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MONTHYEARML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps Project stage: Request ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps Project stage: Request ML1006300132010-03-0505 March 2010 Issuance of Amendment No. 187, Revise TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps (Emergency Circumstances) Project stage: Approval 2010-03-04
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Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Technical Specification
MONTHYEARML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23068A1232023-03-0909 March 2023 Changes to Technical Specification Bases Revisions 91 and 92 ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22067A0302022-03-0808 March 2022 Changes to Technical Specification Bases - Revisions 86, 87, 88, 89, and 90 ML21070A0582021-03-11011 March 2021 Changes to Technical Specification Bases - Revisions 82, 83, 84, and 85 WO 20-0050, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange2020-11-10010 November 2020 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2020-04-20020 April 2020 License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20070L9822020-03-0202 March 2020 Changes to Technical Specification Bases - Revisions 80 and 81 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ML19078A1302019-03-11011 March 2019 Changes to Technical Specification Bases - Revisions 78 and 79 WO 19-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-03-11011 March 2019 Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18075A0242018-03-0808 March 2018 Changes to Technical Specification Bases - Revisions 76 and 77 WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... ML17073A0932017-03-0909 March 2017 Changes to Technical Specification Bases - Revisions 74 and 75 ML17054C2212017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Revised Technical Specification Pages ML17054C2222017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Bases Changes ML17054C2202017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Changes ML16076A3572016-03-10010 March 2016 Changes to Technical Specification Bases - Revisions 67 Through 73 WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 ML15077A0662015-03-11011 March 2015 Changes to Technical Specification Bases, Revisions 61 Through 66 WO 14-0092, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2014-12-15015 December 2014 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ET 13-0028, Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report.2013-09-23023 September 2013 Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report. ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML13079A0602013-03-0808 March 2013 Changes to Technical Specification Bases - Revisions 55 and 56 ML12080A2162012-03-12012 March 2012 Changes to Technical Specification Bases - Revisions 50 Through 54 WO 11-0086, Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating2011-11-30030 November 2011 Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 ML1007801282010-03-11011 March 2010 Changes to Technical Specification Bases - Revisions 41 Through 44 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report2009-09-15015 September 2009 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report WO 09-0022, Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases2009-09-0303 September 2009 Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases ML0907506242009-03-11011 March 2009 Submittal of Changes to Technical Specification Bases - Revisions 36 Through 40 WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A2008-08-18018 August 2008 Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ML0811201492008-04-29029 April 2008 Corrected Technical Specification Pages, Amendment No. 177 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves, to Add Main Feedwater Regulating Valves and MFRV Bypass Valves ML0807805602008-03-0707 March 2008 Changes to Technical Specification Bases - Revisions 32 Through 35 ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections WO 08-0001, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-01-15015 January 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707402282007-03-0909 March 2007 Changes to Technical Specification Bases - Revisions 24 Through 31 ML0631905352006-11-15015 November 2006 Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program ML0627804522006-10-0505 October 2006 Technical Specification Pages - Issuance of Amendment Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0624201502006-08-29029 August 2006 Techncial Specification, Addition of Surveillance Requirement 3.3.1.16 to TS Table 3.3.1.16 WM 06-0033, Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs).2006-08-25025 August 2006 Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs). 2023-03-09
[Table view] Category:Bases Change
