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Issue date | Title | |
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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 Peen | 16 March 2023 | 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 Peened |
ET 17-0007, CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval | 13 April 2017 | CFR 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NRC-2015-0251, Comment (11) of Jamie H. Mccoy on Draft Guidance Documents for Subsequent License Renewal | 29 February 2016 | Comment (11) of Jamie H. Mccoy on Draft Guidance Documents for Subsequent License Renewal |
ML15075A028 | 4 March 2015 | Biennial 50.59 Evaluation Report |
IR 05000482/2010003 | 11 August 2010 | IR 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 |
ML100330574 | 2 February 2010 | IR 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 Report | 4 March 2008 | Wolf Creek Transmittal of Revision 21 to Updated Safety Analysis Report |
ML081790167 | 4 March 2008 | Wolf Creek Transmittal of Revision 21 to Updated Safety Analysis Report |
ML072780003 | 31 October 2007 | Audit Report of Licensee Regulatory Commitment Management Program for Audit Performed August 20-21, 2007 |
ML072490301 | 31 August 2007 | License 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 2004 | 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. |
WM 03-0044, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity | 19 September 2003 | Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity |
ML20216G869 | 9 September 1997 | Requests Approval for Use of Relief Request 12R-22 Alternative to Testing Provisions Provided in 1989 Edition of ASME Section XI |