ML041260514

(BFN) - Unit 3 - Core Operating Limits Report (Colr), for Cycle 12 Operation and Emergency Core Cooling System (ECCS) Evaluation Model Changes

ML041260514
Person / Time
Site:	Browns Ferry
Issue date:	04/30/2004
From:	Abney T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041260514 (41)

Text

R08040430759 April 30, 2004 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of )

Docket No. 50-296 Tennessee Valley Authority )

BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - CORE OPERATING LIMITS REPORT (COLR), FOR CYCLE 12 OPERATION AND EMERGENCY CORE COOLING SYSTEM (ECCS) EVALUATION MODEL CHANGES In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is Revision 0 of the Unit 3 Cycle 12, Core Operating Limits Report (COLR).

BFN Unit 3 Cycle 12 represents the first cycle of operation using Framatome ATRIUM-10 fuel and the first use of Framatome Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) evaluation models at BFN. This letter provides the results of the Framatome LOCA analysis on peak clad temperature (PCT) for the ATRIUM-10 fuel in accordance with 10 CFR 50.46 reporting requirements for changes in ECCS analyses. The calculated Licensing Basis PCT for Atrium-10 fuel is 1866°F.

There are no new commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.

Sincerely, Original signed by T. E. Abney Manager of Licensing and Industry Affairs Enclosure cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 April 30, 2004 Enclosure cc (Enclosure):

Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 3 April 30, 2004 JWD:BAB Enclosure cc (Enclosure):

A. S. Bhatnagar, PAB 1E-BFN M. J. Burzynski, BR 4X-C D. F. Helms, BR 4T-C R. G. Jones, NAB 1A-BFN J. E. Maddox, LP 6A-C R. F. Marks, PAB 1C-BFN J. R. Rupert, NAB 1A-BFN K. W. Singer, LP 6A-C E. J. Vigluicci, ET 11A-K P. W. Wilson, PAB 1G-BFN NSRB Support, LP 5M-C EDMS-K S:lic\\submit\\subs\\COLR Rev U3C12.doc

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 CORE OPERATING LIMITS REPORT (COLR),

FOR CYCLE 12 OPERATION

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 2 Browns Ferry Nuclear PlantUnit3 Cycle12 Revision Log Revision Date Description Affected Pages 0

2/25/2004 InitialRelease forNew Cycle All

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 3 Browns Ferry Nuclear PlantUnit3 Cycle12

1. INTRO DUCTIO N This Core Operating Lim its Report for Browns Ferry Nuclear Plant Unit 3 Cycle 12 is prepared in accordance with the requirem entsofBrowns Ferry TechnicalSpecification 5.6.5.

The core operating lim its presented here were developed using NRC-approved m ethods (References2 and 3). One exception to thisisan issue with the assum ed uncertainty forthe GEXL14 CPR correlation. The NRC has identified that the correlation lacked top-peaked axialpower shape data in its form ulation and in the calculation of the overall correlation uncertainty. As an interim action, an increased GEXL14 uncertainty that incorporates a significantpenalty has been calculated and applied to the M CPR Safety Lim it(SLM CPR)for thiscycle.

Results from the reload analyses for Browns Ferry Unit 3, Cycle 12 are docum ented in Reference 1.

The following coreoperating and TechnicalSpecification lim itsareincluded in thisreport:

a. Average PlanarLinearHeatGeneration Rate(APLHGR)Lim it (TechnicalSpecifications 3.2.1 and 3.7.5)

b. LinearHeatGeneration Rate(LHGR)Lim it (TechnicalSpecification 3.2.3,3.3.4.1,and 3.7.5)

c. M inim um CriticalPowerRatio Operating Lim it(OLM CPR)

(TechnicalSpecifications 3.2.2,3.3.4.1,and 3.7.5)

d. Average PowerRange M onitor(APRM )Flow Biased Rod Block Trip Setting (TechnicalRequirem entsM anualSection 5.3.1 and Table3.3.4-1)

e. Rod Block M onitor(RBM )Trip Setpointsand Operability (TechnicalSpecification Table3.3.2.1-1)

f. Shutdown M argin (SDM )Lim it (TechnicalSpecification 3.1.1)

The Unit3 Cycle12 coreiscom posed of Fram atom e-ANP ATRIUM '-10,GlobalNuclear Fuel GE-14'

, and Global Nuclear Fuel GE-13' assem blies. Throughout this docum ent these arereferred to as A10,GE14,and GE13 with the tradem ark im plied.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 4 Browns Ferry Nuclear PlantUnit3 Cycle12

2. APLH G R LIM IT (TECH NICAL SPECIFICATIO NS 3.2.1 AND 3.7.5)

The APLHGR lim itisdeterm ined by adjusting the rated powerAPLHGR lim itforoff-rated power, off-rated flow, and SLO conditions. The m ost lim iting of these is then used as follows:

APLHGR lim it= M IN (APLHGRP,APLHGRF,APLHGRSLO )

where:

APLHGRP off-rated powerAPLHGR lim it

[APLHGRRATED *M APFAC(P)]

APLHGRF off-rated flow APLHGR lim it

[APLHGRRATED *M APFAC(F)]

APLHGRSLO SLO APLHGR lim it

[ALPHGR RATED *SLO_M ultiplier]

The off-rated powerand flow corrections to the APLHGR lim itonly apply to the GE13 and GE14 fuelin the Browns Ferry Unit3 Cycle12 core.Forthatreason,thism ultiplierissetto 1.0 as shown below forthe A10 fuel.

Rated Power and Flow Lim its:APLH G R RATED The APLHGR lim itsforfullpowerand flow conditions foreach type offuelas afunction of exposure are shown in Figures 1-6.The APLHGR lim itsprovided in the COLR figures for the GE13 and GE14 assem blies are forthe m ostlim iting lattice (excluding naturaluranium )

at each exposure point. The specific values for each GE13 and GE14 lattice are given in Reference 4.The ATRIUM -10 values areprovided in Reference 1.

BundleType Rated Power APLH G R Lim it GE13-P9DTB400-13GZ1 Figure1 GE13-P9DTB414-15GZ Figure2 GE14-P10DNAB402-15GZ Figure3 GE14-P10DNAB401-14GZ Figure4 A10-3813B-13GV80 Figure5 A10-4077B-15GV80 Figure5 A10-4088B-15GV80 Figure5 A10-1623B-5GV80 Figure6

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 5 Browns Ferry Nuclear PlantUnit3 Cycle12 O ff-Rated Power Corrections:APLH G R P The APLHGR lim its for the GE13 and GE14 fuel lattices are adjusted for off-rated power conditions using the ARTS m ultiplier, M APFAC(P). The reduced power m ultiplier, M APFAC(P),for both the GE13 and GE14 fuel is provided in Reference 1. No off-rated powercorrection isrequired forthe A10 rated APLHGR lim its.

