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MONTHYEARML0217906482002-07-0303 July 2002 Request for Additional Information Re Proposed Revision to Kewaunee Nuclear Power Plant Design Basis Radiological Analysis Accident Source Term Project stage: RAI ML0222504372002-08-16016 August 2002 Letter Regarding Review of Submittals Supporting Future Measurement Uncertainty Recapture Power Uprate Project stage: Approval ML0222502672002-08-23023 August 2002 RAI Related to Environmental Qualification for Design-Basis Radiological Analysis Accident Source Term Project stage: RAI ML0222803682002-09-0505 September 2002 Withholding from Public Disclosure, WCAP-15591, MB5718 Project stage: Other ML0231601992002-10-31031 October 2002 E-mail Enclosure, from John Lamb. Provides Draft RAIs for COLR Proposed Amendment for Kewaunee Project stage: Draft RAI ML0231203332002-11-0808 November 2002 Review Regarding Proposed Amendment Request, Core Operating Limits Report (Colr), July 26, 2002 Project stage: Other ML0232600442002-11-21021 November 2002 RAI, Core Operating Limits Report Project stage: RAI ML0233005512002-11-21021 November 2002 E-mail from John Lamb to Ted Maloney Dated November 21, 2002 RAI for Kewaunee Concerning Technical Specification Changes for Use of Westinghouse Vantage Plus Fuel Project stage: RAI ML0233004762002-11-22022 November 2002 Review Regarding Proposed Amendment Request Conforming Technical Specification Changes for Use of Westinghouse Vantage+ Fuel Dated July 26, 2002 Project stage: Other ML0234402972002-12-10010 December 2002 Review Regarding Proposed Amendment Request Conforming TS Changes for Use of Westinghouse Vantage+ Fuel, Dated July 26, 2002 Project stage: Other ML0236501342002-12-31031 December 2002 Review Regarding Proposed Amendment Request Conforming Technical Specification Changes for Use of Westinghouse Vantage+ Fuel, Dated July 26, 2002 Project stage: Other ML0302104852003-01-21021 January 2003 RAI, Proposed Amendment Request Conforming TS Changes for Use of Westinghouse Vantage+ Fuel Project stage: RAI ML0306901422003-02-27027 February 2003 NMC Responses to NRC Request for Additional Information Concerning License Amendment Request 187 Project stage: Response to RAI ML0306901592003-02-27027 February 2003 Part 2, Kewaunee, NMC Responses to NRC Request for Additional Information Concerning License Amendment Request 187 Project stage: Response to RAI ML0307200612003-03-11011 March 2003 TS Pages for Amendment No. 165, Implement a Core Operating Limits Report Project stage: Request ML0307200492003-03-11011 March 2003 Attachment to Safety Evaluation Re Amendment No. 165, Implement a Core Operating Limits Report Project stage: Request ML0307004562003-03-11011 March 2003 License Amendment, Implement a Core Operating Limits Report Project stage: Other ML0302100622003-03-17017 March 2003 Issuance of Amendment No. 166, Revising the Current Radiological Consequence Analyses for the Kewaunee Design-Basis Accidents to Implement the Alternate Source Term as Described in Regulatory Guide 1.183 & Pursuant to 10 CFR 50.67 Project stage: Approval ML0309200202003-03-19019 March 2003 License Amendment Request 187 to the Kewaunee Nuclear Power Plant TS Project stage: Request ML0310504932003-04-0303 April 2003 Response to a Question Concerning License Amendment Request 187 to Kewaunee TS, Conforming TS Changes for Use of Westinghouse Vantage + Fuel. Project stage: Request ML0309707962003-04-0404 April 2003 Tech Spec Pages for Amendment No. 167 to License No. DPR-43 Project stage: Acceptance Review ML0309402762003-04-0404 April 2003 License Amendment 167, Revises TSs for Use of Westinghouse 422 Vantage+ Nuclear Fuel with Performance+ Features Project stage: Approval ML0311305052003-04-15015 April 2003 Correction to License Amendment 167 to the Kewaunee Nuclear Power Plant Technical Specifications Project stage: Other ML0311406322003-04-24024 April 2003 Correction to Issuance of License Amendment Nos. 165 and 167, Respectively, Approving Revisions to TSs 1.0, 2.1, 2.3, 3.1, 3.8, 3.10 & 6.9 Project stage: Approval ML0311806302003-04-24024 April 2003 Technical Specifications for Amendment No. 165, Corrected Pages Project stage: Acceptance Review ML0311806362003-04-24024 April 2003 Technical Specifications for Amendment No. 167, Corrected Pages Project stage: Acceptance Review ML0315007242003-05-22022 May 2003 License Amendment Request 195, Application for Stretch Power Uprate Project stage: Request 2002-09-05
