|
---|
Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Report
MONTHYEARML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23244A2142023-09-0101 September 2023 IAEA Osart Report ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report ML23135A2012022-12-0606 December 2022 EQSD-I, Rev 18, Equipment Qualification Design Basis Document ML23135A1932022-09-0101 September 2022 EQSD-II, Rev 34, Equipment Qualification Summary Document WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2022-08-29029 August 2022 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML22152A2042022-05-18018 May 2022 EQSD-I, Revision 16, Equipment Qualification Design Basis Document ML22152A1992022-05-18018 May 2022 EQSD-II, Revision 33, EQ Program Master List (Table 1) Plus Mild Environment SR Electrical Equipment List (Table 2) ML22152A1942022-05-18018 May 2022 EQSD-I, Revision 15, Equipment Qualification Design Basis Document ML23135A2072022-04-0606 April 2022 EQSD-I, Rev 17, Equipment Qualification Design Basis Document ML20290A6192020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, EQSD-I, Rev. 14, Equipment Qualification Design Basis Document ML20182A4292020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0041, Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II)2020-01-15015 January 2020 Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II) ML19330F8632019-12-0606 December 2019 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, ML19178A3392019-07-0909 July 2019 Staff Assessment of Aging Management Program and Inspection Plan of Reactor Vessel Internals ML19092A1562018-09-18018 September 2018 EQSD-I, Rev 14 ML18093B0112018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Classification Design Basis Document, EQSD-I Rev 13 ML18093B0132018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Qualification Summary Document, EQSD-II, Rev 30, Redacted WO 19-0010, EQSD-II, Rev 312018-02-19019 February 2018 EQSD-II, Rev 31 ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report ML17241A2512017-11-0808 November 2017 Staff Assessment of Flooding Focused Evaluation ML17234A4002017-08-17017 August 2017 Summary of Changes to Three Forms That Implement Radiological Emergency Response Plan (RERP) ML17093A6652017-03-27027 March 2017 Report on Financial Protection Levels ML17151B0452017-03-0909 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 2 - Redacted ML17151B0442017-03-0202 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 1 ML17072A0512017-03-0202 March 2017 Biennial 50.59 Evaluation Report for 01/01/2015 - 12/31/2016 ML17151B0432017-01-26026 January 2017 Equipment Qualification Design Basis Document, EQSD-I, Rev 11 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS2016-12-15015 December 2016 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document.2016-05-31031 May 2016 Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. ML16204A1802016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. WM 16-0008, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted2016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes ML17151B0392015-10-26026 October 2015 E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evaluation ET 16-0003, Flood Hazard Reevaluation Report, Revision 12015-10-21021 October 2015 Flood Hazard Reevaluation Report, Revision 1 ML15216A3202015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights ML15075A0282015-03-0404 March 2015 Biennial 50.59 Evaluation Report ML15062A2752015-02-24024 February 2015 Pressure and Temperature Limits Report, Revision 2 ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-23023 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 2023-09-01
[Table view] Category:Miscellaneous
MONTHYEARML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating ML20182A4292020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0041, Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II)2020-01-15015 January 2020 Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II) ML19330F8632019-12-0606 December 2019 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report ML17234A4002017-08-17017 August 2017 Summary of Changes to Three Forms That Implement Radiological Emergency Response Plan (RERP) ML17093A6652017-03-27027 March 2017 Report on Financial Protection Levels ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS2016-12-15015 December 2016 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes ET 16-0003, Flood Hazard Reevaluation Report, Revision 12015-10-21021 October 2015 Flood Hazard Reevaluation Report, Revision 1 ML15216A3202015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights ML15075A0282015-03-0404 March 2015 Biennial 50.59 Evaluation Report ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-23023 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14136A1712014-05-30030 May 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14077A2812014-02-10010 February 2014 Operating Corporation Flood Hazard Reevaluation Report,Revision 0 ML1307206802013-03-0404 March 2013 Cycle 20 Core Operating Limits Report ET 12-0032, WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-1 Through Page B-502012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-1 Through Page B-50 ML12342A2502012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-51 Through Page B-100 ML12342A2512012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-101 Through Page B-150 ML12342A2532012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Cover Through Appendix a, Seismic Walkdown Checklists (Swcs) Page A-112 ML12342A2542012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-151 Through Page B-184 ML12342A2552012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-185 Through Page B-228 