MONTHYEARML23068A1232023-03-0909 March 2023 Changes to Technical Specification Bases Revisions 91 and 92 ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22067A0302022-03-0808 March 2022 Changes to Technical Specification Bases - Revisions 86, 87, 88, 89, and 90 ML21070A0582021-03-11011 March 2021 Changes to Technical Specification Bases - Revisions 82, 83, 84, and 85 WO 20-0050, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange2020-11-10010 November 2020 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2020-04-20020 April 2020 License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20070L9822020-03-0202 March 2020 Changes to Technical Specification Bases - Revisions 80 and 81 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ML19078A1302019-03-11011 March 2019 Changes to Technical Specification Bases - Revisions 78 and 79 WO 19-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-03-11011 March 2019 Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18075A0242018-03-0808 March 2018 Changes to Technical Specification Bases - Revisions 76 and 77 ML17073A0932017-03-0909 March 2017 Changes to Technical Specification Bases - Revisions 74 and 75 ML17054C2212017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Revised Technical Specification Pages ML17054C2202017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Changes ML17054C2222017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Bases Changes WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 ML15077A0662015-03-11011 March 2015 Changes to Technical Specification Bases, Revisions 61 Through 66 WO 14-0092, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2014-12-15015 December 2014 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ET 13-0028, Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report.2013-09-23023 September 2013 Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report. ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML13079A0602013-03-0808 March 2013 Changes to Technical Specification Bases - Revisions 55 and 56 ML12080A2162012-03-12012 March 2012 Changes to Technical Specification Bases - Revisions 50 Through 54 ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 ML1007801282010-03-11011 March 2010 Changes to Technical Specification Bases - Revisions 41 Through 44 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps WO 09-0022, Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases2009-09-0303 September 2009 Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases ML0907506242009-03-11011 March 2009 Submittal of Changes to Technical Specification Bases - Revisions 36 Through 40 ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ML0807805602008-03-0707 March 2008 Changes to Technical Specification Bases - Revisions 32 Through 35 ML0707402282007-03-0909 March 2007 Changes to Technical Specification Bases - Revisions 24 Through 31 WM 06-0033, Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs).2006-08-25025 August 2006 Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs). ML0607602412006-03-0808 March 2006 Changes to Technical Specification Bases - Revisions 20 Through 23 ML0531401852005-11-0303 November 2005 Application for Technical Specification Improvement Re Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ET 05-0007, Request for Approval of Changes to the Reactor Coolant System Leakage Detection Instrumentation Methodology2005-08-26026 August 2005 Request for Approval of Changes to the Reactor Coolant System Leakage Detection Instrumentation Methodology ML0507704152005-03-10010 March 2005 Changes to Technical Specification Bases - Revisions 17 Through 19 WO 04-0013, Supporting Information for the Revision to Technical Specifications 3.8.1, AC Sources - Operating, and 3.8.4, DC Sources - Operating.2004-04-13013 April 2004 Supporting Information for the Revision to Technical Specifications 3.8.1, AC Sources - Operating, and 3.8.4, DC Sources - Operating. ML0407807542004-03-11011 March 2004 Changes to Technical Specifications Bases - Revisions 14-16 WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)2003-12-15015 December 2003 Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.) ML0307801372003-03-10010 March 2003 Docket 50-482: Wolf Creek Generating Station Changes to TS Bases - Revisions 9 Through 13 ET 02-0033, Revision to Technical Specification 3.1.6, Physics Tests Exceptions - Mode 2.2002-10-0101 October 2002 Revision to Technical Specification 3.1.6, Physics Tests Exceptions - Mode 2. ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 82002-03-0101 March 2002 Changes to Technical Specification Bases - Revisions 6 Through 8 2023-03-09
[Table view] Category:Technical Specifications
MONTHYEARML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18093A9142018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Chapter 16, Technical Requirements Manual (Relocated Technical Specifications) ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation WO 15-0045, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2015-07-27027 July 2015 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML14006A2182014-01-13013 January 2014 Correction to Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test WO 13-0089, Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-12-17017 December 2013 Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 WO 10-0066, Correction of Typographical Error in Technical Specification 5.7.22010-10-21021 October 2010 Correction of Typographical Error in Technical Specification 5.7.2 ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-12010-04-13013 April 2010 Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 WO 10-0010, Updated Safety Analysis Report, Revision 