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Category:Letter
MONTHYEARML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24136A1952024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24130A0022024-05-0909 May 2024 Summary of Facility Changes, Tests and Experiments and Commitment Changes IR 05000305/20240012024-05-0202 May 2024 NRC Inspection Report No. 05000305/2024001 ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24101A0422024-04-22022 April 2024 Solutions Inc. – Exemption from Select Requirements of 10 CFR Part 73 ((Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24106A0492024-04-15015 April 2024 2023 Annual Radioactive Effluent Release Report ML24080A0702024-03-20020 March 2024 Decommissioning Trust Fund Annual Report ML24079A0162024-03-19019 March 2024 Annual Property Insurance Status Report ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24061A0202024-02-15015 February 2024 (Ksp) ISFSI, Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 6 ML23339A1332024-01-26026 January 2024 Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities IR 05000305/20230022023-12-27027 December 2023 NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss) ML23332A1922023-11-28028 November 2023 Solutions, Inc., Request for Exemptions from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23278A1002023-10-0505 October 2023 Response to Request for Additional Information (RAI) Application for Kewaunee Solutions (Ks) Site Restoration Activities ML23222A1522023-08-29029 August 2023 Letter RAI KPS Exemption Site Restoration Final Repaired IR 05000305/20230012023-08-17017 August 2023 NRC Inspection Report No. 05000305/2023001-Kewaunee Power Station ML23171B0822023-07-0505 July 2023 Letter - Kewaunee Power Station - Issuance of Exemption from Certain Requirements from 10 CFR Part 20, Appendix G, Section Iii.E ML23132A0012023-05-11011 May 2023 2022 Annual Radiological Environmental Operating Report ML23116A2182023-04-26026 April 2023 2022 Annual Radioactive Effluent Release Report ML23089A3042023-03-30030 March 2023 Decommissioning Fund Status Report ML23093A0312023-03-29029 March 2023 Solutions, Inc., Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv) for Site Restoration Activities ML23088A2752023-03-29029 March 2023 Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23087A0402023-03-27027 March 2023 Annual Property Insurance Status Report ML23087A0292023-03-27027 March 2023 2022 Annual Report of Occupational Radiation Exposure ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring IR 05000305/20220022023-01-0303 January 2023 NRC Inspection Report Nos. 05000305/2022002(DRSS) Kewaunee Power Station ML22292A2302022-11-25025 November 2022 U.S. Nuclear Regulatory Commissions Analysis of Dominion Energy Kewaunees Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305 ML22290A0052022-10-13013 October 2022 Resubmittal of Kewaunee Power Station Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (Ioep) and IOEP- Emergency Action Level (EAL) Basis Document, Revision 0KS ML24061A0182022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Pla11, Training and Qualification Plan and Safeguards Contingency Plan Revision 5 ML22241A0302022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 5 IR 05000305/20220012022-08-0101 August 2022 NRC Inspection Report Nos. 05000305/2022001(DNMS) - Kewaunee Power Station ML22215A1512022-07-27027 July 2022 Executed Financial Assurance Instruments for the Kewaunee License Transfer License No. DPR-43 (Docket Nos. 50-305, 72-64) ML22209A1252022-07-26026 July 2022 Amendment No. 11 to Indemnity Agreement No. B-53 for Kewaunee Power Station (KPS) - Signed by Kewaunee Solutions, Inc ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure ML22160A5262022-06-28028 June 2022 Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc ML22160A5272022-06-28028 June 2022 Enclosure 1 - Amendment No. 221 to Renewed Facility Operating License No. DPR-43 ML22160A5282022-06-28028 June 2022 Enclosure 2 - Amendment No. 11 to Indemnity Agreement B-53 ML22188A0812022-06-23023 June 2022 ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report ML22172A2452022-06-22022 June 2022 Notification of Planned Closing Date and Required Regulatory Approvals for the Kewaunee License Transfer Transaction ML22175A0662022-06-17017 June 2022 Designation of Additional Reviewing Official for ISFSI and 10 CFR Part 37 Program Security Background Investigations ML22166A3392022-06-13013 June 2022 Notification of Nuclear Insurance ML22138A2552022-05-10010 May 2022 Submittal of 2021 Annual Radiological Environmental Operating Report ML22158A2112022-05-10010 May 2022 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML22091A1892022-04-0101 April 2022 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML22108A0352022-04-0101 April 2022 License Transfer to Kewaunee Solutions, Inc ML22089A2432022-03-30030 March 2022 Decommissioning Funding Status Report, Financial Test and Independent Public Accountants' Letter of Attestation ML22076A0652022-03-15015 March 2022 Energy Solutions and Dominion Energy Kewaunee - Supplement to License Transfer Application Related to Use of Existing Dominion Energy Quality Assurance Program ML22060A1912022-02-25025 February 2022 Response to Request for Additional Information Related to Submittal for Approval of the Kewaunee Solutions Decommissioning Quality Assurance Program (Dqap), Revision O for Kewaunee Power Station (KPS) 2024-06-03
[Table view] 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
[Table view] |
Text
Dominion Energy Kewaunee, Inc.
