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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, 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 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
MONTHYEARCNL-24-080, Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2024-11-20020 November 2024 Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) CNL-24-064, Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R52024-11-0404 November 2024 Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R5 IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 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 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate 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 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection 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 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO 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-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update 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 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 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 2024-09-05
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 October 6, 2017 10 cFR 50.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
REVISION 2 OF THE CYCLE 1 CORE OPERATING LIMITS REPORT (coLR)
Pursuant to Watts Bar Nuclear Plant Technical Specifications Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Revision 2 of the Unit 2 Cycle 1 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 (423) 365-7720.
Respectfully, .a Paul Simmons Site Vice President Watts Bar Nuclear Plant
Enclosure:
Watts Bar Nuclear Plant, Unit 2, Cycle 1 Core Operating Limits Report Revision 2 September 2017
U.S. Nuclear Regulatory Commission Page 2 October 6, 2017 cc (Enclosure):
NRC Regional Administrator - Region ll NRR Project Manager - Watts Bar Nuclear Plant NRC Senior Resident lnspector - Watts Bar Nuclear Plant
ENCLOSURE Watts Bar Nuclear Plant, Unat 2, Cycle 1 Core Operating Limits Report Revision 2 September 2017
QA Record
.136 174922 8A1 WATTS BAR NUCLEAR PLANT, UN IT 2. CYCLE CORE OPERATING LIMITS REPORT Revision 2 September 2A17 Prepared by:
.A. Setter, t nlu-laor:t ngrneenng Date Verified by.
Engineering Date Reviewe$ by:
I Carey, uclear Safelf Analysis M er for C.A. Setter, PWR Fuel Engineering nager ngineering Manager C Chairrnan Plant Date of PORC PORC Meeting Affected Revision Approval Number Paqeb Reason for Revision 0 8127t2014 4439 all initial issue deleted equation shown on header of 1 9124t2015 4478 1.9 Table A. 1 2 See above. yg# 1,3 EOL MTC limits are conected to address CRs 1 330505 and 1341061 jr.?/*tr*
Unit 2 CiSrcle I WATTS BAR Pagc I ofI0 Rcvision 2
1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 2 Cycle I 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 (Fo(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FaH*)
3.2.3 Axial Flux Difference (AFD) 3.9.1 BoronConcentration 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 HotZero Thermal Power EOL End of Cycle Life RTP Rated Thermal Power Unit 2 Cycle I WATTS BAR Page 2 of l0 Revisi on 2
I I
2.1 MODERATOR TEMPERATURE COEFFTCTENT - MTC (LCO 3.r.4) 2.1.1 The MTC limits are:
The ARO/HZP - MTC shall be less positive than or equal to 0 Ak/k/oF (upper limit).
With the measured BOL/ARO/HZP - MTC more positive than -3.33 x lO-s Ak/ldoF (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Aldld'F (upper limit) for all times in core life.
The EOL/ARO/RTP - MTC shall be less negative than or equal to
-3.39 x l0-4 Ak/ldoF (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
-2.59 x l0-4 Ak/ld'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
-3.17 x l0-4 Ak/ld'F.
2.2 SHUTDOWN BANK TNSERTTON LTMTTS (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 TNSERTTON LTMTTS (LCO 3.1.7) 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure l.
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 I WATTS BAR Page 3 of l0 Revisi on 2
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 ll6 226 I l0 ll6 227 llt il6 228 n2 il6 229 I 13 ll6 230 tt4 ll6 23t I 15 I 16 2.4 HEAT FLUX HOT CHANNEL FACTOR - Fo(z) GCO 3.2.r)
Fq(Z) < [CFQ/ P]
- K(Z) for P > 0.5 Fq(Z) < [CFQ/ 0.s]
- 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.
2.43 Faw(Z): Fq"(Z)
- W(ZYP for P > 0.5 Fq*(z) = Fq'(Z)
- w(z)10.5 for P < 0.5 where: W(Z) values are provided in Table A.l. The table provides sufficient information to determine W(Z) versus core height for all cycle bumups.
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 Faw(Z) Penalty Factor the f'ow1Z; penalty factor is provided in Table A.2.
