|
|---|
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
MONTHYEARML23319A2452024-01-29029 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
CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000390/20234412023-12-21021 December 2023
Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public
CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023
Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
IR 05000390/20234042023-12-14014 December 2023
Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404
CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023
Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)
ML23293A0572023-12-0606 December 2023
Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
IR 05000390/20230102023-11-30030 November 2023
RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation
CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000390/20230032023-11-13013 November 2023
Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation
ML23312A1432023-11-0808 November 2023
Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023
Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03
CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision
ML23251A2002023-09-11011 September 2023
Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2
CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64
IR 05000390/20230052023-08-30030 August 2023
Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005
ML23233A0042023-08-28028 August 2023
Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds
IR 05000390/20230022023-08-16016 August 2023
Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002
ML23220A1582023-08-0909 August 2023
Integrated Inspection Report 05000390/2023002 and 05000391/2023002
CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023
License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)
CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023
Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)
ML23192A4472023-07-31031 July 2023
Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information
CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023
Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills
IR 05000390/20230112023-07-24024 July 2023
Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011
CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023
Tennessee Valley Authority - Radiological Emergency Plan Revisions
CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023
Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)
CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023
Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .
ML23122A2322023-06-0707 June 2023
Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs)
CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023
Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out
IR 05000390/20234032023-05-30030 May 2023
Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403
ML23131A1812023-05-23023 May 2023
Correction to Amendment No. 161 to Facility Operating License No. NPF-90
CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023
Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000390/20220032023-05-0909 May 2023
Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003
ML23125A2202023-05-0505 May 2023
Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances)
IR 05000390/20230012023-05-0404 May 2023
Integrated Inspection Report 05000390/2023001 and 05000391/2023001
CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023
Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)
CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41
CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023
Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update
CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023
Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision
CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023
Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML23072A0652023-04-0505 April 2023
Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12
ML23073A2762023-04-0303 April 2023
Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter)
CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023
Annual Insurance Status Report
CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023
TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report
2024-01-09
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 September 27,2018 10 cFR 50.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391
Subject:
UNIT 1 REVISION O OF THE CYCLE 16 CORE OPERATING LIMITS REPORT (coLR)
Pursuant to Watts Bar Nuclear Plant Technical Specifications (Tech Spec) Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Revision 0 of the Unit 1 Cycle 16 COLR. The analytical methods used to determine the core operating limits were previously reviewed and approved by the NRC.
There are no regulatory commitments contained in this letter or the enclosure. Should you have questions regarding this submittal, please contact Kim Hulvey at (23) 365-7720.
Respectfull Paul Simmons Site Vice President Watts Bar Nuclear Plant
U.S. Regulatory Commission Page 2 September 27,2018
Enclosures:
Watts Bar Nuclear Plant, Unit 1, Cycle 16 Core Operating Limits Report, Revision 0, August 2018 cc (Enclosure):
NRC Regional Administrator - Region ll NRR Project Manager NRC Senior Resident lnspector
ENCLOSURE 1 Watts Bar Nuclear Plant, Unit 1, Gycle 16 Gore Operating Limits Report Revision 0 August 2018
OA Record 136 180815 802 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 16 CORE OPERATING LIMITS REPORT Revision 0 August 2018
.'I *,"'
t I t'1" , fi J. C. Bell. PWR Fuel Engineering Date
\ --l Verified by:
Reviewed by:
Selter, el Eng Manager B.T J,Adfk Reactor Engineering Manaser tfu* Date Approved by:
I L-t tuty RC Chairman )atIE Plant t Dl:,:t,t,,tr Date Date of PORC Affected Revision Approval Pages Reason for Revision 0 See Above Ail lnitial lssue I lrrit I Cl cltl lrr
\\'r\'l'I'S RA t( Ilitgc I ol' ()
I{ct isiutt i}
1.0 CORE OPERATII\G LIMITS REPORT This Core Operating Limits Repgrt (COLR) for Watts Bar Unit I Cycle l6 has been prepared in accordance with the requirements of the Technical Specifications (TS) 5.9.5.
The Technical Specifications affected by this report are listed below:
3.1.4 Moderator Temperature Coefficient (MTC) 3.1.5 Rod Group Alignment Limits 3.1.6 Shutdown Bank lnsertion Limits 3.1.7 Control Bank lnsertion Limits 3.2.1 Heat Flux Hot Channel Factor (F,t(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F^r*)
3.2.3 Axial Flux Difference (AFD) 3.9. I 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 2.1 MODERATOR TEMPERATURE COEFFTCTENT - 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/ld'F (upper limit).
