ML061080601

Core Operating Limits Report, for Cycle 13 Operation

ML061080601
Person / Time
Site:	Browns Ferry
Issue date:	04/07/2006
From:	Crouch W Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML061080601 (42)

Text

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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 7, 2006 U.S. Nuclear Regulatory Commission ArTN:

Document Control Desk Mail Stop:

OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of Tennessee Valley Authority

)

Docket No. 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 -

CORE OPERATING LIMITS REPORT (COLR),

FOR CYCLE 13 OPERATION In accordance with the requirements of Technical Soecification 5.6.5.d, enclosed is the Unit 3 Cycle 13, Core Operating Limits Report.

There are no new commitments contained in this letter.

If you have any questions, please contact me at (256) 729-2636.

Sincerely, 6.cL&.

William D. Crouch Manager of Licensing and Industry Affairs Enclosure cc:

See page 2

• OCC)

U.S. Nuclear Regulatory Commission Page 2 April 7, 2006 Enclosure cC (Enclosure):

Mr. Malcolm T. Widmann, 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. Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 CORE OPERATING LIMITS REPORT (COLR)

FOR CYCLE 13 OPERATION (SEE ATTACHED)

Ii TVA Nuclear Fuel Core Operating Limits Report QA Document TVA-COLR-B:-3C) 3 Revision 0. '?ae I

)1 Browns Feny Nuclear Plant Unit 3 Cycle 13 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTHORITY Nuclear Fuel Design BWR Fuel Engineering Department Prepared By:

Earl E. Riley. Sr. Engineering Specialist BWR Fuel Engineering

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Verified Bv:

Approved By:

Reviewed By:

Approved By:

Date:

Z./13/2ooC.

Date:

2 i3/0o.

Date:

21313 6 Date:

Z//3?/O W Date: 2/ / /

BWR Fuel Englneering r,

M. Keck, Supervisor rowns Ferry Reactor Engineering airman Revision 0 (2 i4 2006)

Pages Affected: All Revision 0 (' 14 2006)

Pages Affected: All

TVA Nuclear Fuel Core Operating Limits Rep-..

TVA-COLR-BF3C13 Revision 0, Page 2

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Revision Log Revision Date Description Affected Pages 0

2/14/2006 Initial Release for New Cycle

• All

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Browns Ferry Nuclear Plant Unit 3 Cycle 13

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1. INTRODUCTION

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This Core Operating Limits Report for Browns Ferry Nuclear Plant Unit 3 Cycle 13 is prepared in accordance with the requirements of Browns Ferry Technical Specification 5.6.5.

The core operating limits presented here were developed using NRC-approved methods (References 2 and 3).

One exception to this is an issue with the assumed uncertainty for the GEXLI4 CPR correlation. The NRC has identified that the correlation lacked top-peaked axial power shape data in its formulation and in the calculation of the overall correlation uncertainty. As an interim action, an increased GEXL14 uncertainty that incorporates a significant penalty has been calculated and applied to the MCPR Safely Limit (SLMCPR) calculation for this cycle.

Results from the reload analyses for Browns Ferry Unit 3 Cycle 13 are documented in Reference 1.

The following core operating and Technical Specification limits are included in this report:

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

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

)

c. Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

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

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

f. Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

The Unit 3 Cycle 13 core is composed of Framatome-ANP ATRIUM

-m-10 and Global Nuclear Fuel GE-14Tm assemblies. Throughout this document these are referred to as A10 and GEI4 with the trademark implied.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

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2. APLHGR LIMIT (TECHNICAL SPECIFICATIONS 3.2.1 AND 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

[APLHGRpATED* MAPFAC(F)]

[APLHGRRATED

• MAPFAC(F)]

[ALPHGRRATED* SLO_Multiplier]

The off-rated power and flow corrections to the APLHGR limit only apply to the GEJ14 fuel in the Browns Ferry Unit 3 Cycle 13 core. For that reason, this multiplier is set to 1.0 as shown below for the AI0 fuel.

Rated Power and Flow Limits: APLHGRRATED The APLHGR limits for full power and flow conditions for each type of fuel as a function of exposure are shown in Figures 1-4. The APLHGR limits provided in the COLR figures for the GE14 assemblies are for the most limiting lattice (excluding natural uranium) at each exposure point. The specific values for each GE14 lattice are given in Reference 4. The ATRIUM-10 values are provided in Reference 1.

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Bundle Type Rated Power APLHGR Limit GEI4-PIODNAB402-I5GZ Figure I GEI 4-P IODNAB401-14GZ Figure 2 A]0-3813B-13GV80 Figure 3 A10-4077B-15GV80 Figure 3 AIO-4088B-15GV80 Figure 3 A]0-1623B-5GV80 Figure 4 AIO-4171B-14GV80 Figure 3 AIO-4163B-16GV80 Figure 3 A10-4181B-13GV80 Figure 3

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Browns Ferry Nuclear Plant Unit 3 Cycle 13

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)1 Off-Rated Power Corrections: APLBGRp The APLHGR limits for the GE14 fuel lattices are adjusted for off-rated power conditions using the ARTS multiplier, MAPFAC(P), which is provided in Reference 1. No off-rated power correction is required for the AI0 rated APLHGR limits.

Product Line MAPFAC(P)

GE14 Figure 5 A10 1.0 Off-Rated Flow Corrections: APLHGRF The APLHGR limits for the GE14 fuel lattices are adjusted for off-rated flow conditions using the ARTS multiplier, MAPFAC(F), which is provided in Reference 1. No off-rated flow correction is required for the AI 0 rated APLHGR limits.

Product Line MAPFAC(F)

GE14 Figure 6 A10 1.0

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SLO Corrections: APLHGRsLo Single Recirculation Loop Operation (SLO) requires that the rated power APLH(GR limit (APLHGR,-,,M) be reduced by applying the following multipliers. The GE14 multiplier is provided in Reference 5. The A10 multiplier is provided in Reference 1.

Product Line l

SLO Multiplier GE14 0.93 AIO 0.85

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The rated APLHGR limits in Figures 1-4 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options. This includes combinations of these EOOS options.

In-Service RPTOOS TBVOOS PLUOOS FHOOS (or FFTR)

All equipment In-Service (includes I SRVOOS)

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.

The off-rated power corrections [MAPFAC(P)] in Figure 5 is dependent upon operation of the Turbine Bypass Valve system. For this reason, separate limits are to be applied for TBVIS or TBVOOS operation. The MAPFAC(P) limits have no dependency on RJ'TOOS, PLUOOS, SLO, or FHOOS/FFTR.

The off-rated flow corrections [MAPFAC(F)] in Figure 6 bound both equipement In.Service or EOOS operation.

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3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.2.3, 3.3.4.1, and 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* LHGRFAC(P)]

[LHGRRATED

• LHGRFAC(F)]

The off-rated power and flow corrections to the LHGR limit only apply to the Al 0 fuel in the Browns Ferry Unit 3 Cycle 13 core. For that reason, the multiplier for the GE14 fuel is set to 1.0 as shown below.

Rated Power and Flow Limits: LHGRRATED The LHGR limit is fuel type dependent. The limits for these types are given below:

Fuel Type LHGR Limit GE14 0

Figure 7 A10 Figure 8 Nib The AlO LHGR limit is provided in Reference 6. The GE14 LHGR limit is provided in Reference 12.