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Category:Report
MONTHYEARML20035C7592020-01-16016 January 2020 Redacted - Kewaunee, Request for Exemption from Certain Code of Federal Regulation Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML14126A0052014-04-29029 April 2014 Supplement 4 and Response to Request for Additional Information Regarding License Amendment Request 256, Permanently Defueled License and Technical Specifications ML14118A3822014-04-25025 April 2014 Revision to Post-Shutdown Decommissioning Activities Report ML13066A7802013-02-27027 February 2013 Non-Proprietary - Evaluation of Report Describing the Nature of an Estimated Effect on, Peak Cladding Temperature Resulting from a Significant Emergency Core Cooling System Evaluation Model Error ML12354A4962012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12181A2002012-06-21021 June 2012 Post Accident Monitoring Report ML11277A2402011-09-21021 September 2011 TAC ME7250 - Public - 7 Pages - Kewaunee Power Station License Amendment Request 250: Adoption of NFPA-805 Performance-based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML11255A1342011-08-31031 August 2011 Core Operating Limits Report Cycle 31 Revision 2 ML11252A6532011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2 ML11252A6572011-08-30030 August 2011 License Amendment Request 244, Evaluation of New Proposed Manual Actions, Attachment 5 ML11252A6582011-08-30030 August 2011 License Amendment Request 244, Data Files, Kewaunee Power Station Meterological Data 2002-2006 X/Q Calculation Support, Enclosure 1 ML11252A6512011-08-30030 August 2011 License Amendment Request 244, Discussion of Change, Safety Evaluation, Significant Hazards Determination and Environmental Considerations, Attachment 1 ML1108100712011-03-10010 March 2011 Core Operating Limits Report Cycle 31, Revision 0 ML1032104962010-11-0909 November 2010 Technical Report No. EE-0116 Revision 8, Allowable Values for North Anna Improved Technical Specifications Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications, Section 2.3 and 3.7 and Allowable Values for Ke ML1027001622010-09-23023 September 2010 Response to Request for Additional Information for the Review of the License Renewal Application ML1025714462010-09-0707 September 2010 Holistic Overview of GSI-191 Resolution for Kewaunee Power Station ML1023904192010-08-31031 August 2010 DOM-NAF-2, Rev. 0.2-A, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code. ML1016102862010-05-11011 May 2010 Report No. 0900090.401, Rev. 0, 60-Year EAF Analyses Summary Report, Kewaunee Power Station Charging Nozzle & RCS Hot Leg Surge Nozzle. ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1027303972010-03-30030 March 2010 Allowable Values for North Anna Improved Technical Specifications (ITS) Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications (Cts), Sections 2.3 and 3.7, and Allowable Values for Kewaunee Power Station Improv ML1025714482010-02-0404 February 2010 Enclosure C-1 (RAI 8) Latent Debris Calculation C11928, Revision 0 ML0930701642009-10-15015 October 2009 Technical Report No. EE-0116, Revision 5 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0919705162009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure F, Archaeological and Cultural Resources ML0919705292009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure E, Non-Radiological Waste ML0919705152009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure D, Hydrology Through ML0919705092009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosures D, Appendix a ML1011101282009-06-30030 June 2009 Enclosure 5 - WCAP-16643-NP, Revision 2, Kewaunee Power Station Heatup and Cooldown Limit Curves for Normal Operation ML0826903872008-09-19019 September 2008 Enclosure 1, License Amendment Request 239, Supplement 1 - Request for Review and Approval of Seismic Analysis Methodology for Auxiliary Building Crane ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0816204382008-06-0202 June 2008 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML0809802292008-04-0404 April 2008 Stations - Request for Approval of Appendix C of Fleet Report DOM-NAF-2 Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code ML0807001732008-03-0505 March 