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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML032380569 + (75)
- ML20063A050 + (2)
- ML20082N974 + (111)
- ML20070R769 + (64)
- ML090570554 + (64)
- L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair + (64)
- ML083250292 + (64)
- 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 + (64)
- ML111010044 + (64)
- RS-11-063, Regarding Supplement to Inservice Inspection Relief Request 13R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations + (64)
- AEP-NRC-2020-71, Indiana Michigan Power Co., Supplement to Request for Relief Related to American Society of Mechanical Engineers (Asme)Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04 + (1)
- IR 05000424/2020003 + (64)
- IR 05000334/2021002 + (64)
- ML20215K647 + (111)
- DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies + (63)
- DCL-13-063, Inservice Inspection Report for Seventeenth Refueling Outage + (58)
- RS-11-064, Revised Response to a Request for Additional Information Related to Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations + (64)
- DCL-11-093, Inservice Inspection Report for Sixteenth Refueling Outage + (58)
- DCL-08-058, Transmittal of Inservice Inspection Report, Fourteenth Refueling Outage + (58)
- BYRON 2007-0055, B2R13, Spring 2007 Outage, Inservice Inspection Summary Report, for Inspection Activities from October 12, 2005 to May 3, 2007, Section 5.0 (Continued) Form NIS-2: Repairs/Modifications Through End + (64)
- ML11116A185 + (64)
- ML030020565 + (54)
- 05000334/LER-1982-006-03, Reactor Coolant Pump Cooling Water Return Containment Isolation Trip Valve (TV-CC-105D1) Did Not Hold Test Pressure.Cause Not Stated. Corrective Maint Performed.Valves Retested + (4)
- ML20248A321 + (65)
- ML032380569 + (65)
- L-02-040, Supplemental Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity + (65)
- ML20116L789 + (65)
- ML20129G211 + (65)
- IR 05000416/1996013 + (65)
- ML20196J497 + (65)
- ML20052A479 + (65)
- ML20126D599 + (65)
- ML021150585 + (65)
- ML030020565 + (65)
- ML020950347 + (65)
- ML030020565 + (54)
- ML053200298 + (67)
- IR 05000206/1987021 + (67)
- IR 05000272/2005003 + (67)
- ML20063A050 + (2)
- ML101241109 + (40)
- RNP-RA/02-0170, Revised Relief Request No. 18 Regarding Examination of the Reactor Pressure Vessel Head Penetration Canopy Seal Weld Repairs for the Fourth Ten-Year Inservice Inspection Interval + (50)
- RNP-RA/02-0166, Relief Request No. 18 Regarding Examination of Reactor Pressure Vessel Head Penetration Canopy Seal Weld Repairs for Fourth Ten-Year Inservice Inspection Interval + (50)
- RS-20-080, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) + (68)
- ML081150649 + (68)
- RS-07-055, Inservice Inspection Relief Request I3R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration + (68)
- RNP-RA/03-0018, Submittal of 90 Day Inservice Inspection Summary Report + (68)
- RS-10-046, Request for Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds + (68)
- IR 05000423/1985054 + (13)
- BYRON 2005-0077, Day Response to First Revised NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors + (68)
- ML080220290 + (68)
- RS-14-314, Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds in Accordance with 10 CFR 50.55a(a)(3)(i) + (68)
- IR 05000334/1982011 + (37)
- ML100210231 + (68)