With the measured BOL/ARO/HZP - MTC more positive than -3.277 x 10 5 AVld"F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/ld'F (upper limit) for all times in core life.
The EOLIARO/RTP - MTC shall be less negative than or equal to
-4.5 x l0-aAk/V"F (lower limit).
2.1.2 The 300 ppm surveillance limit is:
The measured 300 ppm IARO/RTP-MTC should be less negative than or equal to -3.75 x l0-a 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 104 Ak/k/"F.
Unit I Cycle 16 WATTS BAR Page2 of 9 Revision 0
2.2 SHUTDOWN MARGIN- SDM (LCO 3.1.5,3.I.6,3.1.7) 2.2.1 For TS 3. I .5, SDM shall be > I .6% Aklk in MODE I and MODE 2.
2.2.2 For TS 3.1.6, SDM shall be > 1.6% Ak/k in MODE I and MODE 2.
2.2.3 For TS 3.1.7, SDM shall be > I .6% Ak/k in MODE I and MODE 2 with keff> 1.0.
2.3 SHUTDOWN BAr\K TNSERTION LIMTTS (LCO 3.r.6) 2.3.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.
2.4 CONTROL BANK TNSERTTON LIMTTS (LCO 3.1.7) 2.4.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure l.
2.4.2Each confrol bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.
2.4.3 T\e confrol 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.
2.4.4 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 09 L6 226 l0 l6 227 ll l6 228 l2 l6 229 l3 l6 230 t4 l6 231 15 l6 2.5 HEAT FLUX TIOT CHAI\INEL FACTOR - rq(Z) (LCO 3.2.1)
Fq(Z) < [CrQ/ P]
- K(Z) for P > 0.5 Fq(Z) < [CFQ/ 0.5]
- K(Z) for P s 0.5 Where P : Thermal Power/ Rated Thermal Power 2.5.1 CFQ:2.50 Unit I Cycle 16 WATTS BAR Page 3 of 9 Revision 0
2.5.2 K(Z) is provided in Figure 2.
2.53 Faw(Z): Fo"(Z)
- W(Z)tp for p > 0.5 Fq"'(Z) : Fq"(Z)
- W(2y0.5 for P < 0.5 where: W(Z) values are provided in Table A.l. The table provides suffrcient information to determine W(Z) versus core height for all cycle burnups.
2.5.4 Part power W(Z) values are only required to be used when the part power surveillance is performed using the moveable incore detector system.
2.3.5 Faw(Z) Penalty Factor the fowlZl penalty factor is provided in Table A.2.
2.6 NUCLEAR ENTHALPY RrSE HOT CHANNEL FACTOR - F*n (LCO 3.2.2' F** S F**" * ( I + PF * ( l-p))
where P - Thermal Power / Rated Thermal Power For*'o : I.65 for RF A-2 fuel, and PF :0.3 2.7 AXIAL FLUX DIFFEREI\CE - AFD (LCO 3.2.3) 2.7.1 The AFD limits for Cycle 16 are provided in Figure 3.
2.8 REFUELINGBORON CONCENTRATION (LCO 3.9.1) 2.8.1 The refueling boron concentration shall be ) 2000 ppm.
3.0 NUMBEROF TPBARS IN REACTOR CORE (TS 4.2.1) 3.0. I There are 1584 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 16.
Unit I Cycle 16 WATTS BAR Page 4 of 9 Revision 0
250 BANK A (ALL POWERS, 225) 225 200 2 175 3
u, o
-F 3 150 vt o.
UJ lh F
Its 725 Itl o
c o.
UI l-1n 100
\,
-z o
o 75 o E, 0,0 4.2 4.4 0.6 0.8 1.0 FRACTION OF RATEDTHERMAI POWER Figure I Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Note: Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of >-225 and323l steps withdrawn.
Unit I Cycle l6 WATTS BAR Page 5 of 9 Revision 0
1.2 1.1 1.0
-r L
-t 0.9 0.8 l-_
(l) o o.7
=
o-LL o __-_t I I 0.6 I Core Height
'r(J (1) j i o.ooo
.N 6.000 I E i 12.000 (
E 0.5 o
z.
