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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23279A067 | 9 November 2023 | Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval | VT-2 |
| ML20036F261 | 4 March 2020 | Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years | Probabilistic Risk Assessment |
| ML19339H747 | 13 December 2019 | Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval | VT-2 Finite Element Analysis Liquid penetrant Pressure Boundary Leakage Dissimilar Metal Weld DM weld |
| ML18106B121 | 25 April 2018 | Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques | Hydrostatic Nondestructive Examination |
| L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography | 24 July 2017 | Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography | Hydrostatic Nondestructive Examination Incorporated by reference Dissimilar Metal Weld |
| ML16330A118 | 15 December 2016 | NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) | Incorporated by reference |
| ML16063A058 | 22 March 2016 | Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection | VT-2 Liquid penetrant DM weld |
| ML15246A305 | 16 September 2015 | Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval | |
| ML15127A291 | 20 May 2015 | Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components | VT-2 Through-Wall Leak |
| NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B | 14 May 2015 | Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B | |
| ML15099A018 | 7 May 2015 | Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test | Hydrostatic VT-2 Pressure Boundary Leakage |
| ML14343A051 | 10 December 2014 | Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval | VT-2 Incorporated by reference Dissimilar Metal Weld |
| ML13329A031 | 20 December 2013 | Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) | Incorporated by reference Liquid penetrant |
| NRC 2013-0020, CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval | 19 March 2013 | CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval | VT-2 |
| ML13079A141 | 19 March 2013 | CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval | VT-2 |
| ML13064A425 | 18 March 2013 | Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld | Nondestructive Examination Incorporated by reference Dissimilar Metal Weld |
| ML12286A104 | 15 November 2012 | Evaluation of Relief Requests RR-2 & RR-3 (ME7974 & ME7975) | Boric Acid Incorporated by reference |
| ML061710364 | 3 July 2006 | Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 | Incorporated by reference |
| ML052700197 | 18 January 2006 | Relief Request - Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 | Incorporated by reference |
| ML052650312 | 27 September 2005 | Relief Requests - the Previsions of ASME Section XI, IWA-5244, Buried Components, RR-1-26 and RR-2-34 | |
| NRC 2005-0084, Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 | 1 July 2005 | Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 | Liquid penetrant |
| NRC 2005-0016, Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 16 | 4 February 2005 | Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 16 | Temporary Modification Liquid penetrant Through-Wall Leak |
| NRC 2005-0015, Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 15 | 21 January 2005 | Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 15 | VT-2 Through-Wall Leak |
| ML040860161 | 1 April 2004 | Request for Relief VRR 03-01 on a One Time Basis for Performing Inservice Testing of Relief Valve 1RH-861C | Boric Acid |
| ML040160738 | 26 February 2004 | Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 | Nondestructive Examination Incorporated by reference Dissimilar Metal Weld |
| ML032310402 | 10 September 2003 | Relief, MR 02 018-2 Pertaining to Reactor Vessel Closure Head Penetration Repair | Nondestructive Examination Incorporated by reference |
| ML030620328 | 21 March 2003 | Relief, Use of Code Case N-600 for the Fourth 10-Year Interval, MB5403 and MB5404 | |
| ML022540109 | 21 March 2003 | Relief Request No 8 - Requirement for Scheduling of Components for Examination | Incorporated by reference |
| ML030210126 | 27 February 2003 | Relief, Alternative to Examine All Three Vessels of the Regenerative Heat Exchanger, MB5401 & MB5402 | High Radiation Area Nondestructive Examination VT-2 Incorporated by reference |
| ML022530006 | 8 October 2002 | Code Relief, ASME Code Section XI, Relief Request 5 Regarding Visual Examination of Insulted Bolting on Borated Systems | Boric Acid VT-2 Incorporated by reference |
| ML022530023 | 8 October 2002 | Relief, Granted for ASME Code Section XI, Relief Request 6 Regarding Evaluation of Leakage with Bolting In-Place | Incorporated by reference |
| NRC 2002-0073, Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-2 | 28 August 2002 | Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-2 | Nondestructive Examination Liquid penetrant Dissimilar Metal Weld |