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NRC Regional Administrator  
NRC Regional Administrator  
-Region II NRC Senior Resident Inspector  
-Region II NRC Senior Resident Inspector  
-Watts Bar Nuclear Plant o: O /printed on recycled paper Enclosure Watts Bar Nuclear Plant, Unit 1 Cycle 11, Core Operating Limits Report Revision 0 QA Record L36 110420 801 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 11 CORE OPERATING LIMITS REPORT Revision 0 April 2011 Prepared by: Nuclear Fuel Date Reviewed by: t. 122 Manager, Nuclear el Engineering Date R Engineering IS  Approved by: / q .L,?, PORC Chairman Date Plant Manager Date Revision 0 Date of PORC Approval q.-,a,. tl PORC Meeting Number LA2ZZT: 4=Affected Pages all Reason for Revision initial issue Unit 1 Watts Bar Cycle 11 Revision 0 Page 1 of 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 11 has been prepared in accordance with the requirements of the Technical Specifications 5.9.5.The Technical Specifications affected by this report are listed below: 3.1.4 3.1.6 3.1.7 3.2.1 3.2.2 3.2.3 3.5.1 3.5.4 3.9.1 Moderator Temperature Coefficient (MTC)Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor (FQ(Z))Nuclear Enthalpy Rise Hot Channel Factor (FAHN)Axial Flux Difference (AFD)Accumulators Refueling Water Storage Tank (RWST)Boron Concentration 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections.
-Watts Bar Nuclear Plant o: O /printed on recycled paper Enclosure Watts Bar Nuclear Plant, Unit 1 Cycle 11, Core Operating Limits Report Revision 0 QA Record L36 110420 801 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 11 CORE OPERATING LIMITS REPORT Revision 0 April 2011 Prepared by: Nuclear Fuel Date Reviewed by: t. 122 Manager, Nuclear el Engineering Date R Engineering IS  Approved by: / q .L,?, PORC Chairman Date Plant Manager Date Revision 0 Date of PORC Approval q.-,a,. tl PORC Meeting Number LA2ZZT: 4=Affected Pages all Reason for Revision initial issue Unit 1 Watts Bar Cycle 11 Revision 0 Page 1 of 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 11 has been prepared in accordance with the requirements of the Technical Specifications 5.9.5.The Technical Specifications affected by this report are listed below: 3.1.4 3.1.6 3.1.7 3.2.1 3.2.2 3.2.3 3.5.1 3.5.4 3.9.1 Moderator Temperature Coefficient (MTC)Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor (FQ(Z))Nuclear Enthalpy Rise Hot Channel Factor (FAHN)Axial Flux Difference (AFD)Accumulators Refueling Water Storage Tank (RWST)Boron Concentration
These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5.The following abbreviations are used in this section: BOL ARO HZP EOL RTP Unit 1 WATTS BAR Beginning of Cycle Life All Rods Out Hot Zero Thermal Power End of Cycle Life Rated Thermal Power Cycle 11 Revision 0 Page 2 of 10 2.1 MODERATOR TEMPERATURE COEFFICIENT  
 
===2.0 OPERATING===
 
LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections.
These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5.The following abbreviations are used in this section: BOL ARO HZP EOL RTP Unit 1 WATTS BAR Beginning of Cycle Life All Rods Out Hot Zero Thermal Power End of Cycle Life Rated Thermal Power Cycle 11 Revision 0 Page 2 of 10  
 
