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 Issue dateTitle
ML17202E9192 August 2017Relief Request 14R-05 from Certain Pressure Test Requirements of the ASME Code for Reactor Pressure Vessel Leak-Off Lines for the Fourth 10 Year Inservice Inspection Interval
ET 17-0007, CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval13 April 2017CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval
ET 16-0030, Relief Request Number 14R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds and Relief Request 14R-04, Request for Relief from Requirements of ASME Code Case N-729-11 November 2016Relief Request Number 14R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds and Relief Request 14R-04, Request for Relief from Requirements of ASME Code Case N-729-1
ET 16-0019, Relief from Impractical Examination Coverage Requirements for the Third 10-Year Inservice Inspection Program Interval23 August 2016Relief from Impractical Examination Coverage Requirements for the Third 10-Year Inservice Inspection Program Interval
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements
ML16204A01131 May 2016Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements
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
ML15226A35421 August 2015Relief Request, Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division1, Excess Letdown Heat Exchanger
IR 05000482/20150017 May 2015IR 05000482/2015001; on 01/01/2015 - 03/28/2015; Wolf Creek Generating Station Integrated Resident and Regional Report: Maintenance Risk Assessments and Emergent Work Control, and Operability Determinations and Functionality Assessments
ML15084A53911 March 2015Updated Safety Analysis Report (Usar), Revision 28, Chapter 18.0, Response to NUREG-0737, Clarification of TMI Action Plan Requirements
ML15040A02012 February 2015Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code, Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval
ML15023A22028 January 2015Relief Request 13R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220 for the Third 10-Year Inservice Inspection Interval
ET 14-0026, Response to Request for Additional Information Regarding Request for Alternative 13R-1 121 August 2014Response to Request for Additional Information Regarding Request for Alternative 13R-1 1
ML14230A75721 August 2014Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval
ML14197A33625 July 2014Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval
ET 14-0019, 10 CFR 50.55a Request 13R-11 for the Third Inservice Inspection Program Interval26 June 201410 CFR 50.55a Request 13R-11 for the Third Inservice Inspection Program Interval
ET 14-0018, 10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval26 June 201410CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval
ML13226A25514 August 2013IR 05000482-13-003, 03/31 - 06/30/2013, Wolf Creek Generating Station, Integrated Resident and Regional Report; Inservice Inspection Activities, Follow-up of Events and Notices of Enforcement Discretion, Other Activities
IR 05000482/201300314 August 2013IR 05000482-13-003, 03/31 - 06/30/2013, Wolf Creek Generating Station, Integrated Resident and Regional Report; Inservice Inspection Activities, Follow-up of Events and Notices of Enforcement Discretion, Other Activities
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
ML11224022312 August 2011IR 05000482-11-003 & Notice of Violation, on 04/1/2011 6/30/2011, Wolf Creek Generating Station, Integrated Resident Report, Adverse Weather Protection, Equipment Alignments, Inservice Inspection Activities, Post Maintenance Testing, Event
IR 05000482/201100312 August 2011IR 05000482-11-003 & Notice of Violation, on 04/1/2011 6/30/2011, Wolf Creek Generating Station, Integrated Resident Report, Adverse Weather Protection, Equipment Alignments, Inservice Inspection Activities, Post Maintenance Testing, Event
ML11028046627 January 2011Notification of Inspection (NRC Inspection Report 05000482-11-003) and Request for Information
IR 05000482/200900511 February 2010IR 05000482-09-005, on 10/01/2009 - 12/31/2009; Wolf Creek Generating Station, Integrated Resident and Regional Report; Fire Protection, Inservice Inspection Activities; Maintenance Risk Assessments and Emergent Work Controls
ML10043071311 February 2010IR 05000482-09-005, on 10/01/2009 - 12/31/2009; Wolf Creek Generating Station, Integrated Resident and Regional Report; Fire Protection, Inservice Inspection Activities; Maintenance Risk Assessments and Emergent Work Controls
ML09191043410 July 2009Notification of Inspection (NRC Inspection Report 05000482-09-005 and Request for Information
ET 09-0014, Response to Request for Additional Information Regarding 10 CFR 50.55a Request I3R-0623 April 2009Response to Request for Additional Information Regarding 10 CFR 50.55a Request I3R-06
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
ML08036054914 February 2008Audit Summary Regarding the License Renewal Application for the Wolf Creek Generating Station - AMP AMR
ML08045060314 February 2008Notification of Inspection (NRC Inspection Report 05000482/2008003) and Request for Information
ML07278000331 October 2007Audit Report of Licensee Regulatory Commitment Management Program for Audit Performed August 20-21, 2007
ML07277001027 September 2007Followup Response to NRC Requests for Additional Information Related to License Renewal Application
ML07249030131 August 2007License Renewal Application, Amendment 3
ML07218022526 July 2007Operating Corporation - Revision to the Aging Management Program, and Time-Limited Aging Analysis Questions and Responses Related to License Renewal Application
ML07215023226 July 2007Followup Response to NRC Requests for Additional Information Related to License Renewal Application
ML07150056525 May 2007Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
ML07138045410 May 2007Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
IR 05000482/20060056 February 2007IR 05000482/2006-005; 10/08/06 - 12/31/06; Wolf Creek Generating Station; Refueling and Outage Activities, Access Control to Radiologically Significant Areas
RA-07-0012, Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report31 January 2007Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report
ML06347008227 December 2006Request for Relief I2R-37 and I2R-38 for the Second 10-year Interval Inservice Inspection, MD0291 and MD0292
WM 06-0051, Day Report for NRC Order EA-03-009, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.20 December 2006Day Report for NRC Order EA-03-009, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.
ML06307058720 November 2006Relief Request I2R-35 for the Second 10-Year Interval Inservice Inspection
ML06307059020 November 2006Relief Request I2R-34 for the Second 10-year Interval Inservice Inspection
ML06307060220 November 2006Relief Request I2R-36 for the Second 10-year Interval Inservice Inspection
ET 06-0027, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-3612 July 2006Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-36
ML0606900444 April 2006Relief, ASME Code Inspection Requirements for Section XI, Class 1, Table IWB-2500-1, Examination Category B-D, Item No. B3.90, Nozzles-to-Vessel Welds for the Second 10-Year Interval
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
ET 06-0011, CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval2 March 2006CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval
ET 05-0027, CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds22 November 2005CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds
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