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 Issue dateTitle
ML23135A1708 May 20236 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML23135A1718 May 20236 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
ML22151A15418 May 20225 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML22151A15618 May 20225 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
IR 05000482/20210029 August 2021Integrated Inspection Report 05000482/2021002
ML21168A1177 June 20214 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML21168A1197 June 20214 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
IR 05000482/202000212 August 2020Integrated Inspection Report 05000482/2020002 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2020001
ML20290A57323 July 2020Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML20290A57423 July 2020Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
ML20111A33727 April 2020Request from Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-666-1
ML19092A07311 March 2019Revision 32 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Public
ML19092A07511 March 2019Revision 32 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
ML18093A8918 March 2018Revision 31 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML18093A8938 March 2018Revision 31 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
ML17151B0009 March 2017Revision 30 to Updated Final Safety Analysis Report, Chapter 5.0, Reactor Coolant System and Connected Systems
ML17151B0029 March 2017Revision 30 to Updated Final Safety Analysis Report, Chapter 6.0, Engineered Safety Features
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems
ML16203A37431 May 2016Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems
ML16203A37531 May 2016Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features
ET 16-0006, 10 CFR 50.55a Request to Use ASME Code Cade N-789-2 for the Fourth Inservice Inspection Program Interval2 March 201610 CFR 50.55a Request to Use ASME Code Cade N-789-2 for the Fourth Inservice Inspection Program Interval
ET 16-0005, Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval23 February 2016Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval
ML15084A50511 March 2015Updated Safety Analysis Report (Usar), Revision 28, Chapter 6.0, Engineered Safety Features
ML15084A50411 March 2015Updated Safety Analysis Report (Usar), Revision 28, Chapter 5.0, Reactor Coolant System and Connected Systems
ML13065A0493 August 2012IR 05000482/12-003, 03/31/2012 - 06/29/2012 for Wolf Creek Generating Station, Integrated Resident and Regional Report; Flood Protection Measures, Plant Modifications - Supersedes ML12219A181
ML12219A1813 August 2012IR 05000482-12-003; 03/31/2012 06/29/2012; Wolf Creek Generation Station, Integrated Resident and Regional Report; Flood Protection Measures, Plant Modifications
ET 09-0008, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification17 February 2009Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
WM 09-0001, Response to NRC Request for Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification16 January 2009Response to NRC Request for Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
IR 05000482/20080037 August 2008IR 05000482-08-003; on 4/07/08 - 6/28/08; Wolf Creek Generating Station; Fire Protection, Maintenance Effectiveness, Operability Evaluations, Outage Activities, Event Follow-up and Other Activities
ML07275061424 September 2007LTR-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.
ML07249030131 August 2007License Renewal Application, Amendment 3
ML07215023226 July 2007Followup Response to NRC Requests for Additional Information Related to License Renewal Application
ET 07-0008, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification18 April 2007Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification
ET 06-0044, Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-052 October 2006Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-05
ET 06-0021, Operating Corporation'S Response to Request for Additional Information Regarding 10 CFR 50.55a Request 13R-05 and Submittal of Revision 1 to 10 CFR 50.55a Request 13R-054 August 2006Operating Corporation'S Response to Request for Additional Information Regarding 10 CFR 50.55a Request 13R-05 and Submittal of Revision 1 to 10 CFR 50.55a Request 13R-05
ML06145031919 May 200610 CFR 50.55a Request I3R-05, Installation and Examination of Full Structural Weld Overlays for Repairing/Mitigating Pressurizer Nozzle-to-Safe End Dissimilar Metal Welds and Adjacent Safe End-to Piping Stainless Steel Welds
ET 06-0010, Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-042 March 2006Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-04
IR 05000482/200500328 July 2005IR 05000482-05-003; on 4/8/05 - 06/26/05; Wolf Creek Generating Station; Access Control to Radiological Significant Areas
ML04177016716 June 2004Issuance of Amendment Extending the Inspection Interval for Reactor Coolant Pump Flywheels
IR 05000482/20030063 February 2004IR 05000482-03-006; 10/4/03 - 12/31/03; Wolf Creek Generating Station. Fire Protection, Access Control to Radiologically Significant Areas, ALARA Planning and Controls
IR 05000482/200200223 July 2002IR 05000482-02-002, on 03/24/2002 - 06/29/2002, Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station
ET 02-0018, Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity3 April 2002Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
IR 05000482/19990045 May 1999Insp Rept 50-482/99-04 on 990405-09.No Violations Noted. Major Areas Inspected:Licensee Implementation of Facility Inservice Insp Program & Followup Review of Previously Identified Insp Findings
IR 05000482/199701729 October 1997Insp Rept 50-482/97-17 on 970929-1010.No Violations Noted. Major Areas Inspected:Maint
IR 05000482/19970142 October 1997Insp Rept 50-482/97-14 on 970810-0920.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support
L-96-026, Tech Evaluation Rept on Second 10 Year Inservice Insp Program Plan:Wolf Creek Nuclear Operating Corp31 July 1997Tech Evaluation Rept on Second 10 Year Inservice Insp Program Plan:Wolf Creek Nuclear Operating Corp
ML20140H1786 May 1997Forwards Response to Request for Addl Info Re Second 10-yr Interval ISI Program Plan & Associated Requests for Relief
ML20091P46430 August 1995Second Interval ISI Program Plan
ML20045F2752 July 1993Responds to NRC Ltr Re Violations Noted in Insp Rept 50-482/93-08.C/As:methodology to Be Used When Removing Surveillances from R-1 Schedule Have Been Evaluated to Include Restoration of Items to Schedule
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