ML071300370

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Unit 2 - Core Operating Limits Report (COLR) for Cycle 15 Operation
ML071300370
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 05/02/2007
From: Crouch W
Tennessee Valley Authority
To:
Document Control Desk, NRC/NRR/ADRO
References
Download: ML071300370 (42)
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Tennessee Valley Authority, Post Office Box 2000, Decatur, AJabama 35609-2000 May 2, 2007 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, Pl-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of )) Docket No. 50-260 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 15 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is the Unit 2 Cycle 15, 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, 4JAýý William D. Crouch Manager of Licensing and Industry Affairs Enclosure cc: See page 2 Am'

U.S. Nuclear Regulatory Commission Page 2 May 2, 2007 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. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739

.j ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 2 CORE OPERATING LIMITS REPORT (COLR),

FOR CYCLE 15 OPERATION (SEE ATTACHED)

TVA Nuclear Fuel QA Document TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 1 Browns Ferry Nuclear Plant.

Unit 2 Cycle 15 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Date: Z- (9-*7 Earl E. Riley, Sf..Engineering Specialist BWRFuel Engineering Verified y: Date: /IA Brye C. Mitchell, Nuclear Engineer BWR Fuel Engineering Approved By: Date: aff0 Greg C. Store, Manager BWR Fuel tEngineering Reviewed By: Date:. A o. 7 jot., J. M.(keck, Supervisor.

-' Browns Ferry Reactor Engineering Approved By: Date: - 7

. PoRC Chairm -

Pages Affected: All Revision 00 (2/21/2007) . Pages Affected: All

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 2 Revision Log Revision Date Description Affected Pages 0 2/21/2007 Initial Release for New Cycle All Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report (COLR) for Browns Ferry Nuclear Plant Unit 2 Cycle 15 is prepared in accordance with the requirements of Browns Ferry Technical Specification 5.6.5. This revision of the COLR supports operation at the current licensed thermal power (CLTP) of 3458 MWt which is 105% of original licensed thermal power (OLTP).

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 GEXL14 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 Safety Limit (SLMCPR) for this cycle.

Results from the reload analyses for Browns Ferry Nuclear Plant Unit 2 Cycle 15 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 Setting (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 2 Cycle 15 core is composed of AREVA-NP ATRIUMTM-10 and Global Nuclear Fuel GE- 14TM assemblies. Throughout this document these are referred to as A 10 and GE 14 with the trademark implied.

Browns FerryNuclear PlantUnit 2 Cycle 15

'I TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 4

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 off-rated power APLHGR limit [APLHGRRATED

  • MAPFAC(P)]

APLHGRF off-rated flow APLHGR limit [APLHGRRATED

  • MAPFAC(F)]

APLHGRSLO SLO APLHGR limit [ALPHGR RATED

  • SLOMultiplier]

The off-rated power and flow corrections to the APLHGR limit only apply to the GE14 fuel in the Browns Ferry Unit 2 Cycle 15 core. For that reason, this multiplier is set to 1.0 as shown below for the A10 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 1-5. 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.

Bundle Type Rated Power APLHGR Limit GE14-P1ODNAB416-16GZ (EDB2600) Figure 1 GE 14-P 1ODNAB416-16GZ (EDB2601) Figure 2 GE 14-P 1ODNAB416-18GZ (EDB2627) Figure 3 GE 14-P 1ODNAB417-18GZ (EDB2628) Figure 4 AIO-3920B-14GV70 Figure 5 A1O-4227B-15GV80-FBB Figure 5 A10-4239B-15GV80-FBB Figure 5 A10-3552B-10GV80-FBB Figure 5 Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 5 Off-Rated Power Corrections: APLHGRP The APLHGR limits for the GE14 fuel lattices are adjusted for off-rated power conditions using the ARTS multiplier, MAPFAC(P). The reduced power multiplier, MAPFAC(P), for the GE14 fuel is provided in Reference 1. No off-rated power correction is required for the A10 rated APLHGR limits.

Product Line MAPFAC(P)

GE14 Figure 6 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). The reduced flow multiplier, MAPFAC(F) is provided in Reference 1. No off-rated flow correction is required for the A10 rated APLHGR limits.

Product Line MAPFAC(F)

GEl4 Figure 7 A10 1.0 SLO Corrections: APLHGRSLO Single Recirculation Loop Operation (SLO) requires that the rated power APLHGR limit (APLHGRrated) be reduced by applying the following multipliers. The GE14 multiplier is provided in Reference 5. The A 10 multiplier is provided in Reference 1.

Product Line SLO Multiplier GEl4 0.90

  • A10 0.85
  • The GE14 SLO multiplier of 0.90 is the more limiting of CLTP and EPU values provided in Reference 5. This value bounds operation at CLTP.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 6 Equipment Out-Of-Service (EOOS) Corrections:

The rated APLHGR limits in Figures 1-5 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.

hI-Service All equipment In-Service (includes 1 SRVOOS)

RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFTR) 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 6 is dependent upon the operating status of the Turbine Bypass Valve (TBV) system. For this reason, separate limits are supplied in these figures to be applied for TBVIS (in service) or TBVOOS (out of service) operation. The MAPFAC(P) limits have no dependency on RPTOOS, SLO, FHOOS/FFTR, or PLUOOS.

The off-rated flow corrections [MAPFAC(F)] in Figure 7 bound both equipment In-Service or EOOS operation.

Browns Ferry Nuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C15 Core Operating Limits Report Revision 0, Page 7

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 off-rated power LHGR limit [LHGRRATED

  • LHGRFAC(P)]

LHGRF off-rated flow LHGR limit [LHGRRATED

  • LHGRFAC(F)]

The off-rated power and flow corrections to the LHGR limit only apply to the A10 fuel in the Browns Ferry Unit 2 Cycle 15 core. For that reason, these multipliers 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 Figure 8 A10 Figure 9 The A10 LHGR limit is provided in References 1 and 6. The GE14 LHGR limit is provided in References 1 and 7.

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 GEl4 rated LHGR limits.

Product Line LHGRFAC(P)

GE14 1.0 A10 Figure 10 Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C15 Core Operating Limits Report Revision 0, Page 8 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.

Product Line LHGRFAC(F)

GE14 1.0 A10 Figure ll 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 All equipment In-Service (includes 1 SRVOOS)

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

The off-rated power corrections [LHGRFAC(P)] in Figure 10 are dependent upon operation of the Turbine Bypass Valve system. For this reason, separate limits are supplied in this figure to be applied for TBVIS or TBVOOS operation. The LHGRFAC(P) limits have no dependency on RPTOOS, PLUOOS, SLO, or FHOOS/FFTR.