232010-03-11011 March 2010 Updated Safety Analysis Report, Revision 23 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).2008-07-10010 July 2008 Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr). ML0808400052008-04-0404 April 2008 Tech Pages for Amendment 178, Revision to Technical Specification 5.5.9 on the Steam Generator Program ML0803701212008-04-0303 April 2008 Tech Spec Pages for Amendment No. 177, Revise TS 3.3.2, ESFAS and TS 3.7.3, Main Feedwater Isolation Valves by Addition of Main Feedwater Regulating Valves and Associated Bypass Valves ML0729700282008-03-0303 March 2008 Tech Spec Pages for Amendment 175 Regarding Changes to Technical Specification Table 3.3.2-1 ML0720603282007-08-28028 August 2007 Tech Spec Pages for Amendment 174 Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-05-0303 May 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program ML0705500202007-04-17017 April 2007 Tech Spec Pages for License Amendment No. 173 Adopting TSTF-372 on Limiting Condition for Operation 3.0.8, Inoperability of Snubbers ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement2007-03-14014 March 2007 Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement ET 06-0053, Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-15015 December 2006 Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0631202612006-11-0707 November 2006 Tech Spec Pages for Amendment 171 Regarding Addition of Actuator Trains to Main Steam and Feedwater Isolation Valves Technical Specifications ML0630502562006-10-31031 October 2006 Technical Specifications, Revision to Reactor Coolant System Specific Activity ML0627201792006-09-28028 September 2006 Tech Spec Pages for Amendment 167 Regarding Extended Containment Isolation Valve Completion Times ML0627000632006-09-26026 September 2006 Tech Spec Pages for Amendment 166 Regarding Changes to the Reactor Coolant System (RCS) Leakage Detection Instrumentation Methodology ET 06-0026, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program.2006-06-30030 June 2006 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program. ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-06-26026 June 2006 Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ML0612804712006-05-0808 May 2006 Tech Spec Pages for Amendment 164, Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0611702372006-04-26026 April 2006 Technical Specifications, Extended Diesel Generator Completion Times ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-03-28028 March 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ET 06-0004, Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program2006-02-21021 February 2006 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program ET 06-0012, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidate Line Item Improvement Process2006-02-21021 February 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidate Line Item Improvement Process 2023-10-03
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Text
W LF CREEK 'NUCLEAR OPERATING CORPORATION Terry J. Garrett Vice President Engineering March 4, 2010 ET 10-0011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
Letter ET 10-0010, dated March 3, 2010, from T. J. Garrett, WCNOC, to USNRC
Subject:
Docket No. 50-482: Supplemental Information for Revision to Technical Specification 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," Auxiliary Feedwater - Trip of All Main Feedwater Pumps Gentlemen:
The Reference provided Wolf Creek Nuclear Operating Corporation's (WCNOC) application to revise Technical Specification (TS) 3.3.2, ESFAS Instrumentation, Condition J, for the start of the motor driven auxiliary feedwater (AFW) pumps on the trip of both main feedwater (MFW) pumps. Supplemental information and a revision to the proposed TS changes are being provided based on discussions with the Nuclear Regulatory Commission (NRC) staff on March 3 and March 4, 2010.
The supplement to the amendment request will remove the proposed Note 2 to Required Actions J.1 and J.2. With the proposed changes to Condition J, WCNOC will place the channels into a tripped condition for the two channels on one main feedwater (MFW) pump when placing the pump into service or removing the pump from service. Therefore, in MODE 1 with one MFW pump in service and the second MFW pump in the process of being placed into service, a start of the motor driven AFW pumps would occur if the in service pump were to fail.
Attachment I provides the supplemental information and a revised significant hazards consideration. Attachment II provides the revised markup of TS. Attachment III provides revised TS Bases changes in support of this amendment request and are provided for information only. Final TS Bases changes will be implemented pursuant to TS 5.5.14, "Technical Specification (TS) Bases Control Program," at the time the amendment is implemented. Attachment IV provides a list of regulatory commitments.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 10-0011 Page 2 of 3 It has been determined that this amendment application does not involve a significant hazard consideration as determined per 10 CFR 50.92. In accordance with 10 CFR 50.91, a copy of this supplemental information, with attachments, is being provided to the designated Kansas State official.
