|
---|
Category:Letter type:ET
MONTHYEARET 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 ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 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 ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program 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 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements 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 ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating 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 ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System 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) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 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. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection 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 ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 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 ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
[Table view] Category:Technical Specification
MONTHYEARML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. 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 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 2024-07-31
[Table view] Category:Bases Change
MONTHYEARML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML23068A1232023-03-0909 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 2024-07-31
[Table view] |
Text
WLF CREEK
'NUCLEAR OPERATING CORPORATION Gary B. Fader Vice President Technical Services
"-* ET02-0033 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: Revision to Technical Specification 3.1.8, "PHYSICS
-TESTS Exceptions-' MODE 2" Gentlemen:
-Wolf Creek Nuclear Operating Corporation (WCNOC) herewith transmits an application for amendment to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS).
The proposed amendment would revise the Limiting- Condition for Operation (LCO) for Technical Specification 3.1.8 to allow one power range neutron flux ch-annel to be bypassed, rather than tripped -(in accordance with LCO 3.3.1 for an inoperable channel), when that channel is used during the performance of physics testing in MODE-2. This -amendment application is taken directly from NRC-approved traveler TSTF-315, without exception. NRC has also approved the implementation of this traveler on a plant-specific basis for TVA's Watts
-Bar Nuclear Plant, Unit 1.
WCNOC is-submitting this license amendment- application in conjunction-with an industry consortium of six plants as a result of a mutual agreement known as Strategic Teaming and Resource Sharing (STARS). The STARS group consists of the six plants operated by TXU Generation Company LP, AmerenUE, Wolf Creek Nuclear Operating Corporation, Pacific Gas and Electric Company, STP Nuclear Operating Company,-- and -Arizona -Public Service
"-Company. AmerenUE's Callaway Plant is the lead'plant for the proposed license amendment.
This license amendment request is submitted on a parallel basis, with plant-specific information presented within brackets in Attachment I.-
f.. 0 P0 Box 411/ Burlington, KS 66839 / Phone. (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
-ET02-0033 Page2of22 The WCNOC Plant Safety Review Committee and the Nuclear Safety Review Committee have reviewed this amendment application. Attachments I through IV provide the Evaluation, Markup of Technical Specifications, Retyped Technical Specifications, -and -Proposed Technical Specification (TS) Bases -Changes, respectively, in support -of -this amendment request.
Attachment IV is provided for information only. Final TS Bases changes will be processed under our program for updates per TS 5.5.14, "Technical Specifications Bases Control Program," at
-the time-this amendment is implemented.--- No other commitments are contained -in this amendment application.
It has been determined that this amendment application does not involve a significant hazard consideration as determined per 10 -CFR-50.92.. Pursiuant-to CFR 51.22(b), no environmental -assessment need be prepared in connection-with the issuance of-this amendment. The ariiendment will be implemented within 90 days after NRC approval.
-In accordance-with 10 CFR 50.91,--a copy -of this application, with attachments, is being provided to the-designated Kansas State Official. If you should have any questions regarding this submittal, please contact me at (620) 364-4034, or Mr. Tony Harris at (620) 364-4038.
Very truly yours, Gary B. Fader GBF/rlr Attachments:- I - Evaluation
-- II - Markup of TechnicalSpecification pages Il -1 Retyped Technical Specification pages IV-- - Proposed Bases Changes (for information only)'
cc: V.- L. Cooper (KDHE), w/a J. N.-Donohew (NRC),_w/a D.-N.-Graves (NRC), w/a -
E. W. Merschoff (NRC), w/a Senior Resident Inspector (NRC), w/a -
STATEOF'KANSAS COUNTY OF COFFEY )
- Gary B.- Fader, of. lawful age, being--first duly sworn upon oath- says that he is Vice President
- Technical Services of -Wolf Creek Nuclear Operating -Corporation; that -he -has read --the'
"* foregoing document and knows the conteints thereof; that he has executed the srnie 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. -*
-Gary B. Fader Vice President Technical Services SUBSCRIBED and sworn-to before me this -* a of- 2002. -O
-Notary Public)
P
- Expiration Date ..... X.. ...
