ML051520534

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Core Operating Limits Report (Colr), for Cycle 14 Operation
ML051520534
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 05/18/2005
From: Abney T
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051520534 (44)
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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 18, 2005 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Stop:

OWFN, Pl-35 f

Washington, D.C. 20555-0001 Gentlemen:

In the Matter of Tennessee Valley Authority

)

Docket No. 50-260 BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 2 -

CORE OPERATING LIMITS REPORT (COLR), FOR CYCLE 14 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is Revision 0 of the Unit 2 Cycle 14, Core Operating Limits Report.

BFN Unit 2 Cycle 14 represents the first cycle of operation, for that unit, using Framatome Advanced Nuclear Power (FANP)

ATRIUM-10 fuel bundles, similar to those currently operating in Unit 3 Cycle 12.

There are no new commitments contained in this letter.

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

S, ncer Manager Licensi g and ndustry Affars Enc osure cc:

Sdd

U.S. Nuclear Regulatory Commission Page 2 May 18, 2005 Enclosure cc (Enclosure):

Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Margaret Chernoff, 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 2 CORE OPERATING LIMITS REPORT (COLR),

FOR CYCLE 14 OPERATION (SEE ATTACHED)

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2Cl4 Revision 0, Page I Browns Ferry Nuclear Plant Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT (COLR)

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

Verified By:

Approved By:

Reviewed By:

Approved By:

Earl E. Riley, Sr. Engineering Specialist BWR Fuel Engineering B5rye C. Mitchell, Nuclear Engineer BWR Fuel Engineering Greg C. Storey, / Manager BWR Fuel Enkineering A.Keck, Supervisor rowns Ferry Reactor Engineering hairman Date:

3-7' Date:

/_/_5 Date:

3__7____

-7/7/0or Date:

Date:

3sj I (C.5 Revision 0 (3/1 0/2005)

Initial Issue Revision 0 (3/10/2005)

Initial Issue Pages Affected: All

TVA Nuclcar Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 2 Revision Log Revision Date Description Affected Pages 0

3/10/2004 Initial Release for New Cycle All Broui'ns Ferry Nuclear Plant Unit 2 C)'cle 14

TVA Nuclear Fuel TVA-COLR-BF2C14 Core Operating Limits Report Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Nuclear Plant Unit 2 Cycle 14 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 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 14 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 14 core is composed of Framatome-ANP ATRIUMTb'-10, Global Nuclear Fuel GE-14Tl, and Global Nuclear Fuel GE-13Tn' assemblies. Throughout this document these are referred to as A10, GE14, and GE13 with the trademark implied.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 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 APLHGRF APLHGRsLo off-rated power APLHGR limit off-rated flow APLHGR limit SLO APLHGR limnit

[APLHGRo-tpDw*

MAPFAC(P)]

[APLHGRRATED

  • MAPFAC(F)]

[ALPHGR^m,* SLO Multiplier]

The off-rated power and flow corrections to the APLHGR limit only apply to the GE13 and GE14 fuel in the Browns Ferry Unit 2 Cycle 14 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 1-8. The APLHGR limits provided in the COLR figures for the GE13 and GE14 assemblies are for the most limiting lattice (excluding natural uranium) at each exposure point. The specific values for each GE13 and GE14 lattice are given in Reference 4. The ATRIUM-1 0 values are provided in Reference 1.

Bundle Type Rated Power APLHGR Limit GE13-P9DTB391-13GZ (EDB 2430)

Figure 1 GEI 3-P9DTB412-2G7.0/l I G5.0 (EDB 2431)

Figure 2 GE14-PIODNAB416-16GZ (EDB2600)

Figure 3 GE14-PIODNAB416-16GZ (EDB2601)

Figure 4 GE14-PIODNAB367-14GZ (EDB2602)

Figure 5 GE14-PIODNAB416-18GZ (EDB2627)

Figure 6 GE14-PIODNAB417-18GZ (EDB2628)

Figure 7 AIO-3920B-14GV70 Figure 8 Browns Ferry Nuclear Plant Unit 2 O'cle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 5 Off-Rated Power Corrections: APLHGRp The APLHGR limits for the GE13 and GE14 fuel lattices are adjusted for off-rated power conditions using the ARTS multiplier, MAPFAC(P). The reduced power multiplier, MAPFAC(P), for both the GE13 and GE14 fuel is provided in Reference 1. No off-rated power correction is required for the AI0 rated APLHGR limits.

Product Line MAPFAC(P)

GE13 Figure 9 GE14 Figure 10 A10 1.0 Off-Rated Flow Corrections: APLHGRF The APLHGR limits for the GE13 and 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 Al 0 rated APLHGR limits.

Product Line MAPFAC(F)

GE13 Figure 1 1 GE14 Figure 12 A10 1.0 SLO Corrections: APLHGRSLO Single Recirculation Loop Operation (SLO) requires that the rated power APLHGR limit (APLHGRrtcd) be reduced by applying the following multipliers. The GE13 and GE14 multipliers are provided in Reference 5. The Al 0 multiplier is provided in Reference 1.

Product Line SLO Multiplier GE13 0.87 GE14 0.93 A10 0.85 Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclcar Fuel TVA-COLR-BF2C14 Core Operating Limits Report Revision 0, Page 6 Equipment Out-Of-Service (EOOS) Corrections:

The rated APLHGR limits in Figures 1-8 are applicable for both Turbine Bypass In-Service (TBVIS) and Turbine Bypass Out-Of-Service (TBVOOS) conditions. The off-rated power corrections [MAPFAC(P)] in Figures 9 and 10 contain separate limits to be applied for TBVIS or TBVOOS. The off-rated flow corrections [MAPFAC(F)] in Figures 11 and 12 bound both TBVIS and TBVOOS operation.

The APLHGR limits in Figures 1-8 are applicable for both End-Of-Cycle Recirculation Pump Trip (RPT) In-Service (RPTIS) and RPT Out-Of-Service (RPTOOS). The off-rated power

[MAPFAC(P)] and flow corrections [MAPFAC(F)] in Figures 9, 10, 11, and 12 bound both RPTIS and RPTOOS operation. No corrections are required to the APLHGR limits for RPTOOS for either rated or off-rated operation.