Upon approval of the proposed changes to the TSs, the amendment will be implemented within 10 days.
If you have any questions concerning this matter, please contact me at (620) 364-4084, or Mr.
Richard D. Flannigan, Manager Regulatory Affairs, at (620) 364-4117.
Sincerely, f/
Terry J. Garrett TJG/rlt Attachments: Supplemental Information IV IlI Revised Technical Specification Changes (Mark-up)
Revised TS Bases Changes (for information only)
IV List of Regulatory Commitments cc: E. E. Collins (NRC), w/a T. A. Conley (KDHE), w/a G. B. Miller (NRC), w/a B. K. Singal (NRC), w/a Senior Resident Inspector (NRC), w/a
ET 10-0011 Page 3 of 3 STATE OF KANSAS )
ss COUNTY OF COFFEY Terry J. Garrett, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By_
Terry J.,Parrett Vice President Engineering SUBSCRIBED and sworn to before me this kI/day of nafl6&1A ,2010.
I oF:ICAL 01-B.;EAL:
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~:RHONDA TIEMEYER 1L.
MY COMMISSION EXPIRES
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Attachment I to ET 10-0011 Page 1 of 4 SUPPLEMENTAL INFORMATION Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) application to revise Technical Specification (TS) 3.3.2, ESFAS Instrumentation, Condition J, for the start of the motor driven auxiliary feedwater (AFW) pumps on the trip of both main feedwater (MFW) pumps. Supplemental information and a revision to the proposed TS changes are being provided based on discussions with the Nuclear Regulatory Commission (NRC) staff on March 3 and March 4, 2010.
The supplement to the amendment request will remove the proposed Note 2 to Required Actions J.1 and J.2.
Proposed changes to the TSs are as follows:
Modify TS 3.3.2, Condition J to read:
"One or more Main Feedwater Pump trip channel(s) inoperable."
- Modify the Note to TS 3.3.2, Required Actions J.1 and J.2:
- 1. One inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels With the proposed changes to Condition J, this would allow placing the channels into a tripped condition for the two channels on one MFW pump when placing the pump into service or removing the pump from service prior to resetting the MFW pump. The taking of a MFW pump out of service takes significantly less time than placing a MFW pump in service. With the revision to the Condition, placing both channels on one MFW pump into a tripped condition would not require into an entry into LCO 3.0.3.
Therefore, in MODE 1 with one MFW pump in service and the second MFW pump in the process of being placed into service, a start of the motor driven AFVV pumps would occur if the in service pump were to fail.
As discussed in the Reference, the anticipatory auto-start of the motor driven AFW pumps on a loss of both MFW pumps is not credited in any Updated Safety Analysis Report (USAR) Chapter 15 accident analysis. This anticipatory auto-start is a defense in depth function that would result in an early initiation of AFW in the event that both MFW pumps tripped.
The TS 3.3.2, Function 6.g, Trip of all Main Feedwater Pumps, was part of the TSs when the plant was licensed. The Wolf Creek Generating Station (WCGS) TSs were based on NUREG-0452, Revision 5, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors." It appears that this anticipatory trip was included in the SNUPPS design work by our Architect-Engineer (Bechtel) as far back as 1975 as discussed in the SNUPPS Preliminary Safety Analysis Report.
Attachment I to ET 10-0011 Page 2 of 4 MFW Pump Trip/Reset The MFW pumps are equipped with mechanical drive turbine MDT-20 hydraulic trip systems.
The MFW pumps are powered from separate control power supplies with the control power to the "A" MFW pump being supplied from PNO9 and the "B" MFW being supplied from PN10.
They are also both equipped with separate/independent control oil systems.
Resetting the "A" MFW pump (FCHIS0018 in the "Reset" position) allows the control header hydraulic pressure to increase to approximately 200 psig. This resets the pressure switches FCPSL0025 (PS15 on drawing 10466-M012-042-05) and FCPSL0026 (PS26 on drawing 10466-M012-042-05) to that nominal operating hydraulic fluid pressure and these are the "A" MFW pump pressure switches that feed the anticipatory auto-start signal to the motor driven AFW pumps. This also supplies hydraulic pressure to the stop and control valves, which enables the control valves to be manually adjusted to the desired MFW pump speed.
