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Category:Fuel Cycle Reload Report
MONTHYEARNL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-22-0273, Core Operating Limits Report, Cycle 23, Version 12022-04-12012 April 2022 Core Operating Limits Report, Cycle 23, Version 1 NL-21-0962, Core Operating Limits Report, Cycle 24, Version 12021-10-26026 October 2021 Core Operating Limits Report, Cycle 24, Version 1 ML21046A0962021-02-15015 February 2021 Core Operating Limits Report, Cycle 1, Version 3 ND-21-0084, (VEGP) Unit 3 - Affidavits of Brian H. Whitley & Zachary S. Harper2020-12-11011 December 2020 (VEGP) Unit 3 - Affidavits of Brian H. Whitley & Zachary S. Harper NL-20-1130, Core Operating Limits Report, Cycle 22, Version 22020-09-29029 September 2020 Core Operating Limits Report, Cycle 22, Version 2 NL-20-0415, Vogle, Unit 1, Core Operating Limits Report Cycle 23 Version 32020-04-13013 April 2020 Vogle, Unit 1, Core Operating Limits Report Cycle 23 Version 3 NL-18-1356, Core Operating Limits Report, Cycle 22, Version 12018-10-30030 October 2018 Core Operating Limits Report, Cycle 22, Version 1 NL-17-1757, Core Operating Limits Report, Cycle 20, Version 12017-11-0202 November 2017 Core Operating Limits Report, Cycle 20, Version 1 NL-17-1063, Core Operating Limits Report, Cycle 21 Version 12017-06-0606 June 2017 Core Operating Limits Report, Cycle 21 Version 1 NL-16-0597, Cycle 19 Core Operating Limits Report, Version 22016-04-20020 April 2016 Cycle 19 Core Operating Limits Report, Version 2 NL-15-2014, Submittal of Core Operating Limits Reports2015-11-0202 November 2015 Submittal of Core Operating Limits Reports NL-15-1602, Cycle 19 Core Operating Limits Report Version 22015-08-21021 August 2015 Cycle 19 Core Operating Limits Report Version 2 NL-14-1719, Cycle 18 Core Operating Limits Report, Version 12014-10-30030 October 2014 Cycle 18 Core Operating Limits Report, Version 1 NL-14-0753, Cycle 19 Core Operating Limits Report2014-05-13013 May 2014 Cycle 19 Core Operating Limits Report ML14133A6772014-05-13013 May 2014 Cycle 19 Core Operating Limits Report NL-14-0753, Vogtle, Unit 1 - Cycle 19 Core Operating Limits Report2014-05-13013 May 2014 Vogtle, Unit 1 - Cycle 19 Core Operating Limits Report NL-13-0646, Cycle 17 Core Operating Limits Reports2013-04-0505 April 2013 Cycle 17 Core Operating Limits Reports NL-12-2622, Unit 1 Cycle 18 Core Operating Limits Report2012-12-19019 December 2012 Unit 1 Cycle 18 Core Operating Limits Report NL-11-2044, Cycle 16 Version 2 Core Operating Limits Report2011-10-26026 October 2011 Cycle 16 Version 2 Core Operating Limits Report NL-11-0919, Cycle 17 Core Operating Limits Report2011-05-16016 May 2011 Cycle 17 Core Operating Limits Report NL-10-1213, Cycle 15 Version 3 Core Operating Limits Report2010-06-28028 June 2010 Cycle 15 Version 3 Core Operating Limits Report NL-10-0662, Unit 2 Cycle 15 Version 2 Core Operating Limits Report2010-04-0202 April 2010 Unit 2 Cycle 15 Version 2 Core Operating Limits Report NL-10-0389, Cycle 15 Core Operating Limits Report2010-03-17017 March 2010 Cycle 15 Core Operating Limits Report NL-09-1588, Cycle 16 Core Operating Limits Report, Rev. 0, & Rev. 12009-10-26026 October 2009 Cycle 16 Core Operating Limits Report, Rev. 0, & Rev. 1 NL-08-1651, Supplement to Unit 2 Cycle 14 Core Operating Limits Report, Rev 02008-10-31031 October 2008 Supplement to Unit 2 Cycle 14 Core Operating Limits Report, Rev 0 NL-07-0744, Cycle 13 Core Operating Limits Report, Rev. 02007-04-11011 April 2007 Cycle 13 Core Operating Limits Report, Rev. 0 NL-07-0012, Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report2007-01-30030 January 2007 Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report NL-06-2319, Cycle 14 and Unit 2 Cycle 12 - Core Operating Limits Reports2006-10-20020 October 2006 Cycle 14 and Unit 2 Cycle 12 - Core Operating Limits