The off-rated flow corrections [LHGRFAC(F)] in Figure 11 bound both equipment In-Service or EOOS operation.

Browns Ferry Nuclear Plant Unit2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 9

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

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 in Figure 12. MCPRp limits are provided in Tables 1 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)

" FuelType (GE14 orA10)

The MCPRF limits are provided in Figure 12. For Unit 2 Cycle 15 the same MCPRF limits apply to both the GE14 and A1O fuel types. 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-Dependent MCPR Limits: MCPRp The MCPRp limits are dependent upon:

  • Core Power Level (% of Rated)
  • Technical Specification Scram Speed (TSSS) or Nominal Scram Speed (NSS)
  • FuelType (GEl4 orAl0)
  • 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 between the specified powers.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 10 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 times 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 table are met (Ref. 9).

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 rods 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 GE 14 and A10 fuel types.

Browns FerryNuclear Plant Unit 2 Cycle 15

0 TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 11

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 NEOC corresponds to 27,788 MWd / MTU BOC to EOC EOC corresponds to 31,075 MWd / MTU BOC to CD CD corresponds to 32,274 MWd / MTU 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:

In-Service All equipment In-Service (includes 1 SRVOOS)

RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service RPTOOS+TBVOOS Combined RPTOOS and TBVOOS PLUOOS Power Load Unbalance Out-Of-Service PLUOOS+RPTOOS Combined PLUOOS and RPTOOS PLUOOS+TBVOOS Combined PLUOOS and TBVOOS PLUOOS+TBVOOS+RPTOOS Combined PLUOOS, RPTOOS, and TBVOOS FHOOS (or FFTR) 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).

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 12

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.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 13

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. 10):

SRB - (0.66(W-AW) + 61%) Allowable Value SRB _ (0.66(W-AW) + 59%) Nominal Trip Setpoint (NTSP) where:

SRB = Rod Block setting in percent of rated thermal power (3458 MWt)

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

The APRM Rod Block trip setting is clamped at a maximum allowable value of 115%

(corresponding to a NTSP of 113%).

Browns Ferry Nuclear PlantUnit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 14

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. 10 & 11):

RBM Trip Setpoint Allowable Value Nominal Trip Setpoint (AV) (NTSP)

LPSP 27% 25%

IPSP 62% 60%

HPSP 82% 80%

LTSP - unfiltered 124.7% 123.0%

- filtered 123.5% 121.8% (1),(2)

ITSP - unfiltered 119.7% 118.0% (1),(2)

- filtered 118.7% 117.0%

HTSP - unfiltered 114.7% 113.0% (1),(2)

- filtered 113.7% 112.0%

DTSP 90% 92%

Notes: (1) These setpoints are based upon an Analytical Limit HTSP of 117% (w/o filter) which corresponds to a MCPR operating limit of 1.42(A1O/GE14), as reported in section 5.5 of Reference 1. Unit 2 Cycle 15 has had a cycle specific CRWE analysis performed and the table provided in section 5.5 of Reference 1 supercedes the OLMCPR values of references 10 and 12.

(2) The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds (reference 10.b)). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference I0.a)).

The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:

THERMAL POWER Applicable Notes from

(% Rated) MCPR (1 Table 3.3.2.1-1

> 27% and < 90% < 1.72 (a), (b), (f), (h) dual loop operation

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

> 90% < 1.47 (g) dual loop operation (2)

Notes: (1) The MCPR values shown correspond to a SLMCPR of 1.08 for dual recirculation loop operation and 1.10 for single loop operation. (Ref. 1).

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

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C15 Core Operating Limits Report Revision 0, Page 15

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. 8).

SDM > 0.38% dk/k Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 16

8. REFERENCES
1. ANP-2592 Rev. 0, "Browns Ferry Unit 2 Cycle 15 Reload Analysis for 105% Original Licensed Thermal Power", dated January 2007.
2. Framatome-ANP Analytical Methodology

References:

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

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), RODEX2A (BWR) Fuel Rod Thermal-MechanicalEvaluation 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 1 and Supplements 1 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 ENC Methodology to B WR 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/MJCROBURN-B2, Siemens 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 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

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 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Programfor Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

1) ANF-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 Correlationsto Co-Resident Fuel, Siemens Power Corporation, August 2000.

o) EMF-2361 (P)(A) Revision 0, EXEM B WR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.

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

3. Global Nuclear Fuel Analytical Methodology

References:

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 17 a) NEDE-24011-P-A-15, "General Electric Standard Application for Reactor Fuel",

September 2005.

b) NEDE-24011-P-A-15-US, "General Electric Standard Application for Reactor Fuel (Supplement for United States)", September 2005.

4. 0000-0006-1355-MAPL Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Unit 2 Reload 12 Cycle 13", February 2003.
5. NEDC-32484P Rev. 6, "Browns Ferry Nuclear Plant Units 1, 2, and 3 - SAFER/GESTR-LOCA Loss-Of-Coolant Accident Analysis", dated February 2005.
6. ANP-2537P Rev. 0, "Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-15 ATRIUMT M-10 Fuel Assemblies", dated May 2006.
7. GE-NE-L12-00889-00-O0P Rev. 0, "GE14 Fuel Design Cycle-Independent Analyses for Browns Ferry Units 2 and 3", dated January 2002.
8. TVA-COLR-BF2C14 Rev. 1, "Browns Ferry Nuclear Plant Unit 2, Cycle 14 Core Operating Limits Report (COLR)", dated April 10, 2006.
9. EMF-3238(P) Rev. 0, "Browns Ferry Unit 2 Cycle 15 Plant Parameters Document", dated January 2006.
10. PRNM Setpoint Calculation:

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

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

11. GE Letter LB#: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.
12. NEDC-32433P, "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.

