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EPID:L-2022-LLA-0008, Removal of the Table of Contents from the Technical Specifications (Approved, Closed) |
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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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. ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 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 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 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 ML23045A1952023-02-14014 February 2023 Transmittal of the National Pollution Discharge Elimination System Permit Renewal Application for Wolf Creek Generating Station I-NE07-PO02 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 22-0010, 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 22-0001, 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 21-0004, 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 21-0005, 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 WO 21-0015, License Amendment Request (LAR) for Revision to the Emergency Plan2021-05-25025 May 2021 License Amendment Request (LAR) for Revision to the Emergency Plan WM 21-0005, Supplement to License Amendment Request for Change to Owner Licensee Names2021-05-24024 May 2021 Supplement to License Amendment Request for Change to Owner Licensee Names 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 WM 20-0006, (WCGS) - License Amendment Request for Change to Owner Licensee Names2020-11-0404 November 2020 (WCGS) - License Amendment Request for Change to Owner Licensee Names 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 20-0004, 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 WO 19-0033, License Amendment Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System2019-08-29029 August 2019 License Amendment Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System WO 19-0031, Supplement 1 to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-08-0808 August 2019 Supplement 1 to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ML19052A5462019-04-0101 April 2019 Issuance of Amendment No. 220 Revision to the Emergency Plan 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 19-0003, 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 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 WO 18-0034, Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-08-0909 August 2018 Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term WO 18-0016, License Amendment Request for Revision to the Emergency Plan2018-05-0909 May 2018 License Amendment Request for Revision to the Emergency Plan ML18135A1462018-05-0909 May 2018 Attachments I to V: Evaluation of Proposed Changes, Emergency Plan Change Summary, ERO Position Matrix, Summary of Shift Staffing and Letter of Consultation and Concurrence from Off-Site Response Organizations Ack of Opportunity 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. ML17363A1422017-12-19019 December 2017 License Amendment Request (LAR) for Revision to the Emergency Plan (Attachments and Enclosures) WM 17-0021, Updated Request for Consent to Indirect Transfer of Control2017-09-0505 September 2017 Updated Request for Consent to Indirect Transfer of Control WO 17-0026, Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses2017-03-22022 March 2017 Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses ML17054C2232017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed COLR Changes ET 17-0001, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 10 - CAW-16-45002017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 10 - CAW-16-4500 ML17054C2322017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - OG-92-25, Steam Generator Tube Uncovery Issue ML17054C2272017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Alternative Source Term, Rev 1 ML17054C2362017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 9 - CAW-16-4499 ML17054C2192017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Evaluation ML17054C2352017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WOG-93-066 ML17054C2262017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WCAP-18083-NP, Rev 0, Westinghouse Revised Thermal Design Procedure Uncertainty Calculations. ML17054C2222017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Bases Changes ML17054C2292017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Responses to NRC RAIs on August 2013 Methodology Transition LAR Submittal 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 ML17054C2332017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - CAW-92-287 2024-07-31
[Table view] |
Text
Stephen L. Smith Engineering Vice President January 12, 2022 ET 22-0001 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: Removal of the Table of Contents from the Technical Specifications Commissioners and Staff:
In accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, Wolf Creek Nuclear Operating Corporation (WCNOC) requests an amendment to Renewed Facility Operating License No. NPF-42 to revise the Technical Specifications (TS) for the Wolf Creek Generating Station (WCGS), Unit 1. The proposed amendment would remove the Table of Contents (TOC) from the TSs and place it under licensee control.
Attachment I provides the evaluation of the proposed change. Attachment II provides the existing TS pages marked up to show the proposed change.
It has been determined that this amendment application does not involve a significant hazard consideration as determine per 10 CFR 50.92, Issue of amendment. Pursuant to 10 CFR 51.22, Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise nor requiring environmental review, Section (b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of this amendment.
The amendment application was reviewed by the Plant Safety Review Committee. In accordance with 10 CFR 50.91, Notice for public comment; State consultation, Section (b)(1), a copy of this amendment application, with Attachments, is being provided to the designated Kansas State official.