Reports NL-06-1092, Cycle 13 Core Operating Limits Report2006-05-31031 May 2006 Cycle 13 Core Operating Limits Report NL-06-0151, Cycle 13 Core Operating Limits Report2006-01-31031 January 2006 Cycle 13 Core Operating Limits Report NL-05-2061, Revision 1 of Unit 1 Cycle 13 Core Operating Limits Report2005-11-18018 November 2005 Revision 1 of Unit 1 Cycle 13 Core Operating Limits Report NL-05-1739, Cycle 12 Core Operating Limits Report2005-09-30030 September 2005 Cycle 12 Core Operating Limits Report NL-05-0533, Cycle 13 Core Operating Limits Report2005-03-21021 March 2005 Cycle 13 Core Operating Limits Report NL-04-0623, Cycle 11 Core Operating Limits Report2004-04-28028 April 2004 Cycle 11 Core Operating Limits Report NL-03-1078, Cycle 11 Core Operating Limits Report2003-05-13013 May 2003 Cycle 11 Core Operating Limits Report ML0230202852002-10-16016 October 2002 Cycle 10 Core Operating Limits Report ML0209301632002-03-28028 March 2002 Cycle 11 Core Operating Limits Report 2024-09-25
[Table view] Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09
[Table view] |
Text
J. Barnie Beasley, Jr., P.E. Southern Nuclear Vice President Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205,992.7110 Fax 205.992.0403 SOUTHERN .. 4A COMPANY Energy to Serve Your WorldSM March 28, 2002 LCV- 1609 Docket Nos: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT Pursuant to the reporting requirements of Vogtle Electric Generating Plant (VEGP)
Technical Specification 5.6.5, Southern Nuclear Operating Company (SNC) is submitting Revision 0 of the Unit 1 Cycle 11 Core Operating Limits Report (COLR).
Sincerely, JBB/RJF Attachment cc: Southern Nuclear Operating Compan'y Mr. J. T. Gasser Mr. M. Sheibani SNC Document Management U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. F. Rinaldi, Vogtle Project Manager, NRR Mr. J. Zeiler, Senior Resident Inspector, Vogtle po o(
VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 0 MARCH 2002
COLR for VEGP UNIT 1 CYCLE 11 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP UNIT 1 CYCLE 11 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Requirement affected by this report is listed below:
13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 The Technical Specifications affected by this report are listed below:
3.1.1 SHUTDOWN MARGIN - MODES 3,4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor - Fa(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor - F H 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration PAGE 1 of 14
COLR for VEGP UNIT 1 CYCLE 11 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 NRC-approved methodologies, including those specified in Technical Specification 5.6.5.
2.1 SHUTDOWN MARGIN - MODES 1 AND 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent Ak/k.
2.2 SHUTDOWN MARGIN - MODES 3,4 AND 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.
2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOLJARO/HZP - MTC shall be less positive than +0.7 x 10-4 Ak/k/lF for power levels up to 70 percent RTP with a linear ramp to 0 Ak/kPOF at 100 percent RTP.
The EOL/ARO/RTP-MTC shall be less negative than
-5.50 x 104 Ak/k/PF. 1 2.3.2 The MTC Surveillance limits are:
The 300 ppm/ARO/RTP-MTC should be less negative than or equal to -4.75 x 104 Ak/k/OF. 1 The 60 ppm/ARO/RTP-MTC should be less negative than
-5.35 x 104 Ak/k/0 F. 1 where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.
2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control banks shall be limited in physical insertion as shown in Figure 3.
1Applicable for full-power T-average of 586.4 0 F to 587.40 F.
PAGE 2 of 14
COLR for VEGP UNIT 1 CYCLE 11 2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1)
RTP Fa 2.6.1 Fo(Z) -
RTP Fo F 0(Z)*< K(Z) for P < 0.5
0.5 where
P = THERMAL POWER RATED THERMAL POWER RTP 2.6.2 F0 = 2.50 2.6.3 K(Z) is provided in Figure 4.