The APLHGR limits in Figures 1-8 are applicable for normal feedwater temperature and Feedwater Heaters Out-Of-Service

/

Final Feedwater Temperature Reduction (FHOOS/FFTR). The off-rated power [MAPFAC(P)] and flow corrections [MAPFAC(F)] in Figures 9, 10, 11, and 12 bound both normal feedwater temperature and FHOOS/FFTR operation. No corrections are required to the APLHGR limits for FHOOS/FFTR for either rated or off-rated operation.

Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers described previously.

Broi'ns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CM4 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 LHGRF off-rated power LHGR limit off-rated flow LHGR limit

[LHGRRATm

  • LHGRFAC(P)]

[LHGRRATL

  • LHGRFAC(F)]

The off-rated power and flow corrections to the LHGR limnit only apply to the Al0 fuel in the Browns Ferry Unit 2 Cycle 14 core. For that reason, these multipliers for the GE13 and GE14 fuel are 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 GE13 1

14.4 kw/ft GE14 13.4 k-w/ft A10 I Figure 13 The AI0 LHGR limit is provided in Reference 6. The GE13 and GE14 LHGR limits are provided in Reference 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 GE13 or GE14 rated LHGR limits.

Product Line LHGRFAC(P)

GE13 & GE14 1.0 A10 Figure 14 Browlns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 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 GE13 and GE14 rated LHGR limits.

Product Line LHGRFAC(F)

GE13 & GE14 1.0 A10 Figure 15 Broiwns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel TVA-COLR-BF2C14 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 by fuel type in Figures 16 through 18. 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)
  • Fuel Type (GE13, GE14, or A10)

The MCPRF limits are provided by fuel type in Figure 16 (GE13), Figure 17 (GE14), and Figure 18 (Al 0). 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)
  • Fuel Type (GE13, GE14, or AlO)

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 Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 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 BOCtoCD 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.

8).

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.

Browns Ferry Nuclear Plant Unit 2 Cj'cle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 11

a. Fuel Type Dependent Limits Separate MCPRp limits are provided for the GE13, GE14, and Al 0 fuel types.
b. 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 30,755 MAVd / MTU 32,798 N"Vd / MTU 33,871 AINVd / 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.

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

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

All equipment In-Service (includes 1 SRVOOS)

EOC-Recirculation Pump Trip Out-Of-Service Turbine Bypass Valve(s) Out-Of-Service Combined 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.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 12

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

Brown:s Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 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. 9):

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

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

Allowable Value Nominal Trip Setpoint (NTSP) where:

SRB =

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

W =

Loop recirculation flow rate in percent of rated AW =

Difference between two-loop and single-loop effective recirculation 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%).

Browuts Ferry Ntclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 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. 9 & 10):

RBM Trip Setpoint Allowable Value Nominal Trip Setpoint (AV)

(NTSP)

LPSP 27%

25%

IPSP 62%

60%

HPSP 82%

80%

LTSP - unfiltered 121.7%

120.0%

- filtered 120.7%

119.0%

ITSP - unfiltered 116.7%

115.0%

- filtered 115.7%

114.0%

HTSP - unfiltered 111.7%

110.0%

- filtered 110.9%

109.2%

DTSP 90%

92%

(1),(2)

(1),(2)

(1),(2)

Notes: (1) These setpoints are based upon an Analytical Limit HTSP of 114% (w/o filter) which corresponds to a MCPR operating limit of 1.35(A10) / 1.33 (GEI3/GE14), as reported in section 5.5 of Reference 1. Unit 2 Cycle 14 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 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 -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)

< 1.75 (a), (b), (f), (h)

> 90%

< 1.42 (g) dual loop operation single loop operation 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 Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 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. 7).

SDM > 0.38% dk/k Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel TVA-COLR-BF2C14 Core Operating Limits Report Revision 0, Page 16

8. REFERENCES
1. EMF-3139 Rev. 1, "Browns Ferry Unit 2 Cycle 14 Reload Analysis", dated February 2005.
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 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

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

e) XN-NF-80-19(P)(A) Volume I 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 Powver Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-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 I 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 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) ANF-1358(P)(A) Revision 1, The Loss of Feedwvater 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 Powver 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, ATRIUMTh.10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

3. Global Nuclear Fuel Analytical Methodology

References:

Bronutns Ferry Nuclear Plant Unit 2 Circle 14

TVA Nuclear Fuci TVA-COLR-BF2C14 Corc Operating Limits Report Revision 0, Page 17 a) NEDE-2401 1-P-A-i4, "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. 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. EMF-3114(P) Rev. 0, "Mechanical Design Report for Browns Ferry Unit 2 Batches BFE2-14 ATRIUM'n"-10 Fuel Assemblies", dated September 2004.
7. TVA-COLR-BF2CI3 Rev. 0, "Browns Ferry Nuclear Plant Unit 2, Cycle 13 Core Operating Limits Report (COLR)", dated February 26, 2003.
8. EMF-3061(P) Rev. 2, "Browns Ferry Unit 2 Cycle 14 Plant Parameters Document", dated January 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 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.

10. 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 Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.

Browns Ferry Nuclear Plant Unit 2 Chicle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 18 Table 1: MCPRp Limits for BOC to NEOC Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 30,755 MWd / MTU)

AICPRP Limit AICPRp Limit EOOS Power A10 GE13 GE14 Option

(% Rated)