Attachment I to ET 02-0033 Page 1 of 8 ATTACHMENT I EVALUATION
- 1. DESCRIPTION
- 2. PROPOSED CHANGE
- 3. BACKGROUND
- 4. TECHNICAL ANALYSIS
- 5. REGULATORY SAFETY ANALYSIS 5.1 NO SIGNIFICANT HAZARDS CONSIDERATION 5.2 APPLICABLE REGULATORY REQUIREMENTSS/CRITERIA
- 6. ENVIRONMENTAL CONSIDERATION
- 7. REFERENCES
Attachment I to ET 02-0033 Page 2 of 8 EVALUATION
1.0 DESCRIPTION
The proposed amendment would revise the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.1.8 to allow one power range neutron flux channel to be bypassed, rather than tripped (in accordance with LCO 3.3.1 for an inoperable channel), when that channel is used during the performance of physics testing in MODE 2.
2.0 PROPOSED CHANGE
The proposed amendment would revise LCO 3.1.8 such that, in addition to allowing test exceptions from the listed LCOs, the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, 6, and 18.e may be reduced from "4" to "3." The specific change involves inserting the following text into LCO 3.1.8:
"and the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, 6, and 18.e, may be reduced to 3 required channels" Functions 2, 3, 6, and 18.e in TS Table 3.3.1-1 are the:
"* Power Range Neutron Flux - High and Power Range Neutron Flux - Low reactor trips (Functions 2.a and 2.b);
"* Power Range Neutron Flux Rate - High [Positive Rate and Power Range Neutron Flux-High Negative Rate reactor trips (Functions 3.a and 3.b]);
"* Overtemperature AT reactor trip (for Function 6, inputs from the power range neutron flux channels are used to determine the magnitude of the f1(AI) axial power imbalance penalty discussed in Note 1 of TS Table 3.3.1-1); and
"* Power Range Neutron Flux P-10 Interlock (Function 18.e).
The power range neutron flux channels are also associated with TS Table 3.3.1-1 Functions 18.b, 18.c, and 18.d; however, the Applicability for those Functions is limited to MODE 1 whereas the Applicability of LCO 3.1.8 is MODE 2 during PHYSICS TESTS. Corresponding changes will also be made to the LCO Bases for TS 3.1.8. Attachments II and III provide the TS markups and the retyped TS for the LCO 3.1.8 revision. Attachment IV provides an information-only copy of the associated TS Bases changes. No changes to the Updated Safety Analysis Report (USAR) will be required in conjunction with this amendment application.
3.0 BACKGROUND
The following discussion covers one portion of the low power physics test program that would take advantage of the proposed amendment; however, the proposed LCO change may be applied throughout the LCO [3.1.8] Applicability.
Attachment I to ET 02-0033 Page 3 of 8 During the performance of bank reactivity worth measurements using the Dynamic Rod Worth Measurement (DRWM) proc6ss, one power range neutron flux channel is used to provide input to the Advanced Digital Reactivity Computer (ADRC). This process is used to measure the integral worth of all the control and shutdown banks by a method of dynamic insertion. Using this process, the selected bank is fully inserted into and withdrawn from the core while measuring reactivity changes with the ADRC. The insertion and withdrawal sequence is repeated for each selected bank to obtain its worth.