Off-Rated Power Corrections: LHGRp The LHGR limits for the A10 fuel are adjusted for off-rated power conditions using the LHGRFAC(P) multiplier which is provided in Reference 1. The LHGRFAC(P) multiplier is dependent on whether the Turbine Bypass system is in-service (TBVIS) or out-of-service (TBVOOS). No off-rated power correction is required for the GE14 rated LHGR limits.

Product Line LHGRFAC(P)

GEM4 1.0 A10 Figure 9 Browns Ferry Nluclear Plant Unit 3 Cycle 13

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Off-Rated Flow Corrections: LHGRF The LHGR limits for the A10 fuel are adjusted for off-rated flow conditions using the LHGRFAC(F) multiplier which is provided in Reference 1. No off-rated flow, correction is required for the GE14 rated LHGR limits.

I Product Line GE14 I

LIUGRFAC(F) 1.0 Figure 10 i

I AI0 I

Equipment Out-Of-Service (EOOS) Corrections:

The rated LHGR limits are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options. This includes combinations of these EOOS options.

In-Service RPTOOS TBVOOS PLUOOS SLO FHOOS (or FFTR)

All equipment In-Service (includes 1 SRVOOS)

EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Power Load Unbalance Out-Of-Service Single Recirculation Loop Operation Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction)

J The off-rated power corrections [LHGRFAC(P)] in Figure 9 are dependent upon operation of the Turbine Bypass Valve system. For this reason, separate limits are to be applied for TBVIS or TBVOOS operation. TIle LHGRFAC(P) limits have no dependency on RPTOOS, PLUOOS, SLO, or FHOOS/FFTR.

The off-rated flow corrections [LHGRFAC(F)] in Figure 10 bound both equipment In-Senrice or EOOS operation.

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4. OLMICPR (TECHNICAL SPECIFICATIONS 3.2.2, 3.3.4.1, AND 3.7.5)

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The MCPR Operating Limit (OLMCPR) is calculated to be the most limiting of the flow-dependent MCPR (MCPRF) and power-dependent MCPR (MCPRp).

OLMCPR limit = MAX ( MCPRF, MCPRp) where:

MCPRF core flow-dependent MCPR limit MCPRp power-dependent MCPR limit MCPRF limits are provided by fuel type in Figures 11 and 12. MCPRp limits are provided in Tables I through 6.

Flow-Dependent MCPR Limits: MCPRF The MCPRF limits are dependent upon:

• Core Flow (% of Rated).

• Max Core Flow Limit (Rated or Increased Core Flow, ICF)

• Fuel Type (GE14 or AI0)

The MCPRF limits are provided by fuel type in Figure 11 (GE14) and Figure 1:2 (A10).

These limits are valid for all EOOS combinations. No adjustment is required to the MCPRF limits for SLO. The MCPRF limits are found in Reference 1.

Power-Devendent MCPR Limits: MCPRp The MCPRp limits are dependent upon:

• Core Power Level (% of Rated)

• Technical Specification Scram Speed (TSSS) or Nominal Scram Speed (NEWS)

• Fuel Type (GE14 orAI0)

• 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 (Ref. 1) 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 MCPRp limits are determined from these tables using linear interpolation

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between the specified powers.

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Exposure Range Scram Speed MCPRp BOC to NEOC NSS Table 1 TSSS Table 2 BOC to EOC NSS Table 3 TSSS Table 4 BOC to CD NSS Table 5 TSSS Table 6

a. Scram Speed Dependent Limits (TSSS vs. NSS)

MCPRp limits are provided for two different sets of assumed scram speeds. The Technical Specification Scram Speed (TSSS) MCPRp limits are applicable at all limes as long as the scram time surveillance demonstrates that the times in Technical Specification table 3.1.4-1 have been met. Nominal Scram Speeds (NSS) may be used as long as the scram time surveillance demonstrates that the times in the following lable are met (Ref. 8).

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Notch Nominal Scram Speed Position (seconds) 46 0.42 36 0.98 26 1.60 06 2.90 In demonstrating compliance with this table, the same surveillance requirements from Technical Specification 3.1.4 apply, except that the definition of SLOW rod; should conform to the scram speeds in the table above. If conformance to this table is not demonstrated, TSSS MCPRp limits shall be used.

On initial cycle startup, TSSS limits are used until the successful completion of scram timing confirms that NSS limits may be used.

b. Fuel Type Dependent Limits Separate MCPRp limits are provided for the GEI 4 and AI 0 fuel types.

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c. Exposure Dependent Limits Exposures are tracked on a Core Average Exposure basis (not Cycle Exposure). The higher exposure MCPRp limits are always more limiting and may be used for any Core Average Exposure up to the ending exposure.

MCPRp limits are provided for the following exposure ranges (Ref. 1):

BOC to NEOC BOC to EOC BOC to CD NEOC corresponds to EOC corresponds to CD corresponds to 31,555 M'bAd I MTU 33,663 M'd / MTU 34,731 MWd / ITU NEOC refers to a Near EOC exposure point.

The EOC exposure point is not the true End-Of-Cycle exposure. Instead it corresponds to a licensing exposure window that exceeds expected end-of-full-power-life.

The CD (CoastDown) exposure point represents a licensing exposure point that exceeds the expected end-of-cycle exposure including cycle extension options.

d. Equipment Out-Of-Service (EOOS) Options EOOS options included in the MCPRp limits are:

A)

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

All equipment In-Service (includes I SRVOOS)

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 EOC, additional combinations of MCPRp limits are also provided that include FHOOS. The CD exposure range assumes application of FFTR, so the CD based MCPRp limits already include FHOOS.

e. Single-Loop-Operation (SLO) Limits The MCPRp limits for SLO are to be increased by 0.02 (Ref. 1).

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f. Below Pbypass Limits Below Pbypass (30% rated power), the MCPRp limits are dependent upon core flow.

One set of MCPRp limits applies if the core flow is above 50% of rated with a second set that applies if the core flow is less than or equal to 50% rated.

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5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL REQUIREMENTS MANUAL SECTION 5.3.1 AND TABLE 3.3.4-1)

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

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

SRtB * (0.66(W-AW) + 59%)

Allowable Value Nominal Trip Setpoint (NTSP) where:

SRB =

W =

AW =

The APRM Rod (corresponding to Rod Block setting in percent of rated thermal power (3458 MWt)

Loop recirculation flow rate in percent of rated Difference between two-loop and single-loop effective recirculaticn flow at the same core flow (AW=0.0 for two-loop operation)

Block trip setting is clamped at a maximum allowable value cf 115%

a NTSP of 113%).

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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 shall be as follows (refs. 9 & 10):

. Trip Allowable Value Nominal Trip Setpoint RBM Trip Setpoit (AV)

(NTSP)

LPSP 27%

25%

IPSP 62%

60%

HPSP 82%

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%

(1),Q2)

(1),(2)

(1),(2)

I Notes: (1) These setpoints are based upon an Analytical Limit HTSP of 117% (w/o filter) which corresponds to a MCPR operating limit of 1.33(GE14/A,10), as reported in section 5.5 of Reference 1. Unit 3 Cycle 13 has had a cycle specific CRWE analysis performed and the table provided in section 5.5 of Reftrence I supercedes the OLMCPR values of references 9 and 11.

(2) The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds (reference 9.b). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference 9.a).