In-100 1.36 1.33 1.37 Service 60 1.52 1.60 1.60 50 1.63 50 1.77 1.72 1.78 30 1.96 2.00 2.10 30 (>so%F) 2.21 2.23 2.36 25 (> 50%F) 2.37 2.41 2.52 30s 50%F) 2.18 2.06 2.35 25 (So5%F) 2.33 2.21 2.52 RPTOOS 100 1.37 1.34 1.39 60 1.52 1.60 1.60 50 1.63 50 1.77 1.72 1.78 30 1.96 2.00 2.10 30 (>50%F) 2.21 2.23 2.36 25 (>50%F) 2.37 2.41 2.52 30 (550%.F) 2.18 2.06 2.35 25 (L5o%F) 2.33 2.21 2.52 TBVOOS 100 1.39 1.36 1.41 60 1.55 1.60 1.63 50 1.65 50 1.77 1.72 1.78 30 1.99 2.02 2.12 30 (> 5o%F) 2.73 2.65 2.82 25 (>50%F) 3.02 2.96 3.09 30 (S50%F) 2.47 2.22 2.61 25 (0so%F) 2.78 2.50 2.93 RPTOOS 100 1.40 1.37 1.42 TBVOOS 60 1.55 1.60 1.63 50 1.65 50 1.77 1.72 1.78 30 1.99 2.02 2.12 30 (>50%F) 2.73 2.65 2.82 25 (>5o%F) 3.02 2.96 3.09 30 (L5o%F) 2.47 2.22 2.61 25 (L5o%F) 2.78 2.50 2.93 EOOS Power A10 GE13 GE14 Option

(% Rated)

FHOOS 100 1.36 1.33 1.37 60 1.57 1.60 1.66 50 1.69 50 1.77 1.72 1.80 30 2.05 2.08 2.20 30 (>5o%F) 2.30 2.31 2.45 25 (>so%F) 2.48 2.51 2.64 30 (550%F) 2.25 2.12 2.44 25 (<s0%F) 2.43 2.30 2.63 RPTOOS 100 1.37 1.34 1.39 FHOOS 60 1.57 1.60 1.66 50 1.69 50 1.77 1.72 1.80 30 2.05 2.08 2.20 30 (>50%F) 2.30 2.31 2.45 25 (>so%F) 2.48 2.51 2.64 30 (S5o%F) 2.25 2.12 2.44 25 (C50%F) 2.43 2.30 2.63 TBVOOS 100 1.39 1.36 1.41 FHOOS 60 1.59 1.60 1.68 50 1.71 50 1.77 1.72 1.81 30 2.06 2.10 2.21 30 (>50%F) 2.79 2.71 2.90 25 (> 5oF) 3.09 3.04 3.18 30 (5so%F) 2.53 2.27 2.68 25 (< 0%F) 2.86 2.56 3.02 RPTOOS 100 1.40 1.37 1.42 TBVOOS 60 1.59 1.60 1.68 FMOOS 50 1.71 50 1.77 1.72 1.81 30 2.06 2.10 2.21 30 (>5o%F) 2.79 2.71 2.90 25 (>50%F) 3.09 3.04 3.18 30 (5o0%F) 2.53 2.27 2.68 25 (55o%F) 2.86 2.56 3.02 Add 0.02 to the above MCPRp limits for SLO.

Browns Feroy Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 19 Table 2: MCPRp Limits for BOC to NEOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 30,755 MWd / MTU)

MICPRp Limit AICPRP Limit EOOS Power A10 GE13 GE14 Option

(% Rated)

In-100 1.37 1.34 1.39 Service 60 1.54 1.60 1.62 50 1.65 50 1.78 1.73 1.79 30 1.98 2.01 2.12 30 (>5o%F) 2.21 2.23 2.36 25 (>5o%F) 2.37 2.41 2.52 30 (S5o%F) 2.18 2.06 2.35 25 (Lf50%F) 2.33 2.21 2.52 RPTOOS 100 1.38 1.36 1.41 60 1.54 1.60 1.62 50 1.65 50 1.78 1.73 1.79 30 1.98 2.01 2.12 30 (>5o%F) 2.21 2.23 2.36 25 (>5o%F) 2.37 2.41 2.52 30 (S5o%F) 2.18 2.06 2.35 25 (s5o%F) 2.33 2.21 2.52 TBVOOS 100 1.41 1.37 1.42 60 1.57 1.60 1.66 50 1.67 50 1.78 1.73 1.79 30 2.01 2.04 2.14 30 (>s5oF) 2.73 2.65 2.82 25 (>5o%F) 3.02 2.96 3.09 30 (s5o%F) 2.47 2.22 2.61 25 (C5o%F) 2.78 2.50 2.94 RPTOOS 100 1.41 1.38 1.44 TBVOOS 60 1.57 1.60 1.66 50 1.67 50 1.78 1.73 1.79 30 2.01 2.04 2.14 30 (>5o%F) 2.73 2.65 2.82 25 (>5o%F) 3.02 2.96 3.09 30 C~so%F) 2.47 2.22 2.61 25 <5o%:F) 2.78 2.50 2.94 EOOS Power A10 GE13 GE14 Option

(% Rated)

FMOOS 100 1.37 1.34 1.39 60 1.59 1.60 1.67 50 1.71 50 1.78 1.73 1.81 30 2.06 2.10 2.22 30 (>50%F) 2.30 2.31 2.45 25 (>5o%F) 2.48 2.51 2.64 30 (L5oF) 2.25 2.12 2.44 25 LCsoF) 2.43 2.30 2.63 RPTOOS 100 1.38 1.36 1.41 FHOOS 60 1.59 1.60 1.67 50 1.71 50 1.78 1.73 1.81 30 2.06 2.10 2.22 30 (>50%oF) 2.30 2.31 2.45 25 (>50%F) 2.48 2.51 2.64 30 (550%'F) 2.25 2.12 2.44 25 (550%F) 2.43 2.30 2.63 TBVOOS 100 1.41 1.37 1.43 FMOOS 60 1.61 1.60 1.70 50 1.73 50 1.78 1.73 1.83 30 2.09 2.12 2.23 30 (>50%F) 2.79 2.72 2.90 25 (>50%!')

3.09 3.04 3.18 30 (550%!F) 2.53 2.27 2.68 25 (Lo50%F) 2.86 2.56 3.02 RPTOOS 100 1.41 1.38 1.44 TBVOOS 60 1.61 1.60 1.70 FHOOS 50 1.73 50 1.78 1.73 1.83 30 2.09 2.12 2.23 30 (>50%!F) 2.79 2.72 2.90 25 (>50%F) 3.09 3.04 3.18 30 (550%!F) 2.53 2.27 2.68 25 (550%'F) 2.86 2.56 3.02 Add 0.02 to the above MCPRP limits for SLO.