ML12342A2572012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix C, Licensing Basis Evaluations Summary, Page C-1 Through End ML12342A2592012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-113 Through Page A-222 ML12342A2602012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-223 Through Page A-320 ML12342A2612012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-321 Through Page A-350 ML12342A2622012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-348 Through Page A-440 ML12100A0762012-03-26026 March 2012 Foreign Ownership, Control or Influence Information - Updated Lists of Owners, Officers, Directors and Executive Personnel ML11133A3482011-05-0808 May 2011 Great Plains Energy, Inc. and Kansas Electric Power Cooperative, Inc. - Item 8. Financial Statemnts and Supplemental Data ML11279A0052011-03-31031 March 2011 John Redmond Reservoir Diversion and Impacts to Downstream Conditions: System Simulation Modeling ML1107500302011-03-10010 March 2011 Biennial 50.59 Evaluation Report ML1023501702010-09-15015 September 2010 Review of the Results of 16th Steam Generator Tube Inservice Inspections Performed During Refueling Outage 17 ML0917607642009-06-24024 June 2009 Phase 3 Potential Loss of RHR Due to Inadequate Cooling of Suction Line During Mode 4 to Mode 3 Transition at Wolf Creek ET 09-0010, Pressure and Temperature Limits Report, Revision 12009-03-0606 March 2009 Pressure and Temperature Limits Report, Revision 1 ET 09-0005, Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-01-29029 January 2009 Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification ML0902704262009-01-16016 January 2009 Wolf Creek, Enclosures Viii & Xxviii to Wm 09-0001 - CS Innovations Report 6002-00026, Als Platform Overview, Rev 2 2023-03-09
[Table view] |
Text
W~FCREEK 'NUCLEAR OPERATING CORPORATION November 4, 2015 Cynthia R. Hafenstine Manager Regulatory Affairs RA 15-0080 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter RA 15-0025, dated March 20, 2015, from S.R. Koenig, WCNOC to USNRC
- 2) Letter from C. F. Lyon, USNRC, to A. C. Heflin, WCNOC, "Wolf Creek Generating Station - Issuance of Amendment re: Revise Technical Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR),"
to Add ASTRUM to the List of Analytical Methods (TAC NO.
MF351 8)," dated August 28, 2015
Subject:
Docket No. 50-482: 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes Gentlemen:
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Wolf Creek Nuclear Operating Corporation (WCNOC) is submitting the attached information to fulfill the 30-day reporting requirement for the Wolf Creek Generating Station (WCGS).
In Reference 1, WCNOC reported the WCGS peak cladding temperature (PCT), calculated based on an-acceptable evaluation model. A new best-estimate large break loss-of-coolant (LOCA) methodology was approved for WCGS in Reference 2, known as Automated Statistical Treatment of Uncertainty Method (ASTRUM). The license amendment was implemented at WCGS on October 26, 2015. The new analysis resulted in changes of greater than 50 0F in the PCT from those previously reported to the NRC in the last 10 CFR 50.46 report (Reference 1).
The calculated PCT for the WCGS large break LOCA remains within the acceptance criteria set forth in 10 CFR 50.46. Additional reanalysis is not required.
Attachment I provides an assessment of the specific changes to the Westinghouse ECCS evaluation model for large break LOCAs.
P.O. Box 41 IBurlington, KS 66839 I Phone: (620) 364-8831 P '-
An Equal Opportunity Employer M/F/HCNVET
RA 15-0080 Page 2 of 2 Attachment II provides an update of the WCGS POT margin utilization for the large break LOCA evaluation model.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.
Sincerely, Cynthia R. Hafenstine CRH/rlt Attachment I Assessment of Changes to the Westinghouse Emergency Core Cooling System (ECCS) Evaluation Model for Large Break Loss-of-Coolant Accident (LOCA)
II Emergency Core Cooling System (ECCS) Evaluation Model Peak Cladding Temperature (PCT) Margin Utilization Rack-up Form cc: M. L. Dapas (NRC), w/a C. F. Lyon (NRC), w/a N. H. Taylor (NRC), wla Senior Resident Inspector (NRC), w/a
Attachment I to RA 15-0080 Page 1 of 2 Assessment of Changes to the Westinghouse Emergency Core Cooling System (ECCS)
Evaluation Model for Large Break Loss-of-Coolant Accident (LOCA)
GENERAL CODE MAINTENANCE
Background
Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include modifying input variable definitions, units and defaults; ,improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451 "Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting."
Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The nature of these changes leads to an estimated peak cladding temperature (PCT) impact of 0° 0F.
ERRORS IN DECAY GROUP UNCERTAINTY FACTORS
Background
Errors in the calculation of decay heat were discovered in the WCOBRA/TRAC code. The decay group uncertainty factors for each fissile isotope are provided in Table 8-14 of WCAP-16009-P-A. The uncertainty factors for 239Pu were applied to 238U, and those for 238U were applied to 2 39pu. This error causes an over-prediction of the uncertainty in decay power from 239pu and an under-prediction of the uncertainty in decay power from 238 U. Further, the decay group uncertainty factor for Decay Group 6 of 235U was erroneously coded as 2.5% instead of 2.25%. Correction of these errors impacts the application of the sampled decay heat uncertainty, which may result in small changes to the decay heat power. These issues have been evaluated to estimate the impact on Automated Statistical Treatment of Uncertainty Method (ASTRUM) best-estimate large break LOCA analysis results. The resolution of these issues represents a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-1 3451.
Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The issues described above were evaluated to account for the correction of these errors. The plant-specific sensitivity study resulted in an estimated PCT impact of -10°F for Wolf Creek Generating Station (WCGS).
Attachment I to PA 15-0080 Page 2 of 2 WCGS CONTAINMENT COOLING CAPACITY
Background
Wolf Creek Nuclear Operating Corporation (WCNOC) identified an error in the containment fan cooler capacity transmitted for use in the best-estimate ASTRUM evaluation model analysis.
This issue has been evaluated to estimate the impact on existing PCT results. The resolution of this issue represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.
Affected Evaluation Models 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The estimated effect was determined for the large break LOCA evaluation model based on the change in calculated containment, pressure resulting from the correct containment cooling capacity. The change in calculated containment pressure leads to an estimated effect of 0°F for the ASTRUM evaluation model analysis.
Attachment II to IRA 15-0080 Page 1 of 1 EMERGENCY CORE COOLING SYSTEM (ECCS) EVALUATION MODEL PEAK CLADDING TEMPERATURE (PCT) MARGIN UTILIZATION RACK-UP FORM
- LARGEBREAK LOCA PCT MARGIN UTILIZATION ***
Evaluation Model: ASTRUM (2004)
Fuel: RFA-2 Peaking Factor: FQ=2.50, FdH=1.65 SG Tube Plugging: 10%
Power Level: 3565 MWth Limiting Break Size: DEG LICENSING BASIS Clad Temp (0 F) Ref. Notes Analysis of Record (AOR) PCT 1900°F 1 MARGIN ALLOCATIONS (APCT)
A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS
- 1. None 0 B. PLANNED PLANT CHANGE EVALUATIONS
- 1. Containment Fan Cooler Capacity 0 2 (a)
C. 2014 PERMANENT ECCS MODEL ASSESSMENTS
- 1. Containment Fan Cooler Capacity 0 2
- 2. Decay Group Uncertainty Factors Errors -10 3 D. OTHER
- 1. None 0 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 1890 0F
References:
- 1. WCAP-17107-P, Revision 1, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Wolf Creek Nuclear Power Plant Using the ASTRUM Methodology,"
January 2014.
- 2. LTR-LIS-14-400, "10 CFR 50.46 Report for the Wolf Creek Large Break LOCA Evaluation of the Change in Containment Cooling Capacity," August 2014.
- 3. LTR-LIS-14-492, "Wolf Creek Unit 1 10 CFR 50.46 Report for the Correction of the Decay Group Uncertainty Factors Errors," November 2014.
Notes:
(a) This effect was estimated based on a cooling capacity intended to bound future implementation of replacement tube bundles in the containment fan coolers.
W~FCREEK 'NUCLEAR OPERATING CORPORATION November 4, 2015 Cynthia R. Hafenstine Manager Regulatory Affairs RA 15-0080 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter RA 15-0025, dated March 20, 2015, from S.R. Koenig, WCNOC to USNRC
- 2) Letter from C. F. Lyon, USNRC, to A. C. Heflin, WCNOC, "Wolf Creek Generating Station - Issuance of Amendment re: Revise Technical Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR),"
to Add ASTRUM to the List of Analytical Methods (TAC NO.
MF351 8)," dated August 28, 2015
Subject:
Docket No. 50-482: 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes Gentlemen:
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Wolf Creek Nuclear Operating Corporation (WCNOC) is submitting the attached information to fulfill the 30-day reporting requirement for the Wolf Creek Generating Station (WCGS).
In Reference 1, WCNOC reported the WCGS peak cladding temperature (PCT), calculated based on an-acceptable evaluation model. A new best-estimate large break loss-of-coolant (LOCA) methodology was approved for WCGS in Reference 2, known as Automated Statistical Treatment of Uncertainty Method (ASTRUM). The license amendment was implemented at WCGS on October 26, 2015. The new analysis resulted in changes of greater than 50 0F in the PCT from those previously reported to the NRC in the last 10 CFR 50.46 report (Reference 1).
The calculated PCT for the WCGS large break LOCA remains within the acceptance criteria set forth in 10 CFR 50.46. Additional reanalysis is not required.
Attachment I provides an assessment of the specific changes to the Westinghouse ECCS evaluation model for large break LOCAs.
P.O. Box 41 IBurlington, KS 66839 I Phone: (620) 364-8831 P '-
An Equal Opportunity Employer M/F/HCNVET
RA 15-0080 Page 2 of 2 Attachment II provides an update of the WCGS POT margin utilization for the large break LOCA evaluation model.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.