Unit 2 Cycle I WATTS BAR Page 4 of 10 Revisi on 2
2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR-F611N (LCO3.2.2)
For* s Far*" * ( I + PF * ( l-P))
where P - Thermal Power I Rated Thermal Power For*tt _ I .65 for RF A-2 fuel, and PF : 0.3 2.6 AXIAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle I 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 1 WATTS BAR Page 5 of l0 Revisi on 2
z L75 3
E a
-E 150
.a
=
A EI l-Itl Y
z o L25 F
6 o
a o-EI l- 100 ln Y
z GT a 75 o
E, 0.2 0.4 0.5 0.8 1.0 FRACTION OF RATED THERMAT POWER Figure I 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 2 Cycle I WATTS BAR Page 6 of l0 Revisi on 2
L,2 1.1 0.9 0.8 L.
o 3 0.7 o,
c, l!
t,o 0.6 LOre Hergnr K(z)
.!! 0.000 1.00( )
o 5.000 1.00( )
E o.s 12.000 1.00t )
o z
0.4 0.3 o,2 0.1 557 10 LL L2 Core Height (feet)
Figure 2 K(Z) - Normalized Fq(Z) as a Function of Core Height Unit 2 Cycle I WATTS B AR Page 7 of t0 Revisi on 2
120 110 100 90 80 Unacceptable Unacceptable o Operation Operation 8ro
=
E E
o f60 E'
o o
f50 o (21 , 50) s 40 30 20 10
-50 40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (nlYt Axial Flux Difference Acceptable Operation #i:"":" function of Rated Thermal Power (RAoC)
Unit 2 Cycle I WATTS BAR Page 8 of 10 Revisi on 2
Table A.l NIax W(z) NIax W(z) N{ax W(z) Max W(z) N{ax W(z) NIax W(z) at 150 at 150 at 150 at 3000 at 8000 at 12000 IvIWD/I\,TTU 1\,IWDINITU N{WD,,'MTU IvtWD/MTU Iv{WDi'NITU MWD/N{TU Heisht tft) (30% Power) (754,b Power) (100o,,b Power) ( 100% Power) ( 100% Power) ( 1000,6 Power)
D.0724 1.0000 r.0000 1.0000 t.0000 1.0000 t.0000 l1.8708 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 tt.6696 1.0000 t.0000 1.0000 1.0000 1.0000 1.0000 l1.468{ 1.0000 1.0000 t.0000 1.0000 1.0000 1,0000 1t.2672 1.0000 1.0000 1.0000 1.0000 1.0000 t.0000 I1.0660 r.0000 r.0000 t.0000 1.0000 1.0000 1.0000 10.8648 1.4001 1.357I 1.2493 1.3471 1.3048 1.2486 10.6636 1.J687 1.3324 t.216e 1.3202 1.2851 r.2301 t0.4621 1.3021 1.2734 1.2471 1.J039 t.2628 1.2r00 10.26t2 1.2706 1.2464 t.21t2 1.2801 1.2381 t.1909 10.0600 1.2459 t.2278 r.2336 1.2535 1.2281 1.1746 9.8588 1.2103 1.2025 1.2183 1.2273 1.2205 1.1704 9.6576 t.r8l2 1.1850 1.2086 t.2177 l.2l t9 1.t728 9.