Browns Ferry NuclearPlant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 18 Table 1: MCPRp Limits for BOC to NEOC Exposures - NSS Scram Times (Applicable up to Core Avera e Exposure of 27,788 MWd / MTU)

MCPRp Limit MCPRp Limit EOOS Power EOOS Power Option (%Rated) Option (% Rated) 100 1.45 1.46 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.61 1.64 63 1.66 1.70 58 1.69 1.73 58 1.75 ---

58 1.78 1.78 58 1.78 1.79 46 1.85 1.89 FHOOS 46 1.90 1.97 Service 30 2.22 2.35 30 2.33 2.49 30 (> 50%F) 2.64 2.79 30 (> 5o/oF) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 500/F) 3.03 3.24 30 (550%F) 2.51 2.68 30 (55o%F) 2.60 2.79 25 (_ 5 0%F) 2.68 2.89 25 (. 5oo/oF) 2.81 3.03 100 1.45 1.46 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.61 1.64 63 1.66 1.70 58 1.69 1.73 58 1.75 ---

58 1.78 1.78 58 1.78 1.79 MOOS 46 1.90 1.97 RPTOOS 46 1.85 1.89 30 2.33 2.49 30 2.22 2.35 30 (> 5o%F) 2.64 2.79 30 (> 5oo/J) 2.75 2.92 25 (> 5o%F) 2.89 3.08 25 (> 50%F) 3.03 3.24 30 (_50%F) 2.51 2.68 30 (5oo/.F) 2.60 2.79 25 (550%F) 2.68 2.89 25 (55oo/F) 2.81 3.03 100 1.49 1.50 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.65 1.67 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.78 1.78 58 1.78 1.81 TBVOOS 46 1.85 1.90 TBOOS 46 1.92 1.98 30 2.35 2.49 30 2.23 2.36 30 (> 5o%F) 3.09 3.20 30 (> 5oo/F) 3.19 3.31 25 (> 50%F) 3.51 3.64 25 (> 500/ 0F) 3.62 3.78 30 (- 5o%F) 2.64 2.79 30 (< 5o0/.F) 2.72 2.88 25 (< 50%F) 2.97 3.18 25 (.<5oo/F) 3.07 3.30 100 1.49 1.50 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.65 1.67 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.78 1.78 RPTOOS 58 1.78 1.81 RTBOOS 46 1.85 1.90 TBVOOS 46 1.92 1.98 30 2.23 2.36 FMOOS 30 2.35 2.49 30 (> 5o%F) 3.09 3.20 30 (> 500F) 3.19 3.31 25 (> 5o%F) 3.51 3.64 25 (> 500o/F) 3.62 3.78 30 (_ 50%F) 2.64 2.79 30 (< 50%F) 2.72 2.88 25 (5 50%F) 2.97 3.18 25 (< 500/.F) 3.07 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 19 Table 1 (Continued): MCPRp Limits for BOC to NEOC Exposures - NSS Scram Times (Applicable up to Core Avera e Exposure of 27,788 MWd / MTU)

MCPRp Limit MCPRP Limit EOOS Power EOOS Power A10 GE14 Option (%Rated) Option (% Rated) 100 1.45 1.46 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.73 1.73 63 1.73 1.73 58 .. ... . 58 .. .. ..

58 1.78 1.78 58 1.78 1.79 PLUOOS 46 1.85 1.89 FHOOS 46 1.90 1.97 30 2.33 2.49 30 2.22 2.35 30 (>50%F) 2.64 2.79 30 (> 5o%/F) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 50%F) 3.03 3.24 30( 50%F) 2.51 2.68 30 (_ 50%F) 2.60 2.79 25 (_50%F) 2.68 2.89 25 (_5o%F) 2.81 3.03 100 1.45 1.46 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.73 1.73 63 1.73 1.73 58 ..... . 58 .... ..

58 1.78 1.78 RPTOOS 58 1.78 1.79 PTOOS 46 1.85 1.89 FHOOS 46 1.90 1.97 30 2.22 2.35 PLUOOS 30 2.33 2.49 30 (> 5o%F) 2.64 2.79 30 (> 5oo/j) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 50%F) 3.03 3.24 30 (<50%F) 2.51 2.68 30 (S 500/.F) 2.60 2.79 25 (550%F) 2.68 2.89 25 (_ 5o%F) 2.81 3.03 100 1.49 1.50 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.73 1.73 63 1.73 1.73 58 .... .. 58 .. .. ..

58 1.78 1.78 TBVOOS 58 1.78 1.81 TBVOOS 46 1.85 1.90 FHOOS 46 1.92 1.98 30 2.23 2.36 PLUOOS 30 2.35 2.49 30 (> 5o%F) 3.09 3.20 30 (> 5oF) 3.19 3.31 25 (> 5o%F) 3.51 3.64 25 (> 5001F) 3.62 3.78 30 (. 5o%F) 2.64 2.79 30 (. 500/F) 2.72 2.88 25 (< 50%F) 2.97 3.18 25 (S 5o%F) 3.07 3.30 100 1.49 1.50 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.73 1.73 63 1.73 1.73 58 .. ... . 58 5 ...- -

RPTOOS RPTOOS 58 1.78 1.78 PTBOOS 58 1.78 1.81 TBOOS 46 1.92 1.98 TBVOOS 46 1.85 1.90 FHOOS 30 2.35 2.49 PLUOOS 30 2.23 2.36 30 (> 5o0F) 3.19 3.31 30 (> 5o%F) 3.09 3.20 25 (> 50%F) 3.51 3.64 25 (> 5OF) 3.62 3.78 30 (S 50%F) 2.64 2.79 30 (S 5o0/0) 2.72 2.88 25 (5 5O%F) 2.97 3.18 25 (< 5oF) 3.07 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 20 Table 2: MCPRp Limits for BOC to NEOC Exposures - TSSS Scram Times (Applicable up to Core Avera e Exposure of 27,788 MWd / MTU)

MCPRp Limit MCPRp Limit EOOS Power EOOS Power A10 GE14 Option (% Rated) Option (% Rated) 100 1.47 1.49 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.63 1.66 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.79 1.79 58 1.79 1.81 In-Service 46 1.86 1.91 FHOOS 46 1.92 1.99 30 2.23 2.37 30 2.35 2.51 30 (> 5o%F) 2.64 2.79 30 (> 5oF) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 500/oF) 3.03 3.24 30 (S 50%F) 2.51 2.68 30 (:S 500%F) 2.60 2.79 25 (_ 50%F) 2.68 2.89 25 (s 5oo/,F) 2.81 3.03 100 1.47 1.49 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.63 1.66 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.79 1.79 58 1.79 1.81 RPTOOS 46 1.86 1.91 RPOOS 46 1.92 1.99 30 2.23 2.37 30 2.35 2.51 30 (> 50%F) 2.64 2.79 30 (> 500/F) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 5oo/F) 3.03 3.24 30 (s 5o%F) 2.51 2.68 30 ( 500/oF) 2.60 2.79 25 (<_5o%F) 2.68 2.89 25 (_/o%F) 2.81 3.03 100 1.51 1.52 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.66 1.69 63 1.70 1.74 58 1.73 1.78 58 ... ...