N490 Hwy 42, Kewaunee, WI 54216 iDominion Web Address: www.dom.com MAR 10 2011 ATTN: Document Control Desk Serial No.11-116 U. S. Nuclear Regulatory Commission LIC/NW/RO Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT CYCLE 31 REVISION 0 Pursuant to Kewaunee Power Station (KPS) Technical Specification 5.6.3.d, enclosed is a copy of the Kewaunee Power Station Core Operating Limits Report Cycle 31, Revision 0.
If you have questions or require additional information, please feel free to contact Mr.
Jack Gadzala at 920-388-8604.
Very truly yours, Mic el J. Wilson Director Safety and Licensing Kewaunee Power Station Commitments made by this letter: NONE Enclosure
- 1. Kewaunee Power Station Core Operating Limits Report Cycle 31, Revision 0.
A-(:)C:) I
Serial No.11-116 Page 2 of 2 cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. K. D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
CORE OPERATING LIMITS REPORT Kewaunee Unit I Cycle 31 Revision 0 February 2011 Page i of 15
1.0 IIqTRODUCTION This Core Operating Limits Report (COLR) for Kewaunee Unit 1 Cycle 31 has been prepared in accordance with the requirements of Kewaunee Technical Specification 5.6.3, A cross reference between the COLR section and the KPS Technical Specifications affected by this report is given below:
KPS Technical Description 7ýý 2.1 Specification 2.1.1 Reactor Core Safety Limit 2.2 3.1.1 Shutdown Margin 2.3 3.1.3 Moderator Temperature Coefficient (MTC) 2.4 3.1.5 Shutdown Bank Insertion Limits 2.5 3.1.6 Control Bank Insertion Limits 2.6 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
2.7 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH) 2.8 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 2.9 3.3.1 Function 6 Reactor Protection System Instrumentation:
Overtemperature AT 2.10 3.3.1 Function 7 Reactor Protection System Instrumentation: Overpower AT 2.11 3.4.1 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 3.9.1 Boron Concentration (Refueling Operations)
Figure 1 2.1 Reactor Core Safety Limits Curve (1772 MWt)
Figure 2 DELETED (Required Shutdown Margin)
Figure 3 DELETED (Hot Channel Factor Normalized Operating Envelope (K(Z)))
Figure 4 3.1.6 Control Bank Insertion Limits Figure 5 N(Z) Values (Top and Bottom 9% excluded)
Figure 6 DELETED (Penalty Factor, Fp, for FQ(Z))
Figure 7 3.2.3 AXIAL FLUX DIFFERENCE Envelope Page 2-o9 15
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 Technical Specification 5.6.3.
2.1 Reactor Core Safety Lirits (TS 2.1. 1)
The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded if the 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 Margin (TS 3.1.1)
Shutdown Margin shall be >_1554 peni.
2.3 Moderator Temverature Coefficient (MTC) (TS 3.1.3) 2.3.1 When the reactor is critical and !5 60% of RATED THERMAL POWER, the moderator temperature coefficient shall be f5 5.0 pcm/°F. When the reactor is > 60% RATED THERMAL POWER, the moderator temperature coefficient shall be zero or negative.
- a. The BOC/ARO-MTC shall be
- 5.0 pcm/0 F (upper limit), when *<60% RTP, and < 0.0 pcm/°F when> 60% RTP.
- b. The EOC/ARO/RTP-MTC shall be less negative than or equal to XX pcmf°F (lower limit)-
MTC surveillance limits are:
i) The 300 ppmi/ARO/RTP-MTC should be less negative than or equal to XX pcmI0 F. If MTC is more negative, then repeat measurement once per 14 EFPD during the remainder of the fuel cycle. Note this surveillance does not need to be repeated if criterion ii, Listed below, is satisfied.
ii) The 60 ppm/ARO/RTP-MTC should be less negative than or equal to XX pcmI'F.
MTC EOC li-mits will be provided following shutdown of Cycle 30.
Page 3 of 15
2.4 Shutdown Bank Insertion Limits (TS 3.1.5)
The shutdown rods shall be fully withdrawn (224 steps) when the reactor is critical or approaching cnticality.
2.5 Control Bank Insertion Limits (TS 3.1.6)
The control rod banks shall be limited in physical insertion as shown in COLR Figure 4.