When the "A" MFW pump is tripped from an automatic or manual trip function (FCHIS0018 in the "Trip" position) the control header hydraulic oil is ported to the hydraulic oil reservoir reducing the header pressure back to 0 psig. With no hydraulic oil pressure in the control header, the high and low stop valves and control valves close. This also eliminates oil pressure to the pressure switches FCPSL0025 and FCPSL0026, which results in the "A" MFW pump tripped inputs (one out of two) to the auxiliary feedwater actuation signal input being provided to start the motor driven AFW pumps.
Resetting the "B" MFW pump (FCHIS01 18 in the "Reset" position) allows the control header hydraulic pressure to increase to approximately 200 psig. This resets pressure switches FCPSLO125 and FCPSLO126 to that nominal operating hydraulic fluid pressure and these are the "B" MFW pump pressure switches that feeds anticipatory auto-start signal to the motor driven AFW pumps. This also supplies hydraulic pressure to the stop and control valves which enables the control valve to be manually adjusted to the desired MFW pump speed.
When "B" MFW pump is tripped from an automatic or manual trip function (FCHIS0118 in the "Trip" position) the control header hydraulic oil is ported to the hydraulic oil reservoir reducing the header pressure back to 0 psig. With no hydraulic oil pressure in the control header the stop valve and control valve both close. This also eliminates oil pressure to the pressure switches FCPSLO125 and FCPSLO1 26, which results in the "B" MFW pump tripped inputs (one out of two) auxiliary feedwater actuation signal input being provided to start the motor driven AFW pumps.
Significant Hazards Consideration The amendment application proposes changes to the Wolf Creek Generating Station (WCGS)
Technical Specifications Limiting Condition for Operation (LCO) of Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation." Wolf Creek Nuclear Operating Corporation (WCNOC) is proposing to modify Technical Specification (TS) 3.3.2, ESFAS Instrumentation, Condition J, for the start of the motor driven auxiliary feedwater (AFW) pumps on the trip of all main feedwater (MFW) pumps. The proposed TS changes will provide a TS Condition that addresses more than one inoperable channel.
Attachment I to ET 10-0011 Page 3 of 4 WCNOC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, Issuance of Amendment:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The design basis events which impose initiation of the AFW System requirements are loss of normal main feedwater, main feed line or main steam line break, loss of offsite power, and small break loss of coolant accident. These design bases event evaluations assume actuation of the AFW System due to loss of offsite power signal, steam generator water level - low-low or a safety injection signal. The anticipatory motor driven AFW pump auto-start signals from the MFW pumps are not credited in any design basis accidents and are, therefore, not part of the primary success path for postulated accident mitigation as defined by 10 CFR 50.36(c)(2)(ii), Criterion 3. Modifying the Condition and Required Actions for more than one inoperable channel for this function will not impact any previously evaluated design basis accidents.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed changes to the TSs would allow two anticipatory motor driven AFW pump start channels to be placed in a tripped condition during the process of removing a MFW pump from service or placing a MFW pump in service. This change involves an anticipatory motor driven AFW pump auto-start function that is not credited in the accident analysis. The proposed change only affects the number of auto-start of motor driven AFW channels that may be inoperable while placing a MFW pump in service or removing a MFW pump from service in MODE 1. The proposed change does not affect the ESFAS functions that actuates AFW due to loss of offsite power, steam generator water level -
low-low or a safety injection signal.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No The proposed changes to the TSs involves the automatic start of the AFW pumps due to trip of both MFW pumps which is not an assumed start signal for design basis events.