WCNOC requests approval of this proposed amendment by November 1, 2022. The license amendment, as approved, will be effective upon issuance and will be implemented within 90 days of the date of issuance.
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831
ET 22-0001 Page 2 of 3 There are no regulatory commitments contained in this submittal. If you have any questions concerning this matter, please contact me at (620) 364-4093, or Ron Benham at (620) 364-4204.
Sincerely, Stephen L. Smith SLS/rlt Attachments: I Evaluation of the Proposed Change II Proposed Technical Specification Changes (Mark-up) cc: S. S. Lee (NRC), w/a S. A. Morris, (NRC), w/a G. E. Werner (NRC), w/a K. S. Steves (KDHE), w/a Senior Resident Inspector (NRC), w/a
Attachment I to ET 22-0001 Page 1 of 5 EVALUATION OF THE PROPOSE CHANGE
Subject:
Removal of the Table of Contents from the Technical Specifications 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
Attachment I to ET 22-0001 Page 2 of 5 1.0
SUMMARY
DESCRIPTION This evaluation supports the Wolf Creek Nuclear Operating Corporation (WCNOC) request to amend Renewed Facility Operating License NFP-42 for Wolf Creek Generating Station, Unit 1. The proposed changes would revise the Technical Specifications (TS) to remove the table of contents (TOC) from the TS and place it under licensee control.
2.0 DETAILED DESCRIPTION The proposed change would remove the TOC from the TS and place it under WCNOC (licensee) control. Note that no TS pages will be issued as a result of this proposed change. The TOC for the TS is not being eliminated. Following approval of this license amendment request (LAR), the responsibility for maintenance and issuance of updates to the TS TOC will transfer from the Nuclear Regulatory Commission (NRC) to WCNOC. The TOC will no longer be included in the TS and as such will no longer be part of the TS (Appendix A to the Renewed Facility Operating License).
3.0 TECHNICAL EVALUATION
The TOC does not meet the criteria specified in 10 CFR 50.36 requiring its inclusion within a plant's TS. 10 CFR 50.36(b) states:
Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or§ 50.22 will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34.
The result of the WCNOC review indicates that the TS TOC was not listed in the regulation as one of the categories listed in 10 CFR 50.36(c).
10 CFR 50.36(a) indicates that a license application may provide other information associated with the TS, and gives an example of this information, i.e., the TS Bases, but also clearly indicates that the Bases are not a part of the TS. 10 CFR 50.36(a)(l) states:
Each applicant for a license ... shall include in his application proposed technical specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications.
Additionally, the Writer's Guide for Plant-Specific Improved Technical Specifications (Reference
- 1) was reviewed for guidance. The writer's guide refers to the TOC as Technical Specification Front Matter, which also includes the Title Page and List of Effective Pages. The writer's guide describes the TS content as starting with Chapter 1,Use and Application, and does not include the TOC as part of the content of the TS.
A TOC for the TS will be maintained under WCNOC control. The TOC will be issued by WCNOC in conjunction with the implementation of NRC-approved TS amendments.
Attachment I to ET 22-0001 Page 3 of 5
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.36(a)(1) states:
Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specification in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specification.
Like the TS Bases, the TOC does not meet the criteria specified in 10 CFR 50.36 for inclusion within a plant's TS.
WCNOC has evaluated this change against the applicable regulatory requirements as described above. Based on this, there is reasonable assurance that the health and safety of the public, following approval of this change will remain unaffected .
4.2 Precedent
- Exelon Generation Company, LLC License Amendments for Braidwood Station Units 1 and 2; Byron Station Units 1 and 2; Dresden Nuclear Power Station, Units 2 and 3; James A.
Fitzpatrick Nuclear Power Plant; R. E. Ginna Nuclear Power Plant; Lasalle Count Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Quad Cities Nuclear Power Station, Units 1 and 2 (Reference 2).
- Point Beach Nuclear Plant License Amendment Nos. 245 and 249 were issued on October 11, 2011 (Reference 3).