Browns Ferry Nuldear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 20 Table 3: MCPRp Limits for BOC to EOC Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 32,798 MWd / MTU)

MCPRp Limit hlCPRP Limit EOOS Power A10 GE13 GE14 Option

(% Rated)

In-100 1.37 1.33 1.37 Service 60 1.52 1.60 1.60 50 1.63 50 1.77 1.72 1.78 30 1.96 2.00 2.10 30 (>50%F) 2.21 2.23 2.36 25 (>50%F) 2.37 2.41 2.52 30 (S5o%F) 2.18 2.06 2.35 25 (so5%F) 2.33 2.21 2.52 RPTOOS 100 1.38 1.35 1.39 60 1.52 1.60 1.60 50 1.63 50 1.77 1.72 1.78 30 1.96 2.00 2.10 30 (>50%F) 2.21 2.23 2.36 25 (>50%F) 2.37 2.41 2.52 30 (F5o%F) 2.18 2.06 2.35 25 (_so%F) 2.33 2.21 2.52 TBVOOS 100 1.40 1.36 1.41 60 1.55 1.60 1.63 50 1.65 50 1.77 1.72 1.78 30 1.99 2.02 2.12 30 (>50%F) 2.73 2.65 2.82 25 (>50%F) 3.02 2.96 3.09 30 ( so%F) 2.47 2.22 2.61 25 (_50%oF) 2.78 2.50 2.93 RPTOOS 100 1.41 1.37 1.42 TBVOOS 60 1.55 1.60 1.63 50 1.65 50 1.77 1.72 1.78 30 1.99 2.02 2.12 30 (>50%F) 2.73 2.65 2.82 25 (>50%F) 3.02 2.96 3.09 30 (5so%F) 2.47 2.22 2.61 25 (<5o%F) 2.78 2.50 2.93 EOOS Power A10 GE13 GE14 Option

(% Rated)

FMOOS 100 1.37 1.33 1.37 60 1.57 1.60 1.66 50 1.69 50 1.77 1.72 1.80 30 2.05 2.08 2.20 30 (>50%F) 2.30 2.31 2.45 25 (>50%F) 2.48 2.51 2.64 30 (s5o%F) 2.25 2.12 2.44 25 ( 5o%F) 2.43 2.30 2.63 RPTOOS 100 1.38 1.35 1.39 FMOOS 60 1.57 1.60 1.66 50 1.69 50 1.77 1.72 1.80 30 2.05 2.08 2.20 30 (>50%F) 2.30 2.31 2.45 25 (>50%F) 2.48 2.51 2.64 30 ( 50%F) 2.25 2.12 2.44 25 (S50%F) 2.43 2.30 2.63 TBVOOS 100 1.40 1.36 1.41 FMOOS 60 1.59 1.60 1.68 50 1.71 50 1.77 1.72 1.81 30 2.06 2.10 2.21 30 (>50%F) 2.79 2.71 2.90 25 (>50%!)

3.09 3.04 3.18 30 (C50%oF) 2.53 2.27 2.68 25 ( 50%F) 2.86 2.56 3.02 RPTOOS 100 1.41 1.37 1.42 TBVOOS 60 1.59 1.60 1.68 FMOOS 50 1.71 50 1.77 1.72 1.81 30 2.06 2.10 2.21 30 (>50%F) 2.79 2.71 2.90 25 (>50%F) 3.09 3.04 3.18 30 (<50%!F) 2.53 2.27 2.68 25 ( 50%oF) 2.86 2.56 3.02 Add 0.02 to the abovc MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 21 Table 4: MCPRp Limits for BOC to EOC Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 32,798 MWd / MTU)

NICPRp Limit AICPRp Limit EOOS Power A10 GE13 GE14 Option

(% Rated)

In-100 1.38 1.34 1.39 Service 60 1.54 1.60 1.62 50 1.65 50 1.78 1.73 1.79 30 1.98 2.01 2.12 30 (>50%F) 2.21 2.23 2.36 25 (>50%F) 2.37 2.41 2.52 30 (Sss0%F) 2.18 2.06 2.35 25 (<sO%F) 2.33 2.21 2.52 RPTOOS 100 1.41 1.39 1.41 60 1.54 1.60 1.62 50 1.65 50 1.78 1.73 1.79 30 1.98 2.01 2.12 30 (> 50s/F) 2.21 2.23 2.36 25 (>50%F) 2.37 2.41 2.52 30 (S50%F) 2.18 2.06 2.35 25 (55o%F) 2.33 2.21 2.52 TBVOOS 100 1.41 1.37 1.42 60 1.57 1.60 1.66 50 1.67 50 1.78 1.73 1.79 30 2.01 2.04 2.14 30 (>50%F) 2.73 2.65 2.82 25 (>5osF) 3.02 2.96 3.09 30 (Sso%w) 2.47 2.22 2.61 25 (@5o%F) 2.78 2.50 2.94 RPTOOS 100 1.45 1.42 1.44 TBVOOS 60 1.57 1.60 1.66 50 1.67 50 1.78 1.73 1.79 30 2.01 2.04 2.14 30 (>50%F) 2.73 2.65 2.82 25 (>so%F) 3.02 2.96 3.09 30 (<fi5o%F) 2.47 2.22 2.61 25 (S5oF) 2.78 2.50 2.94 EOOS Power A10 GE13 GE14 Option

(% Rated)