ProductLine M APFAC(P)

GE13 Figure7 GE14 Figure8 A10 1.0 O ff-Rated Flow Corrections:APLH G R F The APLHGR lim its for the GE13 and GE14 fuel lattices are adjusted for off-rated flow conditions using the ARTS m ultiplier, M APFAC(F). The reduced flow m ultiplier, M APFAC(F), is the sam e for GE13 and GE14 bundles and isprovided in Reference 1.No off-rated flow correction isrequired forthe A10 rated APLHGR lim its.

SLO Corrections:APLH G R SLO Single Recirculation Loop Operation (SLO) requires that the rated power APLHGR lim it (APLHGRrated) be reduced by applying the following m ultipliers. The GE13 and GE14 multipliersareprovided in Reference 5.The A10 m ultiplierisprovided in Reference 1.

ProductLine SLO M ultiplier GE13 0.84 GE14 0.93 A10 0.85 ProductLine M APFAC(F)

GE13 & GE14 Figure9 A10 1.0

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 6 Browns Ferry Nuclear PlantUnit3 Cycle12 Equipm entO ut-O f-Service(EO O S)Corrections:

The rated APLHGR lim itsin Figures 1-6 are applicable forboth Turbine Bypass In-Service (TBVIS) and Turbine Bypass Out-Of-Service (TBVOOS) conditions. The off-rated power corrections [M APFAC(P)] in Figures 7 and 8 contain separate lim its to be applied for TBVIS orTBVOOS.The off-rated flow corrections [M APFAC(F)]in Figure 9 bound both TBVIS and TBVOOS operation.

The APLHGR lim itsin Figures 1-6 areapplicableforbothEnd-Of-CycleRecirculation Pum p Trip (RPT) In-Service (RPTIS)and RPT Out-Of-Service (RPTOOS). The off-rated power

[M APFAC(P)]and flow corrections [M APFAC(F)]in Figures 7,8,and 9bound both RPTIS and RPTOOS operation. No corrections are required to the APLHGR lim its for RPTOOS foreitherrated oroff-rated operation.

Single Recirculation Loop Operation (SLO)requires the application ofthe SLO m ultipliers described previously.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 7 Browns Ferry Nuclear PlantUnit3 Cycle12

3. LH G R LIM IT (TECH NICAL SPECIFICATIO N 3.2.3,3.3.4.1,and 3.7.5)

The LHGR lim itisdeterm ined by adjusting the rated powerLHGR lim itforoff-rated power and off-rated flow conditions.The m ostlim iting ofthese isthen used,as follows:

LHGR lim it= M IN (LHGRP,LHGRF )

where:

LHGRP off-rated powerLHGR lim it

[LHGRRATED

• LHGRFAC(P)]

LHGRF off-rated flow LHGR limit

[LHGRRATED

• LHGRFAC(F)]

The off-rated powerand flow corrections to the LHGR lim itonly apply to the A10 fuelinthe Browns Ferry Unit 3 Cycle 12 core. For that reason, these m ultipliers for the GE13 and GE14 fuelaresetto 1.0 as shown below.

Rated Power and Flow Lim its:LH G R RATED The LHGR lim itisfueltype dependent.The lim itsforthese types aregiven below:

FuelType LH G R Lim it GE13 14.4 kw/ft GE14 13.4 kw/ft A10 Figure10 The A10 LHGR lim itisprovided inReference 6.The GE13 and GE14 LHGR lim itsare provided inReference 7.

O ff-Rated Power Corrections:LH G R P The LHGR lim its for the A10 fuel are adjusted for off-rated power conditions using the LHGRFAC(P)m ultiplierwhich isprovided in Reference 1.The LHGRFAC(P)m ultiplieris dependent on whether the Turbine Bypass system is in-service (TBVIS) or out-of-service (TBVOOS).No off-rated powercorrection isrequired forthe GE13 or GE14 rated LHGR lim its.

ProductLine LH G RFAC(P)

GE13 & GE14 1.0 A10 Figure11

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 8 Browns Ferry Nuclear PlantUnit3 Cycle12 O ff-Rated Flow Corrections:LH G R F The LHGR lim its for the A10 fuel are adjusted for off-rated flow conditions using the LHGRFAC(F) m ultiplier which is provided in Reference 1. No off-rated flow correction is required forthe GE13 and GE14 rated LHGR lim its.

ProductLine LH G RFAC(F)

GE13 & GE14 1.0 A10 Figure12

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 9 Browns Ferry Nuclear PlantUnit3 Cycle12 4.O LM CPR (TECH NICAL SPECIFICATIO NS 3.2.2,3.3.4.1,AND 3.7.5)

The M CPR Operating Lim it (OLM CPR) is calculated to be the m ost lim iting of the flow-dependentM CPR (M CPRF)and power-dependentM CPR (M CPRP).

OLM CPR lim it= M AX (M CPRF,M CPRP )

where:

M CPRF coreflow-dependentM CPR lim it M CPRP power-dependentM CPR lim it M CPRFlim itsareprovided by fueltype in Figures 13 through 15.M CPRP lim itsareprovided in Tables 1 through 6.

Flow-DependentM CPR Lim its:M CPR F The M CPRF lim itsaredependentupon:

CoreFlow (% ofRated)

M ax CoreFlow Lim it(Rated orIncreased CoreFlow,ICF)

FuelType (GE13,GE14,orA10)

The M CPRF lim its are provided by fuel type in Figure 13 (GE13), Figure 14 (GE14), and Figure15 (A10).These lim itsarevalid forallEOOS com binations.No adjustm entisrequired to the M CPRF lim itsforSLO.The M CPRF lim itsarefoundinReference 1.

Power-DependentM CPR Lim its:M CPR P The M CPRP lim itsaredependentupon:

CorePowerLevel(% ofRated)

TechnicalSpecification Scram Speed (TSSS)orNom inalScram Speed (NSS)

FuelType (GE13,GE14,orA10)

CycleOperating Exposure (NEOC,EOC,and CD -as defined in thissection)

Equipm entOut-Of-ServiceOptions Two orSinglerecirculation Loop Operation (TLO vs.SLO)

The M CPRP lim its(Ref.1)areprovided in the following tables,whereeach tablecontains the lim itsforallfueltypes and EOOS options(foraspecified scram speed and exposurerange).