The RBM setpoints in Technical Specification Table 3.3.2.1 -I are applicable " when:

THERMIAL POWER Applicable Notes from

(% Rated)

MICPR (2)

Table 3.3.2.1-1

> 27% and < 90%

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

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

> 90%

< 1.43 (g) dual loop operation single loop operation dual loop operation (3)

Notes: (1) The table confirms that the generic operability limits from reference 11 are bounded by the Unit 3 Cycle 13 CRWE analysis. The actual cyclc specific results indicate that the SLMCPR remains protected throughout the cycle without RBM operation (i.e. unblocked) per reference 1.

(2) The MCPR values shown correspond to a SLMCPR of 1.09 for dual recirculation loop operation and 1.11 for single loop operation.

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

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7. SHUTDOWN MARGIN (SDM) LIMIT (TECHNICAL SPECIFICATION 3.1.1)

The core shall be subcritical with the following margin with the strongest OPERABLE control rod fully withdrawn and all other OPERABLE control rods fully inserted (Ref. 7).

SDM > 0.38% dk/k I

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8. REFERENCES

1. EMF-3264 Rev. 0, "Browns Ferry Unit 3 Cycle 13 Reload Analysis", dated December 2005.

2. Framatome-ANP Analytical Methodology

References:

a) XN-NF-81-58(P)(A)

Revision 2 and Supplements I and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

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

c) EMF-85-74(P) Revision 0 Supplement I (P)(A) and Supplement 2(P)(A), RO.DEX2A (BIJR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

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

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

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

)

g) EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, '3iemens Power Corporation, October 1999.

h) 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.

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

j) 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.

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

I) ANT-1358(P)(A) Revision 1, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.

m) EMF-2209(P)(A) Revision 2, SPCB Critical Power Correlation, Siemens Power

'Corporation, September 2003.

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

o) EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome

)

ANP, May 2001.

p) EMF-2292(P)(A) Revision 0, ATRZUMTh]O: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

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3. Global Nuclear Fuel Analytical Methodology

References:

a) NEDE-2401 I-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 (Supplement for United States)", June 2000.

4. JI 1-03963MAPL Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 3 Reload 10 Cycle 11", March 2002.

5. J1 1-03963SRLR Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 10 Cycle 11 ", March 2002.

6. EMF-3213(P) Rev. 0, "Mechanical Design Report for Browns Ferry Unit 3 Reloa6 BFE3-13 ATRIUMT'-10 Fuel Assemblies", dated September 2005.

7. TVA-COLR-BF3CI2 Rev. 1, "Browns Ferry Nuclear Plant Unit 3, Cycle 12 Core Operating Limits Report (COLR)", dated October 26, 2005.

8. EMF-3191(P) Rev. 0, "Browns Ferry Unit 3 Cycle 13 Plant Parameters Document", dated June 2005.

9. PRNM Setpoint Calculation:

a) Filtered Setpoints - EDE-28-0990 Rev. 3 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condi:ion] for

)

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

b) Unfiltered Setpoints - EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, R13M, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated October 1997.

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

11. NEDC-32433P, "Maximum Extended Load Line Limit and ARTS Improvement P3rogram Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.

12. GE-NE-L12-00889-00-OlP Rev. 0, "GE14 Fuel Design Cycle-Independent Analyses for Browns Ferry Units 2.and 3", dated January 2002.

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TVA-COLR-BF3C 13 Revision 0, Page 18 Table 1: MCPRp Limits for BOC to NEOC Exposures - NSS Scram Times

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(Applicable up to Core Average Exposure of 31,555 MWd / MITU)

MCPRp Limit MCPRp Limit

)

EOOS Power A10 GE14 Option

(% Rated) 100 1.34 1.34 65 1.55 1.54 60 1.56 1.59 50 1.68 1.71 50 1.79 1.79 In-Servce 30 2.06 2.12 30 (> 50%F) 2.36 2.42 25 (> S0%F) 2.53 2.57 30 50%F) 2.29 2.39 25 (50%F) 2.46 2.56 100 1.34 1.34 65 1.55 1.54 60 1.56 1.59 50 1.68 1.71 RPOS 50 1.79 1.79 FLPTOOS 30 2.06 2.12 30 (> so50;F) 2.36 2.42 25 (> 50%F) 2.53 2.57 30 (5oF) 2.29 2.39 25 (50VF) 2.46 2.56 100 1.38 1.37 65 1.59 1.58 60 1.61 1.62 50 1.70 1.73 TNOS 50 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50oF) 2.85 2.90 25 (> 50%F) 3.18 3.22 30 ( 50%F) 2.54 2.64 25 so%F) 2.88 2.96 100 1.38 1.37 65 1.59 1.58 60 1.61 1.62 50 1.70 1.73 RPTOOS 50 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50%F) 2.85 2.90 25 (> 50%F) 3.18 3.22 30 ( 50%F) 2.54 2.64 25 (50%F) 2.88 2.96 EOOS Power Option

(°/ed)

AI GE14 100 1.37 1.37 65 1.56 1.59 60 1.61 1.6.4 50 1.74 1.77 FOS 50 1.79 1.79 FHOOS 30 2.16 2.22 30 (> 5soF) 2.45 2.52 25 (> 50%F) 2.65 2.69 30 (I5OF) 2.36 2.48 25 (.50%F) 2.56 2.67 100 1.37 1.37 65 1.56 1.59 60 1.61 1.64 50 1.74 1.77 RPTOOS 50 1.79 1.79 FHOOS 30 2.16 2.22 30 (> 5o%F) 2.45 2.52 25 (> 50%F) 2.65 2.69 30 (5o%F) 2.36 2.48 25 ( 5o%F) 2.56 2.67 100 1.40 1.40 65 1.60 1.1 60 1.64 1.66 50 1.76 TBVOOS 50 1.79 1.79 FHOOS 30 2.17 2.23 30 (> 50%F) 2.93 2.99 25 (> So%F) 3.27 3.'1i 30 ( 50%F) 2.61 2.1' 25 ( 50%F) 2.97 3.05 100 1.40 1.40 65 1.60 1.61 60 1.64 1.66 RPTOS 50 1.76 RTBOOS 50 1.79 1219 lhVOOS 30 2.17 2.23 30 (> 50%F) 2.93 2.99 25 (> 50%F) 3.27 3.31 30 (0so%F) 2.61 2.'1 25 (50o%F) 2.97 3.05

)

Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limits R tI TVA-COLR-BF3CI3 Revision 0. Page 19 Table 1 (Continued): MICPRp Limits for BOC to NEOC Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 31,555 MWd / MTU)

)1 MCPRp Liniit MCPRp Lint I

FOOS Power A0 G1 Option

(% Rated)

A10 GEI4 100 1.35 1.34 65 1.55 1.54 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 PL Q S30 2.06 2.12 30 (> 50ooF) 2.36 2.42 25 (> 5o%F) 2.53 2.57 30 (E 509SF) 2.29 2.39 25 (E 50sooF) 2.46 2.56 100 1.35 1.34 65 1.55 1.54 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 RPTOOS 30 2.06 2.12 30 (> 50°oF) 2.36 2.42 25 (> 50oF) 2.53 2.57 30 (-so500F) 2.29 2.39 25 (E 50/oF) 2.46 2.56 100 1.38 1.37 65 1.59 1.58 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50%F) 2.85 2.90 25 (> 5o%F) 3.18 3.22 30 L( 5o%F) 2.54 2.64 25 (550%F) 2.88 2,96-100 1.38 1.37 65 1.59 1.58 60 1.73 1.73 FLOS 50 RPTOOS 50 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50%F) 2.85 2.90 25 (> 50%F) 3.18 3.22 30 (E 50%F) 2.54 2.64 25 (L5o%F) 2.88 2.96 EOOS Power A10 GE14 Option

