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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, 1101 Market Street, Chattanooga, Tennessee 37402-2801 October 19, 2009 10 CFR 50.4 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No.:50-390
Subject:
Revisions 2 and 3 of the Cycle 10 Core Operating Limits Report The purpose of this letter is to provide Revisions 2 and 3 of the Cycle 10 Core Operating Limits Report (COLR) in accordance with Watts Bar Nuclear Plant, Technical Specification 5.9.5.d. Revisions 0 and 1 of the COLR were never issued for use during Cycle 10. Revision 2 provided the boron concentrations required for reloading the core and entry into Mode 6 and Mode 5. Revision 3 defines the core operating limits for Cycle 10 operation.
There are no regulatory commitments contained in this letter or its enclosures.
Please direct any questions conderning this matter to Kevin Casey at (423) 751-8523.Respectfully, R. M. Kric Vice President Nuclear Licensing Enclosures
- 1. Revision 2 of the Cycle 10 COLR 2. Revision 3 of the Cycle 10 COLR Printed on recycled paper U.S. Nuclear Regulatory Commission Page 2 October 19, 2009 Enclosures cc (Enclosures):
NRC Regional Administrator
-Region II NRC Senior Resident Inspector
-Watts Bar Nuclear Plant Enclosure 1 Cycle 10 Core Operating Limits Report Revision 2.l E1-1 of 3 COLR for Watts Bar Unit 1, Cycle 10 QA Record L36 091001 802 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 10 MODE 6 AND RESTRICTED MODE 5 CORE OPERATING LIMITS REPORT Revision 2 October 2009 Prepared by: ,I,)(/Nuclear Fuel / Date Reviewed by: /0 1 Manager, Nuclear F4 Engineeing Date Reactor Engineering Supervisor Date Approved by: ,4/ //o PORC Chairman ,Date__', ,oQA Plant Manager Date Date of PORC PORC Meeting Affected Revision Approval Number Pages Reason for Revision 0 n/a n/a n/a not issued 1 n/a n/a n/a not issued 2 1tol &16 16.-1, all initial issue Unit 1 Watts Bar Cycle 10 Page 1 of 2 Revision 2 E1-2 of 3 Mode 6 and Restricted Mode 5 COLR for Watts Bar Unit 1, Cycle 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 10 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 (FQ(Z))3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAHN)3.2.3 Axial Flux Difference (AFD)3.5.1 Accumulators
3.5.4 Refueling
Water Storage Tank (RWST)3.9.1 Boron Concentration
2.0 OPERATING
LIMITS This COLR is only valid for mode 6 and restricted mode 5. The mode 5 restriction does not allow the control rod drive system to withdraw any RCCA. The COLR must be revised before the withdrawal of the RCCAs by the control rod drive system is enabled. The cycle-specific parameter limits for specifications 3.1.4, 3.1.6, 3.1.7, 3.2.1, 3.2.2, and 3.2.3 are not applicable in mode 6 or restricted mode 5 and are not provided.
The parameter limits for the specifications 3.5.1, 3.5.4, and 3.9.1 are provided in the following subsections.
These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5.2.1 REFUELING BORON CONCENTRATION (LCO 3.9.1)2.1.1 The refueling boron concentration shall be a 2000 ppm.2.2 ACCUMULATORS (LCO 3.5.1)2.2.1 There are 240 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 10.2.3 REFUELING WATER STORAGE TANK -RWST (LCO 3.5.4)2.3.1 There are 240 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 10.Unit 1 Cycle 10 Watts Bar Page 2 of 2 Revision 2 E1-3 of 3 Enclosure 2 Cycle 10 Core Operating Limits Report Revision 3 E2-1 of 11 COLR for Watts Bar Unit 1, Cycle 10 QA Record L36 091009 807 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 10 CORE OPERATING LIMITS REPORT Revision 3 October 2009 Prepared by: Nuclear Fuel Date'Reviewed by: /0/,/,S Manager, Nuclear FX E~ngineering Date Reactor Engineering Supervisor Date Date of PORC PORC Meeting Affected Revision Approval Number Pages Reason for Revision 0 n/a n/a n/a not issued 1 n/a n/a n/a not issued 2 1016/09 4273 all Initial issue 3 10/9/09 -all revised to remove mode restriction Unit 1 Watts Bar Cycle 10 Page 1 of 10 Revision 3 E2-2 of 11 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 10 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 Beginning of Cycle Life All Rods Out Hot Zero Thermal Power End of Cycle Life Rated Thermal Power Unit 1 WATTS BAR Page 2 of 10 E2-3 of 11 Cycle 10 Revision 2
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/°F (upper limit). With the measured BOL/ARO/HZP
-MTC more positive than -0.60 x 10-5 Ak/k/°F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/k/°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/IF (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/°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 10 Revision 3 Page 3 of 10 E2-4 of 11 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/P1