The M CPRP lim its are determ ined from these tables using linear interpolation between the specified powers.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 10 Browns Ferry Nuclear PlantUnit3 Cycle12 Exposure Range Scram Speed M CPR P BOC to NEOC NSS Table1 TSSS Table2 BOC to EOC NSS Table3 TSSS Table4 BOC to CD NSS Table5 TSSS Table6

a. Scram Speed DependentLim its(TSSS vs.NSS)

M CPRP lim its are provided for two different sets of assum ed scram speeds. The TechnicalSpecification Scram Speed (TSSS)M CPRP lim its areapplicable atalltim es as long as the scram tim e surveillance dem onstrates thatthe tim es in TechnicalSpecification table 3.1.4-1 have been m et. Nom inal Scram Speeds (NSS) m ay be used as long as the scram tim e surveillance dem onstrates thatthe tim es in the following table are m et(Ref.

8).

Notch Position Nom inalScram Speed (seconds) 46 0.42 36 0.98 26 1.60 06 2.90 In dem onstrating com pliance with this table, the sam e surveillance requirem ents from Technical Specification 3.1.4 apply, except that the definition of SLOW rods should conform to the scram speeds in the table above. If conform ance to this table is not dem onstrated,TSSS M CPRPlim itsshallbe used.

On initial cycle startup, TSSS lim its are used untilthe successful com pletion of scram tim ingconfirm s thatNSS lim itsm ay be used.

b. FuelType DependentLim its SeparateM CPRPlim itsareprovided forthe GE13,GE14,and A10 fueltypes.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 11 Browns Ferry Nuclear PlantUnit3 Cycle12

c. ExposureDependentLim its Exposures are tracked on a Core Average Exposure basis (not Cycle Exposure). The higher exposure M CPRP lim its are always m ore lim iting and m ay be used forany Core Average Exposureup to the ending exposure.

M CPRPlim itsareprovided forthe following exposureranges (Ref.1):

BOC to NEOC NEOC corresponds to 31,722 M W d /M TU BOC to EOC EOC corresponds to 34,028 M W d /M TU BOC to CD CD corresponds to 35,128 M W d /M TU NEOC refersto aNearEOC exposurepoint.

The EOC exposure pointisnotthe true End-Of-Cycle exposure.Instead itcorresponds to alicensing exposurewindow thatexceeds expected end-of-full-power-life.

The CD (CoastDown)exposure pointrepresentsalicensing exposurepointthatexceeds the expected end-of-cycleexposureincluding cycleextension options.

d. Equipm entOut-Of-Service(EOOS)Options EOOS options included in the M CPRPlim itsare:

In-Service Allequipm entIn-Service(includes 1 SRVOOS)

RPTOOS EOC-Recirculation Pum p Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s)Out-Of-Service RPTOOS+TBVOOS Com bined RPTOOS and TBVOOS FHOOS (orFFTR)

FeedwaterHeatersOut-Of-Service(orFinal FeedwaterTem peratureReduction)

Forexposureranges up to NEOC and EOC,additionalcom binations ofM CPRPlim itsare also provided that include FHOOS. The CD exposure range assum es application of FFTR,so the CD based M CPRPlim itsalready include FHOOS.

e. Single-Loop-Operation (SLO)Lim its The M CPRPlim itsforSLO areto be increased by 0.02 (Ref.1).

f. Below Pbypass Lim its Below Pbypass (30% rated power),the M CPRPlim itsaredependentupon coreflow.One setofM CPRP lim itsapplies ifthe coreflow isabove 50% ofrated with asecond setthat applies ifthe coreflow isless than orequalto 50% rated.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 12 Browns Ferry Nuclear PlantUnit3 Cycle12 5.APRM FLO W BIASED RO D BLO CK TRIP SETTING (TECH NICAL REQ UIREM ENTS M ANUAL SECTIO N 5.3.1 AND TABLE 3.3.4-1)

The APRM Rod Block trip setting shallbe (Ref.9):

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

AllowableValue SRB (0.66(W -W )+ 59% )

Nom inalTrip Setpoint(NTSP) where:

SRB =

Rod Block setting in percentofrated therm alpower(3458 M W t)

W =

Loop recirculation flow ratein percentofrated W

=

Difference between two-loopand single-loopeffective recirculationflow atthe sam e coreflow (W =0.0 fortwo-loop operation)

The APRM Rod Block trip setting is clam ped at a m axim um allowable value of 115%

(corresponding to aNTSP of113% ).

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 13 Browns Ferry Nuclear PlantUnit3 Cycle12 6.RO D BLO CK M O NITO R (RBM )TRIP SETPO INTS AND O PERABILITY (TECH NICAL SPECIFICATIO N TABLE 3.3.2.1-1)

The RBM trip setpointsand applicablepowerranges shallbe as follows (refs.9 & 10):

RBM Trip Setpoint AllowableValue (AV)

Nom inalTrip Setpoint (NTSP)

LPSP 27%

25%

IPSP 62%

60%

HPSP 82%

80%

LTSP -unfiltered

-filtered 121.7%

120.7%

120.0%

119.0%

(1),(2)

ITSP -unfiltered

-filtered 116.7%

115.7%

115.0%

114.0%

(1),(2)

HTSP -unfiltered

-filtered 111.7%

110.9%

110.0%

109.2%

(1),(2)

DTSP 90%

92%

Notes: (1) These setpoints are based upon an Analytical Lim it HTSP of 114% (w/o filter) which corresponds to a M CPR operating lim it of1.35(A10) / 1.32(G E14), as reported in section 5.5 ofReference 1.Unit3 Cycle 12 has had acyclespecific CRW E analysisperform ed and the table provided in section 5.5 ofReference 1 supercedes the OLM CPR values of references 9 and 11. GE13 is non-lim iting forthiscycleand isnotused in RBM setpointdeterm ination.

(2)The unfiltered setpointsare consistentwith a nom inalRBM filtersetting of0.0 seconds (reference 9.b). The filtered setpoints are consistent with a nom inal RBM filtersetting < 0.5 seconds (reference 9.a).

The RBM setpointsin TechnicalSpecification Table3.3.2.1-1areapplicablewhen:

TH ERM AL PO W ER

(% Rated)

Applicable M CPR (1)

Notes from Table3.3.2.1-1

> 27% and < 90%

< 1.74 (a),(b),(f),(h) dualloop operation

< 1.77 (a),(b),(f),(h) singleloop operation

> 90%

< 1.43 (g) dualloop operation (2)

Notes:(1)

The M CPR values shown correspond to a SLM CPR of 1.09 for dual recirculation loop operation and 1.11 forsingleloop operation.