When the DRWM process is currently used, the instrument power fuses associated with the power range neutron flux channel to be connected to the ADRC are removed from that power range electronics drawer. This results in the bypass of that power range channel. Since that power range channel is rendered inoperable, the control power fuses are then removed to comply with TS 3.3.1 Conditions D and E. Control power fuse removal results in the trip of that power range channel and a partial reactor trip indication on the status panel. No further Required Actions under LCO 3.3.1 Conditions D and E are necessary, i.e., the inoperable channel is in the tripped condition and THERMAL POWER complies with LCO 3.1.8 (less than or equal to 5% RTP). However, those LCO 3.3.1 Conditions are entered and cannot be exited, and the inoperable channel must be maintained in the tripped condition, until the normal system configuration is restored. The cables are then disconnected from the back of that Nuclear Instrumentation System (NIS) power range drawer and connected to the ADRC NIS field connectors. With one channel tripped, this places the power range NIS trip logic in a one-out-of three coincidence status such that a spurious high signal on any of the other three channels would result in a reactor trip.
The change proposed in this amendment application would eliminate the requirement to trip the power range channel that has been disconnected from its detector and connected to the ADRC.
This would place that channel in a state of bypass and place the NIS trip logic in a two-out-of three coincidence status, precluding spurious signals on one other channel from causing a reactor trip.
This amendment application is taken directly from NRC-approved traveler TSTF-315 (Reference 1) without exception. NRC has also approved the implementation of this traveler on a plant-specific basis for TVA's Watts Bar Nuclear Plant, Unit 1 (Reference 2).
4.0 TECHNICAL ANALYSIS
As proposed herein, implementation of the requested amendment will result in one power range neutron flux channel being in a bypassed state. In this configuration, there will be three available channels with a two-out-of-three coincidence logic required to actuate the reactor trip functions associated with power range neutron flux. As required by LCO 3.1.8, physics testing will be performed while the reactor is in MODE 2 at a power level of less than or equal to 5%
RATED THERMAL POWER (RTP).
While in the proposed physics testing configuration, a postulated single failure will not prevent the power range neutron flux channels from actuating as designed and satisfying the required logic coincidence for a reactor trip.
Since this change affects only the power range neutron flux channels of the NIS, the reactor trip function of the intermediate range neutron flux channels will be unaffected and, therefore, will be available to mitigate a reactivity transient at low power levels. [ ]
Attachment I to ET 02-0033 Page 4 of 8 There are two control functions which use power range channel inputs, rod control (power mismatch compensation as depicted on [USAR Figure 7.2-1 sheet 9 and Figure 7.7-1]) and steam generator water level control (as depicted on [USAR Figure 7.2-1 sheets 9, 13 and 14 and Figure 7.7-6]).
[At a power level of 5 percent or less, rod control is in manual and is not affected by the testing configuration. In addition, this system uses an auctioneered power range flux input as shown on USAR Figure 7.2-1 sheet 9, i.e., bypass of any one power range channel will not eliminate the auctioneered input from the other three power range channels for this portion of the control signal. Therefore, this control system is not adversely affected by the proposed change.]
At power levels below approximately 25% RTP, steam generator water level control is provided by a system that modulates the position of the feedwater control bypass valves. This system also uses an auctioneered power range flux input as shown on [USAR Figure 7.2-1 sheet 9],
i.e., bypass of any one power range channel will not eliminate the auctioneered input from the other three power range channels for this portion of the control signal. Therefore, this control system is not adversely affected by the proposed change.
In its review of TSTF-315, the NRC staff discussed three issues with the Westinghouse Owners Group (WOG). The staff requested the WOG to provide historical data of spurious signals from excore detectors during physics testing that resulted in reactor trips, and requested information on back-up protection during MODE 2. The staff also asked whether additional analysis had been performed to cover all accident conditions during MODE 2 operation. The WOG identified four instances of trips that were caused by spurious signals. The WOG also stated that there is no specific analysis of all accidents for MODE 2 operation since accidents mitigated by the power range neutron flux channels are normally bounded by the full power condition rather than MODE 2 conditions.
During physics testing, LCO 3.1.8 requires that the reactor power level be kept at less than or equal to 5% RTP, the lowest operating reactor coolant system loop average temperature be kept at greater than or equal to 541 0 F, and SHUTDOWN MARGIN (SDM) be kept above the minimum value specified in the CORE OPERATING LIMITS REPORT (COLR) so that the fuel design criteria are not violated. Under the proposed change, the power range neutron flux trip would remain available and functional in a two-out-of three coincidence logic configuration. In addition, the intermediate range neutron flux trip provides back-up protection during low power operation. During physics testing the plant is held in a stable state with minimal changes in steam or feed flow. LCO [3.1.8] is applicable for physics testing that is typically performed at the beginning of the fuel cycle, with minimum fuel burnup and decay heat. The SDM is maintained above the required values and procedural controls are in place for monitoring plant parameters.
Probabilistic Risk Assessment (PRA) Evaluation There is no adverse impact on the [Wolf Creek Generating Station] PRA since that study is concerned mainly with time-averaged equipment functionality during full power operation, not specific NIS configurations during low power physics testing. The functional performance of the power range portion of the NIS is retained in a two-out-of-three coincidence logic configuration and that functionality will continue to be demonstrated by the Surveillance Requirements of TS 3.3.1, including CHANNEL CHECKS, CHANNEL OPERATIONAL TESTS, and CHANNEL CALIBRATIONS. Since the proposed change reduces the plant susceptibility to spurious reactor trips, it would have a risk-neutral to beneficial effect on the initiating event frequency assumed in the PRA.
Attachment I to ET 02-0033 Page 5 of 8 Summary/Conclusion The discussions presented above assess the potential impact of this change which will reduce the plant susceptibility to spurious reactor trips during low power physics testing. On the basis of similar discussions, NRC approved TSTF-315 on a generic basis and for Watts Bar, Unit 1, on a plant-specific basis. There are no unique aspects to this amendment application that would preclude approval of this same change for [WCGS]. The above discussions demonstrate that the proposed change will not adversely affect the design basis or the safe operation of the plant.
5.0 TECHNICAL ANALYSIS
This section addresses the standards of 10CFR50.92 as well as the applicable regulatory requirements and acceptance criteria.
5.1 NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC)
The proposed amendment would revise the LCO for Technical Specification (TS) 3.1.8 to allow one power range neutron flux channel to be bypassed, rather than tripped (in accordance with LCO 3.3.1 for an inoperable channel), when that channel is used during the performance of physics testing in MODE 2. The proposed change does not involve a significant hazards consideration for [Wolf Creek Generating Station] based on the three standards set forth in 10 CFR 50.92(c) as discussed below:
(1) Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No Overall protection system performance will remain within the bounds of the previously performed accident analyses since there are no permanent hardware changes. The design of the RTS instrumentation will be unaffected; only the manner in which the system is connected for short duration physics testing is being changed to allow the temporary bypass of one power range channel. The reactor protection system will continue to function in a manner consistent with the plant design basis since a sufficient number of power range channels will remain OPERABLE to assure the capability of protective functions, even with a postulated single failure. All design, material, and construction standards that were applicable prior to the request are maintained.
The proposed change will allow the temporary bypass of one power range neutron flux channel during the performance of low power physics testing in MODE 2. This results in a temporary change to the coincidence logic from one-out-of-three under the current TS (with a trip imposed on the channel used for physics testing) to two-out-of-three under the proposed TS (the channel used for physics testing would be in a bypassed state). However, this two-out-of-three coincidence logic still supports required protection and control system applications, while reducing plant susceptibility to a spurious reactor trip.
The proposed change will not affect the probability of any event initiators. There will be no change to normal plant operating parameters or accident mitigation performance.
Attachment I to ET 02-0033 Page 6 of 8 The proposed change will not alter any assumptions or change any mitigation actions in the radiological consequence evaluations in the USAR.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No There are no permanent hardware changes nor are there any changes in the method by which any safety-related plant system performs its safety function. This change will not affect the normal method of power operation or change any operating parameters. No performance requirements will be affected.
No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures are introduced as a result of this amendment. There will be no adverse effect or challenges imposed on any safety-related system as a result of this amendment.
The proposed amendment does not alter the design or performance of the 7300 Process Protection System, Nuclear Instrumentation System (other than as discussed above), or Solid State Protection System used in the plant protection systems.