===2.1 MODERATOR===
 
TEMPERATURE COEFFICIENT  
-MTC (LCO 3.1.4)2.1.1 The MTC limits are: The ARO/HZP -MTC shall be less positive than or equal to 0 Ak/k/0 F (upper limit).With the measured BOL/ARO/HZP  
-MTC (LCO 3.1.4)2.1.1 The MTC limits are: The ARO/HZP -MTC shall be less positive than or equal to 0 Ak/k/0 F (upper limit).With the measured BOL/ARO/HZP  
-MTC more positive than -2.04 x 10-' Ak/k/0 F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/k/0 F (upper limit) for all times in core life.The EOL/ARO/RTP  
-MTC more positive than -2.04 x 10-' Ak/k/0 F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/k/0 F (upper limit) for all times in core life.The EOL/ARO/RTP  
-MTC shall be less negative than or equal to-4.5 x 10-4 Ak/k/0 F (lower limit).2.1.2 The 300 ppm surveillance limit is: The measured 300 ppm /ARO/RTP-MTC should be less negative than or equal to-3.75 x 10-4 Ak/k/0 F.2.1.3 The 60 ppm surveillance limit is: The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to-4.28 x 10-4 Ak/k/0 F.2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6)2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.
-MTC shall be less negative than or equal to-4.5 x 10-4 Ak/k/0 F (lower limit).2.1.2 The 300 ppm surveillance limit is: The measured 300 ppm /ARO/RTP-MTC should be less negative than or equal to-3.75 x 10-4 Ak/k/0 F.2.1.3 The 60 ppm surveillance limit is: The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to-4.28 x 10-4 Ak/k/0 F.2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6)2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.
2.3 CONTROL BANK INSERTION LIMITS (LCO 3.1.7)2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.
 
===2.3 CONTROL===
BANK INSERTION LIMITS (LCO 3.1.7)2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.
Unit 1 WATTS BAR Cycle 11 Revision 0 Page 3 of 10 2.3.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.Park Position (steps)225 226 227 228 229 230 231 Bank Overlap (steps)109 110 111 112 113 114 115 Bank Difference(steps) 116 116 116 116 116 116 116 2.4 HEAT FLUX HOT CHANNEL FACTOR -FQ(Z) (LCO 3.2.1)FQ(Z) < [CFQ/ P]
Unit 1 WATTS BAR Cycle 11 Revision 0 Page 3 of 10 2.3.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.Park Position (steps)225 226 227 228 229 230 231 Bank Overlap (steps)109 110 111 112 113 114 115 Bank Difference(steps) 116 116 116 116 116 116 116 2.4 HEAT FLUX HOT CHANNEL FACTOR -FQ(Z) (LCO 3.2.1)FQ(Z) < [CFQ/ P]
* K(Z)for P > 0.5 FQ(Z) _ [CFQ/ 0.5]
* K(Z)for P > 0.5 FQ(Z) _ [CFQ/ 0.5]
* K(Z) for P < 0.5 Where P = Thermal Power / Rated Thermal Power 2.4.1 CFQ = 2.50 2.4.2 K(Z) is provided in Figure 2.2.4.3 FQw(Z) = FQC(Z)
* K(Z) for P < 0.5 Where P = Thermal Power / Rated Thermal Power 2.4.1 CFQ = 2.50 2.4.2 K(Z) is provided in Figure 2.2.4.3 FQw(Z) = FQC(Z)
* W(Z)/P for P > 0.5 FQw(Z) = FQC(Z)
* W(Z)/P for P > 0.5 FQw(Z) = FQC(Z)
* W(Z)/0.5 for P < 0.5 where: W(Z) values are provided in Table A. 1. The table provides sufficient information to determine W(Z) versus core height for all cycle burnups.2.4.4 FQW(Z) Penalty Factor The FQW(Z) penalty factor is provided in Table A.2.Cycle 11 Pane 4 of 10 Revision 0 Unit 1 WATTS BAIR 2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR -FAHIN (LCO 3.2.2)FAHN < FAHRTP * ( 1 + PF * (l-P))where P = Thermal Power / Rated Thermal Power FAHRTP = 1.65 for RFA-2 fuel, and PF =0.3 2.6 AXIAL FLUX DIFFERENCE  
* W(Z)/0.5 for P < 0.5 where: W(Z) values are provided in Table A. 1. The table provides sufficient information to determine W(Z) versus core height for all cycle burnups.2.4.4 FQW(Z) Penalty Factor The FQW(Z) penalty factor is provided in Table A.2.Cycle 11 Pane 4 of 10 Revision 0 Unit 1 WATTS BAIR  
 