FHOOS 100 1.38 1.34 1.39 60 1.59 1.60 1.67 50 1.71 50 1.78 1.73 1.81 30 2.06 2.10 2.22 30 (>50%F) 2.30 2.31 2.45 25 (>50%F) 2.48 2.51 2.64 30 (s5o%F) 2.25 2.12 2.44 25 (55o%F) 2.43 2.30 2.63 RPTOOS 100 1.41 1.39 1.41 FHOOS 60 1.59 1.60 1.67 50 1.71 50 1.78 1.73 1.81 30 2.06 2.10 2.22 30 (>5o%F) 2.30 2.31 2.45 25 (> 50%F) 2.48 2.51 2.64 30 (<so%F) 2.25 2.12 2.44 25 ( so%F) 2.43 2.30 2.63 TBVOOS 100 1.41 1.37 1.43 FMOOS 60 1.61 1.60 1.70 50 1.73 50 1.78 1.73 1.83 30 2.09 2.12 2.23 30 (> 5oF) 2.79 2.72 2.90 25 (> 5o%F) 3.09 3.04 3.18 30 (<so%F) 2.53 2.27 2.68 25 (<50%F) 2.86 2.56 3.02 RPTOOS 100 1.45 1.42 1.44 TBVOOS 60 1.61 1.60 1.70 FHOOS 50 1.73 50 1.78 1.73 1.83 30 2.09 2.12 2.23 30 (>so'%F) 2.79 2.72 2.90 25 (> 5o%F) 3.09 3.04 3.18 30 ( so%F) 2.53 2.27 2.68 25 ( 5o%F) 2.86 2.56 3.02 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 22 Table 5: MCPRp Limits for BOC to CD Exposures - NSS Scram Times (Applicable up to Core Average Exposure of 33,871 MWd / MTU)

All Values Include FFTRPFHOOS and Bound Heaters In-Service

[

MCPR, Limit EOOS Power A10 GE13 GE14 Option

(% Rated)

In-100 1.37 1.33 1.37 Senrice 60 1.57 1.60 1.66 50 1.69 50 1.77 1.72 1.80 30 2.05 2.08 2.20 30 (>5o%F) 2.30 2.31 2.45 25 (>50%F) 2.48 2.51 2.64 30 (S5o%F) 2.25 2.12 2.44 25 (5so%F) 2.43 2.30 2.63 RPTOOS 100 1.38 1.35 1.39 60 1.57 1.60 1.66 50 1.69 50 1.77 1.72 1.80 30 2.05 2.08 2.20 30 (>5o%F) 2.30 2.31 2.45 25 (>50%F) 2.48 2.51 2.64 30 (S5oF) 2.25 2.12 2.44 25 (S5o%F) 2.43 2.30 2.63 TBNVOOS 100 1.40 1.37 1.41 60 1.59 1.60 1.68 50 1.71 50 1.77 1.72 1.81 30 2.06 2.10 2.21 30 (>50%F) 2.79 2.71 2.90 25 (>so%F) 3.09 3.04 3.18 30 (S5o%F) 2.53 2.27 2.68 25 (so5%F) 2.86 2.56 3.02 RPTOOS 100 1.41 1.39 1.43 TBAVOOS 60 1.59 1.60 1.68 50 1.71 50 1.77 1.72 1.81 30 2.06 2.10 2.21 30 (>so%F) 2.79 2.71 2.90 25 (>so%F) 3.09 3.04 3.18 30 (ffi5oF) 2.53 2.27 2.68 25 (S5o%F) 2.86 2.56 3.02 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 23 Table 6: MCPRp Limits for BOC to CD Exposures - TSSS Scram Times (Applicable up to Core Average Exposure of 33,871 MWd / MTU)

All Values Include FFTR/FHOOS and Bound Heaters In-Service

[

MCPRp Limit I

EOOS Power A10 GE13 GE14 Option

(% Rated)

In-100 1.38 1.34 1.39 Service 60 1.59 1.60 1.67 50 1.71 50 1.78 1.73 1.81 30 2.06 2.10 2.22 30 (>5o%F) 2.30 2.31 2.45 25 (>5o%F) 2.48 2.51 2.64 30 (<5oF) 2.25 2.12 2.44 25 (<5oF) 2.43 2.30 2.63 RPTOOS 100 1.41 1.39 1.41 60 1.59 1.60 1.67 50 1.71 50 1.78 1.73 1.81 30 2.06 2.10 2.22 30 (>5o%F) 2.30 2.31 2.45 25 (>5s0%F) 2.48 2.51 2.64 30 (s50%F) 2.25 2.12 2.44 25 (<5oF) 2.43 2.30 2.63 TBVOOS 100 1.41 1.37 1.43 60 1.61 1.60 1.70 50 1.73 50 1.78 1.73 1.83 30 2.09 2.12 2.23 30 (>5o%F) 2.79 2.72 2.90 25 (>5o%)

3.09 3.04 3.18 30 (<5oF) 2.53 2.27 2.68 25 (<5oF) 2.86 2.56 3.02 RPTOOS 100 1.47 1.45 1.47 TBVOOS 60 1.61 1.60 1.70 50 1.73 50 1.78 1.73 1.83 30 2.09 2.12 2.23 30 (>5o%F) 2.79 2.72 2.90 25 (>5o%F) 3.09 3.04 3.18 30 (<5o%F) 2.53 2.27 2.68 25 (_s oF) 2.86 2.56 3.02 Add 0.02 to the above MCPRp limits for SLO.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 24 Figure 1 APLHGR Limits for Bundle Type GE13-P9DTB391-13GZ (GE13 EDB# 2430) 15.00 14.00 13.00 12.00 11.00oo 10.00 9

9.00 8.00 w

7.00 6.00 5.00 4.00 3.00 2.00 1.00 0.00

_____II__I UNPACCPTB OPERA.Ti oNj I

I I

I j1 I

I I

[-ACCEPTABLE OPERATIONL-

., I I I I.L I........,,.......

.I... I I ~... I.! 1...I I I L.,,, I I, '

0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (GWDIMTU)

Most Linltng Lattice for Each Exposure Poht Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Unit Exposure Limit (GWDIMTU)

(kwlft)

(GWDIMTU)

(kwlft)

(GWDIMTU)

(kwlft) 0.00 10.75 7.72 11.45 27.56 10.79.

0.22 2 10.80 8.82 11.55 33.07 10Q24 1.10 10.87 9.2 11.66 38.58 9.85 2.20 10.96

11. 2 11.77 44.09 9A9 3.31 11.06 13.78 11.71 49.60 9.15 4.41 1.15 16.53 11.63 55.12 8.78

.51 1125 9.29 _

1155 60.63 8A5 6.61 11.35 22.05 11.39 63.74 827 These values applyto bothTurbine Bypass In-Servlce and Out-Of ServIce.

