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Category:Fuel Cycle Reload Report
MONTHYEARWBL-23-055, of the Unit 2 Cycle 6 Core Operating Limits Report2023-11-22022 November 2023 of the Unit 2 Cycle 6 Core Operating Limits Report WBL-23-023, of Cycle 19 Core Operating Limit Report2023-04-27027 April 2023 of Cycle 19 Core Operating Limit Report WBL-23-008, Unit 1 Revision 1 of the Cycle 18 Core Operating Limits Report (COLR) and Units 2 Revision 1 of the Cycle 5 Core Operating Limits Report (COLR)2023-02-0707 February 2023 Unit 1 Revision 1 of the Cycle 18 Core Operating Limits Report (COLR) and Units 2 Revision 1 of the Cycle 5 Core Operating Limits Report (COLR) WBL-22-046, Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2)2022-09-0808 September 2022 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) WBL-22-028, of the Unit 2 Cycle 5 Core Operating Limits Report (COLR)2022-05-0404 May 2022 of the Unit 2 Cycle 5 Core Operating Limits Report (COLR) WBL-21-052, of the Unit 1 Cycle 18 Core Operating Limits Report (COLR)2021-11-0909 November 2021 of the Unit 1 Cycle 18 Core Operating Limits Report (COLR) WBL-21-013, of Cycle 4 Core Operating Limits Report2021-03-18018 March 2021 of Cycle 4 Core Operating Limits Report WBL-20-058, Plants, Units 1 and 2 - Revision 1 of the Unit 1 Cycle 17 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 4 Core Operating Limits Report (COLR)2020-11-0505 November 2020 Plants, Units 1 and 2 - Revision 1 of the Unit 1 Cycle 17 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 4 Core Operating Limits Report (COLR) WBL-20-036, of the Unit Cycle 2 Cycle 3 Core Operating Limits Report (COLR)2020-07-29029 July 2020 of the Unit Cycle 2 Cycle 3 Core Operating Limits Report (COLR) WBL-20-022, Unit 1 Revision 0 of the Cycle 17 Core Operating Limits Report (COLR)2020-05-20020 May 2020 Unit 1 Revision 0 of the Cycle 17 Core Operating Limits Report (COLR) L-19-029, Submittal of Revision 0 of Cycle 3 Core Operating Limits Report2019-04-24024 April 2019 Submittal of Revision 0 of Cycle 3 Core Operating Limits Report L-19-011, Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR)2019-01-29029 January 2019 Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR) ML18270A3522018-09-27027 September 2018 Revision 0 of the Cycle 16 Core Operating Limits Report (COLR) ML18232A1722018-08-20020 August 2018 Unit 1 Revision 1 of the Cycle 15 Core Operating Limits Report (COLR) and Unit 2 Revision 1 of the Cycle 2 Core Operating Limits Report (COLR) ML18145A1962018-05-24024 May 2018 Revision 0 of the Cycle 14 and 15 Core Operating Limits Report (COLR) ML17324B3832017-11-20020 November 2017 Revision 0 of the Unit 2 Cycle Core Operating Limits Report (COLR) ML17279A0782017-10-0606 October 2017 Revision 2 of the Cycle 1 Core Operating Limits Report (COLR) ML14141A0842014-05-20020 May 2014 Revision 0 of the Cycle 13 Core Operating Limits Report (COLR) ML12296A2532012-10-16016 October 2012 Revision 0 of the Cycle 12 Core Operating Limits Report (COLR) ML11137A1202011-05-12012 May 2011 Cycle 11, Core Operating Limits Report ML0929402442009-10-19019 October 2009 Revisions 2 and 3 to the Cycle 10 Core Operating Limits Report ML0913101682009-05-0606 May 2009 Core Operating Limits Report (COLR) for Cycle 9, Revision 1 ML0815107992008-05-27027 May 2008 First Revised NRC Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (Pwrs) - Nonvisual Nondestructive Examination Inspection Results ML0807302442008-03-12012 March 2008 Core Operating Limits Report (COLR) for Cycle 9, Revision 0 ML0702601632007-01-22022 January 2007 Core Operating Limits Report for Cycle 8, Revision 3 ML0633201822006-11-21021 November 2006 Core Operating Limits Report for Cycle 8, Revision 2 ML0623501652006-08-17017 August 2006 Core Operating Limits Report (COLR) for Cycle 7, Revision 6 ML0618404762006-06-29029 June 2006 Core Operating Limits Report for Cycle 7, Revision 6 ML0527001322005-09-22022 September 2005 Core Operating Limits Report (COLR) for Cycle 7, Revision 3 ML0518004462005-06-16016 June 2005 Core Operating Limits Report for Cycle 7, Revision 2 ML0510301732005-04-0101 April 2005 Core Operating Limits Report for Cycle 7, Revisions 0 and 1 ML0330304082003-10-27027 October 2003 Core Operating Limits Report for Cycle 6, Revisions 3 & 4 ML0231005762002-11-0101 November 2002 Steam Generator Inservice Inspection - Cycle 4 Twelve Month Report ML0208103922002-03-12012 March 2002 Core Operation Limits Report Cycle 5 Revision 0 2023-04-27