===2.5 NUCLEAR===
ENTHALPY RISE HOT CHANNEL FACTOR -FAHIN (LCO 3.2.2)FAHN < FAHRTP * ( 1 + PF * (l-P))where P = Thermal Power / Rated Thermal Power FAHRTP = 1.65 for RFA-2 fuel, and PF =0.3 2.6 AXIAL FLUX DIFFERENCE  
-AFD (LCO 3.2.3)2.6.1 The AFD limits for Cycle 11 are provided in Figure 3.2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1)2.7.1 The refueling boron concentration shall be >_ 2000 ppm.2.8 ACCUMULATORS (LCO 3.5.1)2.8.1 There are 544 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 11.2.9 REFUELING WATER STORAGE TANK -RWST (LCO 3.5.4)2.9.1 There are 544 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 11.Unit I WATTS BAR Cycle 11 Revision 0 Page 5 of 10 225 150 --{- //z -- --_ -_ -_----- --125 --. .._o __ ... .0 CL 2 /5 o ..... ___- /5 (00, 64J /-*___(0.2 7,0) -... .. .0-0.0 0.2 0.4 0.6 0.8 1.0 FRACTIONAL OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of >_ 225 and _ 231 steps withdrawn.
-AFD (LCO 3.2.3)2.6.1 The AFD limits for Cycle 11 are provided in Figure 3.2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1)2.7.1 The refueling boron concentration shall be >_ 2000 ppm.2.8 ACCUMULATORS (LCO 3.5.1)2.8.1 There are 544 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 11.2.9 REFUELING WATER STORAGE TANK -RWST (LCO 3.5.4)2.9.1 There are 544 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 11.Unit I WATTS BAR Cycle 11 Revision 0 Page 5 of 10 225 150 --{- //z -- --_ -_ -_----- --125 --. .._o __ ... .0 CL 2 /5 o ..... ___- /5 (00, 64J /-*___(0.2 7,0) -... .. .0-0.0 0.2 0.4 0.6 0.8 1.0 FRACTIONAL OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of >_ 225 and _ 231 steps withdrawn.
Unit 1 Cycle 11 WATTS BAR Page 6 of 10 Revision 0 0 ILL cc~0 Z 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1-~ 4 4--4 1 4 4~-4 1 4 4-~-i 4.4 I 4 4.4 1 4 +-Core Height K(Z)0.000 1.000 6.000 1.000 12.000 0.9256 0 0 2 4 6 8 10 12 Core Height (feet)Figure 2 K(Z) -Normalized FQ(Z) as a Function of Core Height Unit I WATTS BAR Cycle 11 Revision 0 Page 7 of 10 120 -.... ..110 ....(-12, 100) 100)100_9 0 --A c c e p t a b le__ -Operation Una-cptabl 80 Unacceptable  
Unit 1 Cycle 11 WATTS BAR Page 6 of 10 Revision 0 0 ILL cc~0 Z 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1-~ 4 4--4 1 4 4~-4 1 4 4-~-i 4.4 I 4 4.4 1 4 +-Core Height K(Z)0.000 1.000 6.000 1.000 12.000 0.9256 0 0 2 4 6 8 10 12 Core Height (feet)Figure 2 K(Z) -Normalized FQ(Z) as a Function of Core Height Unit I WATTS BAR Cycle 11 Revision 0 Page 7 of 10 120 -.... ..110 ....(-12, 100) 100)100_9 0 --A c c e p t a b le__ -Operation Una-cptabl 80 Unacceptable  

Revision as of 21:14, 13 October 2018

Watts Bar Nuclear Plant, Unit 1, Cycle 11, Core Operating Limits Report
ML11137A120
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 05/12/2011
From: Krich R M
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11137A120 (12)
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{{#Wiki_filter:Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing May 12, 2011 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

Watts Bar Nuclear Plant, Unit 1, Cycle 11, Core Operating Limits Report The purpose of this letter is to submit the Watts Bar Nuclear Plant (WBN), Unit 1, Cycle 11, Core Operating Limits Report (COLR), Revision 0, as required by WBN Technical Specification (TS) 5.9.5.d. TS 5.9.5.d states: "The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC." To fulfill this requirement, the Tennessee Valley Authority is submitting the COLR prior to the startup of WBN for Cycle 11 operation. If you have any questions about this report, please contact Kara Stacy at (423) 751-3489.Respectfully,~ ,, R. M. Krich