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

These llmltsarefordual recirculation loop operation. Single Loop Operation (SLO)adJustments are performed as described In Section 2 Browns Ferty Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 25 Figure 2 APLHGR Limits for Bundle Type GE13-P9DTB412-2G7.0/11G5.0 (GE13 EDB# 2431) 15.00 14.00 13.00 12.00 11.00 10.00 9.00 8.00 7.00 6.00 5.00 I

I E

03i

'1' i

.t 1-I-

IACCFPTARI F O)PFRATIOcN1

_ I II I_

'I.uu 3.00-2.0 0 -

_ I

_ I _ _ _ _ I 0.00 1Q00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure(GWDIMTU)

Most Limiting Lattice for Each Exposure Poht Average Planar ILHGR Average Planar LHGR Average Planar ILHGR Exposure Limit Exposure l

Umit Exposure Limit (GWD/MTU)

(kwlft)

(GWDIMTU)

(kwlft)

(GWDIMTU)

(khv/ft)

I0.00 103

.211.58 27.56 11.12 0.22 10.5 8.82 11.73 33.07 1Q78 1.10 10.57 9.92 11.86 38.58 10.46 I

2.20 102 1 10 2 12.00 44.09 10Q01 3.31 10.88 13.78 12.03 49.60 9A9 4.41 11.05-l 16.53 11.96 55.12 9.04 5.51 11 22_

19.29 11.80 l

80.3 8.66 6.61 11.40 22.05 11.59 63.92 l8.5 These values applyto bothTurbine Bypass In-Service and Out-Of-Service.

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

These limitsarefordual recirculation loop operation Single Loop Operation (SLO)adjustmerts are performed as described In Section 2 Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Rcvision 0, Page 26 Figure 3 APLHGR Limits for Bundle Type GE14-PIODNAB416-16GZ (GE14 EDB#2600) 14.00 13.00 12.00 11.00oo 10.00 9.00 f

8.00 l

7.00 0

6.00 C.

5.00 4.00 3.00 2.00 1.00 I2UACCPTABLE OPE 141

_f I

AI O ACCETEABLE OPERN

, ',=,,

- I I I i I I I - I I I I I I..

,:=

L

.... :, -..... ' I..,,

0.00 o

0.coo 10.00 20.00 30.00 40.00 50.00 6Q00 Awrage Planar Exposure (GWDIMTU)

Most Liniting Lattice for Eadc Exposure Poht Average Planar UiGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure Limit (GWD/MTU)

(kw/ft)

(GWDIMTU)

(kwlft)

(GWDIMTFT)

(kiv/ft) 0.00 9.41 8.82 10.56 22.05 10.85 0.22 9.51 9.92 10.65 27.56 1050

............~............................

d Y...........................

1.10 9.61 I11 G

10.74 33.07 10.10

..................~d........................... §~............................ i............................................................................ :............................ : -i................

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

4.41 10.00 14.33 10.86 49.60 8.57 5.51 10.1i4 15.43 io 1.88 55.12 8.02 6.61 1028 16.53 10.91 60.63 624

.'2

'.42 i8'. 74 1'0'94

6' 3.50 4.93 These values applyto both Turbine Bypass In-Service and Out-Of-ServIce.

These values applyto both Recirculatlon Pump Trip In-Service and Out-Of-Service.

These limits are for dual recirculation loop operation. Single Loop Operation (S LO) adjustments are performed as described In Section 2 Brownts Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 27 Figure 4 APLHGR Limits for Bundle Type GE14-PIODNAB416-16GZ (GE14 EDB#2601) 14.00 13.00 12.00 11.00 10.00 9.00 3

8.00 C-E 7.00 6.00 0.

5.00 4.00 3.00 2.00 1.00 J--]PUACCEPTBLE OP 0.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Aerage Planar Exposure (GWDIMTU)

Most LUithg Lattice for Eadc Exposure Poht Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Unit Exposure Limit (GWDtMTU)

(kwfft)

(GWDtMTU)

(kwfft)

(GWDIMTU)

(kwlft) 0.00 9.43 8.82 10.76 22.05 10.88 0.22 9.47 9.92 10.83 27.56 10.50 1.10 9.54 11.c2 10.91 33.07 1Q10 2.20 9.67 12.13 10.99 38.58 9.66 3.31 9.83 13.23 11.03 44.09 9.13

........... id........................................................................................................................................................................

4.41 10.02 14.33 11.02 49.60 8.59 5.51 1021 15.43 11.02 55.12 8.03 6.61 10A3 16.53 11.03 60.63 6.38

'''''''t72'''''''''''''

'62'"'................ 8 7.4''''''''''.'---

0'2'''

682.............

4'.M.......

These values applyto both Turbine Bypass In-Service and Out-Of-Service.

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

These limits are for dual recirculation loop operatlon. Single Loop Operation (S LO) adjustments are performed as described In Section 2 Browns Ferr Nutclear Plant Unit 2 Qcle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 28 Figure 5 APLHGR Limits for Bundle Type GE14-PIODNAB367-14GZ (GE14 EDB# 2602) 12.00 -

NACCEPT ABLEOPERAMON1-11.00 -

onnn _

E

3 i.

8.00 7.00 6.00 5.00 4.00 3.00 2.00 1.00 I __

I

-1ACPTPBLE OPERATION_ ihii:

0.00 4 0.c00 10.00 20.00 30.00 40.00 50.00 60.00 Average Planar Exposure (GWDIMTU)

Most Lmliting Lattice for Each Exposure Poht Average Planar L-iGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Uimt Exposure Limit (GWDIMTU)

(kwtft)

(GWDIMTU)

(kwft)

(GWD/MTU)

(kwvft)

).00 9.80 8.82 10.99 22.05 1Q94 0.22 9.86 9.92 11.14 27.56 10.38

................ i... 6..............................

................ i.............................

............... f.&...................................

1.10 9.96 11.t2 1129 33.07 9.83 2.20 10.09 12 13

_ h S

8. 8 2

3.31 1024 13.23 1154 44.09 8.76

........................ I..

...,4.41 10.40 114.S3 11.53 49.60 823 5.51 10.56 15.43 1149 55.12 7.67 6.61 10.71 16.53 11.3 60.63 5.66 772

10. 8'5

6256

. ' 479 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 recirculatlon loop operaton. Single Loop Operation (SLO) adjustments are performed as described In Section 2 Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 29 Figure 6 APLHGR Limits for Bundle Type GE14-PIODNAB416-18GZ (GE14 EDB# 2627) 14.00 13.00 12.00 11.00 10.00 9.00 8.00 h 7.00 f

6.00 5.