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 change involve a significant reduction in a margin of safety?
Response: No There will be no effect on the manner in which safety limits or limiting safety system settings are determined nor will there be any effect on those plant systems necessary to assure the accomplishment of protection functions. There will be no impact on the overpower limit, departure from nucleate boiling ratio (DNBR) limits, heat flux hot channel factor (FO), nuclear enthalpy rise hot channel factor (FAH), loss of coolant accident peak cladding temperature (LOCA PCT), peak local power density, or any other margin of safety. The radiological dose consequence acceptance criteria listed in the Standard Review Plan will continue to be met.
The proposed change does not eliminate any RTS surveillances or alter the Frequency of surveillances required by the Technical Specifications. The nominal RTS and Engineered Safety Features Actuation System (ESFAS) trip setpoints (TS Bases Tables B 3.3.1-1 and B 3.3.2-1), RTS and ESFAS allowable values (TS Tables 3.3.1-1 and 3.3.2-1), and the safety analysis limits assumed in the transient and accident analyses [(USAR Table 15.0-4)] are unchanged. None of the acceptance criteria for any accident analysis is changed. The potential reduction in the frequency of spurious reactor trips would effectively increase the margin of safety or, at a minimum, be risk-neutral.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Attachment I to ET 02-0033 Page 7 of 8
==
Conclusion:==
Based on the above, [WCNOC] concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 APPLICABLE REGULATORY REQUIREMENTSICRITERIA The regulatory bases and guidance documents associated with the systems discussed in this amendment application include:
GDC-13 requires that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems.
GDC-20 requires that the protection system(s) shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.
GDC-21 requires that the protection system(s) shall be designed for high functional reliability and testability.
GDC-22 through GDC-25 and GDC-29 require various design attributes for the protection system(s), including independence, safe failure modes, separation from control systems, requirements for reactivity control malfunctions, and protection against anticipated operational occurrences.
Regulatory Guide 1.22 discusses an acceptable method of satisfying GDC-20 and GDC-21 regarding the periodic testing of protection system actuation functions. These periodic tests should duplicate, as closely as practicable, the performance that is required of the actuation devices in the event of an accident.
10 CFR 50.55a(h) requires that the protection systems meet IEEE 279-1971. Section 4.2 of IEEE 279-1971 discusses the general functional requirement for protection systems to assure they satisfy the single failure criterion.
There will be no changes to the RTS instrumentation design such that compliance with any of the regulatory requirements and guidance documents above would come into question. The evaluations performed by [WCNOC] confirm that [Wolf Creek Generating Station] will continue to comply with all applicable regulatory requirements.
In conclusion, based on the considerations discussed above, (1) there is 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) issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Attachment I to ET 02-0033 Page 8 of 8
6.0 ENVIRONMENTAL CONSIDERATION
[WCNOC] has determined that the proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However,
[WCNOC] the proposed amendment and has determined that the amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amount of effluent that may be released offsite, or (iii) a significant increase in the individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22 (c)(9). Therefore, pursuant to 10 CFR 51.22 (b), an environmental assessment of the proposed amendment is not required.
7.0 REFERENCES
- 1. Industry/TSTF Standard Technical Specification Change Traveler, TSTF-315, approved by letter from William D. Beckner (NRC) to James Davis (NEI) dated June 19, 1999.
- 2. Amendment Number 28 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1, TAC No. MA9519, dated September 13, 2000.
I I
Attachment II to ET 02-0033 Page 1 of 2 ATTACHMENT II MARKUP OF TECHNICAL SPECIFICATION PAGES
Attachment II to ET 02-0033 Page 2 of 2 PHYSICS TESTS Exceptions - MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";
LCO 3.1.4, "Rod Group Alignment Limits";
LCO 3.1.5, "Shutdown Bank Insertion Limits";
LCO 3.1.6, "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspende , provided:
- a. RCS lowest operating loop average temperature is > 541'F;
- b. SDM is within the limits provided in the COLR; and
- c. THERMAL POWER is 5 5% RTP.