Enclosure:

Watts Bar Nuclear Plant, Unit 1, Cycle 11, Core Operating Limits Report, Revision 0 cc: (Enclosure) NRC Regional Administrator -Region II NRC Senior Resident Inspector -Watts Bar Nuclear Plant o: O /printed on recycled paper Enclosure Watts Bar Nuclear Plant, Unit 1 Cycle 11, Core Operating Limits Report Revision 0 QA Record L36 110420 801 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 11 CORE OPERATING LIMITS REPORT Revision 0 April 2011 Prepared by: Nuclear Fuel Date Reviewed by: t. 122 Manager, Nuclear el Engineering Date R Engineering IS Approved by: / q .L,?, PORC Chairman Date Plant Manager Date Revision 0 Date of PORC Approval q.-,a,. tl PORC Meeting Number LA2ZZT: 4=Affected Pages all Reason for Revision initial issue Unit 1 Watts Bar Cycle 11 Revision 0 Page 1 of 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 11 has been prepared in accordance with the requirements of the Technical Specifications 5.9.5.The Technical Specifications affected by this report are listed below: 3.1.4 3.1.6 3.1.7 3.2.1 3.2.2 3.2.3 3.5.1 3.5.4 3.9.1 Moderator Temperature Coefficient (MTC)Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor (FQ(Z))Nuclear Enthalpy Rise Hot Channel Factor (FAHN)Axial Flux Difference (AFD)Accumulators Refueling Water Storage Tank (RWST)Boron Concentration

2.0 OPERATING

LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5.The following abbreviations are used in this section: BOL ARO HZP EOL RTP Unit 1 WATTS BAR Beginning of Cycle Life All Rods Out Hot Zero Thermal Power End of Cycle Life Rated Thermal Power Cycle 11 Revision 0 Page 2 of 10

2.1 MODERATOR

TEMPERATURE COEFFICIENT -MTC (LCO 3.1.4)2.1.1 The MTC limits are: The ARO/HZP -MTC shall be less positive than or equal to 0 Ak/k/0 F (upper limit).With the measured BOL/ARO/HZP -MTC more positive than -2.04 x 10-' Ak/k/0 F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/k/0 F (upper limit) for all times in core life.The EOL/ARO/RTP -MTC shall be less negative than or equal to-4.5 x 10-4 Ak/k/0 F (lower limit).2.1.2 The 300 ppm surveillance limit is: The measured 300 ppm /ARO/RTP-MTC should be less negative than or equal to-3.75 x 10-4 Ak/k/0 F.2.1.3 The 60 ppm surveillance limit is: The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to-4.28 x 10-4 Ak/k/0 F.2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6)2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.

2.3 CONTROL

BANK INSERTION LIMITS (LCO 3.1.7)2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion. Unit 1 WATTS BAR Cycle 11 Revision 0 Page 3 of 10 2.3.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.Park Position (steps)225 226 227 228 229 230 231 Bank Overlap (steps)109 110 111 112 113 114 115 Bank Difference(steps) 116 116 116 116 116 116 116 2.4 HEAT FLUX HOT CHANNEL FACTOR -FQ(Z) (LCO 3.2.1)FQ(Z) < [CFQ/ P]

  • K(Z)for P > 0.5 FQ(Z) _ [CFQ/ 0.5]
  • K(Z) for P < 0.5 Where P = Thermal Power / Rated Thermal Power 2.4.1 CFQ = 2.50 2.4.2 K(Z) is provided in Figure 2.2.4.3 FQw(Z) = FQC(Z)
  • W(Z)/P for P > 0.5 FQw(Z) = FQC(Z)
  • W(Z)/0.5 for P < 0.5 where: W(Z) values are provided in Table A. 1. The table provides sufficient information to determine W(Z) versus core height for all cycle burnups.2.4.4 FQW(Z) Penalty Factor The FQW(Z) penalty factor is provided in Table A.2.Cycle 11 Pane 4 of 10 Revision 0 Unit 1 WATTS BAIR