< 5.00 4.00 3.00 2.00 1.00 0.00.

0.00 10.00 20.00 3Qoo 40.00 50.00 60.00 Average Planar Exposure (GWDIMTU)

Most Limiting Lattice for Eadc Exposure Poht Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Unit Exposure Limit (GWDIMTU)

(kwlft)

(GWD/IMTU)

(kwlft)

(GWDYMTU)

(kwlft) 0.0p0 9.26 8

82 10.54 22.05 10.85 0.22 9.34 9.92 10.65 2756 1049

....................... 6.......................................................... T................................. T..................

.......................................................... l 1.10 9.47 11.G2 10.75 33.07 10.09

........................... T.6.........

........ I..................

...................... 6....................................

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

.......................................................................... I..................................................................................................

5.51 10.09 15.43 10.88 55.12 8.01 6.61 1025 16.53 10.91 60.63 621

' ' ' 7'72'.-''''''

4 '

81'74

' ' 41'0'93

.'.'.' 6'3.42

'4.'93

These values applyto both Turbine Bypass In-Service and OutiOf-Service.

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

These limits are for dual recirculatlon loop operation. Single Loop Operation (SLO) adjustments are performed as described In Section 2 Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 30 Figure 7 APLHGR Limits for Bundle Type GE14-PlODNAB417-18GZ (GE14 EDB# 2628) 14.00 13.00 12.00 11.00 10.00 I

.E a.

9.00 8.00 7.00 6.00 5.00 4.00 3.00 2.00 1.00 o.oo 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Awrage Planar Exposure (GWD/MTU)

Most Limiting Lattice for Each Exposure Poht Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Unit Exposure Limit (GWD/MTU)

(kw/ft)

(GWDIMTU)

(kw/ft)

(GWD/MTU)

(k.vlft) 0.00 9.39 8.82 10.74 22.05 1Q88

0. 22..,,94,,,,,,,,,,,,,
9.

9 2,

92 10.83

27. 56 10.50 1i. iO 10 9.50 9
0...........

11.......

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 i................I..........

6

....................................................... i...............................................................................

4.41 9.99 14.33 11.02 49.60 8.58

..................:.....................................,,,...................I..

......-.................................................. i. 24

.6 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'*'

...................O 6-4--

.............. 8' 7' '''''

5'5

''"6'3' These values applyto both Turbine Bypass In-Service and Out-Of-Service.

These values applyto both Recirculatlon Pump Trip ln-Service and Out-Of-Service.

These limits are fordual recirculatlon loop operation. Single Loop Operation (SLO) adjustments are performed as described In Section 2 Browns Ferry Nuclear Plant Unit 2 Gdcle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 31 Figure 8 APLHGR Limits for A1O-3920B-14GV70 (A10) 1 3 w II I

I I

I I

lll t

12.00 l UNACCEPTABLE OPERA-i ONl 11.1 Ao

.E 0~

10.1 9.1 8.1 7.1 6.1 5.1 20 20 20 20

=FAEPTABLE OPERAMON 00 -

20 20 20 20 I

4.1 3.1 2.1 i.E 0.1 0.00 10.00 20.00 30.00 40.00 Avorage Planar Exposure(GWDlMTU) 50.00 60.00 Average Planar

.ULHGR Exposure

':Unit (GWDIIYTU)

(kwft) 0.00 12.50 15.00 12 50 These values applyto both Turbine Bypass in-Service and Out-Of-Service.

These values apply to both Recirculation PumpTrip In-Servi ce and Out-Of-Service.

These limits arefordual recirculation loop operatlon. Single Loop Operation (SLO)adjustmerts we performed as described In Section 2 Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 32 Figure 9 GE13 Power Dependent MAPLHGR Multiplier - MAPFAC(P)

NSSITSSS Insertion Times - All Exposures 1.1 I

0.9 0.8 C 0.7 IL G.

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 Powsr(% Ratd)

Turbine Bypass In-Service Turbine Bypass Out-OF-Service Core Power MAPFAC(P) 30 0.51 Core Flow> 50%/ rated 30 0.39 25 1

0.36 Core Flow< 50%/6 rated 30 l

OA3 Core Power MAPFAC(P)

C o ra e dF o) 50 a e 100 0Q91 30 0.51 Core Flow > 50% rated 30 1

0Q33 25 1

0.31 Core Flow < 50% rated 30 n37 25 0.34 25 l

OA2 MAPFAC(P) Is not dependent upon any Equipment Out.Of-Service except Turbine Bypass.

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 33 Figure 10 GE14 Power Dependent MAPLHGR Multiplier - MAPFAC(P)

NSS/TSSS Insertbn Tines-All Exposures 2C ItI Turb.ne Bypass In-%rvic (TBVIS) 0.9 0.7 -

urtbire Bypass Out-Of.Servko, (rBEO0S) 06 0.5 TavB:

<0or Row TBVS: 350%Core 4

TVOOS: < 50%Core TBVOOS: > 50% Core Flow 0.2 3--

25 33 35 40 45

5) 55 60 65 70 75 80 85 0s 95 100 Power (% Ratec Turbine Bypass In-Service Turbine Bypass Out-Of-Service Cor Pwsr MPFAC(P)

(% rated)lM F

()

100 1

30 0.55 Core Flow> 50°/ rated 30 1

.44 25 l

OA2 Core Flow< 5Wo/ rated 30 1

0.50 25 1

0.49 Core Power MAPFAC(P)

Co raedFo) 50 ae 100 0

5 96 30 0 Q54 Core Flow> S0% rated 30 1

0.39 25 1

0.37 Core Flow < 50% rated 30 1

0a43 25 1

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

Browns Ferry Nuclear Plant Unit 2 CQcle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 34 Figure 11 Flow Dependent MAPLHGR Factor - MAPFAC(F)

(GE13) 1.00 0.90

.0.80 M 0.70 0.60 0.50 MAX FLOW. 1025%

Iv__/_

MAX FLOW a 1 7%

F==

1

=

30 40 50 60 70 Core Flow rx. Rated) 80 90 100 Max Core Flow 102.5% Rated Core Flow MAPFAC(F)

(% rated) 30 0.55 80 1.00 102.5 1.00 Max Core Flow 107% Rated Core Flow MAPFAC(F)

(% rated) 30 0.52 85 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 102.50h maximum flow line Is used for operation up to 100% rated flow.