- Calvert Cliffs Nuclear Power Plant License Amendment Nos. 293 and 269 were issued on September 21, 2009 (Reference 4).
4.3 No Significant Hazards Consideration In accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, Wolf Creek Nuclear Operating Corporation (WCNOC) requests an amendment to Renewed Facility Operating License No. NPF-42 to revise the Technical Specifications (TS) for the Wolf Creek Generating Station (WCGS), Unit 1. The proposed amendment would remove the Table of Contents (TOC) from the TSs and place it under licensee control.
WCNOC has evaluated the proposed amendment in accordance with 10 CFR 50.91 against the standards in 10 CFR 50.92 and has determined that the operation of the facility in accordance with the proposed amendment presents no significant hazards consideration. WCNOC's evaluation against each of the criteria in 10 CFR 50.92 is discussed below.
Attachment I to ET 22-0001 Page 4 of 5
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed amendment is administrative and affects control of a document, the TOC, listing the specifications in the plant TS. Transferring control from the Nuclear Regulatory Commission (NRC) to WCNOC does not affect the operation, physical configuration, or function of plant equipment or systems. The proposed amendment does not impact the initiators or assumptions of analyzed events; nor does it impact the mitigation of accidents or transient events.
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 previously evaluated?
Response: No The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The proposed change does not alter any assumptions made in the safety analysis.
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 The proposed change is administrative. The TOC is not required by regulation to be in the TS. Removal does not impact any safety assumptions or have the potential to reduce a margin of safety. The proposed change involves a transfer of control of the TOC from the NRC to WCNOC. No change in the technical content of the TS is involved .
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
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.
4.4 Conclusions 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,
Attachment I to ET 22-0001 Page 5 of 5 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.
5.0 ENVIRONMENTAL EVALUATION The proposed amendment is confined to changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. Technical Specifications Task Force, TSTF-GG-05-01, Writer's Guide for Plant-Specific Improved Technical Specifications, dated June 2005.
- 2. Letter from Blake Purnell (U. S. NRC) to Mr. Bryan C. Hanson (Exelon Generation Company, LLC), Braidwood Station, Units 1 and 2; Byron Station Units 1 and 2; Dresden Nuclear Power Station, Units 2 and 3; James A. Fitzpatrick Nuclear Power Plant; R. E. Ginna Nuclear Power Plant; Lasalle Count Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Quad Cities Nuclear Power Station, Units 1 and 2 - Issuance of Amendments to Remove Table of Contents from Technical Specifications (EPID L-2019-LLA-0125), dated December 18, 2019. (ADAMS Accession No. ML19302E700)
- 3. Letter from Terry A. Beltz (U.S. NRC) to Mr. Larry Meyer (NextEra), Point Beach Nuclear Plant, Units 1 and 2 - Issuance of Amendment RE: Request to Remove the Table of Contents from the Technical Specifications, dated October 11, 2011. (ADAMS Accession No. ML112640016)
- 4. Letter from Douglas V. Pickett (U .S. NRC) to Mr. James A. Spina (CCNPP), Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Amendment RE: Request to Remove the Table of Contents from the Technical Specifications, dated September 21, 2009. (ADAMS Accession No. ML092120042)
Attachment II to ET 22-0001 Page 1 of 5 ATTACHMENT II PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
Attachment II to ET 22-0001 Page 2 of 5 TABLE OF CONTENTS 1.0 USE AND APPLICATION ................................................................................ 1.1-1 1.1 Definitions ................................................................................................ 1.1-1 1.2 Logical Connectors .................................................................................. 1.2-1 1.3 Completion Times .................................................................................... 1.3-1 1.4 Frequency ................................................................................................ 1.4-1 2.0 SAFETY LIMITS (SLs) .................................................................................... 2.0-1 2.1 SLs ................................................................................................... 2.0-1 2.2 SL Violations ............................................................................................ 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .............................. 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ....................................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) ......................................................... 3.1-1 3.1.2 Core Reactivity ................................................................................ 3.1-2 3.1.3 Moderator Temperature Coefficient (MTC) ...................................... 3.1-4 3.1.4 Rod Group Alignment Limits ............................................................ 3.1-7 3.1.5 Shutdown Bank Insertion Limits ...................................................... 3.1-11 3.1.6 Control Bank Insertion Limits ........................................................... 3.1-13 3.1.7 Rod Position Indication .................................................................... 3.1-16 3.1.8 PHYSICS TESTS Exceptions - MODE 2 ....................................... 3.1-19 3.2 POWER DISTRIBUTION LIMITS ............................................................ 3.2-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