o.4 0.3 o.2 o.1 o
0 2 4 6 I 10 12 Core Height (feet)
Figure 2 K(Z) - hlormalized Fq(Z) as a Function of Core Height Unit I Cycle l6 WATTS BAR Page 6 of9 Revision 0
120 110 L_
{Ha j Pl-- 0)r (7, 10 -I 100 I \
90 lr 7]ffi:i,I d t rble on b
o
=
rL 80
-_l J
I unacceptaue I
r IL I
operation L- I T
\
\
\
ll ncceptal Cperatior l'"
-t t-iE 7A I \
E L-o foo I \
E
Yso I \
s o
ts 40 30 20 10
-50 4A -30 -20 -10 0 10 2A 30 40 50 Flux Difference (Al) %
Figure 3 Axial X'lux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)
Unit I Cycle 16 WATTS BAR Page 7 of9 Revision 0
Table A.l RAOC W(Z) Surveillance Factors Max W(z) 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 3000 at 6000 at 8000 at 12000 at 16000 at 18000 Height IIIWD/MTU MWDIMTU MWD/MTU MWD/MTU MWD/MTU [,IwD/MTU MWD/MTU MWD/MTU IIWD/MTU (ft)
(30% (7$Yo (100% (100% (100% (100% (100% (100% (100%
Power) Power) Powerl Powerl Power) Power) Powerl Power) Powerl 12 0742 1 0000 1.0000 1.0000 1.0000 1.0000 1,0000 1.0000 1.0000 1"0000 11,8730 1.0000 1.0000 1 0000 1.0000 1.0000 1.0000 1,0000 1.0000 1.0000 11 .6717 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11 47A5 1.0000 1"0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1 0000 11.2693 1.0000 1.0000 1.0000 1.0000 1,0000 1.0000 1.0000 1.0000 1.0000 11.0680 1.0000 1.0000 1 0000 1.0000 1,0000 1"0000 1,0000 1.0000 1.0000 10.8668 1 .3815 1.4258 1.2750 1.3559 1.2674 1.2444 1.1422 1.1521 1.1763 10,6655 1 3698 1.4012 1 2723 1.3495 1.2636 1.2426 1.1412 1,1502 1 .1693 10.4643 1,3580 1.3751 1"2668 1.3/.02 1.2574 1.2007 1 1380 1.1458 1.1633 10,2631 1.3447 1.3468 1 2611 1.3286 1.2494 1"1971 1,1 335 1.1400 1 1576 10.0618 1.3261 1.3142 1.2554 1 .3155 1_2404 1.1918 1.1269 1.1322 1.1510 9.8606 1.3078 1.2785 1 2479 1.3012 1 2319 1.1846 1.1243 1 1280 1.1433 9.6594 1.2867 1"2484 1.2393 1.2857 1.2243 1.1776 I 1257 1.1276 1.1366 9.4581 1.2664 1.2219 1.2329 1.2693 1.2181 1"1783 1.1249 1.1269 1.1342 9 2569 1.2443 1,1973 1.2263 1.2561 1.2182 1.1795 1 1269 1.1243 1.1366 9.0557 1 .2171 1.',1762 1.2184 1.2483 1.2180 1.1797 1.1277 1.1252 1 .1430 8.8544 1.1860 1,1558 1.2487 1.2422 1.2143 1 1789 1.1287 1.1307 1.1485 8.6532 1.1563 1.1391 1.2006 1.23l2 1.2096 1"1790 1.1353 1.1410 1.'t559 8.4519 1.1326 1.1308 1 .1 994 1.2260 1.2A57 1.1830 1.1455 1.1578 1.1736 8.2507 1.1100 1.1246 1 .1 987 1.2191 1.20A2 1.1850 1.1537 1,1726 1.1892 8.0495 1.0925 1.1201 1.1990 1.2118 1 1958 1.1849 1 1599 1.1849 1.2019 7 8482 1.0769 1.1167 1.1993 1.2034 1"1918 1.1834 1.1ils 1.1955 1.2130 7.6470 1.0625 1.1133 1 1977 1.1942 1.1859 1.1802 1"1674 1.2038 1.2216 7.4458 1.0489 1 1095 1.1942 1 .1 840 1.1787 1.1755 1.1686 1.2100 1_2279 7 _2445 1.0363 1,1056 1.1892 1.1744 1.1702 1_1695 1 1677 1.2140 1.2319 7_0433 1.0243 1 1000 11824 1.1668 1.1604 1.1615 1.1689 1.2160 1.2337 6.8420 1.0138 1.0945 1.1748 1 . 