(% Rzted)

A 100 1.37 1.37 65 1.56 1.59 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 FHOOS 30 2.16 2.22 30 (> so%F) 2.45 2.52 25 (> 5o%F) 2.65 2.09 30 L< 50%F) 2.36 2.48 25 (E 50%F) 2.56 2.07 100 1.37 1.27 65 1.56 1.'9 60 1.73 1.73 PLUOOS 50 RPLUOS 50 1.79 1.719 RFTOOS 30 2.16 2.22 FHOOS 30 (>so%F) 2.45 2.$2 25 (> 5o%F) 2.65 2.69 30 (< 50%F) 2.36 2.'.8 25 (5 50%F) 2.56 2.67 100 1.40 I.40 65 1.60 1.61 60 1.73 1.73 PLOS 50 PLUQO0 S 50 1.79 1.79 TBVOOS 30 2.17 2.,3 F OS 30 (>s5o%F)

.2.93 2.199 25 (> 50%F) 3.27 3.2,1 30 (<s0%F) 2.61 2.71 25 (550%F) 2.97 3.05 100 1.40 1.-I0 65 1.60 1.6I 60 1.73 1.73 PLUOOS 50 RPTOOS 50 1.79 1.79 TBVOOS 30 2.17 2.23 FIHOOS 30 (> 50%F) 2.93 2.5:9 25 (>5o%F) 3.27 3.21 30 (C 50%F) 2.61 2.;11 25 (< 50%F) 2.97 3.C5 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA NuclearFuel Coie Operating Linits Rt.

TVA-COLR-IIF3C13 Revision 0, ?age 20 Table 2: MCPRp Liniits for BOC to NEOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 31,555 MWd t MTU)

N]CPRp Linmt MCPRp Linmi:

EOOS Power Option

(% Rated)

A10 GE14 100 1.36 1.36 65 1.57 1.56 60 1.58 1.61 50 1.69 1.73 50 1.80 1.80 hi-Servce 30 2.08 2.13 30 (>50%F) 2.36 2.42 25 (>5o%F) 2.53 2.57 30 (5o%F) 2.29 2.39 25 So%F) 2.46

.2.56 100 1.36 1.36 65 1.57 1.56 60 1.58 1.61 50 1.69 1.73 RPOS 50 1.80 1.80 R.PTOOS 30 2.08 2.13 30 (>5o%F) 2.36 2.42 25 (>50%F) 2.53 2.57 30 (5soF0 2.29 2.39 25 (sso%F) 2.46 2.56 100 1.40 1.40 65 1.61 1.59 60 1.63 1.64 50 1.72 1.75 TNOS 50 1.80 1.80 TBVOOS 30 2.10 2.16 30 (>soF) 2.85 2.90 25(>50%F) 3.18 3.22 30 (55o%F) 2.54 2.64 25 (50%F) 2.88 2.96 100 1.40 1.40 65 1.61 1.59 60 1.63 1.64 50 1.72 1.75 RPTOOS 50 1.80 1.80 TBVOOS 30 2.10 2.16 30 (>50%F) 2.85 2.90 25 (>50%F) 3.18 3.22 30 (f 50%F) 2.54 2.64 25 (s5o%F) 2.88 2.96 EOOS Power A10 GEI'l 0ption

(

ae) 100 1.39 1.39 65 1.58 1.61 60 1.62 1.66 50 1.75 1.79 FOS50 1.80 1.80 FHOOS 30 2.18 2.24 30 (>sOo%F) 2.45 2.52 25 (>50%F) 2.65 2.6S 30 55o%F) 2.36 2.4.

25 (s0%F) 2.56 2.67 100 1.39 1.39 65 1.58 1.61.

60 1.62 1.66 50 1.75 1.79 RPTOOS 50 1.80 1.80 FHOOS 30 2.18 2.24I 30 (>50%F) 2.45 2.52 25 (>50%F) 2.65 2.69) 30 (so%F) 2.36 2.43 25 (5soF) 2.56 2.67 100 1.42 1.4.2 65 1.62 1.63 60 1.66 1.6?

50 1.77 ThlVOOS 50 1.80 1.81 FHOOS 30 2.20 2.25 30 (>50%F) 2.93 2.99 25(>50%F) 3.27 3.31 30 (50%F) 2.61 2.71 25 (s5%F) 2.97 3.05 100 1.42 1.42 65 1.62 1.03 60 1.66 1.09 RPTOOS 50 1.77 TBOS 50 1.80 1LF I FHOOS 30 2.20 2.25 O

30 (>so%F) 2.93 2.S9 25 (> soF) 3.27 3.'1 30(sso%F) 2.61 2.71 25 (sso0%F) 2.97 3.C5 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuezear Fuel Core Operating Limits R.

t TVA-COLR-BF3C13 Revision 0, Page 21

)

Table 2 (Continued): MCPRp Limits for BOC to NEOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 31,555 MWd / AITU)

MICPRp Limit MCPRp Limit

)

EOOS Power A10 GE14 Option

(% Rated)

AO C1 100 1.37 1.36 65 1.57 1.56 60 1.74 1.74 50 PU S 50 1.80 1.80 PLUOOS 30 2.08 2.13 30 (> 5o%F) 2.36 2.42 25 (> So%F) 2.53 2.57 30 (S 5o%F) 2.29 2.39 25 & so%F) 2.46 2.56 100 1.37 1.36 65 1.57 1.56 60 1.74 1.74 50 PLUOOS 50 1.80 1.80 RPTOOS 30 2.08 2.13 30 (> 5o%F) 2.36 2.42 25 (> S0%F) 2.53 2.57 30 (so%F) 2.29 2.39 25 5o%F) 2.46 2.56 100 1.40 1.40 65 1.61 1.59 60 1.74 1.74 50 PLUOOS 50 1.80 1.80 TBVOOS 30 2.10 2.16 30 (> 5o%F) 2.85 2.90 25 (> SoF) 3.18 3.22 30 (5o%F) 2.54 2.64 25 (so%F) 2.88 2.96 100 1.40 1.40 65 1.61 1.59 60 1.74 1.74 PLOS 50 RPTOOS 50 1.80 1.80 RTBOOS 30 2.10 2.16 TBVOOS 30 (> so%F) 2.85 2.90 25 (> so%)

3.18 3.22 30 ( so%F) 2.54 2.64 25 (S0o%F) 2.88 2.96 EOOS Power A10 GE] 4 Option

(% Rated)

AO GI 100 1.39 1.39) 65 1.58 1.61 60 1.74 1.74 50 PLUOOS 50 1.80 1.8)

FHOOS 30 2.18 2.24 30 (> 5o%F) 2.45 2.52 25 (> sO%F) 2.65 2.69 30 (S5o%F) 2.36 2.48 25 (0so%F) 2.56 2.67 100 1.39 1.39 65 1.58 1.61 60 1.74 1.74 50--

RPTOOS 50 1.80 1.80 RPTOOS 30 2.18 2.24

, OOS 30 (> so%F) 2.45 2.52 25 (> 50%F) 2.65 2.69 30(5 5o%F) 2.36 2.48 25 (<5o%F) 2.56 2.67 100 1.42 1.42 65 1.62 1.63 60 1.74 1.74 TBLUOOS 50 1.80 LE I FT OOS 30 2.20 2.25 30 (> so%F 2.93 2.99 25 (> 50%F 3.27 3.'l1 30 (

5o%F) 2.61 2.71 25 CS5o%F) 2.97 3.(15 100 1.42 1.42 65 1.62

1. 63 60 1.74 1.4 PLUOOS 50 RPTOOS 50 1.80 1.:1 TBVOOS 30 2.20 2.25 FHOOS 30 (> 50%F) 2.93 2.99 25 (>50%F 3.27 3.'1 30 ( 50%F) 2.61 2.71 25 (550%F) 2.97 3.05

)

Acid 0.02 to the above MCPRp limits for SLO.

