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Issue date | Title | Topic | |
---|---|---|---|
ML072120528 | 15 April 2007 | Refueling Outage 13, Special Interest Point Inspection Results Part 1 of 2 | |
ML072120539 | 16 April 2007 | Refueling Outage 13, Special Interest Point Inspection Results, Part 2 of 2 | Hydrostatic |
ML081830087 | 31 March 2008 | Steam Generator Eddy Current Inspection Report, Refueling Outage 15, Attachment B, Inspection Scope, Through Attachment B.2, Cold Leg Bobbin Coil Inspection Scope. | |
ML081830089 | 31 March 2008 | Steam Generator Eddy Current Inspection Report Refueling Outage 15, Attachment B.3, Special Interest Plus-Point Inspection Scope Including Hot Leg Dents and Dings. | |
ML081830090 | 31 March 2008 | Steam Generator Eddy Current Inspection Report Refueling Outage 15, No Special Interest Performed in SG C Cold Leg in B1R15. | Hydrostatic |
ML090260075 | 22 January 2009 | Inservice Inspection Report for Interval 3, Period 1, (B2R14), Cover Through Section 2.0 | Boric Acid Nondestructive Examination VT-2 EVT-1 |
ML090260079 | 22 January 2009 | Inservice Inspection Report for Interval 3, Period 1, (B2R14), Section 3.0 Through Section 4.0 | |
ML090260084 | 22 January 2009 | Inservice Inspection Report for Interval 3, Period 1, (B2R14), Section 5.0 | Hydrostatic |
ML100050357 | 5 January 2010 | 90-Day Inservice Inspection Report for Interval 3, Period 1, (B1R16) | Boric Acid Weld Overlay Nondestructive Examination VT-2 |
ML100050360 | 17 December 2009 | B1R16 Lsi Outage Report, Bolts, Pumps, and Valves Outage Summary | VT-2 |
ML100050362 | 17 December 2009 | B1R16 Lsi Outage Report - Form NIS-1 Owner'S Report for Inservice Inspections | |
ML111010535 | 8 April 2011 | Supplement to Byron Unit 1, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | High Radiation Area Nondestructive Examination |
ML112990783 | 1 February 2012 | Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | Weld Overlay Nondestructive Examination Incorporated by reference |
ML13008A073 | 3 January 2013 | Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XI | Hydrostatic |
ML13008A075 | 3 January 2013 | Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XI | Hydrostatic |
ML13008A076 | 2 January 2013 | Inservice Inspection Summary Report, Common-3rd Interval ASME Section XI Examination Status Report | |
ML13008A077 | 3 January 2013 | Inservice Inspection Summary Report, for Inspection Activities from April 24, 2011 to October 8, 2012 | Boric Acid Nondestructive Examination VT-2 Liquid penetrant |
ML13008A080 | 2 January 2013 | Inservice Inspection Summary Report, Weld/Component Outage Summary, Part 2 of 7-03 | VT-2 |
ML13008A088 | 3 January 2013 | Inservice Inspection Summary Report, Form NIS-1 Owner'S Report for Inservice Inspections, Part 4 of 7-05 | |
ML13008A093 | 3 January 2013 | Inservice Inspection Summary Report, Chapter 6.0, Containment ISI Program, Part 7 of 7-08X | Hydrostatic Moisture barrier |
ML15216A609 | 20 August 2015 | Review of Fall 2014 Steam Generator Tube Inservice Inspection Report | |
ML16203A108 | 21 July 2016 | Fourth Ten-Year Interval Inservice Testing Program | Safe Shutdown Boric Acid Stroke time Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding Grace period |
ML16300A036 | 26 October 2016 | Fourth Ten-Year Interval Inservice Inspection Program | Safe Shutdown Boric Acid Weld Overlay Hydrostatic Coatings Nondestructive Examination VT-2 Incorporated by reference Aging Management Moisture barrier License Renewal Earthquake Through-Wall Leak Through-Wall Leakage Dissimilar Metal Weld |
ML19192A049 | 11 July 2019 | Day Inservice Inspection Report for Interval 4, Period 1, (B2R21) | Through-Wall Leak Through Wall Leak |
ML20240A142 | 17 September 2020 | Day Inservice Inspection Report for Interval 4, Period 2, (B1R23) | Moisture barrier Through Wall Leak |
ML21355A407 | 21 December 2021 | Day Inservice Inspection Report for Interval 4, Period 2, (81 R24) | |
ML23159A130 | 8 June 2023 | Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) | |
NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants | 30 April 2019 | Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants | Boric Acid Loop seal Nondestructive Examination |
NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 | 16 October 2019 | Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 | Boric Acid Nondestructive Examination |
RS-04-104, Second Interval Inservice Inspection Program Relief Request I2R-46 | 22 July 2004 | Second Interval Inservice Inspection Program Relief Request I2R-46 | Boric Acid VT-2 Scaffolding |
RS-04-168, Second Interval Inservice Inspection Program Relief Request 12R-50 | 5 November 2004 | Second Interval Inservice Inspection Program Relief Request 12R-50 | Dissimilar Metal Weld |
RS-07-055, Inservice Inspection Relief Request I3R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration | 13 April 2007 | Inservice Inspection Relief Request I3R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration | Boric Acid Liquid penetrant |
RS-11-045, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 24 March 2011 | Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | Weld Overlay Nondestructive Examination Liquid penetrant |
RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 19 April 2011 | Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | Weld Overlay Nondestructive Examination Liquid penetrant |
RS-14-251, Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 8 September 2014 | Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | Weld Overlay Nondestructive Examination Liquid penetrant |
RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 29 May 2015 | Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | |
RS-15-170, Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval | 22 June 2015 | Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval | Stroke time Grace period |
RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval | 8 November 2016 | Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval | Nondestructive Examination Finite Element Analysis Liquid penetrant |
RS-17-163, Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval | 20 November 2017 | Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval | |
RS-20-085, Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | 24 July 2020 | Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | Coatings Incorporated by reference Fuel cladding |
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | 10 October 2023 | Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | Finite Element Analysis Aging Management License Renewal Subsequent License Renewal |