) 2.50

-MCPRfor Core Flow <= 80%

1.50 =" •

1.00

Kp Multiplier

0.50

0.0020 30 40 50 60 70 80


90 100 110

CorePower Kp

I (% Rated) _

100.0 1.000

70.0 1.16060.0 1.30030.0 1.552


MCPRp

30.0 2.64025.0 2.820


MCPRp30.0 2.15025.0 2.200

Figure 4.6 Kp Multiplier and MCPRp for PLUOOS(Values support ISRVOOS & FHOOS/FFTR conditions)






EDMS: L32 101015 801

5.00

4.50

4.00

3.50

3.00

0t

o 2.50

2.00

1.50

1.00

0.50

0.00

MCPRP for Core Flow >50%

\ MCPRp for Coro Flow - 80%

Kp Multiplier

20 30 40 50 60 70 80


90 100 110

CorePower Kp

(% Rated)100.0 1.000

70.0 1.16060.0 1.30030.0 1.552


MCPRp

30.0 F 3.55025.0 4.290

Core Flow <= t50% Rated

MCPRp

30.0 2.63025.0 3.060

Figure 4.7 Kp Multiplier and MCPRp for RPTOOS, TBVOOS, and PLUOOS(Values support ISRVOOS & FHOOS/FFTR conditions)

Browns Feny Un~ 1 Cyde 9 Page 23


Page 23TVA-COLR-BF1 C9, Rek4sion 0 (Final)




EDMS: L32 101015 801

5 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 7 & 8, and is defined by thefollowing:

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 flowat 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%).






EDMS: L32 101015 801

6 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 7 & 8, are shown inTable 6.1. Setpoints are based on an HTSP, unfiltered analytical limit of 117%. Unfilteredsetpoints are consistent with a nominal RBM filter setting of 0.0 seconds; filtered setpoints areconsistent with a nominal RBM filter setting less than 0.5 seconds.

Table 6.1 Analytical RBM Trip Setpoints*

RBMTrip SetpointLPSPIPSPHPSP

AllowableValue(AV)

27%62%

82%

Nominal TripSetpoint(NTSP)

25%60%80%

LTSP - unfiltered 124.7% 123.0%- filtered 123.5% 121.8%

ITSP - unfiltered 119.7% 118.0%- filtered 118.7% 117.0%

HTSP - unfiltered 114.7% 113.0%- filtered 113.7% 112.0%

DTSP 90% 92%

Generic CRWE based OLMCPR values were reported and verified per References 7, 8, 9, and10. However, Reference 10 generic values were developed assuming a SLMCPR < 1.07.Consequently, cycle specific CRWE analyses were performed to support the current SLMCPR;values are reported in Reference 1. Cycle specific analysis results indicate the SLMCPRremains protected for RBM inoperable conditions (i.e., unblocked). RBM setpoints in TechnicalSpecification Table 3.3.2.1-1 are applicable as shown in Table 6.2.

Table 6.2 RBM Setpoint Applicability

Thermal Power Applicable Notes from(% Rated) MCPRt Table 3.3.2.1-1 Comment

> 27% and < 90% < 1.70 (a), (b), (f), (h) two loop operation

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

-> 90% < 1.40 (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.






EDMS: L32 101015 801

Table 6.3 Control Rod Withdrawal Error Results

RBM CRWESetpoint OLMCPR

Unfiltered

'107 1.31

111 1.31

114 1.32

117 1.38

Results, compared against the base case OLMCPR results of Reference 1, indicate SLMCPRremains protected for RBM inoperable conditions (i.e., unblocked).



~NPG1101 Market Street, Chattanooga, TN 37402



EDMS: L32 101015 801

7 Shutdown Margin Limit(Technical Specification 3.1.1)

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

SDM > 0.38% dk/k

Bmwns Ferry Unit 1 Cyde 9 Page 27

Browns Ferry Unit R Cycle 9Core Operating Limits Report, (1105% OLTP)




Date:

EDMS:

October 15,2010

L32 101015 801

Appendix A: Thermal-Hydraulic Stability


Page 28TVA-COLR-BF1 C9, Revisin 0 (Final)

fNuclear Fuel Engineering - BWRFE



RPS Instrumentation

(Technical Specification 3.3.1.1)

Technical Specification Section 3.3.1.1, LCO 3.3.1.1 states:

The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

Table 3.3.1.1-1, Function 2f, identifies the OPRM upscale function. This function must be

operable in conjunction with the following surveillance requirements:

SR 3.3.1.1.1SR 3.3.1.1.7SR 3.3.1.1.13SR 3.3.1.1.16SR 3.3.1.1.17

Background

Browns Ferry uses the Option III stability Detect and Suppress solution as part of the PRNMsystem. The Option Ill system is based upon combining groups of local LPRM's into cellsknown as OPRM's. The OPRM's generate a combined LPRM signal that is examined for thecharacteristics of a reactor instability event, and if detected, a reactor trip is generated.

The PBDA is the licensing basis portion of the Option III system, requiring a cycle-specificcalculation to determine the amplitude setpoint to generate a reactor trip in time to protect the

fuel from exceeding the SLMCPR.

The OPRM Upscale Trip function is required to be operable when the plant is in a region of

power-flow operation where actual thermal-hydraulic oscillations might occur (T.S. enabled region ,

greater than 25% rated thermal power and loss than 60% reclrculation drive flow).

Setpoints

Instrument setpoints are established such that the reactor will be tripped before an oscillationcan 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. The calculated OLMCPR's are shown.in Table A.1. Review of results,

relative to the base case operation shown in Figure 4.2 indicates an OPRM setpoint of 1.15 can

be supported. Extrapolation beyond a setpoint of 1.15 is not allowed.






EDMS: L32 101015 801

Table A.1 OPRM Setpoints

OPRM OLMCPR OLMCPR

Setpoint (SS) (2PT)

1.05 1.177 1.122

1.06 1.195 1.139

1.07 1.214 1.157

1.08 1.233 1.176

1.09 1.253 1.195

1.10 1.273 1.214

1.11 1.294 1.233

1.12 1.315 1.253

1.13 1.336 1.274

1.14 1.358 1.295

1.15 1.382 1.317

Backup Stability

Should the Option III system be declared inoperable, alternate methods/procedures (i.e.,stability ICA's) are incorporated restricting plant operation in the high power, low core flowregion of the power/flow map. ICA's contain specific operator actions, providing clearinstructions (depending upon the plant type) for operator response to a reactor inadvertently (orunder controlled conditions) entering any of the defined regions. ICA's provide appropriateguidance to reduce the likelihood of hydraulic instability, and enhance early detection in the veryunlikely event a stability threshold is exceeded in spite of the ICA guidelines.

In July 2002, GE recommended the original ICAs, established generically in 1994, be re-evaluated to assure adequate conservatism, given the trend to higher energy cores and moreaggressive fuel management strategies. The recommended replacement regions and theassociated calculational procedure are referred to as BSP, and need to be confirmed on aplant/cycle specific basis. The vendor has performed an ICA/BSP confirmation calculationusing NRC approved methods.

Based upon the above discussion, appropriate stability analyses and evaluations have beenperformed to satisfy licensing requirements.

Browns Ferry Unit 1 Cyde 9Core Operating Umits Report, (105% OLTP)


Documents

Enclosure TVA-COLR-BF1C9, Revision 0, dated October 2010 · 2012-12-04 · Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice