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Category:Fuel Cycle Reload Report
MONTHYEARRS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) BYRON 2023-0012, Cycle 26 Core Operating Limits Report2023-03-16016 March 2023 Cycle 26 Core Operating Limits Report ML22181A0492022-06-30030 June 2022 Core Operating Limits Report (COLR) for Byron Unit 1 Cycle 25 BYRON 2022-0039, Core Operating Limits Report (COLR) for Byron Unit 2 Cycle 242022-06-30030 June 2022 Core Operating Limits Report (COLR) for Byron Unit 2 Cycle 24 BYRON 2022-0028, Cycle 24 Core Operating Limits Report2022-04-28028 April 2022 Cycle 24 Core Operating Limits Report BYRON 2021-0064, Cycle 25 Core Operating Limits Report2021-09-28028 September 2021 Cycle 25 Core Operating Limits Report BYRON 2020-0067, Cycle 22 Core Operating Limits Report2020-10-20020 October 2020 Cycle 22 Core Operating Limits Report BYRON 2020-0015, Cycle 24 Core Operating Limits Report2020-03-17017 March 2020 Cycle 24 Core Operating Limits Report BYRON 2019-0040, Cycle 22 Core Operating Limits Report2019-04-15015 April 2019 Cycle 22 Core Operating Limits Report BYRON 2019-0015, Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report2019-03-0707 March 2019 Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report BYRON 2018-0096, Cycle 23 Core Operating Limits Report2018-09-17017 September 2018 Cycle 23 Core Operating Limits Report BYRON 2017-0098, Cycle 21 Core Operating Limits Report2017-10-0909 October 2017 Cycle 21 Core Operating Limits Report BYRON 2017-0017, Cycle 22 Core Operating Limits Report2017-03-0909 March 2017 Cycle 22 Core Operating Limits Report BYRON 2016-0035, Cycle 20 Core Operating Limits Report2016-04-26026 April 2016 Cycle 20 Core Operating Limits Report BYRON 2015-0103, Cycle 21 Core Operating Limits Report2015-09-22022 September 2015 Cycle 21 Core Operating Limits Report RS-14-118, Annual 1 0 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-04-0707 April 2014 Annual 1 0 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors BYRON 2014-0002, Cycle 19 and Unit 2 Cycle 18 Core Operating Limits Report for Measurement Uncertainty Recapture (Mur) Power Uprate2014-02-13013 February 2014 Cycle 19 and Unit 2 Cycle 18 Core Operating Limits Report for Measurement Uncertainty Recapture (Mur) Power Uprate BYRON 2013-0051, Cycle 18 Core Operating Limits Report2013-04-15015 April 2013 Cycle 18 Core Operating Limits Report BYRON 2012-0104, Cycle 19 Core Operating Limits Report2012-09-20020 September 2012 Cycle 19 Core Operating Limits Report BYRON 2011-0139, Cycle 17 Core Operating Limits Report2011-09-29029 September 2011 Cycle 17 Core Operating Limits Report BYRON 2011-0093, Inservice Inspection Summary Report for Refueling Outage 172011-07-14014 July 2011 Inservice Inspection Summary Report for Refueling Outage 17 BYRON 2011-0059, Submittal of Cycle 18 Core Operating Limits Report, Revision 72011-04-0707 April 2011 Submittal of Cycle 18 Core Operating Limits Report, Revision 7 BYRON 2010-0040, Cycle 16 Core Operating Limits Report2010-05-0303 May 2010 Cycle 16 Core Operating Limits Report BYRON 2009-0107, Cycle 17 Core Operating Limits Report2009-09-30030 September 2009 Cycle 17 Core Operating Limits Report BYRON 2008-0108, Cycle 15 Core Operating Limits Report2008-10-16016 October 2008 Cycle 15 Core Operating Limits Report BYRON 2008-0031, Cycle 16 Core Operating Limits Report2008-04-0404 April 2008 Cycle 16 Core Operating Limits Report BYRON 2007-0050, Cycle 14 Core Operating Limits Report2007-04-17017 April 2007 Cycle 14 Core Operating Limits Report BYRON 2007-0014, Cycle 15 Core Operating Limits Report, Revision 42007-01-23023 January 2007 Cycle 15 Core Operating Limits Report, Revision 4 BYRON 2006-0108, Cycle 15 Core Operating Limits Report2006-09-20020 September 2006 Cycle 15 Core Operating Limits Report ML0600503402006-01-0303 January 2006 Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B.6 Page 23 ML0600503422006-01-0303 January 2006 Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment C - Attachment D.1, Pages 24 Through 31 BYRON 2006-0007, Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 222006-01-0303 January 2006 Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 22 ML0600503362005-12-0505 December 2005 Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Pages 1 Through 16 BYRON 2005-0119, Cycle 13 Core Operating Limits Report2005-10-0707 October 2005 Cycle 13 Core Operating Limits Report BYRON 2005-0037, Cycle 14 Core Operating Limits Report2005-03-23023 March 2005 Cycle 14 Core Operating Limits Report BYRON 2004-0036, Issuance of Core Operating Limits Report, Cycle 122004-04-0505 April 2004 Issuance of Core Operating Limits Report, Cycle 12 BYRON 2003-0093, Issuance of Core Operating Limits Report for Byron Unit One Cycle 132003-10-0707 October 2003 Issuance of Core Operating Limits Report for Byron Unit One Cycle 13 BYRON 2003-0079, to Byron, Unit 1 Cycle 12, Core Operating Limits Report and Revision1 to Byron, Unit 2 Cycle 11, Core Operating Limits Report2003-08-28028 August 2003 to Byron, Unit 1 Cycle 12, Core Operating Limits Report and Revision1 to Byron, Unit 2 Cycle 11, Core Operating Limits Report BYRON 2002-0100, Cycle 11 Core Operating Limits Report2002-09-27027 September 2002 Cycle 11 Core Operating Limits Report BYRON 2002-0074, Cycle 12 Core Operating Limits Report, Revision 22002-08-0606 August 2002 Cycle 12 Core Operating Limits Report, Revision 2 BYRON 2002-0023, Revision 3 to Cycle 11A Core Operating Limits Report2002-02-27027 February 2002 Revision 3 to Cycle 11A Core Operating Limits Report 2024-04-25
[Table view] Category:Letter type:BYRON
MONTHYEARBYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical 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Radiological Environmental Operating Report (AREOR) BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-04-0606 April 2023 Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements BYRON 2023-0012, Cycle 26 Core Operating Limits Report2023-03-16016 March 2023 Cycle 26 Core Operating Limits Report BYRON 2022-0081, CFR72.48 Evaluation Summary Report2022-12-0909 December 2022 CFR72.48 Evaluation Summary Report BYRON 2022-0072, Steam Generator Tube Inspection Report for Refueling Outage 232022-10-27027 October 2022 Steam Generator Tube Inspection Report for Refueling Outage 23 BYRON 2022-0069, 2021 Regulatory Commitment Change Summary Report2022-10-13013 October 2022 2021 Regulatory Commitment Change Summary Report BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment2022-10-13013 October 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment BYRON 2022-0065, Registration of Use of Cask to Store Spent Fuel2022-10-13013 October 2022 Registration of Use of Cask to Store Spent Fuel BYRON 2022-0063, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for September 9, 2021 to September 8, 20222022-09-29029 September 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for September 9, 2021 to September 8, 2022 BYRON 2022-0064, Letter 2022-0064 Submittal of Byron Integrated Initial License Training Examination Materials(Signed)2022-09-28028 September 2022 Letter 2022-0064 Submittal of Byron Integrated Initial License Training Examination Materials(Signed) BYRON 2022-0059, Registration of Use of Cask to Store Spent Fuel2022-09-15015 September 2022 Registration of Use of Cask to Store Spent Fuel BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)2022-07-15015 July 2022 Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) BYRON 2022-0026, Annual Radiological Environmental Operating Report2022-05-0505 May 2022 Annual Radiological Environmental Operating Report BYRON 2022-0030, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Report2022-05-0303 May 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Report BYRON 2022-0028, Cycle 24 Core Operating Limits Report2022-04-28028 April 2022 Cycle 24 Core Operating Limits Report BYRON 2022-0016, Annual Dose Report for 20212022-04-0707 April 2022 Annual Dose Report for 2021 BYRON 2021-0072, Post Exam Submittal Letter2021-10-28028 October 2021 Post Exam Submittal Letter BYRON 2021-0033, Submittal on Initial Operator Licensing Examination Outline2021-10-28028 October 2021 Submittal on Initial Operator Licensing Examination Outline BYRON 2021-0063, Reactor Coolant System Pressure and Temperature Limits Report2021-09-28028 September 2021 Reactor Coolant System Pressure and Temperature Limits Report BYRON 2021-0064, Cycle 25 Core Operating Limits Report2021-09-28028 September 2021 Cycle 25 Core Operating Limits Report BYRON 2021-0032, 2020 Annual Radiological Environmental Operating Report (AREOR)2021-05-0606 May 2021 2020 Annual Radiological Environmental Operating Report (AREOR) BYRON 2021-0031, 2020 Annual Radioactive Effluent Release Report2021-04-21021 April 2021 2020 Annual Radioactive Effluent Release Report BYRON 2021-0027, Annual Dose Report for 20202021-03-30030 March 2021 Annual Dose Report for 2020 BYRON 2021-0023, Registration of Use of Cask to Store Spent Fuel2021-03-25025 March 2021 Registration of Use of Cask to Store Spent Fuel BYRON 2021-0024, 2020 Regulatory Commitment Change Summary Report2021-03-19019 March 2021 2020 Regulatory Commitment Change Summary Report BYRON 2021-0001, Day Inservice Inspection Report for Interval 4, Period 2, (B2R22)2021-01-13013 January 2021 Day Inservice Inspection Report for Interval 4, Period 2, (B2R22) BYRON 2020-0087, National Pollutant Discharge Elimination System (NPDES) Permit No. IL00483132020-12-16016 December 2020 National Pollutant Discharge Elimination System (NPDES) Permit No. IL0048313 BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report2020-12-10010 December 2020 10 CFR 72.48 Evaluation Summary Report BYRON 2020-0085, 10 CFR 50.59 Summary Report2020-12-10010 December 2020 10 CFR 50.59 Summary Report BYRON 2020-0067, Cycle 22 Core Operating Limits Report2020-10-20020 October 2020 Cycle 22 Core Operating Limits Report BYRON 2020-0063, Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Repo2020-10-0101 October 2020 Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Repo BYRON 2020-0053, Steam Generator Tube Inspection Report for Refueling Outage 232020-09-10010 September 2020 Steam Generator Tube Inspection Report for Refueling Outage 23 BYRON 2020-0025, Annual Dose Report 20192020-03-24024 March 2020 Annual Dose Report 2019 BYRON 2020-0015, Cycle 24 Core Operating Limits Report2020-03-17017 March 2020 Cycle 24 Core Operating Limits Report BYRON 2020-0010, Revision to Byron Station Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 172020-02-13013 February 2020 Revision to Byron Station Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 17 BYRON 2020-0008, 2019 Regulatory Commitment Change Summary Report2020-02-0707 February 2020 2019 Regulatory Commitment Change Summary Report BYRON 2019-0105, Post Examination Submittal Letter2019-11-26026 November 2019 Post Examination Submittal Letter BYRON 2019-0095, Registration of Use of Cask to Store Spent Fuel2019-10-10010 October 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0090, Registration of Use of Cask to Store Spent Fuel2019-09-18018 September 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0078, Registration of Use of Cask to Store Spent Fuel2019-08-22022 August 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0041, Revision to Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 162019-04-25025 April 2019 Revision to Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 16 2024-05-09
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N1kac2 ear September 20,2006 LTR: BYRON 2006-01 08 File: 1.10.0101 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit I Facitity Operating License No. NPF- 37 NRC Docket No. STN 50-454
Subject:
Byron Station Unit 1 Cycle 15 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the Unit 1 Cycle 15 COLR. Please note an administrative change has been made to record keeping of revisions to the COLR. Instead of starting each cycle with revision 0, we wilt continue to use the next sequential number. This attached COLR is revision 3, which is the first COLR for Unit 1 cycle 15. Should you have any questions concerning this report, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, ~aCid M ~oots Site Vice President Byron Nuclear Generating Station
Attachment:
Byron Station Unit 1 Cycle 15 COLR AITACHMENT Byron Station Unit 1 Cycle f 5 Core Operating Limits Report CORE OPERATtNG LIMITS REPORT (COLR) FOR BYRON UNIT 1 CYCLE 15 EXELON TRACKING ID: COLR BYRON 1 REVISION 3 COLK BYRON 1 Revision 3 Page 1 of 13 CUR6 OPER.ATtNG LIMITS REPORI' (COLR) for Bl-ROIL C'NIT I CYCLE : 5 1.0 CORE OPERATING LlMtTS REPORT This Core Operating Limits Report (CUR) for Byron Station Unit 1 Cycie 15 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS). The Technical Specifications affected by this report are listed beiow: St 2.1 .I Reactor Core Safety Limits (Stsj LC0 3.1 .I SHUTDOWN MARGIN fSDMf LC0 3.1.3 Moderator Temperature Coefficient (MTC) LCO 3.1.4 Rod Group Alignment Limits LC0 3.2.5 Shutdown Bank Insertion Limits LC0 3.1.6 Control Bank Insertion Limits LC0 3.1.8 PWYStCS TESTS Exceptions - MODE 2 LC0 3.2.1 Heat Flux Hot Channel Factor
{Fa(Z)) LC0 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F'.>~) LC0 3.2.3 AXIAL FLUX DIFFERENCE (AFD) LC0 3.2.5 Departure from Nucleate Boiiing Ratio (DNBR) LC0 3.3.1 Reactor Trip System (RTS)
Instrumentation LC0 3.3.9 Boron Dilution Protection System JBDPS) LC0 3.4.1 Reactor Coolant System (RCS) Pressure. Temperature, and Flow Departure from Nucleate Boiling (DNBf Limits LC0 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below: TRM TLCO 3.1.b Boration Flow Paths - Operating TRM TLCO 3. I .d Charging Pumps - Operating TRM TLCO 3.1 .f Borated Water Sources - Operating TRM TLCO 3. I .g Position indication System - Shutdown TRM TLCO 3.1 .i Shutdown Margin (SDMJ - MODE 5 TRM TLCO 3.1 .j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exceptionj COltE 0PERATIE.G LIMITS REPORI' (COLR) for BIeRO?J LrNl'f I CYCLk. 15 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 2.0 are presenied in the foliowing subsections. These iirnits are applicable for the entire cycle unless otherwise identified. These limits have been developed using the NRC-approved methodologies specified in Technicai Specification 56.5. 2.1 Reactor Core Safety Limits (SLs) (SL 2.1 .I) 2.1.1 In MORES I and 2, the combination of Thermal Power, Reactor Coolant System JRCS) highest loop average temperature, and pressurizer pressure shalt not exceed the limits specified in Figure 2.1 .$ . Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits CCXR BYRON 1 Rci,islon 3 Page 3 of 13 t'ORt: OPERATIYG LIMITS RkPORT fCOLRi for BYRON IJNJ?' I CYCLE 15 2.2 SHUTDOWN MARGIN (SDM) The SDFtl limit for MODES 1, 2, 3, and 4 is: 2.2.1 The SDM shall be greater than or equal to 1.3%
AWk (LC-0s 3.1.1. 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.2.d, 3.l.f, 3.l.h, and 3.l.j). The SDM limit for MODE 5 is: 2.2.2 SDM shall be greater than or equal to 1.3% IMk (LC0 3.1.1, LC0 3.3.9; TRM TLCOs 3.1.i and 3.1.j). 2.3 Moderator Temperature Coeecient (MTC) (LC0 3.2.3) The Moderator Temperature Coefficient (MTCj limits are: 2.3.1 The BOLIAROIHZP-MTC upper limit shall be +2.1 x t0-' Aklki0F. 2.3.2 The EOLIAKOIHFP-MTC lower limit shalt be -4.6 x 10.~ AWW0F 2.3.3 The EOL!ARO/WFP-MTC Surveillance limit at 300 ppm shall be -3.7 x -lo4 nk/ki0F. 2.3.4 The EOLIAROIHFP-MTC Surveillance limit at 60 ppm shall be
-4.3 x 20'"ikIki"~. where: BOL stands for Beginning of Cycle Life ARO stands far All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power
2.4 Shutdown
Bank Insertipn Limits (LC0 3.1.5) 2.4.1 Ali shutdown banks shail be fufly withdrawn to at least 224 steps.
2.5 Controf
Bank insertion Limits (LC0 3.1.6) 2.5.1 The control banks, with Bank A greater than or equai to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1. 2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps. 2.5.3 The control banks shali be operated in sequence by withdrabvat of Bank Ax Bank B, Bank C and Bank D. The control banks shati be sequenced in reverse order upon insertion.
2.5.4 Each controi bank not fully withdrawn from the core shall be operated with the following overlap limits as a f;indion of park position. . . - " Park Position lste~) I Overlao Limit isteol t OLR BY ROV I Rcvisron 3 Pagc 4 of 13 f ORE OPER 47 1Ntj LIMI TS RtPORT iCQLR) ibr Bk-RON LKIT 1 CYCL f-. I5 Figure 2.5.1 : Contrd Bank Insertion Lirniis Verrsus Percent Rated Thermal Power 0 10 20 30 40 50 60 70 80 90 I100 Relative Power (Percent)
COLR BYRON 1 Re~isiorl 3 Page 5 of i 3 CORE OPt.,RAI'IKCr LlVlTS REPORT (COLR) fbr HYRON CYIT I CYCLE I5 2.6 Heat Flux Hot Channel Factor (FGQ (LC0 3.2.1 j 2.6.1 Total Peaking Factor Fog,) sc.di?(Zj
- biP :-0.5 P where: P = the ratio of T HERMAL POWER to RATED THERMAL POWER K(Z) is provided in Figure 2.6.1. 2.6.2 WjZ) Values: a) When PDMS is OPERABLE, W(Z) = 1.00000 for alt axial points. bj When PDMS is inoperabie.
W(Z) is provided in Table 2.6.2.a. The normat operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. Tabie 2.6.2.b shows the
~"~(z) penalty factors that are greater than 2% pet;*3? Effective Full Power Days (EFPD). These values shatl be used to increase the FV',(z) as per Surveiliance Requirenient 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.b.
2.6.3 Uncertainty
The uncertain&, UFQ, to be applied to the Heat FIux Hot Channel Factor Fr;(Z) shall be cafculated by the following formula where: U,,, = Base F, measurement uncertainty
= 1.05 when PDMS is inoperabie jU,.' is defined by PDMS when OPERABLE.)
U, = Engineering uncertainty factor = 1.03 F,(Z:I Warning Setpoint 2 2% of F,(Zj Margin F,fZ) Alarm Setpoint 0% of F&) Margin COLR BYRON I Re\ islon 3 Page6of 13 CORE OPERATIhG LIMITS REPORT (COLR) 'rjr BYRON I NIT 1 CYCLE 15 Figure 2.6,l KfZ) - Normalized F,fZ) as a Function of Core Height 0 123456789101112 BOTTOM Care Weight (ft) "TOP COLR RYRCJK I Rebrs~ct~~
3 Pagc 7 of 13 CCIKE OPERA7 XNG LIYIIII'TS REPORT (COLR) f01 HE'KOh LVIT 1 CYCLE 15 I Table 2.6.2.a W(Z) versus Care Weight Vote. W(Z> values at 200(00 bl:tdD/MTU may be applied to cycle burntips greater than 2Oc00 FilVdD!hi"TLl to prevent LViZ) funct~cn extrapoiation COLR BYKOb 1 Re\- won 3 Pagc 8 of li CORE OPERATlZG LIMJ"I"S REPORT (COLR) for- HYROK L NIT 1 CYCLE IS Penalty Factors in Excess of 2% per 31 EFPD 3.0318 1.0356 1.0388 1.0412 1706 ---- --- 1.0368 . -- 1878 ----- 1.0335 2051 .- 1.0305 2224 1.0279 2397 -- 1.0257 2570 1.0239 2743 1 1.0225 291 5 - 1.0215 3088 3 -- 1 ,0207 1 1 326 1 1.0200 Notes: Linear interpolation is adequate for intermediate cycle burnups All cycle burnups outside the range of the table shal! use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Reqttirements.
f OLR BYRON 1 Kcv~bmn 3 Page 9 of 13 C+C)RF; OPERA?-IUCi LIMITS REPORT (C'OLR) for BYRON UYIT I CYCLE 15 where: P = the ratto of THERMAL POWER to RATED THERMAL POWER FRTP = :x 1.70 PF++ = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, Ur$ti, to be appfied to the Nuclear Enthalpy Rise Hot Channel Factor F",~ shall be calculated by the follow:ng formula: UF $H = Ui" Win where: UF iWra = Base F",, measurement uncertainty
= 1.04 2.7.3 PDMS Alarms: F',~ Warning Setpoint 2 2% of FMjH Margin F~,~ Alarm Setpornt > 0% of F~,~ Margin 2.8 AXIAL FLUX DIFFERENCE (AFD'j (LC0 3.2.3) 2.8.2 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
2.8.2 When PDMS is OPERABLE, no AFD Acceptabfe Operation Limits are applicable.
2.9 Departure
from Nucleate Boilinc; Ratio (DNBR) (LC0 3.2.5) 2.9.1 DNBRA~~: 2 1.536 The Axial Power Shape Limiting DNBR (DNBR,;pst) is applicable with THERhilAL POWER 2 50% RIP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warn~ng Setpo~nt lz 2% of DNBR Margin DNBR Alarm Setpolnt 2 '3% ol UNBK Pnargln C OLR BYKOk i Rcvrsion -3 Page IOof 13 CORE UPkRA'I ING Llhll f S REPORT (COLRI for BYRON UKIT 1 CYCLE 15 Figure 2.8,1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS lnoperabfe AXIAL FLUX DIFFERENCE f%j COL,II BYRCfK 1 Re\ ismn 3 Page I l of 13 CORE OPER.k7'1U(i LIC'IITS REPORT (COLR) ihr B1'KO"L LEI t. 1 CYCtt: 1 ti 2.10 Reactor Trip System IRTS) Instrumentation (LC0 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overiemperaiure ST reactor trip setpoint Ki shall be equai to 1.325. 2.10.2 The Overtemperature tT reactor trip setpoint T,, coefficient K2 shall be equal to 0.0297 1 "F. 2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient Ks shall be equal to 0.00182 /psi. 2.10.4 The nominal T,.*, at RTP jindicatedj T' shall be iess than or equai to 588.0 "F 2.10.5 The nominal RCS operating pressure (indicated)
Pr shall be equal to 2235 psig. 2.10.6 The measured reactor vessel AT leadllag time constant TI shall be equai to 8 sec. 2.10.7 The measured reactor vessei :IT ieadilag time constant ~~shafl be equai to 3 sec. 2.10.8 The measured reactor vessel AT lag time constant 13 shall be less than or equal to 2 see. 2.20.9 The measured reactor vessel average temperature leadllag time constant r4shali be eclual to 33 sec. 2.10.iO The measured reactor vessel average temperature
[eadllag time constant r5sRall be equal to 4 sec. 2.10.1 2 The measured reactor vessel average temperature lag time constant r, shall be less than or equai to 2 see. 2:t0.;2 The f: (A!) "positive" breakpoint shaii be +10% "01. 2 10.1 3 The f: (Ali "negatrve" breakpoint shall be -18% -\I 2 10.14 The i. j/fl) 'pasliive" slope shail be +3.47'/0 i O/o 51. 2 10 15 The f4 (31 "negative" slope shal! be -2 61% / O:o \f C01-R KYROY I Kc\ laiofi 3 Page 12of13 CORE OPIL it ATItiG LIXIITS REPORT (COLR) for HYROR LWIT 1 CYCLE 15 2.1 2 Reactor Tri~ Svstem IRTS) Instrumentation (LC0 3.3.1) - Overpower fT Setpoint Parameter Values 2.1 1 .I The Overpower IT reactor trip setpoint Ks shall be equal to I .072 2.12.2 The Overpower AT reactor trip setpoint T,,, rateilag coefficient Kg shall be equal to 0.02 / "F for increasing T,,, 2.1 1.3 The Overpower AT reactor trip setpoint T, ratellag coefficient Kc shalt be equal to 0 / "F for decreasin~
Pa, 2.1 1 4 The Overpower AT reactor trip setpoint T,, heatup coefficient KE; shall be equal to 0.00245 / "F when T .- f ". 2.5 1.5 The Overpower AT reactor trip setpoint T,,, heatup coefficient Kg shai! be equai to OI°FwhenTIT".
2.1 1.6 The nominal T,,,at RTP (indicated)
T" shaif be less than or equal to 588.0 "F 2.1 2.7 The measured reactor vessel AT leadllag time constant r, shall be equal to 8 sec. 2.1 1.8 The measured reactor vessel AT leadllag time constant r2 shall be equal to 3 sec 2.1 1.9 The measured reactor vessel AT lag time constant T, shall be less than or equat to 2 sec 2.1 1.10 The measured reactor vessei average temperature lag time constant r, shall be less than or equai to 2 see. 2.2 1 .I 1 The measured reactor vessel average temperature ratellag time constant s7 shall be equal to 10 sec. 2 1 ?.I 2 The f? ( 11) "pos~tive" breakpoint shall be 0 for all It. 2.1 1 .I 3 The f, {ill) "negat~ve" breakpoint shall be 0 for all (if. 2 11 .I4 The f, (/\I) "positive" siope shall be 0 for all ll 2 1 'I 15 The f, (11 I 'negative
' slope shalt be 0 for ali _\I CORE OPI-KXTI'LG LlMlTS REPORT (COt-Rj for BYIZON UYIT 1 CYCLk 15 2.12 Reactor Coolant System {RCSf Pressure.
TemBerature.
and Flow De~arture from Nucleate ma (DNB') Limits (LC0 3.4.1 f 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig. 2.12.2 The RCS average temperature (T,,) shail be tess than or equal to 593.1 "F. 2.12.3 The RCS totai flow rate shall be greater than or equal to 386,000 gpm.
2.1 3 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the value given in the Table below (LC0 3 9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle. 2.13.2 To maintain keff 5 0.987 with all shutdown and controt rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.2.g Required Action B.2 and TRf4 TtCO 3.1.k.2), the Reactor Coolant System boron concentratioo shall be greater than or equal to the values given in the Table beiow. COLK I Conditrons Boron Concentration I Section i Refueling 1 1739 a) prior to initial criticality I I 1819 1 2.13.2 ather times in core life 2026 1