Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ET 02-0019, Steam Generator Tube Plugging Report for Wolf Creek Generating Station | 21 April 2002 | Steam Generator Tube Plugging Report for Wolf Creek Generating Station | |
| ET 06-0035, Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove | 5 October 2006 | Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove | Nondestructive Examination Pressure Boundary Leakage |
| ET 06-0044, Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-05 | 2 October 2006 | Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-05 | Weld Overlay Liquid penetrant DM weld |
| ET 06-0049, Response to Request for Additional Information Relating to Pre-Weld Overlay Examination of Pressurizer Nozzle to Safe-End Dissimilar Metal Welds | 29 November 2006 | Response to Request for Additional Information Relating to Pre-Weld Overlay Examination of Pressurizer Nozzle to Safe-End Dissimilar Metal Welds | Dissimilar Metal Weld |
| ET 06-0055, Results of Ultrasonic Examinations of the Full Structural Weld Overlays on Pressurizer Nozzle Welds | 17 November 2006 | Results of Ultrasonic Examinations of the Full Structural Weld Overlays on Pressurizer Nozzle Welds | Weld Overlay DM weld |
| ET 07-0002, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds | 31 January 2007 | Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds | Weld Overlay |
| ET 07-0005, Results of the Fourteenth Steam Generator Tube Inservice Inspection | 19 March 2007 | Results of the Fourteenth Steam Generator Tube Inservice Inspection | Nondestructive Examination |
| 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 |
| ET 07-0050, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls | 16 October 2007 | Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls | Loop seal Stroke time |
| ET 08-0008, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification | 31 January 2008 | Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification | Commercial Grade Dedication |
| ET 08-0016, LTR-CDME-08-43 NP-Attachment, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment. | 18 March 2008 | LTR-CDME-08-43 NP-Attachment, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment. | Finite Element Analysis |
| 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 | |
| ET 09-0005, Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification | 29 January 2009 | Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification | |
| ET 09-0010, Pressure and Temperature Limits Report, Revision 1 | 6 March 2009 | Pressure and Temperature Limits Report, Revision 1 | Hydrostatic Pressure and Temperature 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-50 | 30 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 | Boric Acid Scaffolding |
| 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 |
| 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 Methodology | 21 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 | |
| ET 16-0003, Flood Hazard Reevaluation Report, Revision 1 | 21 October 2015 | Flood Hazard Reevaluation Report, Revision 1 | Safe Shutdown Unanalyzed Condition Ultimate heat sink Hydrostatic Fukushima Dai-Ichi Frazil ice Earthquake |
| ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS | 15 December 2016 | 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS | Probabilistic Risk Assessment Fukushima Dai-Ichi Seismically rugged Earthquake |
| IR 05000482/2008002 | 24 July 2008 | IR 05000482-08-002, on 05/21/2008, for Wolf Creek | Unanalyzed Condition Enforcement Discretion Fire Protection Program |
| ML020790619 | 11 March 2002 | Annual 10 CFR 50.59 Evaluation Report | Safe Shutdown Unanalyzed Condition Boric Acid Offsite Dose Calculation Manual Safe Shutdown Earthquake Probabilistic Risk Assessment Temporary Modification Annual Radioactive Effluent Release Report Hourly Fire Watch |
| ML031980013 | 18 July 2003 | Misc Report ,Stars, 6/10-11/2003 Licensing Workshop Held in Overland Park, Kansas with Strategic Teaming and Resource Sharing-Integrated Regulatory Affairs Group for Licensees of Callaway, Comanche Peak, Diablo Canyon, Palo Verde, So Texas | |
| ML040701090 | 3 March 2004 | Defense-in-Depth and Diversity Assessment (Non-Proprietary) | Safe Shutdown Boric Acid Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Anticipated operational occurrence Water Inventory Control Post Accident Monitoring Operator Manual Action |
| ML042950090 | 29 September 2004 | Attachment I, Administrative Procedure AP 07B-003, Revision 5, Offsite Dose Calculation Manual. | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Power change |
| ML042950094 | 22 May 2003 | Attachment II, Administrative Procedure AP 07B-004, Revision 5, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program). | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report |
| ML042950097 | 1 March 2002 | Attachment III, Administrative Procedure AP 31A-100, Revision 4, Solid Radwaste Process Control Program. | Boric Acid Annual Radioactive Effluent Release Report Process Control Program |
| ML051120341 | 29 April 2005 | LTR-CDME-05-82-NP, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Wolf Creek Generating Station. | Nondestructive Examination Finite Element Analysis |
| ML052270073 | 18 April 2005 | Event Notification Report for April 18, 2005 | Boric Acid Fitness for Duty Reactor Vessel Water Level Packing leak Stolen Troxler Moisture Density Gauge |
| ML053220461 | 14 June 2004 | Power Reactor Status Report for 6/14/04 | |
| ML060230053 | 12 January 2006 | Containment Inservice Inspection Program First Interval, Second Period Owner'S Activity Reports | |
| ML060600458 | 31 January 2006 | Westinghouse Electric Company LLC LTR-CDME-05-209-NP, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at the Wolf Creek Generating Station. | Nondestructive Examination Finite Element Analysis |
| ML063560363 | 20 December 2006 | 12/01/2006 Industry Meeting Handout: Draft Report (December 2006) - 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 |
| ML070170206 | 2 November 2006 | Request for Withholding Proprietary Documentation of Material: White Paper: MRP Review of Implications of Wolf Creek Pressurizer Indications | Weld Overlay Probabilistic Risk Assessment Nondestructive Examination Through Wall Leak DM weld |
| 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 |
| ML070740137 | 9 March 2007 | Biennial 50.59 Evaluation Report for Period Covering January 1, 2005 to December 31, 2006 | |
| 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 |
| ML070850538 | 1 May 2007 | Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by Wolf Creek Nuclear Operating License for Wolf Creek Generating Station | License Renewal |
| ML071160369 | 16 February 2007 | Nutherm Qualification Report WCN-9715R, for CS Innovations Replacement Msfis System, Rev. 0 | Safe Shutdown Earthquake Operating Basis Earthquake Test box |
| ML071160372 | 18 January 2007 | Nutherm Dedication Plan WCN-9715DP, Rev. 0 for Replacement Msfis System | |
| 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 |
| ML071690083 | 8 June 2007 | 10 CFR 50.46 Thirty Day Report of ECCS Model Changes | Stroke time |
| ML071770456 | 30 April 2007 | Reliability Report, Revision 5 | |
| ML071770463 | 30 June 2005 | Procedure STARS-ENG-5000, Rev. 001, Engineering Configuration Management Program. | |
| 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 |
| ML072400199 | 7 September 2007 | (Enclosure 1) Safety Assessment on the Advanced Finite Element Analysis on Growth of Postulated Primary Water Stress Corrosion Cracking Flaws in Pressurizer Nozzle Dissimilar Metal Butt Welds | Safe Shutdown Earthquake Weld Overlay Hydrostatic Finite Element Analysis Earthquake Through-Wall Leak Dissimilar Metal Weld DM weld |
| ML072470394 | 31 August 2007 | Final Report on Implication of Wolf Creek Indications. | Finite Element Analysis Dissimilar Metal Weld DM weld |
| 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 |
| ML080160124 | 8 January 2008 | Summary of the Impact to License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Errors | Probabilistic Risk Assessment |
| 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 |