- 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.Unit 1 WATTS BAR Cycle 10 Revision 3 Page 4 of 10 E2-5 of 11
2.5 NUCLEAR
ENTHALPY RISE HOT CHANNEL FACTOR -FAHN (LCO 3.2.2)FAHN < FAHRTP * (1 + PF * (i-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 10 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 240 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 10.2.9 REFUELING WATER STORAGE TANK -RWST (LCO 3.5.4)2.9.1 There are 240 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 10.Unit 1 WATTS BAR Cycle 10 Revision 3 Page 5 of 10 E2-6 of 11 I-a-W I-0 0 (L I-.z 0 0.0 0.2 0.4 0.6 0.8 FRACTIONAL OF RATED THERMAL POWER 1.0 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 WATTS BAR Cycle 10 Revision 3 Page 6 of 10 E2-7 of 11 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0 CU"-E N 0 z Core Heiqht K(Z)0.000 1.000 6.000 1.000 12.000 0.9256 0.4 0.3 0.2 0.1 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 1 WATTS BAR Cycle 10 Revision 3 Page 7 of 10 E2-8 of 11 120 110 100 90 80 0)E 70 60 50 40 30 20 10 0-50 30 10 0 10 20 30 40 50 Flux Difference (AI) %Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)nit 1 Cycle 10 VATTS BAR Page 8 of 10 Revision 3 E2-9 of 11 I Table A. 1 FQW(Z) = FQC(Z)
- W(Z)Max W(z) at 150 Max W(z) at 150 Max W(z) at 150 Max W(z) at Max W(z) at MWD/MTU MWD/MTU MWD/MTU Max W(z) at 3000 10000 16000 Height (ft) (30% Power) (75% Power) (100% Power) MWD/MTU MWD/MTU MWD/MTU 12.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.6000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.4000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.2000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.0000 1.0000 1.0000 1.0000 .1.0000 1.0000 1.0000 10.8000 1.2811 1.3035 1.1893 1.1903 1.2164 1.2015 10.6000 1.2651 1.2796 1.1864 1.1869 1.2167 1.2033 10.4000 1.2458 1.2508 1.1812 1.1814 1,2157 1.2055 10.2000 1.2262 1.2218 1.1746 1.1745 1.2122 1.1986 10.0000 1.2058 1.1915 1.1672 1.1668 1.2071 1.1848 9.8000 1.1833 1.1622 1.1585 1.1585 1.2007 1.1817 9.6000 1.1615 1.1386 1.1512 1.1606 1.1933 1.1827 9.4000 1.1466 1.1243 1.1515 1.1702 1.1846 1.1826 9.2000 1.1416 1.1225 1.1606 1.1693 1.1754 1.1814 9.0000 1.1316 1.1182 1.1647 1.1666 1.1727 1.1902 8.8000 1.1249 1.1198 1.1727 1.1689 1.1747 1.2049 8.6000 1.1238 1.1295 1.1882 1.1790 1.1857 1.2229 8.4000 1.1230 1.1421 1.2052 1.1929 1.2010 1.2426 8.2000 1.1193 1.1520 1.2186 1.2033 1.2127 1.2588 8.0000 1.1135 1.1597 1.2291 1.2114 1.2222 1.2723 7.8000 1.1062 1.1658 1.2370 1.2173 1.2293 1.2830 7.6000 1.1013 1.1701 1.2422 1.2208 t 1.2340 1.2906 7.4000 1.0967 1.1728" 1.2447 1.2221 .1.2363 1.2952 7.2000 1.0922 1.1733 1.2448 1.2212 1.2363 1.2969 7.0000 1.0873 1.1712 1.2425 1.2186 1.2340 1.2957 6.8000 1.0824 1.1670 1.2380 1.2144 1.2300 1.2917 6.6000 1.0774 1.1621 1.2312 1.2087 1.2245 1.2852 6.4000 1.0727 1.1564 1.2227 1.2009 1.2171 1.2761 6.2000 1.0692 1.1512 1.2141 1.1914 1.2079 1.2646 6.0000 1.0660 1.1470 1.2065 1.1827 1.1971 1.2509 5.8000 1.0622 1.1419 1.1976 1.1746 1.1840 1.2349 5.6000 .1.0596 1.1370 1.1888 1.1677 1.1717 1.2173 5.4000 1.0603 1.1344 1.1823 1.1630 1.1640 1.1992 5.2000 1.0633 1.1332 1.1772 1.1603 1.1591 1.1833 5.0000 1.0675 1.1336 1.1735 1.1574 1.1535 1.1778 4.8000 1.0725 1.1347 1.1702 1.1558 1.1487 1.1752 4.6000 1.0788 1.1363 1.1677 1.1550 1.1445 1.1698 4.4000 1.0874 1.1392 1.1670 1.1533 1.1402 1.1639 4.2000 1.0964 1.1415 1.1661 1.1531 1.1378 1.1571 4.0000 1.1047 1.1437 1.1645 1.1532 1.1353 1.1490 3.8000 1.1150 1.1482 1.1650 1.1558 1.1322 1.1430 3.6000 1.1277 1.1550 1.1676 1.1620 1.1311 1.1415 3.4000 1.1405 1.1611 1.1693 1.1698 1.1330 1.1417 3.2000 1.1558 1.1692 1.1727 1.1771 1.1344 1.1414 3.0000 1,1780 1.1842 1.1830 1.1848 1.1418 1.1436 2.8000 1.2044 1.2034 1.1977 1.1990 1.1567 1.1472 2.6000 1.2351 1.2266 1.2163 1.2187 1.1753 1.1531 2.4000 1.2722 1.2556 1.2412 1.2376 1.1934 1.1662 2.2000 1.3089 1.2835 1.2656 1.2611 1.2114 1.1812 2.0000 1.3426 1.3097 1.2881 1.2849 1.2290 1.1960 1.8000 1.3765 1.3405 1.3140 1.3079 1.2459 1.2102 1.6000 1.4144 1.3780 1.3456 1.3345 1.2619 1.2236 1.4000 1.4594 1.4165 1.3786 1.3664 1.2760 1.2356 1.2000 1.5070 1.4521 1.4087 1.3953 1.2874 1.2450 1.0000 1.0000 1,0000 1.0000 1.0000 1.0000 1.0000 0.8000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.6000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.4000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1,0000 1.0000 1.0000 1.0000 Unit 1 WATTS BAR Cycle 10 Revision 3 Page 9 of 10 E2-10 of 11 Table A.2 FQW(Z) Penalty Factor Core FQW(Z)Burnup Penalty (MWD/MTU)
Factor All Burnups 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 10 Revision 3 Page 10 of 10 E2-11 of 11