Browns Ferry N'uclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Ccre Operating Limits F t

TVA-COLR-BF3C13 Revision 0, Page 22 Table 3: MCPRp Limits for BOC to EOC Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 33,663 MWd / NITU)

NlCPRp Liniit MCPRp Liniit EOOS Power A10 GE1 Option

(% Rated) 100 1.36 1.36 65 1.55 1.54 60 1.56 1.59 50 1.68 1.71

.e50 1.79 1.79 In-Service 30 2.06 2.12 30 (> 50%F) 2.36 2.42 25 (> 50%F) 2.53 2.57 30 ('50%F) 2.29 2.39 25 (s5O%F) 2.46 2.56 100 1.36 1.36 65 1.55 1.54 60 1.56 1.59 50 1.68 1.71 50 1.79 1.79 RPTOOS 30 2.06 2.12 30 (> 50%F) 2.36 2.42 25 (> 50%F) 2.53 2.57 30 (s50%F) 2.29 2.39 25 (S50%F) 2.46 2.56 100 1.41

].40 65 1.59 1.58 60 1.61 1.62 50 1.70 1.73 TBOS so 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50%F) 2.85 2.90 25 (> so%F) 3.18 3.22 30 L< 50%F) 2.54 2.64 25 (S50%F) 2.88 2.96.

100 1.41 1.40 65 1.59 1.58 60 1.61 1.62 50 1.70 1.73 RPTOOS 50 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50%F) 2.85 2.90 25 (>50%F) 3.18 3.22 30 (s 50%F) 2.54 2.64 25 (L 5O%F) 2.88 2.96 EOOS Power Option

(

Rated)4 100 1.38 1.37 65 1.56 1.59 60 1.61 1.64 50 1.74 1.77 FOS 50 1.79 1.759 FHOOS 30 2.16 2.22 30 (> so%F) 2.45 2.52 25 (> so%F) 2.65 2.69 30 ( 50o%F) 2.36 2.483 25 (S5o%F) 2.56 2.67.

100 1.38 1.37 65 1.56 1.59 60 1.61 1.64 50 1.74 1.77 RPTOOS 50 1.79 1.79 FHOOS 30 2.16 2.22 30 (> so%F) 2.45 2.52 25 (> 50%F) 2.65 2.69 30 (so%F) 2.36 2.48 25 (.50%F) 2.56 2.67 100 1.41 1.41 65 1.60 1.61 60 1.64 1.66 50 1.76 TBVOOS 50 1.79 1.79 FHOOS 30 2.17 2.23 30 (> 50%F) 2.93 2.99 25 (> 50%F) 3.27 3.31 30 (. 5o%F) 2.61 2.71 25 ( 50%F) 2.97 3.05 i00 1.41 1.41 65 1.60

1. 1 60 1.64 1.(6 RPTOOS 50 1.76 1.

TBVOOS 30 2.17 2.23 FHOOS 30 (> so%F) 2.93 2.S9 25 (> 5o%F) 3.27 3.31 30 (50%F) 2.61 2.71 25 (sso%F) 2.97 3.05

)

Ae d 0.02 to the above MCPRP limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

• TVA Nuclear Fuel Core Operating Limits R

.t TVA-COLR-BF3CI3 Revision 0, Page 23 Table 3 (Continued): MCPRp Limits for BOC to EOC Exposures - NSS Scram lTimes

)

(Applicable up to Core Average Exposure of 33,663 MWd / MTU)

DNICPRp Limit MCPRp Lunit

)

EOOS Power A0 G1 Option

(% Rated)

A1 l GE14 100 1.37 1.37 65 1.55 1.54 60 1.73 1.73 50 PLUOS 50 1.79 1.79 30 2.06 2.12 30 (> 5o%F) 2.36 2.42 25 (> 5o%F) 2.53 2.57 30 ( so%F) 2.29 2.39 25 (E so%F) 2.46 2.56 100 1.37 1.37 65 1.55 1.54 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 RPTOOS 30 2.06 2.12 30 (> sm) 2.36 2.42 25 (> 5o%F) 2.53 2.57 30 ( 5o%F) 2.29 2.39 25 L<50%F) 2.46 2.56 100 1.41 1.40 65 1.59 1.58 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 TBVOOS 30 2.08 2.14 30 (> 50%F) 2.85 2.90 25 (> soF) 3.18 3.22 30( 5oF) 2.54 2.64 25 IS50%F) 2.88 2.96 100 1.41 1.40 65 1.59 1.58 60 1.73 1.73 PLOS 50 RPLUOS 50 1.79 1.79 RTBOOS 30 2.08 2.14 TBVO05 30 (> 50%F) 2.85 2.90 25 (> 50%F) 3.18 3.22 30 (t 50%sF3 2.54 2.64 25 (5 so%F) 2.88 2.96 EOOS Power A0 G1 Option NRlated)

A1 GEl4 100 1.38 1.37 65 1.56 1.'9 60 1.73 1.I3 50_

PLUOOS 50 1.79 1.i9 FUOOS 30 2.16 2.22 30 (> 50%F) 2.45 2.';2 25 (> S0%F) 2.65 2.69 30 ( S0%F) 2.36 2.48 25 (-f 50%F) 2.56 2.67 100 1.38 1.37 65 1.56 1.59 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 RPTOOS 30 2.16 2.22 MOOS 30 (> 50%F) 2.45 2.52 25 (> 5o%F) 2.65 2.69 30 (<S 0%F) 2.36 2.48 25 (.< 50%F) 2.56 2.'57 100 1.41 1.41 65 1.60 1.151 60 1.73 1.73 50 PLUOOS 50 1.79 1.79 TBVOOS 30 2.17 2.23 FHOO0S 30 (> 50%F) 2.93

2. ?9 25 (> 50%F) 3.27 3.31 30 ( 50%F) 2.61 2.71 25 (S5o%F) 2.97 3.05 100 1.41 1.41 65 1.60 1.61 60 1.73 1.73 PLUOOS 50 RPTOOS 50 1.79 1.79 TBVOOS 30 2.17 2.23 FHOOS 30 (> 50%F) 2.93 2.99 25 (> 50%F) 3.27 3.31 30 ( 5o%F) 2.61 2.71 25 (S5o%F) 2.97 3.D5

)

Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limits R t

TVA-COLR-BF3C 13 Revision 0, Page 24 Table 4: MCPRp Limits for BOC to EOC Exposures - TSSS Scram Times

)

(Applicable up to Core Average Exposure of 33,663 MWd / MITU)