2.6 Nuclear Heat Flux Hot Channel Factor 0 Z) (TS 3.2.1) 2.6.1 F (Z) Limits for Fuel
( ) **1.03 F#Q(Z) . 3 1. s <CFQ
P for P > 0.5 [422V+]
FfN Z 1 . 3 *1 0 < cFQ Q'(Z)
0.5 Where
P is the fraction of full power at which the core is operating K(Z) is 1.0 for all core heights Z is the core height location for the FQ of interest CFQ equals 2.50 FQj(Z) is a measured FQ distribution obtained during the target flux determination 2.6.2 F(T(Z) Limits for Fuel FP (Z)
-- p
Where:
P is the fraction of full power at which the core is operating K(Z) is 1.0 for all core heights Z is the core height location for the FQ of interest CFQ equals 2.50 Fp is the penalty factor described in 2.6.3 N(Z) is a cycle-specific non-equilibrium multiplier on FQ'(Z) to account for power distribution transients during normal operation, provided in Figure 5.
FQ' (Z) is a measured FQ distribution obtained during the target flux determination The N(z) decks are generatedfor normal operationflux maps thaotaretypically taken atfidl power, ARO.
Additional N(z) decksmay be generated, f necessary, consistent with the methodology described in Reference 7.
Page 4. of !5
2.6.3 A penalty factor of 1.00 shall be used unless the Note criteria of TS SR 3.2.1.2 is met, at which time a penalty of 1.02 shall be used.
2.7 Nuclear Enthalpy.Rise Hot Channel Factor LFp ) (TS 3.2.2)
FI!>
- 1.04 <-CFDH *[1 + PFDH * (1 - P)] [422 V+]
Where:
P is the fraction of full power at which the core is operating CFDH equals 1.70 PFDH equals 0.3 2.8 AXIAL FLUX DIFFERENCE (AFD) (TS 3.2.3)
The AFD acceptable operation limits are provided in COLR Figure 7.
2.9 Overtemperature AT Setjoint (TS 3.3.1 Function 6)
-AT:ýATo* + K 3 *(P-P*)-f1 (M AT0 = Indicated AT at RATED THERMAL POWER, %
s = Laplace transform operator, sec-1 .
T = Average temperature, OF T') N 573.0 OF P = Pressurizer Pressure, psig P, > 2235 psig K,
- 1.195 K2 - 0.015/OF K3 Ž 0.00072/psig Tj Ž 30 seconds T2 4 seconds fl(AI) = An even fun-ction 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 RATED THERMAL POWER, such that (a) For qt - qb within -15, +6 %, f(AI) = 0 (b) For each percent that the magnitude of qt - qb exceeds +6%, the AT trip setpoint shall be automatically reduced by an equivalent of 1.51% of RATED THERMAL POWER.
(c) For each percent that the magnitude of qt - qb exceeds -15%, the AT trip setpoint shall be a*Aomatically reduced by an equivalent of 3.78% of RATED THERMAL POWER.
Page 5 of 15
2.10 Overpower AT Setpoint (TS 3.3.1 Function 7)
AT* ATO* K4 -K 5
- T3s *T-K6 * (T- T') - f2 (AI)
ATo = Indicated AT at RATED THERMAL POWER, %
s = Laplace transform operator, sec-1.
T = Average temperature, OF T < 573.0 OF K4 - 1.095 K5 Ž> 0.0275/1F for increasing T
Ž 0 for decreasing T K6 Ž 0.00103/°F for T > T'
Ž0 forT<T'
"' Ž 10 seconds f2(AJ) 0 for all AI 2.11 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (D2NB) Limits (TS 3.4.1) 2.11.1 During steady state power operation, Tavg shall be *< 576.7 OF for control board indication or
<*576.5 'F for computer indication.
2.11.2 During steady state power operation, pressurizer pressure shall be Ž> 2217 psig for control board indication or Ž2219 psig for computer indication.
2.11.3 During steady state power operation, reactor coolant total flow rate shall be _Ž 186,000 gpm.
2.12 Boron Concentration (iRefueling Operations) (TS 3.9.1)
When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of Ž__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.
Page 6 of 15
Figure 1 (TS 2.1.1)
Reactor Core Safety Limits Curve (1772 Mwt)
(Cores Containing 422V+ fuel) 665 i-0 645 E
' 605 0
.0 0
w 565 0 20 40 60 80 1100 120 Core Power (percent of 1772 MWt)
Page 7 of 15
Figure 2 Margin vs. Boron Concentration Required Shutdown DELETED Figure 3 Normalized Operating Envelope (K(Z))
Hot Channel Factor DELETED Page 8 o*i 15
Figuree4 Control Bank Insertion Limits (TS 3.1.6)
Fully W/D Position 224 Steps 240 220 200 180 160 140
-o 120
- 0. 100 Q
80 60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Percent of RATED THERMAL POWER Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.