(2)

Greaterthan 90% rated powerisnotattainablein singleloop operation.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 14 Browns Ferry Nuclear PlantUnit3 Cycle12 7.SH UTDO W N M ARG IN (SDM )LIM IT (TECH NICAL SPECIFICATIO N 3.1.1)

The core shall be subcritical with the following m argin with the strongest OPERABLE controlrod fully withdrawn and allotherOPERABLE controlrods fully inserted (Ref.7).

SDM > 0.38% dk/k

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 15 Browns Ferry Nuclear PlantUnit3 Cycle12

8. REFERENCES

1. EM F-3019 Rev.1,Browns Ferry Unit3 Cycle12 Reload Analysis,dated February 2004.

2. Fram atom e-ANP AnalyticalM ethodology

References:

a) XN-NF-81-58(P)(A)Revision 2 and Supplem ents1 and 2,RODEX2 FuelRod Thermal-M echanicalResponse Evaluation M odel,Exxon NuclearCom pany,M arch 1984.

b) XN-NF-85-67(P)(A) Revision 1,Generic M echanical Design for Exxon Nuclear Jet Pump BW R Reload Fuel,Exxon NuclearCom pany,Septem ber1986.

c) EM F-85-74(P) Revision 0 Supplem ent 1(P)(A) and Supplem ent2(P)(A),RODEX2A (BW R)FuelRod Thermal-M echanicalEvaluation M odel,Siem ens PowerCorporation, February 1998.

d) ANF-89-98(P)(A) Revision 1 and Supplem ent 1,Generic M echanical Design Criteria for BW R FuelDesigns,Advanced NuclearFuelsCorporation,M ay 1995.

e) XN-NF-80-19(P)(A)Volum e 1 and Supplem ents1 and 2, Exxon Nuclear M ethodology for Boiling W ater Reactors - Neutronic M ethods for Design and Analysis, Exxon NuclearCom pany,M arch 1983.

f) XN-NF-80-19(P)(A) Volum e 4 Revision 1,Exxon Nuclear M ethodology for Boiling W ater Reactors:Application ofthe ENC M ethodology to BW R Reloads,Exxon Nuclear Com pany,June 1986.

g) EM F-2158(P)(A) Revision 0,Siemens Power Corporation M ethodology for Boiling W ater Reactors: Evaluation and Validation of CASM O-4/M ICROBURN-B2, Siem ens PowerCorporation,October1999.

h) XN-NF-80-19(P)(A) Volum e 3 Revision 2, Exxon Nuclear M ethodology for Boiling W ater Reactors, THERM EX: Thermal Limits M ethodology Summary Description, Exxon NuclearCom pany,January 1987.

i) XN-NF-84-105(P)(A) Volum e 1 and Volum e 1 Supplem ents1 and 2,XCOBRA-T: A Computer Code for BW R TransientThermal-Hydraulic Core Analysis,Exxon Nuclear Com pany,February 1987.

j) ANF-524(P)(A)Revision 2 and Supplem ents1 and 2,ANF CriticalPower M ethodology for Boiling W ater Reactors,Advanced NuclearFuelsCorporation,Novem ber1990.

k) ANF-913(P)(A) Volum e 1 Revision 1 and Volum e 1 Supplem ents 2, 3 and 4, COTRANSA2: A Computer Program for Boiling W ater Reactor Transient Analyses, Advanced NuclearFuelsCorporation,August1990.

l) ANF-1358(P)(A) Revision 1, The Loss of Feedwater Heating Transient in Boiling W ater Reactors,Advanced NuclearFuelsCorporation,Septem ber1992.

m) EM F-2209(P)(A) Revision 2, SPCB Critical Power Correlation, Siem ens Power Corporation,Septem ber2003.

n) EM F-2245(P)(A) Revision 0,Application of Siemens Power Corporations Critical Power Correlations to Co-ResidentFuel,Siem ens PowerCorporation,August2000.

o) EM F-2361(P)(A) Revision 0,EXEM BW R-2000 ECCS Evaluation M odel,Fram atom e ANP,M ay 2001.

p) EM F-2292(P)(A) Revision 0, ATRIUM '-10: Appendix K Spray Heat Transfer Coefficients,Siem ens PowerCorporation,Septem ber2000.

3. GlobalNuclearFuelAnalyticalM ethodology

References:

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 16 Browns Ferry Nuclear PlantUnit3 Cycle12 a) NEDE-24011-P-A-14, "General Electric Standard Application for Reactor Fuel", June 2000.

b) NEDE-24011-P-A-14-US, "General Electric Standard Application for Reactor Fuel (Supplem entforUnited States)",June 2000.

4. J11-03963M APL Rev. 0, "Lattice-Dependent M APLHGR Report for Browns Ferry NuclearPlantUnit3 Reload 10 Cycle11,M arch 2002.

5. J11-03963SRLR Rev.0,"Supplem entalReload Licensing ReportforBrowns Ferry Nuclear PlantUnit3 Reload 10 Cycle11,M arch 2002.

6. EM F-2971(P)Rev.1,M echanicaland Therm al-HydraulicDesign ReportforBrowns Ferry Unit3 Batches BFC-1and BFC-1A ATRIUM '-10FuelAssem blies,dated January 2004.

7. TVA-COLR-BF3C11 Rev. 0, Browns Ferry Nuclear Plant Unit 3, Cycle 11 Core Operating Lim itsReport(COLR),dated M arch 30,2002.

8. EM F-2793(P)Rev.1,Browns Ferry Unit3 Cycle 12 PlantParam etersDocum ent,dated June 2003.

9. PRNM SetpointCalculation:

a) Filtered Setpoints -EDE-28-0990 Rev. 3 Supplem ent E, PRNM (APRM, RBM, and RFM )SetpointCalculations [ARTS/M ELLL (NUM AC)-Power-UprateCondition]for Tennessee Valley Authority Browns Ferry NuclearPlant,dated October1997.

b) Unfiltered Setpoints-EDE-28-0990 Rev.2 Supplem entE,PRNM (APRM,RBM,and RFM )SetpointCalculations [ARTS/M ELLL (NUM AC)-Power-UprateCondition]for Tennessee Valley Authority Browns Ferry NuclearPlant,dated October1997.

10. GE Letter LB#: 262-97-133, Browns Ferry Nuclear Plant Rod Block M onitor Setpoint Clarification-GE Proprietary Inform ation,dated Septem ber12,1997.

