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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
- NL-02-107, ASME Section XI, Inservice Inspection (ISI) Program Relief Request No. 60 + (ASME Section XI, Inservice Inspection (ISI) Program Relief Request No. 60)
- ML040220680 + (ASME Section XI, Inservice Inspection (ISI) Summary Report for the Fifth Cycle of Operation)
- ML040340247 + (ASME Section XI, Inservice Inspection (ISI) Program, Withdrawal of Request for Relief 3-ISI-13)
- ML040160647 + (ASME Section XI, Inservice Inspection (ISI) Program, Withdrawal of Request for Relief 3-ISI-13)
- NL-03-179, ASME Section XI, Inservice Inspection (ISI) Program Relief Request No. 69 + (ASME Section XI, Inservice Inspection (ISI) Program Relief Request No. 69)
- ML040650355 + (ASME Section XI, Inservice Inspection (ISI) Program, Request to Use Subsequent Edition and Addenda of ASME Section XI for Qualification of Alternative VT-2 Examination Personnel)
- ML062060439 + (ASME Section XI, Inservice Inspection Program - First Ten-Year Inspection Interval, Reactor Pressure Vessel Longitudinal Shell Weld Examinations, Request for Relief 1-ISI-21)
- ML020420257 + (ASME Section XI, Inservice Inspection Program, Revision to Request for Relief 3-ISI-11)
- ML082240529 + (ASME Section XI, Inservice Inspection Program for the Third Ten-Year Inspection Interval - Request for Relief 3-ISI-23 - Response to NRC Request for Additional Information (RAI))
- ML030550559 + (ASME Section XI, Inservice Inspection program-Relief Request RR-IWE9 for Containment Testing)
- L-2013-112, ASME Section XI, Inservice Inspection, Relief Requests No. 11 Alternative Through-Wall Sizing Requirements for Implementation of Appendix Viii, Supplement 10 + (ASME Section XI, Inservice Inspection, Relief Requests No. 11 Alternative Through-Wall Sizing Requirements for Implementation of Appendix Viii, Supplement 10)
- ML15190A330 + (ASME Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owners Activity Report for Cycle 18 Operation)
- ML022540528 + (ASME Section XI, Inservice Testing Program for Third Ten-Year Interval)
- ML20148G614 + (ASME Section XI, Revised Pump & Valve Test Program)
- ML16021A066 + (ASME Section XI, Second 10-Year Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 13 Operation)
- ML20219A150 + (ASME Section Xi_Division 2 Rim Response Letter)
- ML042940289 + (ASME Section Xl Inservice Inspection Program Partial Examination Relief Request)
- ML11270A122 + (ASME Section Xl Inservice Inspection Program Relief Request N2-I3-PRT-002 - Limited Coverage Examinations Performed in the Third Ten-Year Inspection Interval)
- ML060930300 + (ASME Section Xl Inservice Inspection Program Relief Request NDE-SBR)
- DCL-05-152, ASME Section Xl Inservice Inspection Program Relief Request NDE-SLH + (ASME Section Xl Inservice Inspection Program Relief Request NDE-SLH)
- L-2004-164, ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds + (ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds)
- ML25091A269 + (ASME Viii Interpretation Response)
- ML23004A020 + (ASME XI Requirements for Insulation Removal)
- ML25134A250 + (ASME e-mail Response to Invitation to Consult on Section 106 of the National Historic Preservation Act Vallecitos Boilin)
- ML14056A268 + (ASME, Section XI Code, Inservice Inspection Program for Unit I Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval, and Unit 3 Third Ten-Year Inspection Interval, Request for Relief ISI-44)
- ML24150A112 + (ASME_Presentation_on_Performance-Based_Engineering)
- ML16160A094 + (ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004))
- ML16160A095 + (ASP ANALYSIS-REJECT- Callaway Unit 1 Auxiliary Feedwater Control Valves in Motor Driven Pump Train Inoperable Due to Faulty Electric Positioner Cards (LER 483-2015-003 and 483-2015-004))
- ML16165A280 + (ASP Analysis - Reject - Diablo Canyon Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld (LER 275/2015-001))
- ML16237A427 + (ASP Analysis - Reject - Peach Bottom HPCI System Inoperable for 17 Hours Due to Flow Controller Failure - LER 278-2015-001)
- ML16138A336 + (ASP Analysis - Reject Perry Nuclear Power Plant, Unit 1 (440-2014-004))
- ML16138A334 + (ASP Analysis - Reject Perry Nuclear Power Plant, Unit 1 (440-2014-005))
- ML16266A230 + (ASP Analysis Reject - Calvert Cliffs, Unit 2 Automatic Reactor Trip Due to Loss of Offsite Power to Safety Related Buses (LER-318-2015-002))
- ML17109A455 + (ASP Analysis Reject- Brunswick Steam Electric Plant Units 1 and 2, Emergency Diesel Generator 3 Inoperable Due to Failure to Auto-Start (LER 325-2016-002))
- ML16349A563 + (ASP Analysis Reject-FitzPatrick, Frazil Ice Leads to Manual Scram with Subsequent Loss of Non-Vital Buses Due to Fast Transfer Failure (LER-333-2016-001))
- ML17005A527 + (ASP Analysis Reject-Pilgrim-Online Maintenance Configuration Could Result in De-energized Electrical Buses During a Postulated Transient (LER-393-2016-002-01))
- ML16145A114 + (ASP Analysis- Reject- Browns Ferry Nuclear Plant, Unit 3, High Pressure Coolant Injection and Reactor Core Isolation Cooling Inoperable Due to No Suction Source Aligned (LER 296-2015-001))
- ML17011A202 + (ASP Analysis-Reject-Farley TDAFW Pump Design Issue Resulted in a Degraded Condition in Both Unites(Ler 348-2015-005))
- ML16344A443 + (ASP Analysis-Reject-Final Susquehanna-HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient (LER 388-2016-005))
- ML16347A325 + (ASP Analysis-Reject-South Texas Manual Reactor Trip and Valid Auxiliary Feedwater System Actuation-LER 498-2015-001)
- ML17349A967 + (ASP Efficiency Review Memo)
- ML063170256 + (ASP Final Precursor Analysis - Fort Calhoun Nuclear Station)
- ML063180121 + (ASP Final Precursor Analysis - Indian Point Generating Plant, Unit 2)
- ML063170280 + (ASP Final Precursor Analysis - Kewaunee Power Station)
- ML063170289 + (ASP Final Precursor Analysis - Millstone 3)
- ML063170266 + (ASP Final Precursor Analysis - Watts Bar Unit 1)
- ML20049G017 + (ASP Program 2019 Annual Report)
- ML20321A317 + (ASP Program Presentation-23rd Psaea Meeting)
- ML20049G020 + (ASP Program Summary Description (Revision 1))
- ML21067A520 + (ASP Report Transmittal Letter)
- ML16138A335 + (ASP Screening Analysis - Reject Fermi Unit 2 (341-15-002))