58 1.79 1.79 58 1.79 1.83 TBVOOS 46 1.87 1.93 TBOOS 46 1.94 2.00 30 2.37 2.52 30 2.25 2.39 30 (> 50%F) 3.10 3.20 30 (> 5o0/.F) 3.20 3.31 25 (> 5o%F) 3.52 3.64 25 (> 50%F) 3.63 3.78 30 (. 50%F) 2.65 2.79 30 (. 50%/0F) 2.72 2.88 25 (:_5o%F) 2.97 3.19 25 (S 500/oF) 3.08 3.30 100 1.51 1.52 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.66 1.69 63 1.70 1.74 58 1.73 1.78 58 .. .. ..

58 1.79 1.79 RPTOOS 58 1.79 1.83 TOOS 46 1.87 1.93 TBVOOS 46 1.94 2.00 30 2.25 2.39 FHOOS 30 2.37 2.52 30 (> 50%F) 3.10 3.20 30 (> 50/F) 3.20 3.31 25 (> 50%F) 3.52 3.64 25 (> 5oo/0 ) 3.63 3.78 30 (S 50%F) 2.65 2.79 30 (_ 500/OF) 2.72 2.88 25 (. 50%F) 2.97 3.19 25 (. 500%F) 3.08 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 21 Table 2 (Continued): MCPRp Limits for BOC to NEOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 27,788 MWd / MTU)

MCPRp Limit F MCPRP Limit EOOS Power EOOS Power Option (% Rated) Option (% Rated) 100 1.47 1.49 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.74 1.74 63 1.74 1.74 58 .... .. 58 .. .. ..

58 1.79 1.79 58 1.79 1.81 PLUOOS 46 1.86 1.91 FHOOS 46 1.92 1.99 30 2.35 2.51 30 2.23 2.37 30 (> 50%F) 2.64 2.79 30 (> 500/.F) 2.75 2.92 25 (> 5oF) 2.89 3.08 25 (> 5O%/F) 3.03 3.24 30 (_50%F) 2.51 2.68 30 (<5OoF) 2.60 2.79 25 (5 o%F) 2.68 2.89 25 (50o/.F) 2.81 3.03 100 1.47 1.49 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.74 1.74 63 1.74 1.74 58 .... .. 58 .... ..

58 1.79 1.79 RPTOOS 58 1.79 1.81 PTOOS 46 1.86 1.91 FHOOS 46 1.92 1.99 30 2.23 2.37 PLUOOS 30 2.35 2.51 30 (> 50%F) 2.64 2.79 30 (>50%F) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 50-/F) 3.03 3.24 30 (<50%F) 2.51 2.68 30 (5 5oF) 2.60 2.79 25 (_50%F) 2.68 2.89 25 (5o%F) 2.81 3.03 100 1.51 1.52 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.74 1.74 63 1.74 1.74 58 .. .... 58 .. .. ..

58 1.79 1.79 TBVOOS 58 1.79 1.83 TBVOOS 46 1.87 1.93 FHOOS 46 1.94 2.00 30 2.25 2.39 PLUOOS 30 2.37 2.52 30 (> 5o%F) 3.10 3.20 30 (> 5oo/0F) 3.20 3.31 25 (> 5O%F) 3.52 3.64 25 (> 50%oF) 3.63 3.78 30 (. 5o%F) 2.65 2.79 30 (< 500/0) 2.72 2.88 25 (< 5O%F) 2.97 3.19 25 ( 500JF) 3.08 3.30 100 1.51 1.52 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.74 1.74 63 1.74 1.74 58 .... .. 58 5 ...- -

RPTOOS RPTOOS 58 TOOS 58 1.79 1.83 1.79 1.79 TBVOOS 46 TBOOS 46 1.94 2.00 1.87 1.93 PLUOOS 30 FHOOS 30 2.37 2.52 2.25 2.39 30 (> 5O%F) 3.10 30 (> 50/.F) 3.20 3.31 3.20 25 (> 50%F) 3.52 3.64 25 (> 50oF) 3.63 3.78 30 (S 5o%F) 2.65 2.79 30 (_ 500/.F) 2.72 2.88 25 (5 50%F) 2.97 3.19 25 (< 50/F) 3.08 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 22 Table 3: MCPRp Limits for BOC to EOC Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 31,075 MWd / MTU)

MCPRp Limit MCPRp Limit EOOS Power EOOS Power Option (% Rated) Option (% Rated) 100 1.45 1.47 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.61 1.64 63 1.66 1.70 58 1.69 1.73 58 1.75 ---

58 1.78 1.78 58 1.78 1.79 in 46 1.85 1.89 FHOOS 46 1.90 1.97 30 2.22 2.35 30 2.33 2.49 30 (> 50%F) 2.64 2.79 30 (> 5o0/F) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 5o0/0F) 3.03 3.24 30 (_ 5o%F) 2.51 2.68 30 (_ 5oF) 2.60 2.79 25 (_ 50%F) 2.68 2.89 25 (5<o/.F) 2.81 3.03 100 1.45 1.47 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.61 1.64 63 1.66 1.70 58 1.69 1.73 58 1.75 ---

58 1.78 1.78 58 1.78 1.79 RPTOOS 46 1.85 1.89 FHOOS 46 1.90 1.97 30 2.33 2.49 30 2.22 2.35 30 (> 5o%F) 2.64 2.79 30 (>500F) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 5oF) 3.03 3.24 30 (_ 5o%F) 2.51 2.68 30 (_ 50/.F) 2.60 2.79 25 (_ 5o%F) 2.68 2.89 25( 500/F) 2.81 3.03 100 1.49 1.51 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.65 1.67 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.78 1.78 58 1.78 1.81 TBVOOS TBOOS 46 1.92 1.98 46 1.85 1.90 30 2.35 2.49 30 2.23 2.36 30 (> 5o%F) 3.09 3.20 30 (> 50%F) 3.19 3.31 25 (> 5o%F) 3.51 3.64 25 (> 50%F) 3.62 3.78 30 (< 50%F) 2.64 2.79 30 (o 50%F) 2.72 2.88 25 (S 5o%F) 2.97 3.18 25 (_ 500%F) 3.07 3.30 100 1.49 1.51 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.65 1.67 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.78 1.78 RPTOOS 58 1.78 1.81 TOOS 46 1.85 1.90 TBVOOS 46 1.92 1.98 30 2.23 2.36 FHOOS 30 2.35 2.49 30 (> 5o%F) 3.09 3.20 30 (> 5oF) 3.19 3.31 25 (> 5o%F) 3.51 3.64 25 (> 500F) 3.62 3.78 30 (_ 50%F) 2.64 2.79 30 (S 500/.F) - 2.72 2.88 25 (. 5o%F) 2.97 3.18 25 ( 500%F) 3.07 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 23 Table 3 (Continued): MCPRp Limits for BOC to EOC Exposures - NSS Scram Times (Applicable up to Core Avera e Exposure of 31,075 MWd / MTU)

MCPRp Limit I MCPRp Limit EOOS Power EOOS Power Option (% Rated) Option (% Rated) 100 1.45 1.47 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.73 1.73 63 1.73 1.73 58 .. .. .. 58 ... ...