11.NEDC-32433P, M axim um Extended Load Line Lim it and ARTS Im provem ent Program Analyses forBrowns Ferry NuclearPlantUnit1,2,and 3,dated April1995.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 17 Browns Ferry Nuclear PlantUnit3 Cycle12 Table1:M CPR P Lim itsfor BO C to NEO C Exposures - NSS Scram Tim es (ApplicableuptoCoreAverage Exposureof31,722 M W d /M TU)

M CPR P Lim it M CPR P Lim it EO O S O ption Power

(% Rated)

A10 G E13 G E14 EO O S O ption Power

(% Rated)

A10 G E13 G E14 In-Service 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.35 1.53 1.69 2.01 2.28 2.46 2.19 2.35 1.29 1.51 1.66 1.96 2.20 2.39 2.06 2.18 1.34 1.56 1.75 2.11 2.36 2.54 2.36 2.54 FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.36 1.56 1.75 2.09 2.35 2.56 2.25 2.44 1.30 1.55 1.72 2.03 2.27 2.48 2.12 2.27 1.35 1.62 1.81 2.19 2.43 2.65 2.43 2.65 RPTO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.35 1.53 1.69 2.01 2.28 2.46 2.19 2.35 1.32 1.51 1.66 1.96 2.20 2.39 2.06 2.18 1.35 1.56 1.75 2.11 2.36 2.54 2.36 2.54 RPTO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.36 1.56 1.75 2.09 2.35 2.56 2.25 2.44 1.32 1.55 1.72 2.03 2.27 2.48 2.12 2.27 1.35 1.62 1.81 2.19 2.43 2.65 2.43 2.65 TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.39 1.58 1.72 2.03 2.83 3.17 2.49 2.80 1.32 1.53 1.69 1.99 2.67 3.00 2.28 2.54 1.38 1.60 1.77 2.12 2.83 3.17 2.62 2.97 TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.40 1.60 1.77 2.11 2.90 3.24 2.54 2.87 1.33 1.57 1.74 2.06 2.73 3.07 2.34 2.60 1.39 1.64 1.82 2.20 2.90 3.26 2.69 3.06 RPTO O S TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.39 1.58 1.72 2.03 2.83 3.17 2.49 2.80 1.35 1.53 1.69 1.99 2.67 3.00 2.28 2.54 1.39 1.60 1.77 2.12 2.83 3.17 2.62 2.97 RPTO O S TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.40 1.60 1.77 2.11 2.90 3.24 2.54 2.87 1.35 1.57 1.74 2.06 2.73 3.07 2.34 2.60 1.39 1.64 1.82 2.20 2.90 3.26 2.69 3.06 Add 0.02 to the above M CPRP lim itsforSLO.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 18 Browns Ferry Nuclear PlantUnit3 Cycle12 Table2:M CPR P Lim itsfor BO C to NEO C Exposures - TSSS Scram Tim es (ApplicableuptoCoreAverage Exposureof31,722 M W d /M TU)

M CPR P Lim it M CPR P Lim it EO O S O ption Power

(% Rated)

A10 G E13 G E14 EO O S O ption Power

(% Rated)

A10 G E13 G E14 In-Service 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.37 1.54 1.70 2.03 2.28 2.46 2.19 2.35 1.30 1.52 1.68 1.97 2.20 2.39 2.06 2.18 1.36 1.58 1.76 2.12 2.36 2.54 2.36 2.54 FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.37 1.58 1.76 2.10 2.35 2.56 2.25 2.44 1.31 1.57 1.73 2.05 2.27 2.48 2.12 2.27 1.36 1.64 1.83 2.20 2.43 2.65 2.43 2.65 RPTO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.37 1.54 1.70 2.03 2.28 2.46 2.19 2.35 1.33 1.52 1.68 1.97 2.20 2.39 2.06 2.18 1.37 1.58 1.76 2.12 2.36 2.54 2.36 2.54 RPTO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.37 1.58 1.76 2.10 2.35 2.56 2.25 2.44 1.33 1.57 1.73 2.05 2.27 2.48 2.12 2.27 1.37 1.64 1.83 2.20 2.43 2.65 2.43 2.65 TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.59 1.73 2.05 2.83 3.17 2.49 2.80 1.34 1.55 1.70 2.00 2.67 3.00 2.28 2.54 1.40 1.62 1.78 2.14 2.83 3.17 2.62 2.97 TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.61 1.78 2.13 2.90 3.24 2.54 2.87 1.35 1.59 1.76 2.07 2.73 3.07 2.34 2.60 1.40 1.67 1.84 2.21 2.90 3.26 2.69 3.06 RPTO O S TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.59 1.73 2.05 2.83 3.17 2.49 2.80 1.36 1.55 1.70 2.00 2.67 3.00 2.28 2.54 1.40 1.62 1.78 2.14 2.83 3.17 2.62 2.97 RPTO O S TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.61 1.78 2.13 2.90 3.24 2.54 2.87 1.37 1.59 1.76 2.07 2.73 3.07 2.34 2.60 1.41 1.67 1.84 2.21 2.90 3.26 2.69 3.06 Add 0.02 to the above M CPRP lim itsforSLO.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 19 Browns Ferry Nuclear PlantUnit3 Cycle12 Table3:M CPR P Lim itsfor BO C to EO C Exposures - NSS Scram Tim es (Applicableup to CoreAverage Exposureof34,028 M W d /M TU)

M CPR P Lim it M CPR P Lim it EO O S O ption Power

(% Rated)

A10 G E13 G E14 EO O S O ption Power

(% Rated)

A10 G E13 G E14 In-Service 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.36 1.53 1.69 2.01 2.28 2.46 2.19 2.35 1.31 1.51 1.66 1.96 2.20 2.39 2.06 2.18 1.36 1.56 1.75 2.11 2.36 2.54 2.36 2.54 FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.36 1.56 1.75 2.09 2.35 2.56 2.25 2.44 1.31 1.55 1.72 2.03 2.27 2.48 2.12 2.27 1.36 1.62 1.81 2.19 2.43 2.65 2.43 2.65 RPTO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.36 1.53 1.69 2.01 2.28 2.46 2.19 2.35 1.34 1.51 1.66 1.96 2.20 2.39 2.06 2.18 1.37 1.56 1.75 2.11 2.36 2.54 2.36 2.54 RPTO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.36 1.56 1.75 2.09 2.35 2.56 2.25 2.44 1.34 1.55 1.72 2.03 2.27 2.48 2.12 2.27 1.37 1.62 1.81 2.19 2.43 2.65 2.43 2.65 TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.40 1.58 1.72 2.03 2.83 3.17 2.49 2.80 1.34 1.53 1.69 1.99 2.67 3.00 2.28 2.54 1.39 1.60 1.77 2.12 2.83 3.17 2.62 2.97 TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.40 1.60 1.77 2.11 2.90 3.24 2.54 2.87 1.35 1.57 1.74 2.06 2.73 3.07 2.34 2.60 1.39 1.64 1.82 2.20 2.90 3.26 2.69 3.06 RPTO O S TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.40 1.58 1.72 2.03 2.83 3.17 2.49 2.80 1.38 1.54 1.69 1.99 2.67 3.00 2.28 2.54 1.40 1.60 1.77 2.12 2.83 3.17 2.62 2.97 RPTO O S TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.40 1.60 1.77 2.11 2.90 3.24 2.54 2.87 1.38 1.57 1.74 2.06 2.73 3.07 2.34 2.60 1.40 1.64 1.82 2.20 2.90 3.26 2.69 3.06 Add 0.02 to the above M CPRP lim itsforSLO.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 20 Browns Ferry Nuclear PlantUnit3 Cycle12 Table4:M CPR P Lim itsfor BO C to EO C Exposures-TSSS Scram Tim es (ApplicableuptoCoreAverage Exposureof34,028 M W d /M TU)

