Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen16 March 202310 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened
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
NRC-2015-0251, Comment (11) of Jamie H. Mccoy on Draft Guidance Documents for Subsequent License Renewal29 February 2016Comment (11) of Jamie H. Mccoy on Draft Guidance Documents for Subsequent License Renewal
ML15075A0284 March 2015Biennial 50.59 Evaluation Report
IR 05000482/201000311 August 2010IR 05000482-10-003, on 4/01/2010 - 6/30/2010; Wolf Creek Generating Station, Integrated Resident and Regional Report; Flood Protection, Operability Evaluations and Identification and Resolution of Problems
ML1003305742 February 2010IR 05000482-09-007 on 09/21/09 - 12/4/09 for Wolf Creek; Special Inspection in Response to Loss of Offsite Power and Essential Service Water Leak on August 19, 2009
WM 08-0003, Wolf Creek Transmittal of Revision 21 to Updated Safety Analysis Report4 March 2008Wolf Creek Transmittal of Revision 21 to Updated Safety Analysis Report
ML0817901674 March 2008Wolf Creek Transmittal of Revision 21 to Updated Safety Analysis Report
ML07278000331 October 2007Audit Report of Licensee Regulatory Commitment Management Program for Audit Performed August 20-21, 2007
ML07249030131 August 2007License Renewal Application, Amendment 3
WO 04-0039, 60-Day Response to NRC Bulletin 2004-01, 'Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.27 July 200460-Day Response to NRC Bulletin 2004-01, 'Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.
WM 03-0044, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity19 September 2003Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity
ML20216G8699 September 1997Requests Approval for Use of Relief Request 12R-22 Alternative to Testing Provisions Provided in 1989 Edition of ASME Section XI