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 Issue dateTitleTopic
ML07212052815 April 2007Refueling Outage 13, Special Interest Point Inspection Results Part 1 of 2
ML07212053916 April 2007Refueling Outage 13, Special Interest Point Inspection Results, Part 2 of 2Hydrostatic
ML08183008731 March 2008Steam Generator Eddy Current Inspection Report, Refueling Outage 15, Attachment B, Inspection Scope, Through Attachment B.2, Cold Leg Bobbin Coil Inspection Scope.
ML08183008931 March 2008Steam Generator Eddy Current Inspection Report Refueling Outage 15, Attachment B.3, Special Interest Plus-Point Inspection Scope Including Hot Leg Dents and Dings.
ML08183009031 March 2008Steam Generator Eddy Current Inspection Report Refueling Outage 15, No Special Interest Performed in SG C Cold Leg in B1R15.Hydrostatic
ML09026007522 January 2009Inservice Inspection Report for Interval 3, Period 1, (B2R14), Cover Through Section 2.0Boric Acid
Nondestructive Examination
VT-2
EVT-1
ML09026007922 January 2009Inservice Inspection Report for Interval 3, Period 1, (B2R14), Section 3.0 Through Section 4.0
ML09026008422 January 2009Inservice Inspection Report for Interval 3, Period 1, (B2R14), Section 5.0Hydrostatic
ML1000503575 January 201090-Day Inservice Inspection Report for Interval 3, Period 1, (B1R16)Boric Acid
Weld Overlay
Nondestructive Examination
VT-2
ML10005036017 December 2009B1R16 Lsi Outage Report, Bolts, Pumps, and Valves Outage SummaryVT-2
ML10005036217 December 2009B1R16 Lsi Outage Report - Form NIS-1 Owner'S Report for Inservice Inspections
ML1110105358 April 2011Supplement to Byron Unit 1, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head PenetrationsHigh Radiation Area
Nondestructive Examination
ML1129907831 February 2012Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head PenetrationsWeld Overlay
Nondestructive Examination
Incorporated by reference
ML13008A0733 January 2013Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XIHydrostatic
ML13008A0753 January 2013Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XIHydrostatic
ML13008A0762 January 2013Inservice Inspection Summary Report, Common-3rd Interval ASME Section XI Examination Status Report
ML13008A0773 January 2013Inservice Inspection Summary Report, for Inspection Activities from April 24, 2011 to October 8, 2012Boric Acid
Nondestructive Examination
VT-2
Liquid penetrant
ML13008A0802 January 2013Inservice Inspection Summary Report, Weld/Component Outage Summary, Part 2 of 7-03VT-2
ML13008A0883 January 2013Inservice Inspection Summary Report, Form NIS-1 Owner'S Report for Inservice Inspections, Part 4 of 7-05
ML13008A0933 January 2013Inservice Inspection Summary Report, Chapter 6.0, Containment ISI Program, Part 7 of 7-08XHydrostatic
Moisture barrier
ML15216A60920 August 2015Review of Fall 2014 Steam Generator Tube Inservice Inspection Report
ML16203A10821 July 2016Fourth Ten-Year Interval Inservice Testing ProgramSafe Shutdown
Boric Acid
Stroke time
Cold shutdown justification
Power-Operated Valves
Power Operated Valves
Scaffolding
Grace period
ML16300A03626 October 2016Fourth Ten-Year Interval Inservice Inspection ProgramSafe 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
ML19192A04911 July 2019Day Inservice Inspection Report for Interval 4, Period 1, (B2R21)Through-Wall Leak
Through Wall Leak
ML20240A14217 September 2020Day Inservice Inspection Report for Interval 4, Period 2, (B1R23)Moisture barrier
Through Wall Leak
ML21355A40721 December 2021Day Inservice Inspection Report for Interval 4, Period 2, (81 R24)
ML23159A1308 June 2023Day Inservice Inspection Report for Interval 4, Period 3, (B1R25)
NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants30 April 2019Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for PlantsBoric 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-87916 October 2019Byron 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-879Boric Acid
Nondestructive Examination
RS-04-104, Second Interval Inservice Inspection Program Relief Request I2R-4622 July 2004Second Interval Inservice Inspection Program Relief Request I2R-46Boric Acid
VT-2
Scaffolding
RS-04-168, Second Interval Inservice Inspection Program Relief Request 12R-505 November 2004Second Interval Inservice Inspection Program Relief Request 12R-50Dissimilar Metal Weld
RS-07-055, Inservice Inspection Relief Request I3R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration13 April 2007Inservice Inspection Relief Request I3R-14: Alternative Requirements for the Repair of a Reactor Vessel Head PenetrationBoric Acid
Liquid penetrant
RS-11-045, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations24 March 2011Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head PenetrationsWeld 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 Penetrations19 April 2011Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head PenetrationsWeld 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 Penetrations8 September 2014Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head PenetrationsWeld 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 Penetrations29 May 2015Response 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 Interval22 June 2015Submittal of Relief Requests Associated with the Fourth Inservice Testing IntervalStroke 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 Interval8 November 2016Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection IntervalNondestructive Examination
Finite Element Analysis
Liquid penetrant
RS-17-163, Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval20 November 2017Withdrawal 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 Requirements24 July 2020Submittal 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 RequirementsCoatings
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 Sections10 October 2023Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius SectionsFinite Element Analysis
Aging Management
License Renewal
Subsequent License Renewal