58 1.78 1.78 58 1.78 1.79 PLUOOS 46 1.85 1.89 FHOOS 46 1.90 1.97 30 2.33 2.49 30 2.22 2.35 30 (> 50%F) 2.64 2.79 30 (> 50o/F) 2.75 2.92 25 (> 5o%F) 2.89 3.08 25 (> 500/.F) 3.03 3.24 30 (_5o%F) 2.51 2.68 30 (_ 50%F) 2.60 2.79 25 (. 50%F) 2.68 2.89 25 (5 50%F) 2.81 3.03 100 1.45 1.47 100 1.48 1.50 69 1.58 1.62 69 1.61 1.64 63 1.73 1.73 63 1.73 1.73 58 .... .. 58 58 1.78 1.78 RPTOOS 58 1.78 1.79 PTOOS 46 1.85 1.89 FHOOS 46 1.90 1.97 30 2.22 2.35 PLUOOS 30 2.33 2.49 30 (> 5o%F) 2.64 2.79 30 (> 500/.F) 2.75 2.92 25 (> 5o%F) 2.89 3.08 25 (> 50%F) 3.03 3.24 30 (5 5o%F) 2.51 2.68 30 (. 500/%F) 2.60 2.79 25 (5 50%F) 2.68 2.89 25 (_ 50%/.F) 2.81 3.03 100 1.49 1.51 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.73 1.73 63 1.73 1.73 58 .. .. .. 58 ... ...

58 1.78 1.78 TBVOOS 58 1.78 1.81 TBVOOS 46 1.85 1.90 FHOOS 46 1.92 1.98 30 2.23 2.36 PLUOOS 30 2.35 2.49 30 (> 50%F) 3.09 3.20 30 (> 5o%F) 3.19 3.31 25 (> 50%F) 3.51 3.64 25 (> 5o%F) 3.62 3.78 30 (S 50%F) 2.64 2.79 30 (S 5o%F) 2.72 2.88 25 (5 50%F) 2.97 3.18 25 ( 50o0/) 3.07 3.30 100 1.49 1.51 100 1.51 1.53 69 1.62 1.66 69 1.64 1.66 63 1.73 1.73 63 1.73 1.73 58 .... .. 58 5 ...- -

RPTOOS RPTOOS 58 1.78 1.78 RTBOOS 58 1.78 1.81 TBVOOS 46 1.85 1.90 TBOOS 46 1.92 1.98 PLUOOS PHOOS 30 2.35 2.49 30 2.23 2.36 30 (> 5o/F) 3.19 3.31 30 (> 50%F) 3.09 3.20 25 (> 50%F) 3.51 3.64 25 (> 5o0/F) 3.62 3.78 30 (S 50%F) 2.64 2.79 30 (5 50/F) 2.72 2.88 25 (S 50%F) 2.97 3.18 25 (_5O/.F) 3.07 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C15 Core Operating Limits Report Revision 0, Page 24 Table 4: MCPRp Limits for BOC to EOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 31,075 MWd / MTU)

MCPRp Limit MCPRp Limit EOOS Power EOOS Power Option (% Rated) Option (%Rated) 100 1.47 1.49 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.63 1.66 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.79 1.79 58 1.79 1.81 Service 46 1.86 1.91 FHOOS 46 1.92 1.99 30 2.23 2.37 30 2.35 2.51 30 (> 50%F) 2.64 2.79 30 (> 50/F) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 500/.F) 3.03 3.24 30 (_50%F) 2.51 2.68 30 (_ 500/.F) 2.60 2.79 25 (_50%F) 2.68 2.89 25 (51%F) 2.81 3.03 100 1.47 1.50 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.63 1.66 63 1.68 1.72 58 1.71 1.75 58 1.77 ---

58 1.79 1.79 58 1.79 1.81 RPTOOS 46 1.86 1.91 MOOS 46 1.92 1.99 30 2.35 2.51 30 2.23 2.37 30 (> 50%F) 2.64 2.79 30 (>5oF) 2.75 2.92 25 (> 50%F) 2.89 3.08 25 (> 5o0/oF) 3.03 3.24 30 (<50%F) 2.51 2.68 30 ( 500/oF) 2.60 2.79 25 (_50%F) 2.68 2.89 25( 50o/.F) 2.81 3.03 100 1.51 1.52 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.66 1.69 63 1.70 1.74 58 1.73 1.78 58 .... ..

58 1.79 1.79 58 1.79 1.83 TBVOOS 46 1.87 1.93 TBOOS 46 1.94 2.00 30 2.37 2.52 30 2.25 2.39 30 (> 5o%F) 3.10 3.20 30 (> 50/F) 3.20 3.31 25 (> 50%F) 3.52 3.64 25 (> 500/.F) 3.63 3.78 30 (_5o%F) 2.65 2.79 30 (< 50%F) 2.72 2.88 25( 50%F) 2.97 3.19 25 (_ 500%F) 3.08 3.30 100 1.52 1.53 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.66 1.69 63 1.70 1.74 58 1.73 1.78 58 . ... ..

58 1.79 1.79 RPTOOS 58 1.79 1.83 RTBOOS 46 1.87 1.93 TBVOOS 46 1.94 2.00 30 2.25 2.39 FHOOS 30 2.37 2.52 30 (> 5o%F) 3.10 3.20 30 (> 50/F) 3.20 3.31 25 (> 5o%F) 3.52 3.64 25 (> 500/F) 3.63 3.78 30 (S 5o%F) 2.65 2.79 30 (_ 50-/F) 2.72 2.88 25 (. 5o%F) 2.97 3.19 25 (. 500/%F) 3.08 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 25 Table 4 (Continued): MCPRp Limits for BOC to EOC Exposures - TSSS Scram Times (Applicable up to Core Avera e Exposure of 31,075 MWd / MTU)

MCPRp Limit MCPRp Limit EOOS Power EOOS Power Option (% Rated) Option (% Rated) 100 1.47 1.49 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.74 1.74 63 1.74 1.74 58 ... ... 58 ... ...