[Table view] Category:Letter
MONTHYEARIR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),”2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),” ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 2024-08-07
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Tennessee Valley Authority, Post Office Box 2000 , Spring C ity , Te nne ssee 3738 1-2 000 November 20, 20 1 7 ATTN: Document Contro l Desk U.S. Nuclear Regu l atory Com mi ss io n Washingto n, D.C. 20555-0001 Watts Bar Nuclear P l ant, Unit 2 Faci lity Operating License No. NPF-96 NRC Docket No. 50-391 10 CFR 50.4
Subject:
REVISION 0 OF THE UNIT 2 CYCLE 2 CORE OPERATING LIMITS REPORT (COLR) Pursuant to Watts Bar Nuclear P l ant Techn i cal Specificatio n s Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Rev i sion 0 of the Unit 2 Cyc l e 2 COLR. The ana lyti ca l methods used to determine the core operating limit s were prev iou s ly reviewed and approved by the NRC. There are no regu l atory comm itm ents contained i n th i s letter or the enc l osu r e. Should you have quest i ons r egard in g this submittal, please contact K im Hulvey at (423) 365-7720. Respectful ly, Paul S imm ons Site V i ce Pres id ent Watts Bar Nuc l ear Pla nt
Enclosure:
Watts Bar Nuc l ear P l ant, Unit 2, Cyc l e 2 Core Operating Limits Report Rev i s ion 0 November 2 01 7 U.S. Nuclear Regulatory Commission Page 2 November 20, 2017 cc (Enclosure):
NRC Regional Administrator
- Region II NRR Project Manager
- Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant
ENCLOSURE Watts Bar Nuclear Plant, Unit 2, Cycle 2 Core Operating Limits Report Revision 0 November 201 7 QA Record L36171016 801 WATTS BAR NUCLEAR PLANT, UNIT 2 , CYCLE 2 CORE OPERA TING LIMITS REPORT Revision 0 November 2017 Prepared by: W. Andrew Whitener.
Nuclear Fuel Programs & Oversight Reviewed by: Christine A. Setter. Manager:PWR\lel Engineering Approved by: c_' , Plant Manager Revision 0 Unit 2 Watts Bar Date of PORC Approval See above Affected Pages Reason for Revision All Initial issue Page 1 of 10 \ \ -(o ... 201 ::r Date .11/6/2011 I Date Date /l/)L/17 Date Date Cycle 2 Revision 0 Unit 2 Cycle 2 WATTS BAR Page 2 of 10 Revision 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 2 Cycle 2 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 Moderator Temperature Coefficient (MTC) 3.1.6 Shutdown Bank Insertion Limits 3.1.7 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (F Q (Z)) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH N) 3.2.3 Axial Flux Difference (AFD) 3.9.1 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 -- Beginning of Cycle Life ARO -- All Rods Out HZP -- Hot Zero Thermal Power EOL -- End of Cycle Life RTP -- Rated Thermal Power Unit 2 Cycle 2 WATTS BAR Page 3 of 10 Revision 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 k/k/ F (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -2.25 x 10
-5 k/k/ F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 k/k/F (upper limit) for all times in core life. The EOL/ARO/RTP - MTC shall be less negative than or equal to -4.50 x 10
-4 k/k/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 -3.65 x 10
-4 k/k/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 -4.18 x 10
-4 k/k/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 2 Cycle 2 WATTS BAR Page 4 of 10 Revision 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) Bank Overlap (steps) Bank Difference (steps) 225 109 116 226 110 116 227 111 116 228 112 116 229 113 116 230 114 116 231 115 116 2.4 HEAT FLUX HOT CHANNEL FACTOR - F Q(Z) (LCO 3.2.1)
F Q (Z) [CFQ / P]
- K(Z) for P > 0.5 F Q (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 F Q W(Z) = F Q c(Z)
- W(Z)/P for P > 0.5 F Q W(Z) = F Q c (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 Part power W(Z) values are only required to be used when the part power surveillance is performed using the fixed incore detector system. 2.4.5 F Q W(Z) Penalty Factor The F Q W(Z) penalty factor is provided in Table A.2.