MCPRp Limit MCPRp LiMit I

tion Power A10 GEI4 100 1.38 1.37 65 1.57 1.56 60 1.58 1.61 50 1.69 1.73 I

Service 50 1.80 1.80 30 2.08 2.13 30 (> 5o%F) 2.36 2.42 25 (> 5o%F) 2.53 2.57 30 (s 5o%F) 2.29 2.39 25 <50o%F) 2.46 2.56 100 1.38 1.38 65 1.57 1.56 60 1.58 1.61 50 1.69 1.73 RPOS 50 1.80 1.80 FPTOOS 30 2.08 2.13 30 (> 5o%F) 2.36 2.42 25 (> 5o%F) 2.53 2.57 30 50%F) 2.29 2.39 25 (S5o%F) 2.46 2.56 100 1.42 1.41 65 1.61 1.59 60 1.63 1.64 50 1.72 1.75 TNOS 50 1.80 1.80 TBXOOS 30 2.10 2.16 30 (> 5o%F) 2.85 2.90 25 (> 5o%F) 3.18 3.22 30 LE so%F) 2.54 2.64 25 L< 5o%F) 2.88 2.96 100 1.42 1.42 65 1.61 1.59 60 1.63 1.64 50 1.72 1.75 RPTOOS 50 1.80 1.80 TBVOOS 30 2.10 2.16 30 (> 5o%F) 2.85 2.90 25 (> 5o%F) 3.18 3.22 30 (s 5o%F) 2.54 2.64 25 L< 5o%)

2.88 2.96 EOOS Power A10 GE14 Option

(% Rued) 100 1.39 1.39 65 1.58 1.61t 60 1.62 1.66 50 1.75 1.79 FOS50 1.80 1.81 FHOOS 30 2.18 2.24 30 (> 5o%F) 2.45 2.52 25 (> so%F) 2.65 2.69) 30< 5o%F) 2.36 2.4:3 25 (55o%F) 2.56 2.67 100 1.39 1.3 P 65 1.58 1.61 60 1.62 1.66 50 1.75 1.79 RPTOOS 50 1.80 1.80 FHIOOS 30 2.18 2.24 30 (> 50%F) 2.45 2.52 25 (> So%F) 2.65 2.69 30 (So%F) 2.36 2.48 25 ( soF) 2.56 2.67 100 1.43 1.42 65 1.62 1.63 60 1.66 1.69 50 1.77 TBVOOS 50 1.80 1.81 FHOOS 30 2.20 2.25 30 (> so%F) 2.93 2.99 25 (> so%F) 3.27 3.31 30 (s0%F) 2.61 2.71 25 (0so%F) 2.97 3.C05 100 1.43 1.43 65 1.62 1.63 60 1.66 1.69 RPTOS 50 1.77 RTBOOS 50 1.80 I.E.1 FBVOOS 30 2.20 2.25 30 (> so%F) 2.93 2.5,9 25 (> 50%F) 3.27

3. I 30 (sS0%F 2.61 2.;1 25 ( so%F) 2.97 3.G5 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limlts R.

i TVA-COLR-BF3C 13 Revision 0, Page 25 Table 4 (Continued): MICPRp Limits for BOC to EOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 33,663 NINVd / MTU)

MCPRp Limit I MCPRp Limit N)

EOOS Power AlO GE14 Option

(% Rated)

AO E4 100 1.39 1.38 65 1.57 1.56 60 1.74 1.74 50 PLOS 50 1.80 1.80 PLUOOS 30 2.08 2.13 30 (> 5ooF) 2.36 2.42 25 (> SoF) 2.53 2.57 30 o

5°oF) 2.29 2.39 25 L 50%F) 2.46 2.56 100 1.39 1.39 65 1.57 1.56 60 1.74 1.74 50 PLUOOS 50 1.80 1.80 RPTOOS 30 2.08 2.13 30 (> 50VoF) 2.36 2.42 25 (> 50%F) 2.53 2.57 30> 50%F) 2.29 2.39 25 50%F) 2.46 2.56 100 1.42 1.41 65 1.61 1.59 60 1.74 1.74 50 PLUOOS 50 1.80 1.80 TBVOOS 30 2.10 2.16 30 (> 5o%F) 2.85 2.90 25 (> 50%F) 3.18 3.22 30 L< 5o%F) 2.54 2.64 25 (L5o%F) 2.88 2.96 100 1.42 1.42 65 1.61 1.59 60 1.74 1.74 PLUOS 50 RPLUOS 50 1.80 1.80 TBVOOS 30 2.10 2.16 30 (> 5o%F) 2.85 2.90 25 (> 50%F) 3.18 3.22 30( 550%F) 2.54 2.64 25 ( So%F) 2.88 2.96 EOOS Power AI GE Option

(% Rated)

A10 GEI4 100 1.39 1.39) 65 1.58 1.61 60 1.74 1.7-4 50 PLUOOS 50 1.80 1.83 FHOOS 30 2.18 2.24 30 (> 50%F) 2.45 2.52 25 (> 50%F) 2.65 2.69 30 (5o%F) 2.36 2.48 25 (< 5o%F) 2.56 2.67 100 1.39 1.39 65 1.58 1.61 60 1.74 1.4 PLOS 50 RPLUOS 50 1.80 1.80 RPTOOS 30 2.18 2.24 FOS 30 (> so%F) 2.45 2.52 25 (>5o%F) 2.65 2.E9 30 L<5o%F) 2.36 2.48 25 L so%F) 2.56 2.(7 100 1.43 1.42 65 1.62 1.63 60 1.74 1.74 50 PLUOOS 50 1.80 1.81I TBVOOS 30 2.20 2.2.5 FHOOS 30 (>5o%F) 2.93 2.99 25 (> so%)

3.27 3.3 1 30 5so%F) 2.61 2.1 1 25 (S0%F) 2.97 3.05 100 1.43 1.43 65 1.62 1.63 60 1.74 1.74 PLUOOS 50 RPTOOS 50 1.80 1.31 TBVOOS 30 2.20 2.25 FHOOS 30 (> so%F) 2.93 2.99 25 (> 50%F 3.27 3.31 30 (5o%F 2.61 2.71 25 5o%F) 2.97 3.05 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferrt' Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limits R

.t TVA-COLR-BF3C13 Revision 0, Page 26 I

Table 5: MCPRp Limits for BOC to CD Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 34,731 MWd / MTU)

All Values Include FFTR/FJOOS and Bound Heaters In-Sen'ice l

MICPRp Limit l I MCPRp Limit EOOS Power Option

( Rated)

AID GE14 100 1.38 1.37 65 1.56 1.59 60 1.61 1.64 50 1.74 1.77 ISe ce 50 1.79 1.79

[n-Service 30 2.16 2.22 30 (> 5oF) 2.45 2.52 25 (> 50soF) 2.65 2.69 30d 5osoF) 2.36 2.48 25 (5o/oF) 2.56 2.67 100 1.38 1.37 65 1.56 1.59 60 1.61 1.64 50 1.74 1.77 RP0S 50 1.79 1.79 RPTOOS 30 2.16 2.22 30 (> So0°%F) 2.45 2.52 25 (> 5oF) 2.65 2.69 30 (_so 50F) 2.36 2.48 25 < 50oF) 2.56 2.67 100 1.42 1.41 65 1.60 1.61 60 1.64 1.66 50 1.76 TB00 s

1.79 1.79 TBVOOS 30 2.17 2.23 30 (> SooF) 2.93 2.99 25 (> 50%F) 3.27 3.31 30 (5 oF) 2.61 2.71 25 (o50%F) 2.97 3.05 100 1.42 1.42 65 1.60 1.61 60 1.64 1.66 50 1.76 RPTOOS 50 1.79 1.79 TBVOOS 30 2.17 2.23 30 (> 50%F) 2.93 2.99 25 (> 50%F) 3.27 3.31 30 (50%F) 2.61 2.71 25 (S50%F) 2.97 3.05 EOOS Power A1 GE4 Option

( Rated)

Al GE.14 100 1.38 1.37 65 1.56 1.59 60 1.73 1.73 50 PLOS 50 1.79 1.79 PLUOOS 30 2.16 2.22 30 (> 50%F) 2.45 2.52 25 (> 50%F) 2.65 2.69 30( 50%F) 2.36 2.48 25 ( 50%F) 2.56

2. 7 100 1.38 1.38 65 1.56 1.'9 60 1.73 1.1 3 50 PLUOOS 50 1.79 1.79 RPTOOS 30 2.16 2., 2 30 (> 50%F) 2.45 2.';2 25 (> 50%F) 2.65 2.69 30 (E 50%F) 2.36

2..8 25 Cs 50%F).