58 1.79 1.79 58 1.79 1.81 PLUOOS 46 1.86 1.91 FIIOOS 46 1.92 1.99 30 2.35 2.51 30 2.23 2.37 30 (> 5o%F) 2.64 2.79 30 (> 50%F) 2.75 2.92 25 (>50%F) 2.89 3.08 25 (> 5oF) 3.03 3.24 30 (_50%F) 2.51 2.68 30 (< 5oo/F) 2.60 2.79 25 (550%F) 2.68 2.89 25 (_<5oF) 2.81 3.03 100 1.47 1.50 100 1.50 1.52 69 1.59 1.65 69 1.63 1.66 63 1.74 1.74 63 1.74 1.74 58 .... .. 58 .... ..

58 1.79 1.79 RPTOOS 58 1.79 1.81 RPTOOS 46 1.86 1.91 FHOOS 46 1.92 1.99 30 2.23 2.37 PLUOOS 30 2.35 2.51 30 (> 5o%F) 2.64 2.79 30 (> 5o%/F) 2.75 2.92 25 (> 5O%F) 2.89 3.08 25 (> 5o0AF) 3.03 3.24 30 (<5o%F) 2.51 2.68 30 (< 5o/.F) 2.60 2.79 25 (5o%F) 2.68 2.89 25 (.5 5o%/F) 2.81 3.03 100 1.51 1.52 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.74 1.74 63 1.74 1.74 58 .... .. 58 . ... ..

58 1.79 1.79 TBVOOS 58 1.79 1.83 TBVOOS 46 1.87 1.93 FHOOS 46 1.94 2.00 30 2.25 2.39 PLUOOS 30 2.37 2.52 30 (> 50%F) 3.10 3.20 30 (> 500/F) 3.20 3.31 25 (> 50%F) 3.52 3.64 25 (> 50%F) 3.63 3.78 30 (< 50%F) 2.65 2.79 30 (< 500/.F) 2.72 2.88 25 (_<50%F) 2.97 3.19 25 (< 500/.F) 3.08 3.30 100 1.52 1.53 100 1.53 1.55 69 1.64 1.65 69 1.66 1.68 63 1.74 1.74 63 1.74 1.74 58 .... .. 58 5 ...- -

RPTOOS TOOS 58 1.79 1.83 RPTOOS 58 1.79 1.79 TBOOS 46 1.94 2.00 TBVOOS 46 1.87 1.93 FHOOS 30 2.37 2.52 PLUOOS 30 2.25 2.39 30 (> 5o%F) 3.10 3.20 30 (> 50%F) 3.20 3.31 25 (> 5o%F) 3.52 3.64 25 (> 500/F) 3.63 3.78 30 (< 5o%F) 2.65 2.79 30 (_ 500/.F) 2.72 2.88 25 (L 50%F) 2.97 3.19 25 ( 5oo/0F) 3.08 3.30 Add 0.02 to the above MCPRp limits for SLO.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 26 Table 5: MCPRp Limits for BOC to CD Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 32,274 MWd / MTU)

All Values Include FFTRIFHOOSand Bound HeatersIn-Service MCPRp Limit I [ MCPRp Limit EOOS Power EOOS Power Option (% Rated) Option (% Rated) 100 1.48 1.50 100 1.48 1.50 69 1.61 1.64 69 1.61 1.64 63 1.66 1.70 63 1.73 1.73 58 1.75 --- 58 .. .. ..

58 1.78 1.79 58 1.78 1.79 Service 46 1.90 1.97 PLUOOS 46 1.90 1.97 30 2.33 2.49 30 2.33 2.49 30 (> 5o%F) 2.75 2.92 30 (> 5o0F) 2.75 2.92 25 (> 5o%F) 3.03 3.24 25 (> 5o%F) 3.03 3.24 30 (S_5oF) 2.60 2.79 30 (_ 50%F) 2.60 2.79 25 (< 50%F) 2.81 3.03 25 (L5o.0%F) 2.81 3.03 100 1.48 1.50 100 1.48 1.50 69 1.61 1.64 69 1.61 1.64 63 1.66 1.70 63 1.73 1.73 58 1.75 --- 58 ---

58 1.78 1.79 58 1.78 1.79 RPTOOS 46 1.90 1.97 RPTOOS 46 1.90 1.97 30 2.33 30 2.33 2.49 2.49 30 (> 50%F) 2.75 2.92 30 (> 5o00) 2.75 2.92 25 (> 5o%F) 3.03 3.24 25 (> 50%F) 3.03 3.24 30 (< 50%F) 2.60 2.79 30 L< 50%F) 2.60 2.79 25 (< 50%F) 2.81 3.03 25 (_ 50%/F) 2.81 3.03 100 1.51 1.53 100 1.51 1.53 69 1.64 1.66 69 1.64 1.66 63 1.68 1.72 63 1.73 1.73 58 1.77 --- 58 58 1.78 1.81 58 1.78 1.81 TBVOOS 46 TBVOOS 46 1.92 1.98 1.92 1.98 30 30 2.35 2.49 2.35 2.49 30 (> 50%F) 3.19 3.31 30 (> 500F) 3.19 3.31 25 (> 5o%F) 3.62 3.78 25 (> 5o/.F) 3.62 3.78 30 (< 50%F) 2.72 2.88 30 (_ 5 00%F) 2.72 2.88 25 (. 50%F) 3.07 3.30 25 (< 500%J) 3.07 3.30 100 1.51 1.53 100 1.51 1.53 69 1.64 1.66 69 1.64 1.66 63 1.68 1.72 63 1.73 1.73 58 1.77 --- 58 58 1.78 1.81 RPTOOS 58 1.78 1.81 TOOS 46 1.92 1.98 30 2.35 TBVOOS 46 1.92 1.98 2.49 PLUOOS 30 2.35 2.49 30 (> 50%F) 3.19 3.31 30 (> 50%F) 3.19 3.31 25 (> 5O%F) 3.62 3.78 25 (> 500/F) 3.62 3.78 30 (.50%F) 2.72 2.88 30 (_5001F) 2.72 2.88 25 (._50%F) 3.07 3.30 25 (_ 5001F) 3.07 3.30 AOd U.U2 to the above MCPKp lunits for SLU.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 27 Table 6: MCPRp Limits for BOC to CD Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 32,274 MWd / MTU)

All Values Include FFTR/FHOOSand Bound HeatersIn-Service MCPRp Limit [ MCPRp Limit EOOS Power EOOS Power Option (% Rated) Option (% Rated) 100 1.50 1.52 100 1.50 1.52 69 1.63 1.66 69 1.63 1.66 63 1.68 1.72 63 1.74 1.74 58 1.77 --- 58 ... ...