Unit 2 Cycle 2 WATTS BAR Page 5 of 10 Revision 2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FH N (LCO 3.2.2)
FH N FH RTP * ( 1 + PF * ( 1-P)) where P = Thermal Power / Rated Thermal Power FH RTP = 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 2 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.
Unit 2 Cycle 2 WATTS BAR Page 6 of 10 Revision 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 positionwithin the interval of 225 and 231 steps withdrawn.
0 25 50 75100 125 150 175200225 2500.00.20.40.60.81.0 RODBANKSTEPPOSITION(STEPSWITHDRAWN)
FRACTIONOFRATEDTHERMALPOWER BANKA BANKB BANKC BANKD (0.197,225)(0.0,180)(0.703,225)(1.0,177)(0.0,64)(0.227,0)(ALLPOWERS,225)
Unit 2 Cycle 2 WATTS BAR Page 7 of 10 Revision Figure 2 K(Z) - Normalized F Q(Z) as a Function of Core Height 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.20123456789101112NormalizedF Q*PowerCoreHeight(feet)CoreHeightK(Z)0.0001.000 6.0001.000 12.0001.000 Unit 2 Cycle 2 WATTS BAR Page 8 of 10 Revision Figure 3 Axial Flux Difference Acceptable Operation Limits as a Function of Rated Thermal Power (RAOC)
Figure 3 Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC) 0 10 20 30 40 50 60 70 80 90100110 120-50-40-30-20-1001020304050Flux Difference (I) %% of Rated Thermal Powe r(7, 100)(-12, 100)(-28, 50)Unacceptable OperationAcceptable Operation(21, 50)Unacceptable Operation Unit 2 Cycle 2 WATTS BAR Page 9 of 10 Revision Table A.1 RAOC W(Z) Surveillance Factors Height (ft) Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) at 150 at 150 at 150 at 2000 at 6000 at 10000 at 14000 at 16000 MWD/MTU MWD/MTU MWD/
MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU (30% Power) (75% Power) (100% Po wer) (100% Power) (100% Power) (100% Power) (100% Power) (100% Power) 12.0720 1.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 011.8708 1.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 011.6696 1.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 011.4684 1.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 011.2672 1.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 011.0660 1.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 010.8648 1.408 4 1.457 3 1.328 61.323 5 1.327 5 1.182 01.157 4 1.153 110.6636 1.388 6 1.428 7 1.322 11.318 5 1.312 7 1.177 31.152 6 1.148 710.4624 1.362 6 1.390 6 1.315 01.316 6 1.289 7 1.171 81.146 9 1.143 510.2612 1.341 9 1.363 3 1.306 01.311 4 1.266 2 1.165 11.140 5 1.137 810.0600 1.317 1 1.331 0 1.295 21.303 2 1.259 4 1.157 41.133 2 1.136 39.858 81.293 4 1.301 4 1.287 91.294 1 1.231 8 1.149 51.125 5 1.134 09.657 61.277 4 1.287 6 1.282 21.284 3 1.223 0 1.141 71.117 3 1.131 19.456 41.252 9 1.263 6 1.274 61.272 8 1.222 9 1.138 71.118 0 1.129 29.255 21.225 4 1.234 4 1.265 31.259 9 1.221 3 1.145 61.126 4 1.138 69.054 01.201 9 1.208 5 1.258 61.250 7 1.218 8 1.150 81.137 0 1.146 58.852 81.186 6 1.213 3 1.264 01.258 0 1.212 6 1.153 21.144 4 1.152 98.651 61.176 6 1.217 1 1.271 91.261 4 1.213 1 1.155 71.158 4 1.165 58.450 41.163 9 1.213 9 1.276 31.262 8 1.226 1 1.162 11.180 3 1.184 78.249 21.155 4 1.198 9 1.278 41.266 2 1.237 7 1.170 41.199 1 1.205 28.048 01.144 0 1.211 3 1.285 81.275 1 1.246 4 1.177 81.215 6 1.224 47.846 81.136 6 1.222 2 1.293 91.280 9 1.252 5 1.188 11.229 7 