2.56 2.67 100 1.42 1.'~ 1 65 1.60 1.61 60 1.73 1.73 50 PLUOOS S0 1.79

1..'9 TBVOOS 30 2.17 2.!23 30 (> 50%F 2.93 2.99 25 (> 50%F) 3.27 3.3 1 30 ( 50%F) 2.61 2.21 25 (E 50%F) 2.97 3.05 100 1.42 1.42 65 1.60 1.61 60 1.73 1.73 50UOS 5

RPLUOS 50 1.79 1.179 RPTOOS

30.

2.17 2.23 BVO 30 (> 50%F) 2.93 2.99 25 (>50%F) 3.27 3.:1 30 50%F 2.61

2. '1 25 (50%F) 2.97 3.05 Aid 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

• TVA Nuclear Fuel Core Operating Limits Re, TVA-COLR-E;F3C13 Revision 0, Page 27

)

Table 6: MCPRp Limits for BOC to CD Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 34,731 MWd / MTU)

All Values Include FFTRJFHOOS and Bound Heaters In-Sernice l MCPRp Lunit I MCPRp Limit

)

EOOS Power A10 GE14 Option

(%Rated)

A 100 1.39 1.39 65 1.58 1.61 60 1.62 1.66 50 1.75 1.79 In-Service 50 1.80 1.80 30 2.18 2.24 30 (>5o%F) 2.45 2.52 25 (>5o%F) 2.65 2.69 30(

5o%F) 2.36 2.48 25 (L5o%F) 2.56 2.67 100 1.39 1.39 65 1.58 1.61 60 1.62 1.66 50 1.75 1.79 RPOS 50 1.80 1.80 FPTOOS 30 2.18 2.24 30 (> so%F) 2.45 2.52 25 (> so%F) 2.65 2.69 30(

50%Fl 2.36 2.48 25 (50%F) 2.56 2.67 100 1.43 1.43 65 1.62 1.63 60 1.66 1.69 50 1.77 TBOS 50 1.80 1.81 TBVOOS 30 2.20 2.25 30 (> 50%F) 2.93 2.99 25 (> 5o%F) 3.27 3.31 30 (50%F) 2.61 2.71 25 (5soF) 2.97 3.05 100 1.43 1.44 65 1.62 1.63 60 1.66 1.69 50 1.77 RPTOOS 50 1.80 1.81 TBVOOS 30 2.20 2.25 30 (> 5oF) 2.93 2.99 25 (>s0oF) 3.27 3.31 30 (550oF) 2.61 2.71 25 (550%F) 2.97 3.05 EOOS Power A10 GEM Option (N RPAed) 100 1.39 1.39 65 1.58 1.61 60 1.75 1.75 50 PLUOOS 50 1.80 1.80 30 2.18 2.24 30 (>5o%F) 2.45 2.52 25 (> 5o%F) 2.65 2.69 30 (so%F) 2.36 2.4 25 (5o5%F) 2.56 2.61 100 1.39 1.39 65 1.58 1.6-.

60 1.75 1.75}

50 PLUOOS 50 1.80 1.81)

RPTOOS 30 2.18 2.24 30 (> 50%r) 2.45 2.52 25 (> 50%F) 2.65 2.69 30 L5o%r) 2.36 2.43 25 (s50%F) 2.56 2.67 100 1.43 1.43 65 1.62 1.63 60 1.75 1.75 50 PLUOOS 50 1.80 1.81 TBVOOS 30 2.20 2.25 30 (>5o%F) 2.93 2.9 25 (> 50%F) 3.27 3.31 30 Ls 5o%F 2.61 2.71 25 (55o%F 2.97 3.05 100 1.43 1.44 65 1.62 1.63 60 1.75 1.'5 PL0OS 5

RPLUOS 50 1.80 1.8 I RPTOOS 30 2.20 2.25 TBVOOS 30 (> 5o%F) 2.93 2.99 25 (> 50%F 3.27 3.:1 30 ( 5oF) 2.61 2.11 25 (50%F) 2.97 3.05 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 3 Cycle 13.

EVA Nuclear Fuel Cre Operating Limits F t

TVA-COLR.-BF3Cl3 Revision 0, Page 28 Figure 1: APLHGR Limits for Bundle Type GE14-PIODNAB402-1SGZ (GE1 4) 1)'

14.00 13.00 12.00 11.00 10.00 a lrim

-Z

-- ~

1 8.00 E:n 7.00 cc X

6.00

-J 0.

U).wv 4.00 3.00 2.00 I

1.00 0.00 I 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (GWD/MTU)

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure L.imit (GWD/MTU)

(kwlft)

(GWD/MTU)

(kw/tt)

(GWD/MTU)

(Ow/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 1104 38.58 9.66 3.31 9.99 13.23 11.05 44.09 9.13 4.41

.18 14.33 11.04 49.60 13;59_

5.51 10.38 15.43 11.04 55.12 13.03 661

- 10.58 16.53 11.04 60.63 li.36 7.72 10.72 18.74 11.02 63.75 4.92 These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2. These rated power limits are applicable for all other EOOS options.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TI/A Nuclear Fuel Core Operating Limits R t

TVA-COLR-BF3CI3 Revision 0, Page 29 Figure 2: APLIGR Limnits for Bundle Type GE14-PIODNAB401-14GZ

)

(GE14)

E

-J 0.

I 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (GWDIMTU)

Most Umiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LlIGR Exposure Limit Exposure Limit Exposure Limit (GWD/MTU)

(kw/tt)

(GWD/MTU)

(kw/ft)

(GWD/MTU)

(kwlft) 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 10.1 1.309644.09.

9.1 1 4.41 10.18 14.33 10.96 49.60 13.57 5.51 10.37 15.43 10.98 55.12

.03 6.61 10.50 16.53 10.99 60.63

.30 7.72 10.58 18.74 10.99 63.63

.93

)

These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2. These rated power limits are applicable for all other EOOS options.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limits R..

TVA-COLR-BF3CI3 Revision 0, Page 30 Figure 3: APLHGR Limits for all ATRIUM-10 except AIO-1623B-SGV80 (AM0) 14.00 E

-C 0.00 4-_

0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (GWD/MTU)

Average Planar LHGR Exposure Limit (GWDIMTU)

(kwltt) 0.00 12.50 67.00 7.30 These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are pzrtormed as described in Section 2. These rated power limits are applicable for all other EOOS options.

Browns Ferry Nuclear Plant Unit 3 Cycle 13

T\\'A Nuclear Fuel Core Operating Limits R._

TVA-COLR-13F3C1 3 Revision 0, Page 31 Figure 4: APLHGR Limits for A10-1623B-5GV80 (A10) 14.00 E

-Js.