M CPR P Lim it M CPR P Lim it EO O S O ption Power

(% Rated)

A10 G E13 G E14 EO O S O ption Power

(% Rated)

A10 G E13 G E14 In-Service 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.38 1.54 1.70 2.03 2.28 2.46 2.19 2.35 1.32 1.52 1.68 1.97 2.20 2.39 2.06 2.18 1.37 1.58 1.76 2.12 2.36 2.54 2.36 2.54 FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.38 1.58 1.76 2.10 2.35 2.56 2.25 2.44 1.32 1.57 1.73 2.05 2.27 2.48 2.12 2.27 1.37 1.64 1.83 2.20 2.43 2.65 2.43 2.65 RPTO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.38 1.54 1.70 2.03 2.28 2.46 2.19 2.35 1.35 1.52 1.68 1.97 2.20 2.39 2.06 2.18 1.38 1.58 1.76 2.12 2.36 2.54 2.36 2.54 RPTO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.38 1.58 1.76 2.10 2.35 2.56 2.25 2.44 1.35 1.57 1.73 2.05 2.27 2.48 2.12 2.27 1.38 1.64 1.83 2.20 2.43 2.65 2.43 2.65 TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.59 1.73 2.05 2.83 3.17 2.49 2.80 1.35 1.55 1.70 2.00 2.67 3.00 2.28 2.54 1.40 1.62 1.78 2.14 2.83 3.17 2.62 2.97 TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.42 1.61 1.78 2.13 2.90 3.24 2.54 2.87 1.36 1.59 1.76 2.07 2.73 3.07 2.34 2.60 1.40 1.67 1.84 2.21 2.90 3.26 2.69 3.06 RPTO O S TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.59 1.73 2.05 2.83 3.17 2.49 2.80 1.38 1.55 1.70 2.00 2.67 3.00 2.28 2.54 1.42 1.62 1.78 2.14 2.83 3.17 2.62 2.97 RPTO O S TBVO O S FH O O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.42 1.61 1.78 2.13 2.90 3.24 2.54 2.87 1.39 1.59 1.76 2.07 2.73 3.07 2.34 2.60 1.42 1.67 1.84 2.21 2.90 3.26 2.69 3.06 Add 0.02 to the above M CPRP lim itsforSLO.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 21 Browns Ferry Nuclear PlantUnit3 Cycle12 Table5:M CPR P Lim itsfor BO C to CD Exposures - NSS Scram Tim es (ApplicableuptoCoreAverage Exposureof35,128 M W d /M TU)

AllValues Include FFTR/FHOOS and Bound Heaters In-Service M CPR P Lim it EO O S O ption Power

(% Rated)

A10 G E13 G E14 In-Service 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.37 1.56 1.75 2.09 2.35 2.56 2.25 2.44 1.32 1.55 1.72 2.03 2.27 2.48 2.12 2.27 1.36 1.62 1.81 2.19 2.43 2.65 2.43 2.65 RPTO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.37 1.56 1.75 2.09 2.35 2.56 2.25 2.44 1.35 1.55 1.72 2.03 2.27 2.48 2.12 2.27 1.37 1.62 1.81 2.19 2.43 2.65 2.43 2.65 TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.60 1.77 2.11 2.90 3.24 2.54 2.87 1.35 1.57 1.74 2.06 2.73 3.07 2.34 2.60 1.40 1.64 1.82 2.20 2.90 3.26 2.69 3.06 RPTO O S TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.41 1.60 1.77 2.11 2.90 3.24 2.54 2.87 1.38 1.57 1.74 2.06 2.73 3.07 2.34 2.60 1.40 1.64 1.82 2.20 2.90 3.26 2.69 3.06 Add 0.02 to the above M CPRP lim itsforSLO.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 22 Browns Ferry Nuclear PlantUnit3 Cycle12 Table6:M CPR P Lim itsfor BO C to CD Exposures - TSSS Scram Tim es (ApplicableuptoCoreAverage Exposureof35,128 M W d /M TU)

AllValues Include FFTR/FHOOS and Bound Heaters In-Service M CPR P Lim it EO O S O ption Power

(% Rated)

A10 G E13 G E14 In-Service 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.38 1.58 1.76 2.10 2.35 2.56 2.25 2.44 1.33 1.57 1.73 2.05 2.27 2.48 2.12 2.27 1.37 1.64 1.83 2.20 2.43 2.65 2.43 2.65 RPTO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.39 1.58 1.76 2.10 2.35 2.56 2.25 2.44 1.37 1.57 1.73 2.05 2.27 2.48 2.12 2.27 1.39 1.64 1.83 2.20 2.43 2.65 2.43 2.65 TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.42 1.61 1.78 2.13 2.90 3.24 2.54 2.87 1.36 1.59 1.76 2.07 2.73 3.07 2.34 2.60 1.41 1.67 1.84 2.21 2.90 3.26 2.69 3.06 RPTO O S TBVO O S 100 60 45 30 30 (> 50% F) 25 (> 50% F) 30 (< 50% F) 25 (< 50% F) 1.42 1.61 1.78 2.13 2.90 3.24 2.54 2.87 1.41 1.59 1.76 2.07 2.73 3.07 2.34 2.60 1.42 1.67 1.84 2.21 2.90 3.26 2.69 3.06 Add 0.02 to the above M CPRP lim itsforSLO.