2008 U.S. Dept of Homeland Security/Final Report of the December 4, 2007, Radiological Emergency Preparedness Full Participation Plume Pathway Exercise for the Kewaunee Power Station/Report ML0731706782007-05-19019 May 2007 SCS-00684, Rev. Draft-2, Design Report, ASME Bp&V Section III, Class 3, SS-45S8-18622-NSR Ball Valve, SS-45XS8-18623-NSR Ball Valve, Enclosure 2 ML0710603922007-04-16016 April 2007 Request for Approval of Topical Report DOM-NAF-5, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps.) ML0710201612007-03-29029 March 2007 Generator Tube Inspection Report ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0633906662006-12-0505 December 2006 Closure of Kewaunee Improvement Initiatives to Corrective Action Program ML0632504212006-11-14014 November 2006 Attachment 3, Submittal of Irradiated Reactor Vessel Surveillance Capsule Test Results for Capsule T Per 10 CFR 50 Appendix H ML0632504182006-10-31031 October 2006 Master Curve Assessment of Kewaunee Power Station Reactor Pressure Vessel Weld Metal, WCAP-16609-NP, Revision 0 ML0632504152006-10-31031 October 2006 Analysis of Capsule T from the Dominion Energy Kewaunee Power Station Reactor Vessel Radiation Surveillance Program, WCAP-16641-NP, Revision 0 ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0616604372006-06-20020 June 2006 Technical Report (TAC MC7897) on Third 10-Year Inservice Inspection Interval Request for Relief for Nuclear Management Company, LLC ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0603804892006-02-0606 February 2006 Closed Gc TAC Report (10/01/2005 - 12/31/2005) ML0536100952005-12-16016 December 2005 Appendix C - Fault Tree Analysis - Attachment 1 - Human Error Probabilities; Attachment 1:A - Human Error Probabilities ML0536100922005-12-0101 December 2005 Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 1, Revision 1 ML0536101002005-12-0101 December 2005 Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 2, Revision 1 ML0524403512005-08-25025 August 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report 2020-01-16
[Table view] Category:Miscellaneous
MONTHYEARML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML14126A0052014-04-29029 April 2014 Supplement 4 and Response to Request for Additional Information Regarding License Amendment Request 256, Permanently Defueled License and Technical Specifications ML14118A3822014-04-25025 April 2014 Revision to Post-Shutdown Decommissioning Activities Report ML13066A7802013-02-27027 February 2013 Non-Proprietary - Evaluation of Report Describing the Nature of an Estimated Effect on, Peak Cladding Temperature Resulting from a Significant Emergency Core Cooling System Evaluation Model Error ML12354A4962012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12181A2002012-06-21021 June 2012 Post Accident Monitoring Report ML11255A1342011-08-31031 August 2011 Core Operating Limits Report Cycle 31 Revision 2 ML1108100712011-03-10010 March 2011 Core Operating Limits Report Cycle 31, Revision 0 ML1027001622010-09-23023 September 2010 Response to Request for Additional Information for the Review of the License Renewal Application ML1025714462010-09-0707 September 2010 Holistic Overview of GSI-191 Resolution for Kewaunee Power Station ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0919705092009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosures D, Appendix a ML0919705152009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure D, Hydrology Through ML0919705292009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure E, Non-Radiological Waste ML0919705162009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure F, Archaeological and Cultural Resources ML0816204382008-06-0202 June 2008 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML0807001732008-03-0505 March 2008 U.S. Dept of Homeland Security/Final Report of the December 4, 2007, Radiological Emergency Preparedness Full Participation Plume Pathway Exercise for the Kewaunee Power Station/Report ML0710201612007-03-29029 March 2007 Generator Tube Inspection Report ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0633906662006-12-0505 December 2006 Closure of Kewaunee Improvement Initiatives to Corrective Action Program ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0603804892006-02-0606 February 2006 Closed Gc TAC Report (10/01/2005 - 12/31/2005) ML0524403512005-08-25025 