1.241 07.645 61.129 6 1.218 5 1.296 71.282 4 1.254 7 1.195 51.240 5 1.254 27.444 41.123 8 1.212 6 1.296 81.281 3 1.254 8 1.201 21.249 4 1.265 47.243 21.115 2 1.207 4 1.293 61.277 0 1.251 7 1.204 21.254 9 1.272 97.042 01.104 6 1.205 5 1.288 31.270 6 1.246 5 1.205 31.257 7 1.277 56.840 81.095 3 1.197 7 1.280 11.261 6 1.239 2 1.204 31.258 1 1.279 46.639 61.088 3 1.187 3 1.268 71.250 0 1.229 8 1.201 51.256 1 1.278 56.438 41.084 3 1.178 2 1.256 11.237 0 1.218 9 1.197 61.252 3 1.276 06.237 21.067 8 1.166 7 1.242 01.222 7 1.206 5 1.192 21.246 4 1.270 96.036 01.057 7 1.154 3 1.225 91.206 6 1.192 4 1.185 11.238 3 1.263 45.834 81.050 5 1.140 7 1.207 51.188 5 1.176 8 1.176 51.228 0 1.253 55.633 61.045 8 1.127 4 1.188 01.169 5 1.160 2 1.166 71.215 7 1.241 45.432 41.031 8 1.113 2 1.169 51.153 7 1.148 5 1.159 91.205 1 1.229 45.231 21.026 6 1.106 2 1.158 51.146 2 1.141 3 1.159 11.206 7 1.230 45.030 01.031 6 1.105 2 1.152 81.140 3 1.138 2 1.159 91.208 1 1.230 14.828 81.035 1 1.102 9 1.145 51.133 4 1.137 2 1.163 61.208 3 1.228 14.627 61.037 5 1.100 1 1.137 61.125 7 1.135 4 1.166 01.207 9 1.224 44.426 41.039 1 1.096 2 1.128 81.117 3 1.132 9 1.167 71.206 4 1.218 94.225 21.039 7 1.090 7 1.119 01.108 1 1.129 7 1.168 41.203 5 1.212 74.024 01.045 5 1.086 1 1.108 41.098 2 1.125 7 1.168 31.199 3 1.206 03.822 81.050 6 1.081 1 1.097 31.087 5 1.121 0 1.167 41.193 6 1.197 53.621 61.043 9 1.072 7 1.086 01.078 9 1.115 9 1.165 11.186 2 1.187 03.420 41.045 6 1.066 9 1.075 81.077 5 1.110 9 1.168 21.184 4 1.179 73.219 21.055 6 1.066 1 1.069 81.077 4 1.111 1 1.171 41.185 1 1.176 03.018 01.066 6 1.069 4 1.068 51.079 9 1.115 0 1.177 71.188 2 1.177 32.816 81.086 5 1.082 0 1.076 61.095 8 1.129 6 1.188 01.203 1 1.194 32.615 61.115 8 1.103 8 1.093 71.117 8 1.154 2 1.203 51.222 5 1.212 42.414 41.144 4 1.124 6 1.109 71.138 7 1.177 7 1.225 21.240 5 1.230 32.213 21.180 3 1.147 6 1.126 11.160 4 1.202 0 1.248 41.258 6 1.248 22.012 01.216 5 1.171 5 1.142 91.182 4 1.226 5 1.271 01.275 8 1.265 21.810 81.246 0 1.194 0 1.159 61.204 3 1.250 5 1.292 71.291 9 1.281 11.609 61.278 0 1.214 9 1.175 21.224 9 1.273 2 1.313 01.307 2 1.296 21.408 41.312 2 1.234 4 1.189 71.243 9 1.294 1 1.331 81.321 9 1.310 81.207 21.343 1 1.252 8 1.203 01.261 4 1.313 2 1.348 81.335 5 1.324 61.006 01.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 00.804 81.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 00.603 61.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 00.402 41.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 00.201 21.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 00.000 01.000 0 1.000 0 1.000 01.000 0 1.000 0 1.000 01.000 0 1.000 0 Unit 2 Cycle 2 WATTS BAR Page 10 of 10 Revision Table A.2 F Q W(Z) Penalty Factor Burnup Penalty (MWD/MTU)Factor 150 1.02 37 300 1.02 44 451 1.02 50 601 1.02 54 751 1.02 53 902 1.02 48 1052 1.02 37 1203 1.02 21 1353 1.02 011503 1.0200 11715 1.0200 11863 1.0203 12012 1.0206 12160 1.0210 12308 1.0209 12456 1.0205 12605 1.0201 12753 1.0200 Note: 1.The Penalty Factor, which is applied to F Q W(Z) for compliance with Surveillance Requireme nt 3.2.1.2, is the maximum factor by which F Q W(Z) is expected to increase per 31 Effective Full PowerDays (EFPD) starting from the burnup at which the F Q W(Z) was determ ined.