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 23 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 1 APLHGR Limits for Bundle Type GE13-P9DTB400-13GZ1 (GE13)

M ostLim iting Lattice forEach Exposure Point Average Planar LHG R Average Planar LHG R Average Planar LHG R Exposure Lim it Exposure Lim it Exposure Lim it (G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft) 0.00 10.61 7.72 11.77 27.56 11.24 0.22 10.64 8.82 11.94 33.07 10.65 1.10 10.72 9.92 12.13 38.58 10.10 2.20 10.87 11.02 12.30 44.09 9.57 3.31 11.05 13.78 12.47 49.60 9.10 4.41 11.26 16.53 12.39 55.12 8.71 5.51 11.46 19.29 12.18 60.63 8.39 6.61 11.61 22.05 11.89 64.61 8.19 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its are for dualrecirculation loop operation.Single Loop O peration (SLO )adjustm ents are perform ed as described in Section 2 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (G W D/M TU)

APLHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 24 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 2 APLHGR Limits for Bundle Type GE13-P9DTB414-15GZ (GE13)

M ostLim iting Lattice forEach Exposure Point Average Planar LHG R Average Planar LHG R Average Planar LHG R Exposure Lim it Exposure Lim it Exposure Lim it (G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft) 0.00 10.40 7.72 11.43 27.56 11.09 0.22 10.46 8.82 11.54 33.07 10.67 1.10 10.56 9.92 11.67 38.58 10.20 2.20 10.71 11.02 11.81 44.09 9.74 3.31 10.88 13.78 11.89 49.60 9.28 4.41 11.04 16.53 11.95 55.12 8.85 5.51 11.18 19.29 11.80 60.63 8.43 6.61 11.31 22.05 11.55 63.72 8.20 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its are for dualrecirculation loop operation.Single Loop O peration (SLO )adjustm ents are perform ed as described in Section 2 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (G W D/M TU)

APLHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 25 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 3 APLHGR Limits for Bundle Type GE14-P10DNAB402-15GZ (GE14)

M ostLim iting Lattice forEach Exposure Point Average Planar LHG R Average Planar LHG R Average Planar LHG R Exposure Lim it Exposure Lim it Exposure Lim it (G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft) 0.00 9.57 8.82 10.80 22.05 10.88 0.22 9.61 9.92 10.88 27.56 10.50 1.10 9.68 11.02 10.96 33.07 10.10 2.20 9.82 12.13 11.04 38.58 9.66 3.31 9.99 13.23 11.05 44.09 9.13 4.41 10.18 14.33 11.04 49.60 8.59 5.51 10.38 15.43 11.04 55.12 8.03 6.61 10.58 16.53 11.04 60.63 6.36 7.72 10.72 18.74 11.02 63.75 4.92 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its are for dualrecirculation loop operation.Single Loop O peration (SLO )adjustm ents are perform ed as described in Section 2 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (G W D/M TU)

APLHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 26 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 4 APLHGR Limits for Bundle Type GE14-P10DNAB401-14GZ (GE14)

M ostLim iting Lattice forEach Exposure Point Average Planar LHG R Average Planar LHG R Average Planar LHG R Exposure Lim it Exposure Lim it Exposure Lim it (G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft)

(G W D/M TU)

(kw /ft) 0.00 9.63 8.82 10.67 22.05 10.87 0.22 9.67 9.92 10.75 27.56 10.50 1.10 9.73 11.02 10.84 33.07 10.10 2.20 9.86 12.13 10.94 38.58 9.64 3.31 10.01 13.23 10.96 44.09 9.11 4.41 10.18 14.33 10.96 49.60 8.57 5.51 10.37 15.43 10.98 55.12 8.03 6.61 10.50 16.53 10.99 60.63 6.30 7.72 10.58 18.74 10.99 63.63 4.93 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its are for dualrecirculation loop operation.Single Loop O peration (SLO )adjustm ents are perform ed as described in Section 2 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (G W D/M TU)

APLHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 27 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 5 APLHGR Limits for A10-3813B-13GV80, A10-4077B-15GV80, and A10-4088B-15GV80 (A10)

Average Planar LHG R Exposure Lim it (G W D/M TU)

(kw /ft) 0.00 12.50 15.00 12.50 67.00 7.30 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its are for dualrecirculation loop operation.Single Loop O peration (SLO )adjustm ents are perform ed as described in Section 2 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (G W D/M TU)

APLHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 28 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 6 APLHGR Limits for A10-1623B-5GV80 (A10)

Average Planar LHG R Exposure Lim it (G W D/M TU)

(kw /ft) 0.00 11.50 15.00 11.50 67.00 6.30 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its are for dualrecirculation loop operation.Single Loop O peration (SLO )adjustm ents are perform ed as described in Section 2 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (G W D/M TU)

APLHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 29 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 7 GE13 Power Dependent MAPLHGR Multiplier - MAPFAC(P)

NSS/TSSS Insertion Tim es -AllExposures Turbine Bypass In-Service Turbine Bypass O ut-O f-Service Core Pow er

(% rated)

M APFAC(P)

Core Pow er

(% rated)

M APFAC(P) 100 1

100 0.98 30 0.53 30 0.53 Core Flow > 50% rated Core Flow > 50% rated 30 0.39 30 0.33 25 0.37 25 0.31 Core Flow < 50% rated Core Flow < 50% rated 30 0.44 30 0.36 25 0.43 25 0.35 M APFAC(P)is notdependentupon any Equipm entO ut-O f-Service exceptTurbine Bypass.

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

1.1 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Pow er (% Rated)

M APFAC(P)

TBVO O S: < 50% Core TBVO O S: > 50% Core Flow TBVIS: > 50% Core TBVIS: < 50% Core Flow Turbine Bypass O ut-O f-Service (TBVO O S)

Turbine Bypass In-Service (TBVIS)

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 30 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 8 GE14 Power Dependent MAPLHGR Multiplier - MAPFAC(P)

NSS/TSSS Insertion Tim es -AllExposures Turbine Bypass In-Service Turbine Bypass O ut-O f-Service Core Pow er

(% rated)

M APFAC(P)

Core Pow er

(% rated)

M APFAC(P) 100 1

100 1

30 0.58 30 0.57 Core Flow > 50% rated Core Flow > 50% rated 30 0.45 30 0.40 25 0.42 25 0.37 Core Flow < 50% rated Core Flow < 50% rated 30 0.51 30 0.43 25 0.49 25 0.41 M APFAC(P)is notdependentupon any Equipm entO ut-O f-Service exceptTurbine Bypass.

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

1.1 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Pow er (% Rated)

M APFAC(P)

TBVO O S: < 50% Core TBVO O S: > 50% Core Flow TBVIS: > 50% Core TBVIS: < 50% Core Flow Turbine Bypass O ut-O f-Service (TBVO O S)

Turbine Bypass In-Service (TBVIS)

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 31 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 9 Flow Dependent MAPLHGR Factor - MAPFAC(F)

(GE13 / GE14)

M ax Core Flow 102.5% Rated M ax Core Flow 107% Rated Core Flow

(% rated)

M APFAC(F)

Core Flow

(% rated)

M APFAC(F) 30 0.592 30 0.577 74.8 1.000 78.4 1.000 102.5 1.000 107 1.000 These values bound both Turbine Bypass In-Service and O ut-O f-Service.