August 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0522403702005-08-0404 August 2005 Executed Support, Indemnity, and Qualified Decommissioning Trust Agreements ML0522700732005-04-18018 April 2005 Event Notification Report for April 18, 2005 ML0514402902004-10-26026 October 2004 Revision to Emergency Action Levels, 2.2 Location Through 7.0 Appendices ML0514604942004-04-0909 April 2004 Licensee Root Cause Report, CAP55527, Industrial Safety Issues and Poor Work Practices During Nozzle Dam Installation, with R. Alexander'S (Riii) Notes ML0332103202003-11-0505 November 2003 Enclosure E, Response to Request for Additional Information and Supplemental Information Regarding LAR 195 ML0332103152003-11-0505 November 2003 Enclosure a: Kewaunee Nuclear Plant, Response to Requests for Additional Information and Supplemental Information Regarding LAR 195 ML0318909462003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Duane Arnold, K ML0307200492003-03-11011 March 2003 Attachment to Safety Evaluation Re Amendment No. 165, Implement a Core Operating Limits Report ML0208705652002-03-19019 March 2002 Revision to the Design Basis Radiological Analysis Accident Source Term 2016-10-28
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TRM 2. 1 Kewaunee Nuclear Power Plant CORE OPERATING LIMITS REPORT (COLR)
CYCLE 25 REVISION 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMI1TS REPORT CYCLE 25 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Nuclear Power Plant (KNPP) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.4.
A cross-reference between the COLR sections and the KNPP Technical Specifications affected by this report is given below:
COLR KNPP Description Section TS 2.1 2.1 Reactor Core Safety Limits 2.2 3.10.a Shutdown Margin 2.3 3.1.f.3 Moderator Temperature Coefficient 2.4 3.10.d.1 Shutdown Bank Insertion Limit 2.5 3.10.d.2 Control Bank Insertion Limits 2.6 3.10.b.1.A Heat Flux Hot Channel Factor (FQ(Z))
3.10.b.4 3.1 0.b.5.C.i 2.7 3.10.b.1.B Nuclear Enthalpy Rise Hot Channel Factor (FNH) 2.8 3.10.b.9 Axial Flux Difference (AFD) 3.10.b.1 1.A 2.9 2.3.a.3.A Overtemperature AT Setpoint 2.10 2.3.a.3.B Overpower AT Setpoint 2.11 3.10.k RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling 3.10.1 (DNB) Limits 3.10.m.1 2.12 3.8.a.5 Refueling Boron Concentration Figure 1 Safety Limits-Reactor Core Figure 2 Required Shutdown Margin Figure 3 K(Z) Normalized Operating Envelope Figure 4 Control Bank Insertion Limits Figure 5 V(Z) as a Function of Core Height Cycle 25 Page 2 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 2.0 Operatinq 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 Technical Specification 6.9.a.4 2.1 Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1. The safety limit is exceeded ifthe point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line 2.2 Shutdown Marqin 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.
2.3 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and _<60% RATED POWER, the moderator temperature coefficient shall be _ 5.0 pcm/°F, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.
2.3.2 The reactor will have a moderator temperature coefficient no less negative than -8 pcm/°F for 95% of the cycle time at full power.
2.4 Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn when the reactor is critical or approaching criticality 2.5 Control Bank Insertion Limit 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4 Cycle 25 Page 3 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 2.6 Nuclear Heat Flux Hot Channel Factor (Fo N(Z))
2.6.1 F0 N(Z) Limits for FRA-ANP Fuel FaN(Z) X 1.03 x 1.05 < (2.35)/P x K(Z) for P > 0.5 [Hvy]
F0 N(Z) x 1.03 x 1.05 < (4.70) x K(Z) for P *0.5 [Hvy]
FaN(Z) x 1.03 x 1.05 < (2.28)/P x K(Z) for P > 0.5 [Std]
F0 N(Z) x 1.03 x 1.05 < (4.56) x K(Z) for P _ 0.5 [Std]
where:
P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the FQ of interest 2.6.2 The measured FQEQ(Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for FRA ANP fuel:
FaEQ(Z) X 1.03 x 1.05 x V(Z) _ (2.35)/P x K(Z) [Hvy]
FQEQ(Z) X 1.03 x 1.05 x V(Z) < (2.28)/P x K(Z) [Std]
where:
P is the fraction of full power at which the core is OPERATING V(Z) is defined in COLR Figure 5 FaEQ(Z) is a measured F0 distribution obtained during the target flux determination 2.6.3 The penalty factor for TS 3.10.b.5.C.i shall be 2%.