Page 9 of 15
Figure 5 N(Z) Values 1 NODE HEIGHT 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to XXXX0 XXXXX to EOC (FEET) MWD/MTU MWD/MTU IV1WD/MTU MWD/MTU MWD/MTU MWD/MTU MWDIMTU Top 6 11.0 7 10.8 8 10.6 9 10.4 10 10.2 11 10.0 12 9.8 13 9.6 14 9.4 15 9.2 16 9.0 17 8.8 The N(z) data will be provided 18 8.6 following shutdown of Cycle 30.
19 8.4 20 8.2 21 8.0 22 7.8 23 7.6 Cycle Specific N(Z) Data 24 7.4 25 7.2 26 7.0 27 6.8 28 6.6 29 6.4 30 6.2 31 6.0 32 5.8 33 5.6 34 5.4 35 5.2 3G 5.0 37 4.8 38 4.6 39 4.4 40 4.2 41 4.0 42 3.8 43 3.6 44 3.4 45 3.2 46 3.0 47 2.8 43 2.6 49 2.4 50 2.2 Page 10 of 15
Figure 5 (continued)
N(Z) Values' 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 900D 9000 to X)OO( XXXXX.to EOC NODE HEIGHT MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU (FEET) 51 2.0 52 1.8 53 1.6 54 1.4 55 1.2 56 1.0 Bottom
- 1) Excludes top and bottom 9%
ARO.
These decks were generatedfor normal operationflux maps that are typically taken at full power Additional N(z) decks may be generated, if necessary, consistent with the methodology described in Reference 1.
Page 11 of 15
i" Figure 6 Penalty Factor, Fp, for FQ (Z)
DELETED Page 12 of 15
Figure 7 AXIAL FLUX DIFFERENCE Target Band (TS 3.2.3) 110
(-9.0, 100.0) (6.0, 100.0) 100 Unacceptable Unacceptable Operation Operation 90 3:z O 80 0L Acceptable Operation 70 LU U 6
'-- 70 50
(-22.0, 50.0) (20.0, 50.0) 40
-40 -30 -20 -10 0 "10 20 30 40 AXIAL FLUX DIFFERENCE (% Delta-I)
Page 13 of15
3.0 REFERENCES
- 1. Topical Report DOM-NAF-5-A, Revision 0.2-A, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS)," January 2011.
Methodology for:
TS 2.1.1 - Reactor Core Safety Limit; TS 3.1.1 - Shutdown Margin; TS 3.1.3 - Moderator Temperature Coefficient; TS 3.1.5 - Shutdown Bank Insertion Limits; TS 3.1.6 - Control Bank Insertion Linmits; TS 3.2.1 - Heat Flux Hot Channel Factor (FQ (Z));
TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor (FA,*);
TS 3.2.3 - AXIAL FLUX DIFFERENCE (AFD);
TS 3.4.1 - RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits; TS 3.9.1 -Boron Concentration (Refueling Operations)
- 2. Topical Report WPSRSEM-NP, Revision 3, "Kewaunee Nuclear Power Plant - Review for Kewaunee Reload Safety Evaluation Methods," September 10, 2001.
Methodology for:
TS 3.1.1 -Shutdown Margin
- 3. WCAP-12945-P-A (Proprietary), "Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Revision 2, and Volume H1-V, Revision 1, March 1998.
Methodology for:
TS 3.2.1 - Heat Flux Hot Channel Factor (FQ(Z))
TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor (FANM);
- 4. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.
Methodology for:
TS 3.2.1 - Heat Flux Hot Chanmel Factor (FQ (Z))
- 5. WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and the COSI Condensation Model," July 1997.
Methodology for:
TS 3.2.1 - Heat Flux Hot Channel Factor (F0 (Z))
Page 14 of 15
- 6. WCAP-9272-P-A: "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Methodology for:
TS 2.1.1 -Reactor Core Safety Limit; TS 3.1.3 - Moderator Temperature Coefficient;
- 7. WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature -AT and Thermal Overpower AT trip functions," September 1986.
Methodology for:
TS 3.3.1 Function 6 - Overtemperature AT Setpoint; TS 3.3.1 Function 7- Overpower AT Setpoint
- 8. WCAP-14449-P-A, Revision 1, "Application of Best Estimate Large-Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," October 1999.
Methodology for:
TS 3.2.1 - Heat Flux Hot Channel Factor (FQ (Z))
TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor (FAN);
- 9. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995.
Methodology for:
TS 3.2.1 - Heat Flux Hot Channel Factor (FQ (Z))
- 10. CENP-397-P-A, Revision 1, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology," May 2000.
Methodology for:
TS 3.3.1 Function 6 - Overtemperature AT Setpoint; TS 3.3.1 Function 7 - Overpower AT Setpoint Page 15 fo15