These values bound both Recirculation Pum p Trip In-Service and O ut-O f-Service.

The 102.5% m axim um flow line is used for operation up to 100% rated flow.

The 107% m axim um flow line is used for operation up to 105% rated flow (ICF).

0.500 0.600 0.700 0.800 0.900 1.000 30 40 50 60 70 80 90 100 Core Flow (% Rated)

M APFAC(F).

M AX FLO W = 102.5%

M AX FLO W = 107%

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 32 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 10 LHGR Limits for all ATRIUM-10 Fuel (A10)

Pellet LHG R Exposure Lim it (G W D/M TU)

(kw /ft) 0.00 13.40 18.90 13.40 74.40 7.10 These values apply to both Turbine Bypass In-Service and O ut-O f-Service.

These values apply to both Recirculation Pum p Trip In-Service and O ut-O f-Service.

These lim its apply to both Tw o Loop O peration (TLO )and Single Loop O peration (SLO ).

0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 PelletExposure (G W D/M TU)

LHG R Lim it(kw /ft).

UNACCEPTABLE O PERATIO N ACCEPTABLE O PERATIO N

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 33 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 11 A10 Power Dependent LHGR Multiplier - LHGRFAC(P)

NSS/TSSS Insertion Tim es -AllExposures Turbine Bypass In-Service Turbine Bypass O ut-O f-Service Core Pow er

(% rated)

LHG RFAC(P)

Core Pow er

(% rated)

LHG RFAC(P) 100 1.00 100 1.00 30 0.70 30 0.69 Core Flow > 50% rated Core Flow > 50% rated 30 0.59 30 0.49 25 0.55 25 0.44 Core Flow < 50% rated Core Flow < 50% rated 30 0.63 30 0.58 25 0.60 25 0.52 LHG RFAC(P)is notdependentupon any Equipm entO ut-O f-Service exceptTurbine Bypass.

0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Pow er (% Rated)

M APFAC(P)

TBVO O S: < 50% Core TBVO O S: > 50% Core Flow TBVIS: > 50% Core TBVIS: < 50% Core Flow Turbine Bypass O ut-O f-Service (TBVO O S)

Turbine Bypass In-Service (TBVIS)

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 34 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 12 Flow Dependent LHGR Multiplier - LHGRFAC(F)

(A10 Fuel)

M ax Core Flow 102.5% Rated M ax Core Flow 107% Rated Core Flow

(% rated)

LHG RFAC(F)

Core Flow

(% rated)

LHG RFAC(F) 30 0.905 30 0.865 45.3 1.000 52.1 1.000 102.5 1.000 107 1.000 These values bound both Turbine Bypass In-Service and O ut-O f-Service.

These values bound both Recirculation Pum p Trip In-Service and O ut-O f-Service.

The 102.5% m axim um flow line is used for operation up to 100% rated flow.

The 107% m axim um flow line is used for operation up to 105% rated flow (ICF).

0.800 0.850 0.900 0.950 1.000 30 40 50 60 70 80 90 100 Core Flow (% Rated)

LHG RFAC(F).

M AX FLO W = 102.5%

M AX FLO W = 107%

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 35 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 13 Flow Dependent MCPR Limit - MCPR(F)

(GE13 Fuel)

M ax Core Flow 102.5% Rated M ax Core Flow 107% Rated Core Flow

(% rated)

M CPR(F)

Core Flow

(% rated)

M CPR(F) 30 1.73 30 1.77 90 1.21 94 1.21 102.5 1.21 107 1.21 These values bound both Turbine Bypass In-Service and O ut-O f-Service.

These values bound both Recirculation Pum p Trip In-Service and O ut-O f-Service.

The 102.5% m axim um flow line is used for operation up to 100% rated flow.

The 107% m axim um flow line is used for operation up to 105% rated flow (ICF).

1.18 1.23 1.28 1.33 1.38 1.43 1.48 1.53 1.58 1.63 1.68 1.73 1.78 30 40 50 60 70 80 90 100 Core Flow (% Rated)

M CPR(F).

M AX FLO W = 102.5%

M AX FLO W = 107%

TVA NuclearFuel TVA-COLR-BF3C12 CoreOperating Lim itsReport Revision 0, Page 36 Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 14 Flow Dependent MCPR Limit - MCPR(F)

(GE14 Fuel)

M ax Core Flow 102.5% Rated M ax Core Flow 107% Rated Core Flow

(% rated)

M CPR(F)

Core Flow

(% rated)

M CPR(F) 30 1.63 30 1.65 88 1.21 92 1.21 102.5 1.21 107 1.21 These values bound both Turbine Bypass In-Service and O ut-O f-Service.

These values bound both Recirculation Pum p Trip In-Service and O ut-O f-Service.

The 102.5% m axim um flow line is used for operation up to 100% rated flow.

The 107% m axim um flow line is used for operation up to 105% rated flow (ICF).

1.18 1.23 1.28 1.33 1.38 1.43 1.48 1.53 1.58 1.63 1.68 30 40 50 60 70 80 90 100 Core Flow (% Rated)

M CPR(F).

M AX FLO W = 102.5%

M AX FLO W = 107%

TVA NuclearFuel TVA-COLR-BF3C11 CoreOperating Lim itsReport Revision 0, Page 37 (Final)

Browns Ferry Nuclear PlantUnit3 Cycle12 Figure 15 Flow Dependent MCPR Limit - MCPR(F)

(A10 Fuel)

M ax Core Flow 102.5% Rated M ax Core Flow 107% Rated Core Flow

(% rated)

M CPR(F)

Core Flow

(% rated)

M CPR(F) 30 1.64 30 1.70 88 1.21 92 1.21 102.5 1.21 107 1.21 These values bound both Turbine Bypass In-Service and O ut-O f-Service.

These values bound both Recirculation Pum p Trip In-Service and O ut-O f-Service.

The 102.5% m axim um flow line is used for operation up to 100% rated flow.

The 107% m axim um flow line is used for operation up to 105% rated flow (ICF).

1.18 1.23 1.28 1.33 1.38 1.43 1.48 1.53 1.58 1.63 1.68 1.73 30 40 50 60 70 80 90 100 Core Flow (% Rated)

M CPR(F).

M AX FLO W = 102.5%

M AX FLO W = 107%