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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

• ML20129G211  + (65)
• IR 05000416/1996013  + (65)
• ML20196J497  + (54)
• ML20052A479  + (65)
• ML20126D599  + (38)
• ML021150585  + (65)
• ML020950347  + (74)
• 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)
• ML053200298  + (67)
• 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)
• PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years  + (40)
• IR 05000289/2008002  + (68)
• RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75  + (68)
• BYRON 2008-0119, 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)
• 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)

• ML101241109  + (69)
• ML080250142  + (69)
• NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)  + (69)
• NL-15-062, Response to Request for Additional Information Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years  + (69)
• ML15138A415  + (69)
• ML16057A536  + (69)
• ML053200298  + (69)
• ML15349A794  + (69)
• ML16057A552  + (69)
• ML15072A417  + (69)
• NL-12-065, 2012 Summary Report for In-Service Inspection and Repairers and Replacements  + (69)
• 05000366/LER-1986-020, :on 860924,primary Containment Penetrations Failed Local Leak Tests.Caused by Normal Equipment Wear. Affected Valves of 34 Failed Penetration Tests Cycled, Repaired,Rebuilt or Replaced  + (69)
• IR 05000255/1990021  + (69)
• BW120081, Inservice Inspection Summary Report  + (69)
• ML073230117  + (69)

• IR 05000250/2017002  + (7)
• ML20063A050  + (2)
• ML021700642  + (7)
• ML11159A011  + (6)
• 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)
• ML20214T607  + (7)
• LIC-05-0057, Revised Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors  + (6)
• RA-21-0144, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant  + (74)
• 05000270/LER-2011-001, For Oconee, Unit 2, Regarding Technical Specification Violation Involving a Notice of Enforcement Discretion for an Inoperable Containment Isolation Valve  + (6)
• ML021570004  + (7)
• IR 05000280/1988014  + (70)
• IR 05000280/1988018  + (70)
• TXX-6277, Forwards Responses to 870205 Request for Info Re Insp Repts 50-445/85-07,50-446/85-05,50-445/85-14,50-446/85-11, 50-445/85-16,50-446/85-13,50-445/86-06 & 50-446/86-04. Statistical Analysis of Concrete Tests Also Encl  + (7010179000)
• NL-05-040, NRC First Revised Order EA-03-009; Revised Relaxation Request for Inspection of IP3 Reactor Pressure Vessel Head  + (71)
• ML24295A123  + (71)
• 2CAN102402, Enclosure 2: Framatome Affidavit  + (71)
• ML24295A120  + (71)
• ML24316A003  + (71)