2.5 NUCLEAR

ENTHALPY RISE HOT CHANNEL FACTOR -FAHIN (LCO 3.2.2)FAHN < FAHRTP * ( 1 + PF * (l-P))where P = Thermal Power / Rated Thermal Power FAHRTP = 1.65 for RFA-2 fuel, and PF =0.3 2.6 AXIAL FLUX DIFFERENCE -AFD (LCO 3.2.3)2.6.1 The AFD limits for Cycle 11 are provided in Figure 3.2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1)2.7.1 The refueling boron concentration shall be >_ 2000 ppm.2.8 ACCUMULATORS (LCO 3.5.1)2.8.1 There are 544 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 11.2.9 REFUELING WATER STORAGE TANK -RWST (LCO 3.5.4)2.9.1 There are 544 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 11.Unit I WATTS BAR Cycle 11 Revision 0 Page 5 of 10 225 150 --{- //z -- --_ -_ -_----- --125 --. .._o __ ... .0 CL 2 /5 o ..... ___- /5 (00, 64J /-*___(0.2 7,0) -... .. .0-0.0 0.2 0.4 0.6 0.8 1.0 FRACTIONAL OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of >_ 225 and _ 231 steps withdrawn. Unit 1 Cycle 11 WATTS BAR Page 6 of 10 Revision 0 0 ILL cc~0 Z 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1-~ 4 4--4 1 4 4~-4 1 4 4-~-i 4.4 I 4 4.4 1 4 +-Core Height K(Z)0.000 1.000 6.000 1.000 12.000 0.9256 0 0 2 4 6 8 10 12 Core Height (feet)Figure 2 K(Z) -Normalized FQ(Z) as a Function of Core Height Unit I WATTS BAR Cycle 11 Revision 0 Page 7 of 10 120 -.... ..110 ....(-12, 100) 100)100_9 0 --A c c e p t a b le__ -Operation Una-cptabl 80 Unacceptable -- Unacceptable Operation Operation 70 -.. ....... .0 of 0 60 .... .. ...a30 t-(-28, 50)(2 ,5 : "0 30 ..... ...10-50 30 10 0 10 20 30 40 Flux Difference (Al) %Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (I Unit 1 Cycle 11 WATTS BAR Page 8 of 10 Revision 0 50 tAOC)v Table A.1 F 0 w(Z) = F C(Z)