& annet -Gr 3. 3. 1 T r 4t m r A A o~
anc ivle- r'uxr'k-;ei OF -r9L .wrfeTCA6-iJ C eeCLxit 3 itCO ar'e-s n
2,3Lt, CeG,amr~6e-e,rn 0-1 ID APPLICABILITY: MODE 2 during PHYSICS TESTS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.
AND A.2 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TESTS exceptions.
B. THERMAL POWER not B.1 Open reactor trip Immediately within limit. breakers.
(continued)
Wolf Creek - Unit 1 3.1-19 Amendment No. 123
Attachment III to ET 02-0033 Page 1 of 2 ATTACHMENT III RETYPED TECHNICAL SPECIFICATION PAGES
PHYSICS TESTS Exceptions - MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";
LCO 3.1.4, "Rod Group Alignment Limits";
LCO 3.1.5, "Shutdown Bank Insertion Limits";
LCO 3.1.6, "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended and the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, 6, and 18.e, may be reduced to 3 required channels, provided:
- a. RCS lowest operating loop average temperature is > 541°F;
- b. SDM is within the limits provided in the COLR; and
- c. THERMAL POWER is
APPLICABILITY: MODE 2 during PHYSICS TESTS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.
AND A.2 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TESTS exceptions.
B. THERMAL POWER not B.1 Open reactor trip Immediately within limit, breakers.
(continued)
Wolf Creek - Unit 1 3.1-19 Amendment No. 4-23,
Attachment IVto ET 02-0033 Page 1 of 2 ATTACHMENT IV PROPOSED BASES CHANGES (for information only)
Attachment IV to ET 02-0033 Page 2 of 2 PHYSICS TEST Exceptions - MODE 2 B 3.1.8 BASES APPLICABLE criteria for inclusion in the Technical Specifications, since the components SAFETY ANALYSES and process variable LCOs suspended during PHYSICS TESTS meet (continued) Criteria 1,2, and 3 of 10 CFR 50.36(c)(2)(ii).
LCO This LCO allows the reactor parameters of MTC and minimum rr. ?Ouer R .O Aetemperature for criticality to be outside their specified limits. In addition, it allows selected control and shutdown rods to be positioned outside of cbn.ncl *.A be.- _/cA. (zU,1" their specified alignment and insertion limits. Operation beyond specified 4brh nu-mbL*roCe(u%.A rvayrzks- limits is permitted for the purpose of performing PHYSICS TESTS and 4 0P 1a .
4- poses no threat to fuel integrity, provided the SRs are met.
The requirements of LCO 3.1.3, LCO 3.1.4, LCO 3.1.5, LCO 3.1.6, and LCO 3.4.2 may be suspended during the performance of PHYSICS TESTS provided:
- a. RCS lowest operating loop average temperature is > 541 *F;
- b. SDM is within the limits provided in the COLR; and YeL~~t* reU~roea d~ae\y~-k
- c. THERMAL POWER is <5% RTP.
APPLICABILITY This LCO is applicable in MODE 2 when performing low power PHYSICS TESTS. The applicable PHYSICS TESTS are performed in MODE 2 at HZP.
ACTIONS Al andA2 If the SDM requirement is not met, boration must be initiated promptly. A Completion Time of 15 minutes is adequate for an operator to correctly align and start the required systems and components. The operator should begin boration with the best source available for the plant conditions. Boration will be continued until SDM is within limit.
Suspension of PHYSICS TESTS exceptions requires restoration of each
-of the applicable LCOs to within specification.
"B..I When THERMAL POWER is > 5% RTP, the only acceptable action is to open the reactor trip breakers (RTBs) to prevent operation of the reactor beyond its design limits. Immediately opening the RTBs will shut down Wolf Creek - Unit 1 B 3.1.8-3 Revision 0