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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23244A214 | 1 September 2023 | IAEA Osart Report | FLEX Aging Management Foreign Material Exclusion Severe Accident Management Guideline Pandemic Fire Watch Scaffolding |
| ML23135A201 | 6 December 2022 | EQSD-I, Rev 18, Equipment Qualification Design Basis Document | Safe Shutdown Boric Acid Mission time Fire Barrier Anticipated operational occurrence Hydrostatic Functionality Assessment Aging Management Operability Determination License Renewal Earthquake Grace period GOTHIC Operability Assessment |
| ML23135A193 | 1 September 2022 | EQSD-II, Rev 34, Equipment Qualification Summary Document | Safe Shutdown Boric Acid Ultimate heat sink Safe Shutdown Earthquake |
| WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report | 29 August 2022 | Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report | Post Accident Monitoring |
| ML22152A204 | 18 May 2022 | EQSD-I, Revision 16, Equipment Qualification Design Basis Document | Safe Shutdown Boric Acid Mission time Fire Barrier Anticipated operational occurrence Hydrostatic Functionality Assessment Aging Management Operability Determination License Renewal Earthquake Grace period GOTHIC Operability Assessment |
| ML22152A199 | 18 May 2022 | EQSD-II, Revision 33, EQ Program Master List (Table 1) Plus Mild Environment SR Electrical Equipment List (Table 2) | Safe Shutdown Boric Acid Ultimate heat sink Safe Shutdown Earthquake |
| ML22152A194 | 18 May 2022 | EQSD-I, Revision 15, Equipment Qualification Design Basis Document | Safe Shutdown Boric Acid Mission time Fire Barrier Anticipated operational occurrence Hydrostatic Functionality Assessment Aging Management Operability Determination License Renewal Earthquake Grace period GOTHIC Operability Assessment |
| ML23135A207 | 6 April 2022 | EQSD-I, Rev 17, Equipment Qualification Design Basis Document | Safe Shutdown Boric Acid Mission time Fire Barrier Anticipated operational occurrence Hydrostatic Functionality Assessment Aging Management Operability Determination License Renewal Earthquake Grace period GOTHIC Operability Assessment |
| ML20290A619 | 23 July 2020 | Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, EQSD-I, Rev. 14, Equipment Qualification Design Basis Document | Safe Shutdown Boric Acid Fire Barrier Anticipated operational occurrence Tornado Missile Hydrostatic Functionality Assessment Aging Management Operability Determination License Renewal Earthquake Grace period GOTHIC Operability Assessment |
| ML19092A156 | 18 September 2018 | EQSD-I, Rev 14 | |
| ML18093B011 | 8 March 2018 | Revision 31 to Updated Safety Analysis Report, Equipment Classification Design Basis Document, EQSD-I Rev 13 | |
| ML18093B013 | 8 March 2018 | Revision 31 to Updated Safety Analysis Report, Equipment Qualification Summary Document, EQSD-II, Rev 30, Redacted | |
| WO 19-0010, EQSD-II, Rev 31 | 19 February 2018 | EQSD-II, Rev 31 | |
| ML17151B045 | 9 March 2017 | Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 2 - Redacted | Boric Acid Ultimate heat sink |
| ML17151B044 | 2 March 2017 | Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 1 | |
| ML17151B043 | 26 January 2017 | Equipment Qualification Design Basis Document, EQSD-I, Rev 11 | Safe Shutdown Boric Acid Fire Barrier Anticipated operational occurrence Hydrostatic Functionality Assessment Aging Management Operability Determination License Renewal Earthquake Grace period GOTHIC Operability Assessment |
| ML17054C230 | 17 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 | |
| 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. | 31 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. | |
| ML16204A180 | 31 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 Redacted | 31 May 2016 | Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted | Hot Short Safe Shutdown Boric Acid Ultimate heat sink Safe Shutdown Earthquake |
| ML17151B039 | 26 October 2015 | E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evaluation | Hot Short Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Ultimate heat sink Temporary Modification Multiple Spurious Operation Arc flash Emergency Lighting Fire Protection Program |
| ML15062A275 | 24 February 2015 | Pressure and Temperature Limits Report, Revision 2 | Hydrostatic Pressure and Temperature Limits Report |
| ML14189A498 | 19 June 2014 | Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request | Commercial Grade Dedication Coatings Finite Element Analysis |
| ML14064A329 | 26 February 2014 | NP-Attachment to LTR-LIS-13-557, Rev 0, Application of Westinghouse Best-Estimate Large Break LOCA Methodology to the Wolf Creek Generating Station | Fuel cladding |
| ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis | 25 February 2014 | Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis | Offsite Dose Calculation Manual Temporary Modification Functionality Assessment Missed surveillance Grace period |