Sincerely, Cynthia R. Hafenstine CRH/rlt Attachment I Assessment of Changes to the Westinghouse Emergency Core Cooling System (ECCS) Evaluation Model for Large Break Loss-of-Coolant Accident (LOCA)
II Emergency Core Cooling System (ECCS) Evaluation Model Peak Cladding Temperature (PCT) Margin Utilization Rack-up Form cc: M. L. Dapas (NRC), w/a C. F. Lyon (NRC), w/a N. H. Taylor (NRC), wla Senior Resident Inspector (NRC), w/a
Attachment I to RA 15-0080 Page 1 of 2 Assessment of Changes to the Westinghouse Emergency Core Cooling System (ECCS)
Evaluation Model for Large Break Loss-of-Coolant Accident (LOCA)
GENERAL CODE MAINTENANCE
Background
Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include modifying input variable definitions, units and defaults; ,improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451 "Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting."
Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The nature of these changes leads to an estimated peak cladding temperature (PCT) impact of 0° 0F.
ERRORS IN DECAY GROUP UNCERTAINTY FACTORS
Background
Errors in the calculation of decay heat were discovered in the WCOBRA/TRAC code. The decay group uncertainty factors for each fissile isotope are provided in Table 8-14 of WCAP-16009-P-A. The uncertainty factors for 239Pu were applied to 238U, and those for 238U were applied to 2 39pu. This error causes an over-prediction of the uncertainty in decay power from 239pu and an under-prediction of the uncertainty in decay power from 238 U. Further, the decay group uncertainty factor for Decay Group 6 of 235U was erroneously coded as 2.5% instead of 2.25%. Correction of these errors impacts the application of the sampled decay heat uncertainty, which may result in small changes to the decay heat power. These issues have been evaluated to estimate the impact on Automated Statistical Treatment of Uncertainty Method (ASTRUM) best-estimate large break LOCA analysis results. The resolution of these issues represents a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-1 3451.
Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The issues described above were evaluated to account for the correction of these errors. The plant-specific sensitivity study resulted in an estimated PCT impact of -10°F for Wolf Creek Generating Station (WCGS).
Attachment I to PA 15-0080 Page 2 of 2 WCGS CONTAINMENT COOLING CAPACITY
Background
Wolf Creek Nuclear Operating Corporation (WCNOC) identified an error in the containment fan cooler capacity transmitted for use in the best-estimate ASTRUM evaluation model analysis.
This issue has been evaluated to estimate the impact on existing PCT results. The resolution of this issue represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.
Affected Evaluation Models 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The estimated effect was determined for the large break LOCA evaluation model based on the change in calculated containment, pressure resulting from the correct containment cooling capacity. The change in calculated containment pressure leads to an estimated effect of 0°F for the ASTRUM evaluation model analysis.
Attachment II to IRA 15-0080 Page 1 of 1 EMERGENCY CORE COOLING SYSTEM (ECCS) EVALUATION MODEL PEAK CLADDING TEMPERATURE (PCT) MARGIN UTILIZATION RACK-UP FORM
- LARGEBREAK LOCA PCT MARGIN UTILIZATION ***
Evaluation Model: ASTRUM (2004)
Fuel: RFA-2 Peaking Factor: FQ=2.50, FdH=1.65 SG Tube Plugging: 10%
Power Level: 3565 MWth Limiting Break Size: DEG LICENSING BASIS Clad Temp (0 F) Ref. Notes Analysis of Record (AOR) PCT 1900°F 1 MARGIN ALLOCATIONS (APCT)
A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS
- 1. None 0 B. PLANNED PLANT CHANGE EVALUATIONS
- 1. Containment Fan Cooler Capacity 0 2 (a)
C. 2014 PERMANENT ECCS MODEL ASSESSMENTS
- 1. Containment Fan Cooler Capacity 0 2
- 2. Decay Group Uncertainty Factors Errors -10 3 D. OTHER
- 1. None 0 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 1890 0F
References:
- 1. WCAP-17107-P, Revision 1, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Wolf Creek Nuclear Power Plant Using the ASTRUM Methodology,"
January 2014.
- 2. LTR-LIS-14-400, "10 CFR 50.46 Report for the Wolf Creek Large Break LOCA Evaluation of the Change in Containment Cooling Capacity," August 2014.
- 3. LTR-LIS-14-492, "Wolf Creek Unit 1 10 CFR 50.46 Report for the Correction of the Decay Group Uncertainty Factors Errors," November 2014.
Notes:
(a) This effect was estimated based on a cooling capacity intended to bound future implementation of replacement tube bundles in the containment fan coolers.