(FQ Methodology) ....................................................................... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH) ............................ 3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) ................................................... 3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR) .................................... 3.2-10 3.3 INSTRUMENTATION .............................................................................. 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation .................................... 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)
Instrumentation .......................................................................... 3.3-22 3.3.3 Post Accident Monitoring (PAM) Instrumentation ............................ 3.3-38 3.3.4 Remote Shutdown System .............................................................. 3.3-42 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation .......................................................................... 3.3-45 Wolf Creek - Unit 1 i Amendment No. 123, 173, 183, 227
Attachment II to ET 22-0001 Page 3 of 5 TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.6 Containment Purge Isolation Instrumentation ................................. 3.3-47 3.3.7 Control Room Emergency Ventilation System (CREVS)
Actuation Instrumentation .......................................................... 3.3-51 3.3.8 Emergency Exhaust System (EES) Actuation Instrumentation .......................................................................... 3.3-56 3.4 REACTOR COOLANT SYSTEM (RCS) .................................................. 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................................................... 3.4-1 3.4.2 RCS Minimum Temperature for Criticality ....................................... 3.4-5 3.4.3 RCS Pressure and Temperature (P/T) Limits .................................. 3.4-6 3.4.4 RCS Loops - MODES 1 and 2 ......................................................... 3.4-8 3.4.5 RCS Loops - MODE 3 ..................................................................... 3.4-9 3.4.6 RCS Loops - MODE 4 ..................................................................... 3.4-12 3.4.7 RCS Loops - MODE 5, Loops Filled ................................................ 3.4-15 3.4.8 RCS Loops - MODE 5, Loops Not Filled ......................................... 3.4-18 3.4.9 Pressurizer ...................................................................................... 3.4-20 3.4.10 Pressurizer Safety Valves ............................................................... 3.4-22 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ...................... 3.4-24 3.4.12 Low Temperature Overpressure Protection (LTOP) System ........... 3.4-27 3.4.13 RCS Operational LEAKAGE............................................................ 3.4-32 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................. 3.4-34 3.4.15 RCS Leakage Detection Instrumentation ........................................ 3.4-38 3.4.16 RCS Specific Activity ....................................................................... 3.4-42 3.4.17 Steam Generator (SG) Tube Integrity ............................................. 3.4-44 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ............................. 3.5-1 3.5.1 Accumulators ................................................................................... 3.5-1 3.5.2 ECCS - Operating............................................................................ 3.5-4 3.5.3 ECCS - Shutdown ........................................................................... 3.5-7 3.5.4 Refueling Water Storage Tank (RWST) .......................................... 3.5-9 3.5.5 Seal Injection Flow .......................................................................... 3.5-11 3.6 CONTAINMENT SYSTEMS .................................................................... 3.6-1 3.6.1 Containment .................................................................................... 3.6-1 3.6.2 Containment Air Locks .................................................................... 3.6-2 3.6.3 Containment Isolation Valves .......................................................... 3.6-7 3.6.4 Containment Pressure ..................................................................... 3.6-14 3.6.5 Containment Air Temperature ......................................................... 3.6-15 3.6.6 Containment Spray and Cooling Systems ....................................... 3.6-16 3.6.7 Spray Additive System .................................................................... 3.6-20 Wolf Creek - Unit 1 ii Amendment No. 123, 131, 157, 164, 167 170, 183, 212, 227