| ML14034A054 | 12 February 2014 | Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML14023A614 | 3 February 2014 | Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Wolf Creek Generating Station, TAC No.: MF0788 | Safe Shutdown Boric Acid High winds Ultimate heat sink Mission time Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Severe Accident Management Guideline Frazil ice Earthquake |
| ML13247A077 | 31 August 2013 | WCAP-17658-NP, Rev. 0, Wolf Creek Generating Station Transition of Methods for Core Design and Safety Analyses - Licensing Report | Boric Acid Shutdown Margin Loop seal Stroke time Anticipated operational occurrence License Renewal Earthquake Fuel cladding Power change Coast down Power Uprate Measurement Uncertainty Recapture |
| ML13247A078 | 31 August 2013 | WCAP-17746-NP, Rev. 0 Westinghouse Setpoint Methodology as Applied to the Wolf Creek Generating Station | |
| ML13247A079 | 31 August 2013 | WCAP-17602-NP, Rev. 0, Westinghouse Setpoint Calculations for the Wolf Creek Generating Station Control, Protection, and Indication Systems | |
| ML13247A080 | 13 August 2013 | Full Scope Implementation of the Alternative Source Term | Safe Shutdown Boric Acid High winds Ultimate heat sink Grab sample Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Safe Shutdown Earthquake Post Accident Monitoring Probabilistic Risk Assessment Nondestructive Examination Incorporated by reference Annual Radioactive Effluent Release Report Large early release frequency Earthquake Deep Dose Equivalent Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Power change Unidentified leakage Overexposure |
| ML13177A285 | 30 June 2013 | WCAP-17678-NP, Supplement 1, Revision 1, Wolf Creek Generating Station Supplemental Information for Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report, Part 3 of 3 | Boric Acid Ultimate heat sink Commercial Grade Dedication Earthquake Scaffolding |
| ML12340A398 | 30 November 2012 | PEUS-WR-12-5, Revision 1, Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report | Unanalyzed Condition Ultimate heat sink Hydrostatic Functionality Assessment Fukushima Dai-Ichi Earthquake |
| ML122260214 | 16 August 2012 | Iolb Evaluation of Ifr 2012-04 Relating to Wolf Creek Loss of Offsite Power and Notification of Unusual Event | Safe Shutdown |
| ML12129A387 | 30 August 2011 | Enclosure III, Wolf Creek Nuclear Operating Corporation Administrative Procedure AP 31A-100, Revision 8, Solid Radwaste Process Control Program. | Process Control Program |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| ML082270298 | 30 July 2008 | CS Innovations Report 6002-00002, Rev. 2, Als Configuration Management Plan, Non-Proprietary, Enclosure II | |
| ML082270301 | 29 July 2008 | CS Innovations Report 6002-00026, Rev. 1, Als Platform Overview, Non-Proprietary, Enclosure Viii | |
| ML082270300 | 29 July 2008 | CS Innovations Report 6101-00200, Rev. 3, Msfis V & V Report, Non-Proprietary, Enclosure VI | Commercial Grade Dedication |
| ML082270299 | 29 July 2008 | CS Innovations Report 6002-00001, Rev. 2, Als Quality Assurance Plan, Non-proprietary, Enclosure IV | |
| ET 08-0032, Submittal of Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification | 14 May 2008 | Submittal of Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification | |
| ML080440100 | 31 January 2008 | Westinghouse Electric Company LLC LTR-CDME-08-11 NP-Attachment, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone | |
| ML072750614 | 24 September 2007 | LTR-CDME-07-198 NP-Attachment, Response to NRC RAI Relating to LTR-CDME-07-72 P-Attachment and LTR-CDME-05-209-P of the Wolf Creek Generating Station (WCGS) Permanent B* License Amendment Request. | Finite Element Analysis Liquid penetrant Through-Wall Leak |
| ML072470394 | 31 August 2007 | Final Report on Implication of Wolf Creek Indications. | Finite Element Analysis Dissimilar Metal Weld DM weld |
| ML071970083 | 14 July 2007 | Draft a EPRI Report: Advanced Fea Industry Corres Presentation Studies | Safe Shutdown Earthquake |
| ML072000312 | 13 July 2007 | Summary of Impact to Wolf Creek License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Error | Probabilistic Risk Assessment |
| ML071560398 | 30 April 2007 | Evaluation of Circumferential Indications in Pressurizer Nozzle Dissimilar Metal Welds at the Wolf Creek Power Plant - Non-Proprietary Report | Non-Destructive Examination Finite Element Analysis Dissimilar Metal Weld DM weld |
| ET 07-0008, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification | 18 April 2007 | Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification | Safe Shutdown Safe Shutdown Earthquake Coatings Earthquake Liquid penetrant |
| ML070800198 | 13 March 2007 | 9100-00003-NP, Rev. 1, Wolf Creek Generating Station Main Steam and Feedwater Isolation System (Msfis) Controls Summary. | Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
| ML070240159 | 22 January 2007 | MRP 2007-003 Attachment 1, Implications of Wolf Creek Pressurizer Butt Weld Indications Relative to Safety Assessment and Inspection Requirements. | Boric Acid Safe Shutdown Earthquake Weld Overlay Probabilistic Risk Assessment Nondestructive Examination Finite Element Analysis Through-Wall Leak Dissimilar Metal Weld DM weld |