58 1.79 1.81 58 1.79 1.81 In-Service 46 1.92 1.99 PLUOOS 46 1.92 1.99 30 2.35 2.51 30 2.35 2.51 30 (> 5o%F) 2.75 2.92 30 (> 50%F) 2.75 2.92 25 (> 50%F) 3.03 3.24 25 (> 500/.F) 3.03 3.24 30 (5 5o%F) 2.60 2.79 30 (_ 50%/oF) 2.60 2.79 25 (L 5o%F) 2.81 3.03 25 (. 50%oF) 2.81 3.03 100 1.50 1.52 100 1.50 1.53 69 1.63 1.66 69 1.63 1.66 63 1.68 1.72 63 1.74 1.74 58 1.77 --- 58 ... ...

58 1.79 1.81 58 1.79 1.81 RPTOOS PTOOS 46 1.92 1.99 46 1.92 1.99 30 2.35 2.51 30 2.35 2.51 30 (> 50%F) 2.75 2.92 30 (> 50oF) 2.75 2.92 25 (> 50%F) 3.03 3.24 25 (> soo0/) 3.03 3.24 30 (L 50%F) 2.60 2.79 30 (. 50%F) 2.60 2.79 25 (_ 50%F) 2.81 3.03 25 (_ 50/%F) 2.81 3.03 100 1.53 1.55 100 1.53 1.55 69 1.66 1.68 69 1.66 1.68 63 1.70 1.74 63 1.74 1.74 58 .. .. .. 58 58 1.79 1.83 58 1.79 1.83 TBVOOS 46 1.94 2.00 TBVOOS 46 1.94 2.00 30 2.37 2.52 30 2.37 2.52 30 (> 5o%F) 3.20 3.31 30 (> 500/F) 3.20 3.31 25 (> 50%F) 3.63 3.78 25 (> 50%F) 3.63 3.78 30 (S 5o%F) 2.72 2.88 30 (S 50%/.F) 2.72 2.88 25 (< 50%F) 3.08 3.30 25 (.500/%F) 3.08 3.30 100 1.54 1.55 100 1.54 1.55 69 1.66 1.68 69 1.66 1.68 63 1.70 1.74 63 1.74 1.74 58 .. .. .. 58 58 1.79 1.83 RPTOOS 58 1.79 1.83 TOOS 46 1.94 2.00 TBVOOS 46 1.94 2.00 30 2.37 2.52 PLUOOS 30 2.37 2.52 30 (> 5o%F) 3.20 3.31 30 (> 5o%F) 3.20 3.31 25 (> 50%F) 3.63 3.78 25 (> 50%F) 3.63 3.78 30 (S 50%F) 2.72 2.88 30 (5 500/.F) 2.72 2.88 25 (s 5o%F) 3.08 3.30 25 (s 50oF) 3.08 3.30 IAddU U.U2 Lo LtLhabove IVMU..R*p huJntLS lfor ,LU.

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 28 Figure 1 APLHGR Limits for Bundle Type GE14-P1ODNAB416-16GZ (GE14 EDB#2600) 14.00 13.00 NACCEPTABLE OPERATION 12.00 11.00 10.00 9.00 8.00 E

3 C,,

,.I 7.00 6.00 AOCEPTAB'E OPEOP BLE PERTIO a.

5.00 4.00 3.00 2.00 1.00 0.00 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 Limit (GWDIMTU) (kw/ft) (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) 0.00 9.41 8.82 10.56 22.05 10.85 0.22 9.51 9.92 10.65 27.56 10.50 1.10 9.61 11.02 10.74 33.07 10.10 2.20 9.73 12.13 10.85 38.58 9.63 3.31 9.86 13.23 10.85 44.09 9.10 4.41 10.00 14.33 10.86 49.60 8.57

.............. 5. .........................1....... . ...................... ....43 ....... ........10......

.. . ..................5..5.. .............. ................ 2.........

6.61 10.28

............ ..............................- 16.53

---I .................... 10.91

... ....... ............... 60.63

................................ 6.24 7.72 10.42 18.74 10.94 63.50 4.93 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2 Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 29 Figure 2 APLHGR Limits for Bundle Type GE14-P1ODNAB416-16GZ (GE14 EDB#2601)

I E

0 z-J 0.

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

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure Limit (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) 0.00 9.43 8.82 10.76 22.05 10.88

................ 0.22 . .... ................ 9.47...........

.......... ....... 9.92 ................

............... f........ ......... 10.83o.9................. 27.56...............

.............. 3.3........ ....... 10.50 i.. 0.

1.10 9.54 11.02 10.91 33.07 10.10 2.20 9.67 12.13 10.99 38.58 9.66 3.31 9.83 13.23 11.03 44.09 9.13

................ 4.41 .. .................. ........... 10.02

............. 14.33................. ..................

................ 11.02 2......... .............. 49.60

5. 5.

....................... ........ 8.59

. 0......

8. .........

5.51 10.21 15.43 11.02 55.12

......... :..................... ............... 11....I.......... .......................................

8.03

6.61

.I............................. 10.43

.. .......................... 16.53

.. ........................................ 11.03 60.63 6.38..........

7.72 10.62 18.74 11.02 63.82 4.92 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2 Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 30 Figure 3 APLHGR Limits for Bundle Type GE14-P1ODNAB416-18GZ (GE14 EDB# 2627) 14.00 13.00 12.00 11.00 10.00 9.00 8.00 L

E 7.00

  • 6.00

-J 5.00 4.00 3.00 2.00 1.00 0.00 4--

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 Limit (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) 0.00 9.26 8.82 10.54 22.05 10.85 0.22 9.34 9.92I...........-............................................

10.65 27.56 10.49 1.10 9.477.

~i`6 ...............

............. K 11.02

1. 02........................

10.75 33.07 10.09 2.20 9.62 12.13 10.85 38.58 9.60 3.31 9.77 13.23 10.85 44.09 9.09

........... ... 4.41

. . ............................... 9.93

. .. . ..... ................... 14.33

...................... 10.86

............................. 49.60

............................... ........ 8.56

  • 5 *5.110

............ .... ...... 9........... .............. 1.43

.......... !.0. 0.... ............. ..... ...