RTP 2.6.4 FQ(Z)* Fon *K(Z) for P > 0.5 P *W(Z)
RTP FQ(Z) <*F
- K(Z) for P < 0.5 0.5 *W(Z) 2.6.5 W(Z) values are provided in Figures 6 through 9.
2.6.6 The Fa(Z) penalty factors are provided in Table 1.
PAGE 3 of 14
COLR for VEGP UNIT 1 CYCLE 11 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FNH (Specification 3.2.2) 2.7.1 F*H!FT (1 + PFAH * (l-P))
where: P = THERMAL POWER RATED THERMAL POWER 2.7.2 F = 1.65 2.7.3 PFAH = 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 5.
2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 1970 ppm.1
'This concentration bounds the condition of kef < 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B13depletion.
PAGE 4 of 14
COLR for VEGP UNIT 1 CYCLE 11 TABLE 1 Fo(Z) PENALTY FACTOR Cycle Fa(Z)
Burnup Penalty (MWD/MTU) Factor 30 1.020 150 1.030 363 1.029 576 1.025 789 1.022 1002 1.020 Notes:
- 1. The Penalty Factor, to be applied to Fa(Z) in accordance with SR 3.2.1.2, is the maximum factor by which Fa(Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting from the burnup at which the Fa(Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle burnups.
- 3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.
PAGE 5 of 14
COLR for VEGP UNIT 1 CYCLE 11 nn-t3f3 I I
,J .UU ACCEPTABLE OPERATING REGION z 3.00 -
I _________________ L REQI UIRED SHUT DOWN
- 1 (2500, 3.1jjo 0010 MAt RGIN z0 (1600,Z.50 D' AA-- I _ __ _ _ _ 1 I__ 4 mB Z.uu o3 UNACCEPTABLE OPERATING (950, 1.30) REGION 1.00 I + t -~~~~~I-----------
1.00 -
A nrI J AA 0 500 1000 1500 2000 2500 21r5-1 RCS BORON CONCENTRATION (ppm)
FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (MODE 4 WITH AT LEAST ONE REACTOR COOLANT PUMP RUNNING)
PAGE 6 of 14
COLR for VEGP UNIT 1 CYCLE 11 Y
5.00 p (2500, 4.90) i2 4.00 1 4 ACCEPTABLE OPERATING REGION i I 000 E 3.00 (1250, 2.85) z REQUIRED SHUTDOWN MARGIN O* 2.00
/
0 I-co UNACCEPTABLE
..1- OPERATING REGION A I -
1.4t3t3 nn-m i r (460,1.00)
A' nn, 0 500 1000 1500 2000 2500 2176-1 RCS BORON CONCENTRATION (ppm)
FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WITH NO REACTOR COOLANT PUMPS RUNNING)
PAGE 7 of 14
COLR for VEGP UNIT 1 CYCLE 11 (Fully Withdrawn *)
225 220 280%225) (78.0%, 225-1 14 200 BNKB KB 180 160 r(0%. 161) _ (100%, 161) z 4-o 140 BANKC __
0)
(0 80o 120/-
100
/ I 80 BANK D 0
cc O 60 40 *(0%, 46) /
20 A nI (30.2%, 0)-
0 20 40 60 80 100 POWER (percent of Rated Thermal Power) 2175-1
- Fully withdrawn shall be the condition where control rods are at a position within the interval ;225 and s231 steps withdrawn.
NOTE: The Rod Bank Insertion Umits are based on the control bank withdrawal sequence A,B, C,D and a control bank tip-to-tip distance of 115 steps.
FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER PAGE 8 of 14
COLR for VEGP UNIT 1 CYCLE 11 1.20 1.00 0
I 0.80 CD IL 0.60 N 2 z
0.4 F0 =2.50 CORE HEIGHT KZ 0.2 0o 0.000 1.000 6.000 1.000 12.000 0.925 n _ ___L_._
0 2.0 4.0 6.0 8.0 10.0 12.0 2175-"
CORE HEIGHT (ft)
FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT PAGE 9 of 14
COLR for VEGP UNIT 1 CYCLE 11 12[I "1 Vt I I I, I
(-12, 100) (+10, 100)1_____
100 UNACCEPTABLE UNACCEPTABLE
- 0t 80 ACCEPTABLE "C
60 n
-o a, (-25, 50) (+26, 50) 40 w
20
- 0) - - - - -~-L
-5C ) -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent Al)
FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FOR RAOC PAGE 10 of 14
COLR for VEGP UNIT 1 CYCLE 11 Axial Elevation BOL Point
- 1 3 11.60 1.0000 4 11.20 1.0000 5 11.00 1.0000
- t 6 10.80 1.0000 7 10.60 1.0000 It 8 10.40 1.0000 9 10.20 1.0000 10 11 10.00 1.3488 12 9.80 1.3221 13 9.60 1.2927 14 9.40 1.2699 15 9.20 1.2496 16 9.00 1.2289 17 8.80 1.2186 18 8.60 1.2164 19 8.40 1.2196 20 8.20 1.2203 21 8.00 1.2243 22 7.80 1.2299 23 7.60 1.2317 24 7.40 1.2313 N 25 7.20 1.2286 26 7.00 1.2240 27 6.80 1.1935 28 6.60 1.1859 29 6.40 1.1784 30 6.20 1.16%
31 6.00 1.1592 32 5.80 1.1539 33 5.60 1.1546 34 5.40 1.1643 35 5.20 1.1783 36 5.00 1.1924 37 4.80 1.2053 38 4.60 1.2176 39 4.40 1.2290 40 4.20 1.2393 41 4.00 1.2484 42 3.80 1.2526 43 3.60 1.2570 44 3.40 1.2602 45 3.20 1.2609 46 3.00 1.2694 47 2.80 1.2865 48 2.60 1.3060 49 2.40 1.3252 50 2.20 1.3451 51 2.00 1.3659
.0 6.0 8.0 12.0 :
41 52 53 54 1.80 1.60 1.A0 1.0000 1.0000 1.0000 Core Height - feet *t 55 1.20 1.0000
- t 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 "Thisfigure ib referred to by Spedfication B32..1 *t 60 0.20 1.0000 61 0.00 1.0000 Top and Bottom 15% Excluded per Tedgcal SpedficationB I32.1 These W(Z) values are consistent with Figure 5 and are valid over the HFP Tavg temperature range from 586.4 0F to 587.40 F.
FIGURE 6 RAOC W(Z) AT 150 MWD/MTU PAGE 11 of 14
COLR for VEGP UNIT 1 CYCLE 11 Elevation MOL-1 Point
8 10.80 1.0000 10.60 1.0000
- 10 10.20 1.0000 11 10.00 1.3554 12 9.80 1.3231 13 9.60 12937 14 9.40 12756 15 9.20 12540 16 9.00 12404 17 8.80 12.374 18 8.60 1.2374 19 8.40 12406 20 8.20 12412 21 8.00 1.2392 22 7.80 1.2351 23 7.60 1.2290 24 7.40 1.2211 N 25 7D0 12114 26 7.00 12001 27 6.80 1.1776 28 6.60 1.1680 29 6.40 1.1582 30 620 1.1499 31 6.00 1.1606 32 5.80 1.1548 33 5.60 1.1516 34 5.40 1.1560 35 5.20 1.1633 36 5.00 1.1702 37 4.80 1.1763 38 4.60 1.1816 39 4.40 1.1861 40 4.20 1.1896 41 4.00 1.1924 42 3.80 1.1987 43 3.60 1.2063 44 3.40 12125 45 3.20 12202 46 3.00 1.2329 47 2.80 12525 48 2.60 1.2766 49 2.40 13002 50 2.20 13236 51 2.00 1.3469
- 52 1.80 1.0000 12.0 53 1.60 1100 0.0 2.0 4.0 6.0 8.0 10.0 ** 54 1.40 1.0000
- 55 1.20 1)000 Core Height - feet
- 59 0.40 1.0000 This fige Is referred to by Specification I3V 1
- 61 0.00 1.000 Top and Bottom 15% Exduded per Technical Spedfication B3.2.1 These W(Z) values are consistent with Figure 5 and are valid over the HFP Tavg temperature range from 586.40Fto 587.40F.