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

Browvns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclcar Fuel Core Operating Limits Report TVA-COLR-BF2Cl4 Revision 0, Page 35 Figure 12 Flow Dependent MAPLHGR Factor - MAPFAC(F)

(GE14) 1.00 0.90 0.

M 0.70 0.60 0.50 MAX FLOW.w1Z 7

MAX FLOW

  • 107%

30 40 50 60 70 Core Flow (r/ Rated) 80 90 100 Max Core Flow 102.5% Rated Core Rlow MAPFAC(F)

(% rated) 30 0.55 78 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 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 upto 105% rated flow (ICF).

Browns Ferry Ntclear Plant Unit 2 Cycle 14

TVA Nuclcar Fuel Core Operating Limits Report TVA-COLR-BF2Cl4 Revision 0, Page 36 Figure 13 LHGR Limits for all ATRIUM-10 Fuel (Al O) 14.00 13.00 12.00 11.00 10.00 9.00 E

3, L

8.00 7.00 6.00 5.00

__=____,ULNACCEPTABLE OPERAllON

... jACCEPrABLE O P 4.00 3.00 2.00 1.00 000 0.00 10.00 20.00 30.00 40.00 Pellet Exposure (GWDIMTU) 50.00 60.00 70.00 PeIlet LHGR Exposure Unit (GWDIMTU)

(kwlft) 0.00 13.40

.90 13.40.

74.40 7.10 These values applyto both Turbine Bypass In-Service and Out-Of-Service.

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

These limitsapplyto both Two Loop Operation (TLO)and Single Loop Operation (SLOB Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclcar Fuel Corc Operating Limits Rcport TVA-COLR-BF2CI4 Rcvision 0, Page 37 Figure 14 A10 Power Dependent LHGR Multiplier - LIIGRFAC(P)

NSSITSSS Insertion Times-All Exposures 1.00 Turbine lvpas In-Servlo (TOiS) 0.90 0.80 _

0.70 -

0.70 lTurbine Bypas COut-t -Seri c(TSVO S) 060T8V0S 1 -CwFl ow 060.

V1"S 5 % Cr 1

U U<

I' 0.50 0.40 0.30 TBVOOS:

50#%Core I

I

.11

'T8VOOS: >50%Cor*Fl m

1. -...1. I - I.....

I I..

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 l H GRFAC(P)

_100 l

1.00 30 0.69 Core Flow > 501/6 rated 30 1

0.58 25 1

0.54 Core Flow: 5 0'/6 rated 30 1

0.61 25 1

0.58

(%/ rated) l F

100 1.00-30 0

Q69 lCore Flow> S0% rated 1 30 1

0.49 25 1

0.44 lCore Flow < S0% rated 30 1

0.58 25 1

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

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 38 Figure 15 Flow Dependent LHGR Multiplier -LHGRFAC(13)

(AIO Fuel) 1.00 0.95 0 0.90 CD 0.85 0.80 30 40 50 60 70 80 90 10i Core Flow (%/ Rated)

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

(% rated) 30 0.84 55 1.00 102.5 1.00 Max Core Flow 107% Rated CoreFlow 1LHGRFAC(

(% rated)

(

30 0.82 60 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 102.50/h maximum flow line is used for operation up to 100% rated flow.

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

Browns Ferry Nuclear Plant Unit 2 Chicle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C14 Revision 0, Page 39 Figure 16 Flow Dependent MCPR Limit MCPR(F)

(GE13 Fuel) 1.78 1.73 1.68 1.63 1.58 1.53

'r 1.48 n

1.43 1.38 1.33 1.28 1.23 1.18 MAX F LOW 1025%

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

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

(% rated) 30 1.73 88 121 102.5 121 Max Core Flow 107% Rated Core Flow MCPR(F)

(% rated) 30 1.77 88 121 107 121 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 102.50/% maximum flow line Is used for operation up to 100% rated flow.

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

Browns Ferry Nuclear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI4 Revision 0, Page 40 Figure 17 Flow Dependent MCPR Limit - MCPR(F)

(GE14 Fuel) 1.68 1.63 1.58 1.53 1.48 it 1.43 0.

E 1.38 1.33 1.28 1.23 1.18 MAX FLOW

  • 107%

_-4 MAX FLOW.1025%

I =

=

I

-t,--

111 30 40 50 60 70 Core Flow (K. Rated) 80 90 i0o Max Core Flow 102.5% Rated Core Flow MCPR(F)

(% rated) 30 1.63 88 121 102.5 121 Max Core Flow 107% Rated Core Flow MCPR(F)

(% rated) 30 1.65 88 121 107 121 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%/6 maximum flow line Is used for operation up to 100% rated flow.

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

Browns Ferry Nuldear Plant Unit 2 Cycle 14

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2Cl4 Revision 0, Page 41 Figure 18 Flow Dependent MCPR Limit - MCPR(F)

(AIO Fuel) 1.73 1.68 1.63 1.58 1.53 i

1.48 0.

c., 1.43 1.38 1.33 1.28 1.23 1.18

____1___1 F

7% -

MAX FLOW

  • 102.5%

1 1

1

, 1 1 1 1 ' '.

E1 -

I 30 40 50 60 70 Core Flow C/ Rated) 80 90 1ic Max Core Flow 102.5% Rated Core Flow MCPR(F)

(% rated) 30 1.66 88 121 102.5 121 Max Core Flow 107% Rated Core Flow MCPR(F)

(% rated) 30 1.71 88 121 107 121 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 102.55/ maximum flow line Is used for operation up to 100% rated flow.

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

Revision 0 (3/10/2005)

Initial Issue Revision 0 (3/10/2005)

Initial Issul Pages Affected: All

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