  • W(Z)Max W(z) at Max W(z) at Max W(z) at Max W(z) at Max W(z) at 150 MWD/MTU 150 MWD/MTU 150 MWD/MTU Max W(z) at 2000 10000 16000 Height (ft) (30% Power) (75% Power) (100% Power) MWD/MTU MWD/MTU MWD/MTU 12.0760 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8750 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.6730 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.4720 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.2710 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.0700 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10.8680 1.4838 1.4728 1.3056 1.3898 1.2075 1.2196 10.6670 1.4501 1.4433 1.3033 1.3808 1.1984 1.2109 10.4660 1.4152 1.4099 1.2983 1.3686 1.1908 1.1988 10.2650 1.3790 1.3757 1.2915 1.3544 1.1764 1.1853 10.0630 1.3425 1.3405 1.2837 1.3376 1.1649 1.1666 9.8620 1.3054 1.3062 1.2740 1.3221 1.1552 1.1575 9.6610 1.2715 1.2782 1.2659 1.3091 1.1486 1.1587 9.4600 1.2468 1.2607 1.2660 1.2965 1.1564 1.1601 9.2580 1.2328 1.2527 1.2730 1.2888 1.1601 1.1607 9.0570 1.2179 1.2439 1.2770 1.2797 1.1617 1.1646 8.8560 1.1992 1.2324 1.2760 1.2686 1.1638 1.1677 8.6540 1.1798 1.2239 1.2754 1.2627 1.1655 1.1713 8.4530 1.1633 1.2206 1.2783 1.2640 1.1682 1.1925 8.2520 1.1471 1.2148 1.2778 1.2635 1.1744 1.2114 8.0510 1.1317 1.2068 1.2744 1.2604 1.1807 1.2267 7.8490 1.1157 1.1966 1.2679 1.2557 1.1848 1.2404 7.6480 1.1006 1.1858 1.2612 1.2491 1.1881 1,2512 7.4470 1.0919 1.1804 1.2601 1.2407 1.1921 1.2593 7.2460 1.0833 1.1744 1.2567 1.2303 1.1957 1.2647 7.0440 1.0749 1.1683 1.2504 1.2206 1.1976 1.2675 6.8430 1.0674 1.1626 1.2428 1.2122 1.1977 1.2678 6.6420 1.0599 1.1557 1.2337 1.2033 1.1965 1.2659 6.4410 1.0524 1.1480 1.2229 1.1927 1.1937 1.2621 6.2390 1.0447 1.1390 1.2103 1.1804 1.1892 1.2559 6.0380 1.0369 1.1291 1.1966 1.1687 1.1839 1.2473 5.8370 1.0308 1.1201 1.1836 1.1580 1.1783 1.2366 5.6350 1.0278 1.1136 1.1729 1.1489 1.1725 1.2236 5.4340 1.0276 1.1092 1.1640 1.1434 1.1671 1.2088 5.2330 1.0302 1.1069 1.1571 1.1379 1.1633 1.1951 5.0320 1.0333 1.1049 1.1510 1.1318 1.1596 1.1901 4.8300 1.0368 1.1028 1.1450 1.1259 1.1579 1.1894 4.6290 1.0405 1.1005 1.1387 1.1203 1.1581 1.1857 4.4280 1.0435 1.0976 1.1314 1.1140 1.1590 1.1813 4.2270 1.0464 1.0944 1.1234 1.1070 1.1593 1.1758 4.0250 1.0485 1.0903 1.1147 1.0996 1.1588 1.1694 3,8240 1.0505 1.0859 1.1057 1.0919 1.1588 1.1624 3.6230 1.0517 1.0805 1.0958 1.0838 1.1616 1.1549 3.4220 1.0528 1.0748 1.0858 1.0755 1.1683 1.1470 3.2200 1.0627 1.0777 1.0846 1.0717 1.1747 1.1439 3.0190 1.0747 1.0824 1.0853 1.0746 1.1805 1.1484 2.8180 1.0908 1.0909 1.0895 1.0864 1.1918 1.1627 2.6160 1.1186 1.1103 1.1047 1.1021 1.2107 1.1787 2.4150 1.1497 1.1327 1.1229 1.1222 1.2315 1.1960 2.2140 1.1817 1.1550 1.1412 1.1425 1.2521 1.2129 2.0130 1.2141 1.1777 1.1596 1.1626 1.2720 1.2292 1.8110 1.2449 1.1996 1.1768 1.1826 1.2913 1.2450 1.6100 1.2772 1.2233 1.1953 1.2016 1.3093 1.2598 1.4090 1.3196 1.2550 1.2216 1.2192 1.3255 1.2730 1.2080 1.3634 1.2862 1.2471 1.2342 1.3387 1.2836 1.0060 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.8050 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.6040 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.4030 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2010 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.000 Unit 1 WATTS BAR Cycle 11 Revision 0 Page 9 of 10 Table A.2 FQW(Z) Penalty Factor Core Fvv(Z).................

1 urn-ulp .P nalty (MWD/MTU) Fator 603 1.0200 754 1.0207 905 1.0204 1057 1.0200 9065 1.0200 9216 1.0225 9367 1.0240 9518 1.0218 9669 1.0200 Note: 1. The Penalty Factor, which is applied to FQW(Z) for compliance with Surveillance Requirement 3.2.1.2.a, is the maximum factor by which FQW(Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the burnup at which the FQW(Z) was determined. Unit 1 WATTS BAR Cycle 11 Revision 0 Page 10 of 10}}

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