FIGURE 7 RAOC W(Z) AT 4000 MWD/MTU PAGE 12 of 14
COLR for VEGP UNIT 1 CYCLE 11 Axial Elevation MOL-2 Point (1ee W0 6 . 1 1 79 2 11.80 1.0000
- 5 11.20 1.0000 6 11.00 1.0000
- 1. ,J
- 8 10.60 1.0000 9 10.40 1.0000
- 10 10.20 1.0000 11 10.00 1.3024 12 9.80 1.2899 13 9.60 1.2855 14 9.40 1.2785 15 9.20 1.2662 16 9.00 12544 17 8.80 1.2405 18 8.60 1.2309 19 8.40 1.2321 20 8.20 1.2315
. 21 8.00 1.2334 22 7.80 1.2390 N 23 7.60 12405
.24 7.40 1.2397 25 7.20 12362
'-1 L11LL-----Ii IIL 26 7.00 1.2305 AA 27 6.80 1.2225 28 6.60 1.2127 29 6.40 1.2015 30 .620 1.1898 AAA, Aa1 A 31 6.00 1.1781 A' 32 5.80 1.1699 A 33 5.60 1.1679 1.:2 34 35 5.40 5520 1.1710 1.1753 36 5.00 1.1785 37 4.80 1.1803 38 4.60 1.1808 39 4.40 1.1799 40 4.20 1.1778 41 4.00 1.1739 42 3.80 1.1707
- 1. 43 3.60 1.1693 44 3.40 1.1673 45 3.20 1.1659 46 3.00 1.1659 47 2.80 1.1698 48 2.60 1.1775 49 2.40 1.1856 50 2.20 1.1937
-51 2.00 12025 1 ri - 52 1.80 1.0000 0.0 2.0 4.0 6.0 8.0 10.0 12.0
- 53 54 1.60 1.40 1.0000 1.0000 Core Height - feet
- 55 1.20 1.0000 56 1.00 1.0000
- 57 0.80 1.0000 58 0.60 1.000
- 59 0.40 1.0000 This figure is referred to by Spedflcation 3.2.1 60 0.20 1.0000 61 0.00 1.0000 Top and Bottom 15% Exduded per Techmial Spedaiction B3.2.
These W(Z) values are consistent with Figure 5 and are valid over the HFP Tavg temperature range from 586.40Fto 587.4 0F.
FIGURE 8 RAOC W(Z) AT 12000 MWD/MTU PAGE 13 of 14
COLR for VEGP UNIT 1 CYCLE 11 Axial Elevation EOL Point
'II II6 I
- 1 11.80 1.0000 2 11.60 1.0000 3 11.40 1.0000 4 11.20 1.0000 5 11.00 1.0000 6 10.80 1.0000 P 7 10.60 1.0000
- 1. 5-I
- 8 10.40 1.0000 9 10.20 1.0000 10 11 10.00 1.2251 12 9.80 1.2274 13 9.60 1.2273 14 9.40 1.2268 15 9.20 1.2255 16 9.00 1.2335 17 8.80 1.2507 18 8.60 1.2647 19 8.40 1.2749 20 8.20 1.2862 21 8.00 1.2946 22 7.80 1.2917 23 7.60 1.3028 24 7.40 1.3092 v 1.3 25 7.20 1.3121 A hA 26 7.00 1.3116 27 6.80 1.3079 A 28 6.60 1.3012 29 6.40 1.2918 30 6.20 12800 SA 'AAAA 31 6.00 1.2653 32 5.80 1.2501 33 5.60 1.2416 A A* 34 5.40 1.2419 1.2 hAA*A 35 5.20 1.2441 36 5.00 1.2443 37 4.80 1.2424 38 4.60 1.2382 39 4.40 1.2318 40 4.20 1.2234 41 4.00 1.2120 42 3.80 1.2016 43 3.60 1.1940 1.1 44 3.40 1.1850 45 3.20 1.1746 46 3.00 1.1772 47 2.80 1.1760 48 2.60 1.1823 49 2.40 1.1875 50 220 1.1955 51 2.00 1.2045 1.01t
- 52 1.80 1.0000 00 2.0 4.0 6.0 8.0 10.0 12.0 *
- 53 1.60 1.0000 54 1.40 1.0000 Core Height - feet 55 1.20 1.0000 56 1.00 1.0000 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 This figure Is referred to by Spedfication B3..Li
- 60 0.20 1.0000 61 0.00 1.0000
- Top and Bottom 15% Exduded per Tecnical Specfition B32-1 These W(Z) values are consistent with Figure 5 and are valid over the HFP Tavg temperature range from 586.40 F to 587.4 0F.
FIGURE 9 RAOC W(Z) AT 20000 MWD/MTU PAGE 14 of 14