.3.... 10.88*.8..8.... ................... 5.5.

.. .2..

55.12 8.0....

....................... 8.01 .........

6.61 10.25 16.53 10.91 60.63 6.21 7.72 10.41 18.74 10.93 63.42 4.93 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2 Browns Ferry Nuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 31 Figure 4 APLHGR Limits for Bundle Type GE14-P1ODNAB417-18GZ (GE14 EDB# 2628) 14.00 E

CL 0 .0 0 . . . . . . . . . . . . . . .. . . . . .  !.. .

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 Limit (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) (GWD/MTU) (kw/ft) 0.00 9.39 8.82 10.74 22.05 10.88

............... 0.22 9.43

.. .... ................ ............................. 9.92

....................... . .. . .. .. .. 10.83

. ......................... 27.56

. . . . . . .......................... 10.50 1.10 9.50 11.02 10.91 33.07 10.10

... 2.20

......................................... 9.63 ............

................ 12.13

............................. 11.00

............................ 38.58

  • ..................................... 9.62 3.31 9.80 13.23 11.02 44.09 9.12 4.41

....................................... 9.99

............................ 14.33

.......................................... 11.02

........................... 49.60

............ ........................... 8.58 5.51 10.19 15.43 11.02 55.12 8.02 6.61................ ...... ... ....

... 10.41

... ... ... ... ... ... ... ...... ... 16.53

...................... 11.03

............................ 60.63 6.35 7.72 10.64 18.74 11.02 63.74 4.92 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2 Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C15 Core Operating Limits Report Revision 0, Page 32 Figure 5 APLHGR Limits for all ATRIUM-10M Fuel (A10) 14.00 13.00 12.00 (UNACC EPTABLE OPERZATION 11.00 10.00 9.00 8.00 E

3 7.00 C, ACCEPTABLE OPERATION

- 6.00

-J 5.00 4.00 3.00 2.00 1.00 0.00 0 .00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (GWD/MTU)

Average Planar LHGR Exposure Limit (GWD/MTU) (kw/ft) 0.00 12.50 15.00 12.50 67.00 7.30 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits are for dual recirculation loop operation. Single Loop Operation (SLO) adjustments are performed as described in Section 2 Browns Ferry Nuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 33 Figure 6 GE14 Power Dependent MAPLHGR Multiplier - MAPFAC(P)

NSS/TSSS Insertion Times - All Exposures 1.1 0.9 0.8 E' 0.7 2 0.6 0.5 0.4 0.3 0.2 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 MAPFAC(P) is not dependent upon any Equipment Out-Of-Service except Turbine Bypass.

Browns FerryNuclearPlant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C15 Core Operating Limits Report Revision 0, Page 34 Figure 7 Flow Dependent MAPLHGR Factor - MAPFAC(F)

(GE14) 1.00 0.90 0.80 0.

S0.70 0.60 0.50 30 40 50 60 70 80 90 100 Core Flow (% Rated)

Max Core Flow 102.5% Rated Max Core Flow 107% Rated Core Flow MAPFAC(F) Core Flow MAPFAC(F)

(% rated) (% rated) 30 0.62 30 0.60 71 1.00 75 1.00 102.5 1.00 107 1.00 These values bound both Turbine Bypass In-Service and Out-Of-Service.

These values bound both Recirculation Pump Trip In-Service and Out-Of-Service.

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 PlantUnit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 35 Figure 8 LHGR Limits for all GE-14 Fuel (GE14) 14.00 13.00 12.00 UNACCEPTABLE OPERATION 11.00 10.00 9.00 8.00 E 7.00 S1ACEPTABLE OPERATION (D 6.00

-J 5.00 4.00 3.00 2.00 1.00 0.00 0 .00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 Pellet Exposure (GWD/MTU)

Pellet LHGR Exposure Limit (GWD/MTU) (kwlft) 0.00 13.40 16.00 13.40 63.50 8.00 70.00 5.00 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits apply to both Two Loop Operation (TLO) and Single Loop Operation (SLO).

Browns FerryNuclear Plant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 36 Figure 9 LHGR Limits for all ATRIUM-10 Fuel (A10) 14.00 13.00 12.00 11.00 10.00 9.00 8.00 E 7.00 o 6.00

-J-5.00 4.00 3.00 2.00 1.00 0.00 4-0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 Pellet Exposure (GWD/MTU)

Pellet LHGR Exposure Limit (GWDIMTU) (kw/ft) 0.00 13.40 18.90 13.40 74.40 7.10 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

These limits apply to both Two Loop Operation (TLO) and Single Loop Operation (SLO).

Browns Ferry Nuclear PlantUnit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 37 Figure 10 A10 Power Dependent LHGR Multiplier - LHGRFAC(P)

NSS/TSSS Insertion Times - All Exposures 0.

4l 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 LHGRFAC(P) is not dependent upon any Equipment Out-Of-Service except Turbine Bypass.

Browns FerryNuclearPlant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 38 Figure 11 Flow Dependent LHGR Multiplier - LHGRFAC(F)

(A10 Fuel) 1.00 ~MAXFLOW -102.5%

0.95

" 0.90

/

/ MAX F LOW = 107%

U.~T + 4 4

  • F 4 4 U OU *+.. . . __ _

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

Max Core Flow 102.5% Rated Max Core Flow 107% Rated Core Flow LHGRFAC(F) Core Flow LHGRFAC(F)

(% rated) (% rated) 30 0.91 30 0.88 48 1.00 54.4 1.00 102.5 1.00 107 1.00 These values bound both Turbine Bypass In-Service and Out-Of-Service.

These values bound both Recirculation Pump Trip In-Service and Out-Of-Service.

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 FerryNuclearPlant Unit 2 Cycle 15

TVA Nuclear Fuel TVA-COLR-BF2C 15 Core Operating Limits Report Revision 0, Page 39 (Final)

Figure 12 Flow Dependent MCPR Limit - MCPR(F)

(All Fuel) 1.43 1.38 1.33 a-.

tU 1.28 1.23 1.18 30 40 50 60 70 80 90 100 Core Flow (% Rated)

Max Core Flow 102.5% Rated Max Core Flow 107% Rated Core Flow Core Flow MCPR(F

(% rated) MCPR(F) (% rated) MCPR(F) 30 1.37 30 1.40 72 1.21 78 1.21 102.5 1.21 107 1.21 These values bound both Turbine Bypass In-Service and Out-Of-Service.

These values bound both Recirculation Pump Trip In-Service and Out-Of-Service.

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 FerryNuclearPlant Unit 2 Cycle 15

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