This change does not modify any values or limits involved in a safety related function or accident analysis.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Attachment I to ET 10-0011 Page 4 of 4 Conclusion Based on the considerations discussed above, 1) there is a reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, 2) such activities will be conducted in compliance with the Commission's regulations, and 3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
References
- 1. Letter ET 10-0010, Revision to Technical Specification 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," Auxiliary Feedwater - Trip of All Main Feedwater Pumps" T. J. Garrett, WCNOC, to USNRC, March 3, 2010.
Attachment II to ET 10-0011 Page 1 of 2 Revised Technical Specification Changes (Mark-up)
Attachment II to ET 10-0011 Page 2 of 2 ESFAS Instrumentation 3.3.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME I .I One ain Feedwater P9Z - NOTE-Pump trip channeI g inoperable channel may be inoperable. bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels.
J.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ORR J.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> t t K. One channel inoperable. -NOTE One additional channel may be tripped for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for I surveillance testing.
K.1 Place channel in bypass. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR K.2.1 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND
.1.
K.2.2 Be in MODE 5. 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />
____________________
(continued)
I Wolf Creek - Unit 1 3.3-26 Amendment No. 42*3, 156
Attachment III to ET 10-0011 Page 1 of 3 Revised TS Bases Changes (for information only)
Attachment III to ET 10-0011 Page 2 of 3 ESFAS Instrumentation B 3.3.2 BASES ACTIONS 1.1 and 1.2 (continued)
The allowed Completion Time of Required Action 1.2 is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging unit systems. In MODE 3, these Functions are no longer required OPERABLE.
The Required Actions are modified by a Note that allows the inoperable channel to be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels. The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed to place the inoperable channel in the tripped condition, and the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed for a second channel to be in the bypassed condition for testing, are justified in Reference 12.
J.1 and J.2 ý" o-r-Condition J applies to the AFW pump start on trip of all MFW pumps.
This action addresses the train orientation of the BOP ESFAS for the auto start function of the AFW System on loss of all MFW pumps. The OPERABILITY of the AFW System must be assured b allowin automatic start of the AFW System pumps. fatChp e1ieinppete 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to place the channel in the tnppe cond on. t e channel cannot be tripped in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 6 additional hours are allowed to place the unit in MODE 3. The allowed Completion lime of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging unit systems. In MODE 3, the unit does not have any analyzed transients or conditions that require the iuse of the protection function noted above. The Required Actions are modified by a Note that allowsa*7" inoperable channel to be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels.
K.1. K.2.1. and K.2.2 Condition K applies to the RWST Level - Low Low Coincident with Safety Injection Function.
RWST Level - Low Low Coincident with SI provides actuation of switchover to the containment recirculation sumps. Note that this Function requires the bistables to energize to perform their required Wolf Creek- Unit I B 3.3.2-42 Revision 20
Attachment Ill to ET 10-0011 Page 3 of 3 INSERT B 3.3.2-42 A MFW pump is in service when the pump's stop valves are open, the governor control valves are either in manual or automatic control, and feedwater is being supplied to the steam generators (i.e., the MFW pump is at the required operating speed). One MFW pump may be in service in MODE 1 at reduced power levels ifthe other MFW pump has been removed from service for maintenance or has not yet been placed into service during power ascension.
During the process of removing a MFW pump from service and prior to placing a MFW pump into service, its control circuitry is placed in a reset condition such that the two oil pressure switch channels on that pump continue to experience oil pressures indicative of an operating pump and, therefore, would not satisfy the AFW start function actuation logic (one tripped channel on each MFW pump in the same separation group will initiate an auxiliary feedwater actuation). This ESFAS actuation function is an anticipatory start signal for which no credit is taken in any safety analysis. The safety analyses credit actuation of the motor driven AFW pumps upon a low-low steam generator water level signal in any steam generator and after a safety injection signal.
Attachment IV to ET 10-0011 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by WCNOC in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Mr.
Richard Flannigan at (620) 364-4117.
REGULATORY COMMITMENT DUE DATE/EVENT Upon approval of the proposed changes to the TSs, the amendment Within 10 days of will be implemented within 10 days. approval