Attachment II to ET 22-0001 Page 4 of 5 TABLE OF CONTENTS 3.7 PLANT SYSTEMS .................................................................................... 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) ................................................ 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) and MSIV Bypass Valves..... 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves ............ 3.7-9 3.7.4 Atmospheric Relief Valves (ARVs) ................................................... 3.7-13 3.7.5 Auxiliary Feedwater (AFW) System .................................................. 3.7-15 3.7.6 Condensate Storage Tank (CST) ..................................................... 3.7-18 3.7.7 Component Cooling Water (CCW) System ...................................... 3.7-20 3.7.8 Essential Service Water System (ESW) ........................................... 3.7-22 3.7.9 Ultimate Heat Sink (UHS) ................................................................. 3.7-24 3.7.10 Control Room Emergency Ventilation System (CREVS) ................. 3.7-26 3.7.11 Control Room Air Conditioning System (CRACS) ............................ 3.7-29 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System - Not Used ................................................. 3.7-32 3.7.13 Emergency Exhaust System (EES) .................................................. 3.7-33 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) -
Not Used ..................................................................................... 3.7-37 3.7.15 Fuel Storage Pool Water Level ......................................................... 3.7-38 3.7.16 Fuel Storage Pool Boron Concentration ........................................... 3.7-39 3.7.17 Spent Fuel Assembly Storage .......................................................... 3.7-41 3.7.18 Secondary Specific Activity ............................................................... 3.7-43 3.7.19 Secondary System Isolation Valves (SSIVs) .................................... 3.7-44 3.7.20 Class 1E Electrical Equipment Air Condition (A/C) System ............. 3.7-46 3.8 ELECTRICAL POWER SYSTEMS........................................................... 3.8-1 3.8.1 AC Sources - Operating .................................................................... 3.8-1 3.8.2 AC Sources - Shutdown.................................................................... 3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ........................................ 3.8-21 3.8.4 DC Sources - Operating.................................................................... 3.8-24 3.8.5 DC Sources - Shutdown ................................................................... 3.8-28 3.8.6 Battery Cell Parameters .................................................................... 3.8-30 3.8.7 Inverters - Operating ......................................................................... 3.8-34 3.8.8 Inverters - Shutdown ......................................................................... 3.8-35 3.8.9 Distribution Systems - Operating ...................................................... 3.8-37 3.8.10 Distribution Systems - Shutdown ...................................................... 3.8-39 3.9 REFUELING OPERATIONS ..................................................................... 3.9-1 3.9.1 Boron Concentration ......................................................................... 3.9-1 3.9.2 Unborated Water Source Isolation Valves ....................................... 3.9-2 3.9.3 Nuclear Instrumentation .................................................................... 3.9-3 3.9.4 Containment Penetrations ................................................................ 3.9-5 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level .................................................... 3.9-7 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level ...................................................... 3.9-9 Wolf Creek - Unit 1 iii Amendment No. 123, 132, 134, 163, 171, 177, 184, 219
Attachment II to ET 22-0001 Page 5 of 5 TABLE OF CONTENTS 3.9 REFUELING OPERATIONS (continued) 3.9.7 Refueling Pool Water Level ...................................................................... 3.9-11 4.0 DESIGN FEATURES ........................................................................................ 4.0-1 4.1 Site Location ............................................................................................ 4.0-1 4.2 Reactor Core ............................................................................................. 4.0-1 4.3 Fuel Storage .............................................................................................. 4.0-1 5.0 ADMINISTRATIVE CONTROLS ...................................................................... 5.0-1 5.1 Responsibility ............................................................................................ 5.0-1 5.2 Organization .............................................................................................. 5.0-2 5.3 Unit Staff Qualifications............................................................................. 5.0-4 5.4 Procedures ................................................................................................ 5.0-5 5.5 Programs and Manuals ............................................................................. 5.0-6 5.6 Reporting Requirements ........................................................................... 5.0-24 5.7 High Radiation Area .................................................................................. 5.0-29 Wolf Creek - UnIt 1 iv Amendment No. 123, 142, 158, 164 179