1616 1.1 543 1.1576 1.1709 1.2157 1.2331 6 6408 1.0077 1.0920 1 .1 700 1.1579 1.1531 1.1571 1.1707 1.2136 1.2305 6.4396 1.0078 1.0945 1.1699 1.1540 1 1501 1"1569 1,1697 1.2102 1.2263 6.2383 1.0090 1.0967 1.1690 1.1496 1.1454 1j547 1.1672 1.2049 1.2202 6.0371 1.0094 1.0969 1 .1658 1.1463 1.1418 1,1513 1_1628 1.1977 1.2119 5.8359 1.0123 1 0982 1,1637 1 1431 1.1388 1.1462 1 1584 1.1887 1"2018 5.6346 1,0178 1.1018 1,1635 1 .1 385 1.1 354 1.1406 1.1556 1"1779 1.1898 5.4334 1.0230 1.1045 1.1617 1.1330 1.1326 1.1 381 1.1534 1"1679 1-1777 5.2322 1.0284 1.1064 1.1589 1.1267 1.1309 1 1384 1_1528 1.1675 1.1707 5.0309 1.0338 1.1072 1.1552 1.1197 1.1299 1.1396 1.1524 1.1689 1.1699 4.8297 1.0393 1 .1071 1"1505 1.1120 1.1287 1.1406 1"1530 1 1701 1 1708 4.6284 1.4447 1.1064 1.1451 1.1038 1.1270 1.1411 1,1568 1.170/. 1.1700 4.4272 1.0498 1 1A52 1"1389 1.0952 1.1248 1.1410 1.1609 1.1699 1.1684 4.2260 1,0552 1 1035 1"1321 1.0864 1.1222 1.1404 1.1il7 1.1703 1.1663 4.4247 1.0608 1.1015 1 1247 1.0771 1 1191 1,1394 1.1682 1 .1719 1.1632 3.8235 1.0670 1.0993 1"1169 1.4707 1.1159 1 .1 382 1.1715 1.1730 1.1614 3.6223 1.0727 1.0967 1.1087 1.0698 1 1123 1.1366 1 .1 746 1,1749 1.1617 3.4210 1.0795 1.0950 1.1016 1.A722 1.1093 1.1348 1.1776 1"18',17 1,1673 3.2198 1.0947 1.1011 1.1024 1,0749 1.1109 1.1369 1,1837 1.1899 1.1723 3.0186 1.1113 1.1078 1,1040 1.4764 1 117 1 1.1446 1.1933 1.1969 1.1783 2.8173 1.130't 1.1165 1.1074 1.0839 1.1302 1.1594 1.2096 1.2106 1.1921 2.6161 1.1564 1.1319 1,1172 11002 1.1491 1 1798 1.2322 1.2333 1,213r'.
2.4148 1.1868 1.1502 1.1299 1.1 158 1.1677 1.1997 1.2537 1_2543 1.2332 2.2136 1.2182 1.1685 1.1424 1.1315 1.1862 1 2193 1"2746 1.27M 1.2524 2"4124 1,2491 1.1861 1.1540 1.1468 1.2044 1.2385 1.2946 1,2938 1.2748 1 8111 1.2817 1.2042 1.1660 1.1614 1,2218 1.2568 1.3135 1.3118 1,2881 1.6099 1.3126 1.2224 1.1782 1.1750 1,2380 1.2738 1"3308 1.3283 1.3040 1.4087 1 3387 1.2380 '1.1883 1.1866 1.2520 1.2883 't.3453 1.3/21 1,3173 1.2474 1.3613 1.2501 1.1948 1.1947 1.2623 1"2990 1.3556 1.3516 1.32U 1"0062 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 't.0000 1 0000 1.0000 0.8049 1.0000 1.0000 1,0000 1.0000 1.0000 1"0000 1.0000 1,0000 1.0000 0.6037 1"0000 1.0000 1,0000 1.0000 't.0000 1.0000 1.0000 1.0000 1.0000 0.4025 1.0000 1"0000 1.0000 1.0000 1.0000 1"0000 1.0000 1.0000 1.0000 o"2012 1.0000 1.0000 1.0000 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 1.0000 1.0000 1.0000 Unit I Cycle l6 WATTS BAR Page 8 of 9 Revision 0
Table 4.2 Fqtt'(Z) Penalty Factor Fe'n (z)
Core Burnup Penalty (MWD/MrU)
Factor All Burnups 1.0200 Note:
- l. The Penalty Factor, which is applied to Faw(Z) for compliance with Surveillance Requirement 3.2.1.2, is the maximum factor by which Fq'(Z) is expected to increase per 3l Effective Full Power Days (EFPD) starting from the burnup at which the Fqwlz; was determined.
Unit I Cycle 16 WATTS BAR Page 9 of 9 Revision 0