Cycle 25 Page 4 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 2.7 Nuclear Enthalpv Rise Hot Channel Factor (FAH^N) 2.7.1 FAHN Limits for FRA-ANP Fuel FAHN x 1.04 *1.70 [1 + 0.2(1-P)] [Hvy]
FAHN x 1.04*< 1.55 [1 + 0.2(1-P)] [Std]
where:
p is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) 2.8.1 The indicated axial flux target band shall be the area maintained within +/- 5%
about the target flux difference.
2.8.2 The envelope is an area whose outer limits are described by -10% and +10%
from the target axial flux difference at 90% rated power and increasing by
-1% and +1% from the target axial flux difference for each 2.7% decrease in rated power < 90% and > 50%.
Cycle 25 Page 5 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:
ATo = Indicated AT at RATED POWER, %
T = Average temperature, OF T' = 567.3 OF P = Pressurizer Pressure, psig P = 2235 psig K1 = 1.11 K2 = 0.0090 K3 = 0.000566 T = 30 seconds T2 = 4 seconds f(AI) = An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a) For qt - qb within -12, +9 %, f(AI) = 0 (b) For each percent that the magnitude of qt - qb exceeds +9 % the AT trip setpoint shall be automatically reduced by an equivalent of 2.5 % of RATED POWER.
(c) For each percent that the magnitude of qt - qb exceed -12 % the AT trip setpoint shall be automatically reduced byan equivalent of 1.5 % of RATED POWER.
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
AT0 = Indicated AT at RATED POWER, %
T = Average temperature, OF T' = 567.3 OF K4 < 1.10 K5 > 0.0275 for increasing T; 0 for decreasing T K6 - 0.002 for T > T' ; 0 for T < T' "T = 10 seconds f(AI) = Same as in 2.9 Cycle 25 Page 6 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
Limits 2.11.1 During steady state power operation, Tavg shall be < 568.80 F.
2.11.2 During steady state power operation, Pressurizer Pressure shall be > 2205 psig 2.11.3 During steady state power operation, reactor coolant flow rate shall be
> 93,000 gpm per loop.
2.12 Refueling Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2200 ppm and a shutdown margin of> 5% Ak/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.
Cycle 25 Page 7 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 Figure 1 Safety Limits-Reactor Core 660 650 640 630 620 610 0
E LL 600 CU, 0
r.r_
a) 590 580 570 560 550 540 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent Rated Core Power Cycle 25 Page 8 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 Figure 2 Required Shutdown Reactivity vs Boron Concentration 2000 1900 1800 1700 1600 1500 4-. 1400 C. 1300 Cu 1200 1100 "0) E. 1000 0.
C_
900 0"
800 700 600 500 400 300 200 100 0
0 200 400 600 800 1000 1200 1400 1600 1800 2000 Full Power Equilibrium Boron Concentration (ppm)
Cycle 25 Page 9 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 Figure 3 Hot Channel Factor Normalized Operating Envelope 1.2 1.1 (0,1.0) (6,1.0) 1 0.9 (12,0.925) 0.8 0.7 I I I 0.5 0.4 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 10 11 12 Core height (ft)
Cycle 25 Page 10 of 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATING LIMITS REPORT CYCLE 25 Figure 4 Control Bank Insertion Limits 0
z 0
U/)
z z
03 1-U/)
0n z
co 0 20 40 60 80 100 POER LE-VE % OF RATED PQAER Cycle 25 Page CeRof 12 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 DRAFT CORE OPERATIN4G LIMITS REPORT CYCLE 25 Figure 5 V(Z) as a Function of Core Height 1.18 1.16 1.14 1.12 1.1 V(Z) 1.08 1.06 1.04 1.02 1
0 2 4 6 8 10 12 CORE HEIGHT (FT)
Cycle 25 Page 12 of 12 Rev. 0