)

0.00 '

0.00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (GWDIMTU)

Average Planar LHGR Exposure Limit (GWDIMTU)

(kw/tt) 0.00 11.50 15.00 11.50 67.00 6.30 These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2. These rated power limits are applicable for all other EOOS options.

Browns Ferri Nuclear Plant Unit 3 Cycle 13

FVA Nuclear Fuel Core Operating Limits R TVA-COLR-BF3CI 3 Revision 0, Page 32 Figure 5: GE14 Power Dependent MAPLHGR Multiplier - MAPFAC(P)

NSS/TSSS Insertion Times - All Exposures

)3 Eg 0.7 a,

X 0.6

)

25 30 35 40 45 50 55 60 65 70 75 80 85 90 9,3 100 Power (% PAWd)

Turbine Bypass In-Service Turbine Bypass Out-Of-Service Core Power MAPFAC(P) 100 I

_ 30 0.57 Core Flow > 50% rated 30 1

0.45 25 1

0.42 Core Flow c 50% rated 30 0.51 25 0.49 Core Power MAPFAC(P)

___100 I

30 F 0.57 Core Flow > 50%h rated 30 1

0.40 25 1

0.37 Core Flow_

< 501 rated 30~

1 0.43 25 1

0.41-Browns Ferry Nuclear Plant Unit 3 Cycle 13

TV/A Nuzlear Fuel Core Operating Limits R.

TVA-COLR-BF3C13 Revision 0, Page 33 Figure 6: GE14 Flow Dependent MAPLBGR Factor - NIAPFAC(F)

(GE14)

)

1.00 0.90

..- 0.80 C.)

IL 4

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

)

Max Core Flow 102.5% Rated Core Flow MAPFAC(F)

(% rated) 30 0.57 77 1.00 102.5 1.00 Max Core Flow 107% Rated Core Flow MAPFAC(F)

(% rated) 30 0.55 81 1.00 107 1.00 These values bound all Equipment In-Service and Out-Of-Service options.

The 102.5% maximum flow line is used for operation up to 100% rated flow.

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

.)

Browns Ferry Nuclear Plant Unit 3 Cycle 13

T1A Nuclear Fuel Core Operating Limits R I

• TVA-COLR**BF3C13 Revision 0, Page 34 Figure 7: LHGR Limits for all GE14 (GE14)

I4 14.00 13.00 12.00 11.00 10.00 -

9.00 8.00 E

7.00 o

6.00 5.00 4.00 3.00 2.00 1.00 NACCEPTABLE OPERATION)

\\UACCEPTABLE OPERATION I)

V.

0.00 10.00 20.00 30.00 40.00 Pellet Exposure (GWDIMTUI) 50.00 60.00 70.00 Pellet LHGR Exposure Limit (GWDIMTU)

(kw/tt) 0.00 13.40 16.00 13.40 63.50 8.00 70.00 5.00 These rated power limits bound all Equipment In-Service and Out-Of-Service options;.

I Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limits Ro

.l TVA-C0LR-BF3C13 Revision 0, Page 35 Figure 8: LHGR Limits for all ATRIUM-10

)

(A10) 14.00 13.00 12.00 11.00 10.00

-4 E

-J 9.00 8.00 7.00 6.00 5.00 4.00 3.00 2.00

)

1.00" 0.00 10.00 20.00 30.00 40.00 50.00 60.00

70. DO Pellet Exposure (GWDIMTU)

Pellet LHGR Exposure Limit (GWD/MTU)

(kwhlt) 0.00 13.40 18.90 13.40 7... 0 7.....10....

_.__.10 These rated power limits bound all Equipment In-Service and Out-Of-Service options.

Browns Ferry ANuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limnits R I

TVA-COLR-BF3C13 Revision 0, Page 36 1)

Figure 9: ATRIUM-10 Power Dependent LHGR Multiplier - LHGRFAC(P)

NSS/TSSS Insertion Times - All Exposures (A10) 1.10 1.00 0.90 0.80 El

. 0.70 a.

Turbine Bypass Out-OU-Service (TSVOOS)

TBVIS: 5 50% Core Fow TBVIS: s WIY. Core TBVOOS: S 0% Core 0.50 jz 7A TSVOOS:

50@.% Core Flow C.40 4

)

C.30 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Turbine Bypass In-Service Turbine Bypass Out-Of-Service Core Power LHGRFAC(P) 1 oo 1.00 30 o

0.71 Core Flow > 50% rated 30 l

0.60 25 1

0.55 Core Flow < 50% rated 30 0.65 25 0.62 i

M rated) 1 00 0.98 30 F 0.69 Core Flow > 50% rated 30 1

0.50 25 1

0.45 Core Flow < 50YO rated 30 1

0.60 25 1

0.53 LHGRFAC(P) is not dependent upon any Equipment Out-Of-Service except Turbine Bypass.

Browns Ferry Auclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Core Operating Limits R t

TVA-COLR-BF3Cl 3 Revision 0, Page 37

)1 Figure 10: ATRIUM-10 Flow Dependent LHGR Multiplier - LIIGRFAC(F, (A1l )

1.00 MAX FLOW = 102.5%

0.95 L.0MAX FLOW-107%

C,: 0.90-

/

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

)

Max Core Flow 102.5% Rated Core Flow LHGRFAC{F)

(% rated)

LGFCF 30 0.84 55 1.00 102.5 1.00 Max Core Flow 107% Rated Core Flow LHGRFAC(F)

(% rated) 30 0.82 60 1.00 107 1.00 These values bound all Equipment In-Service and Out-Of-Service options.

The 102.5% maximum flow line is used for operation up to 100% rated flow.

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

)

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TVA Nuclear Fuel Co: e Operating Limits Rep TVA-COLR-EIF3C I3 Revision 0, Page 38 Figure 11: GE14 Flow Dependent MCPR Limit - MCPR(F)

(GE1 4) 1.68 1.63 1.58 1.53 1.48 ix 1.43 C) 2 1.38 1.33 1.28 1.23 1.18 30 40 50 60 70 80 90 100 Core Flow (% Rated)

Max Core Flow 102.5% Rated Core Flow MCRF

(% rated)

MCPR(F) 30 1.63 88 1.21 102.5 1.21 Max Core Flow 107% Rated Core Flow MCPR(F)

(% rated) 30 1.65 92 1.21 107 1.21 These values bound all Equipment In-Service and Out-Of-Service options.

The 102.5% maximum flow line is used for operation up to 100% rated flow.

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

Browns Ferry Nuclear Plant Unit 3 Cycle 13

TV'A Nuclear Fuel Core Operating Limits Re, TVA-COLR-BF3C13 Revision 0, Page 39 (Final)

Figure 12: ATRIUM-10 Flow Dependent MCPR Limit - MCPR(F)

(AlO)

)

1.73 1.68 1.63 1.58 1.53 C. 1.48 a-o 1.43 1.38 1.33 1.28 1.23 1.18 30

)

40 50 60 70 80 90 100 Core Flow (% Rated)

Max Core Flow 102.5% Rated Core Flow MCPR(F)

(% rated) 30 1.64 88 1.21 102.5 1.21 Max Core Flow 107% Rated Core Flow MCPR(F)

(% rated) 30 1.70 92 1.21 107 1.21 These values bound all Equipment In-Service and Out-Of-Service options.

The 102.5% maximum flow line is used for operation up to 100% rated flow.

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

Browns Ferry Nuclear Plant Unit 3 Cycle 13