{564 1.t711 1.t890 1.220e 1.2220 1.2074 1.1734 9.2552 1.1677 1.1942 r.2324 1.2238 t.204{ 1.t725 9.0s40 l.t6l0 1.2000 1.2434 1.2331 1.2086 1.1808 9.8528 l.l56l 1.2067 1.2553 1.2458 1.2162 r.r882 8.6516 t.l5l.l t.2tt7 1.2640 1.2725 t.2201 l.l92l 8..150.1 1.1537 t.2217 1.2771 1.2984 r.2J44 1.20{3 8.2492 r.1644 1.2395 1.2990 t.3178 1.2512 1.22s7 8.0480 t.r783 1.25e3 1.3218 1.3338 1.2702 1.24s8 7.8.168 l.l88{ 1.2743 1.3386 1.3437 1.2817 1.2619 7.6{56 1.1947 t.2846 1.3498 r.3486 1.2896 1.2750 7.4414 t.t982 1.2906 1.3s62 t.34e0 t.2942 r.28s4 7.2432 1.2005 r.2940 1.3588 1.3456 1.2955 t.2e26 7.0420 t.2017 1.2e50 1.3579 1.3387 t.2e37 1.2965 6.8408 1.r993 1.2920 1.3527 1.3281 1.2890 1.2974 6.6396 l.l9s0 1.28s8 1.3447 l.3l.l5 1.2825 1.2963 6.,t384 l.1886 1.2761 1.3J36 1.2981 t.2732 t.2925 6.2372 r.1820 1.2667 1.32r r 1.2798 1.2617 1.2860 6.0360 t.t742 1.2555 t.307t r.2s93 1.2480 1.2768 5.8348 l. t64s 1.2421 t.2906 1.2117 1.2326 1.2653 s.6336 1.1546 t.2277 1.2724 1.2295 1.2156 r.2sl3 5.4324 1.1498 1.2176 1.2590 t.2165 1.2032 1.238e s.2312 l.lsol t.2t29 1.2s02 1.2065 1.1959 1.237e s.0300 1.1485 t.2061 1.2399 1.1957 1.1879 1.2360 4.8288 1.1472 l.t99l r.2300 1.1837 1.1859 1.2321 1.6276 r.1457 1.1920 1.2t88 1.1778 1.1832 t.2279 1.4264 t.1422 1.1829 1.2061 1.1709 l.l 793 1.2213 4.2252 r.1384 1.1739 r.1938 r. t63 I l.l74l l.2l3l
{.02.10 1.1329 1.1637 l.r80J t.l53E r.1675 1.2030 3.8228 1.1298 1.1550 1.1674 1.1437 1.1596 l.l9l0 3.62t6 l.l28l l.l.t64 t.1555 1.1330 t.1507 1.1809 3.4204 1.1260 1.t385 1.1436 1.1246 1.t459 l.l7l9 3.21e2 l.l2s2 t.r3l4 1.133{ l.l 182 l.l.l07 1.1629 3.0180 l.lJ99 r.l40t l.l39l 1.1304 1.1465 t.1590 2.8168 t.1608 l.l55.l 1.1509 l. l{s4 t.t640 1.1728 2.6156 1.1832 1.1723 1.163E 1.t626 l.l8l3 1.1904 2.1111 1.2065 t.1898 l.l78l t.1796 1.t987 t.2479 2.2t32 t.2291 1.2065 l.lel8 1.1965 1.2158 1.2253 2.0120 r.2s43 t.2248 1.206s 1.2179 1.2397 1.2424 1.8108 l.2E0l t.2434 1.22 l s 1.2494 1.2720 1.2588 1.6096 1.3067 1.2627 t.2360 1.2785 1.3016 1.2717 1.4084 t.3328 r.2813 r.2s05 r.306t 1.3296 r.2903 1.2072 1.3628 1.3037 1.2650 1.3320 1.3555 1.30s2 1.0060 1.0000 1.0000 1.0000 1.0000 1.0000 r.0000 0.8048 1.0000 1.0000 1.0000 r.0000 1.0000 1.0000 0.6036 1.0000 t.0000 1.0000 r.0000 1.0000 1.0000 0.402{ 1.0000 1.0000 1.0000 1.0000 r.0000 1.0000 0.2012 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 t.0000 1.0000 1.0000 1.0000 Unit 2 Cycle 1 WATTS BAR Page 9 of l0 Revisi on 2
Table A.2 Fq*(Z) Penalty Factor Core Fa,*(z)
Burnup Penalty (MWD/MTU) Factor 450 r.0200 s99 1.0222 749 1.0247 899 1.0263 1049 1.0267 I r99 1.0250 t349 1.0226 I 498 1.0200 Note:
- l. The Penalty Factor, which is applied to Fq*(z) for compliance with Surveillance Requirement 3.2.1 .2, is the maximum factor by which Fqn (Z) is expected to increase per 3 I Effective Full Power Days (EFPD) starting from the burnup at which the Fo*(Z) was determined.
Unit 2 Cycle I WATTS BAR Page l0 of l0 Revisi on 2