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- L-87-135, IAEA RO 87-02:on 870315,informed NRC of Necessity of Removing IAEA Seals on Equipment Hatch & Missile Shields to Perform Insp & Maint Activities.Surveillance of Reactor Maintained by Three Remaining Seals on Reactor Head + (IAEA RO 87-02:on 870315,informed NRC of Necessity of Removing IAEA Seals on Equipment Hatch & Missile Shields to Perform Insp & Maint Activities.Surveillance of Reactor Maintained by Three Remaining Seals on Reactor Head)
- ML20295A681 + (IAEA Radiation Safety 2020 Conference Poster: Phase 3 Materials Inspection Program Revisions)
- ML18061A036 + (IAEA Report of the Operational Safety Review Team (Osart) Mission to the Sequoyah Nuclear Power Plant)
- ML24284A230 + (IAEA SMR Conference - Cybersecurity Presentation Track C.11 301 - Rivera - Presentation)
- ML24320A126 + (IAEA SMR Conference - Cybersecurity Presentation Track C.11 301 Rivera Paper)
- ML20015A389 + (IAEA Safeguards at United States Commercial Nuclear Facilities and Locations)
- ML20011F559 + (IAEA Safety Guide 50-SG-D2,Rev 1, Fire Protection in Nuclear Power Plants)
- ML19321B219 + (IAEA Safety Guide SG-07,Revision 7, Maint of Nuclear Power Plants)
- ML19345E461 + (IAEA Safety Guide SG-S4, Site Selection & Evaluation for Nuclear Power Plants W/Respect to Population Distribution)
- ML19327B119 + (IAEA Safety Targets & PRA:State-of-the-Art & Shortcomings of Pra)
- ML18276A060 + (IAEA Symposium 2018 Implementing a Modified Small Quantities Protocol in the U.S. Caribbean Terriories)
- ML18277A152 + (IAEA Symposium 2019 Hanks)
- ML19182A080 + (IAEA Symposium 2019 Hanks)
- ML18276A065 + (IAEA Symposium Sqp Paper (08.30.18))
- ML19290B982 + (IAEA Technical Assistance in Nuclear Reactor Safety: Philippines, Prepared by Philippine AEC)
- ML012750493 + (IAEA Technical Committee Meeting on the Scope of Regulatory Control of Radiation Exposure)
- ML24327A253 + (IAEA Topics to Consider for the Next International Conference on Computer Security in the Nuclear World-Securing the Future - Presentation)
- ML24278A268 + (IAEA Trip Report: PSA Assessment on Non-reactor Nuclear Facilities)
- ML21349A925 + (IAEA Workshop on Applying Graded Approach to Regulatory Functions for Czech Republic - Jan 2022)
- ML21271A201 + (IAEA Workshop on the Application of Graded Approach on Regulating Nuclear Installations - October 2021)
- ML20219A759 + (IAEA a Harmonized Safety Culture Model)
- ML22250A554 + (IAEA-CN-084 TIC2022 Seymour Presentation)
- ML20010F313 + (IAEA_N71 (OMB Copy))
- ML20010F314 + (IAEA_N72 (OMB Copy))
- ML20010F316 + (IAEA_N74 (OMB Copy))
- ML20010F317 + (IAEA_N75 (OMB Copy))
- ML20010F305 + (IAEA_N76 (OMB Copy))
- ML20010F307 + (IAEA_N77 (OMB Copy))
- ML20010F308 + (IAEA_N91 (OMB Copy))
- ML20010F309 + (IAEA_N92 (OMB Copy))
- ML20010F311 + (IAEA_N93 (OMB Copy))
- ML20010F312 + (IAEA_N94 (OMB Copy))
- ML20062C236 + (IAW Tech Spec LCO 3.7.8.1.,reports Inoperability of Fire Suppression Sys on 781003 at Subj Facil.Caused by Isolation of Yard Loop During Investigation of Underground Leak.Leak Was Determined to Be in Underground Potable Water Line)
- ML20059B967 + (IC HX Equipment Requirements Specification)
- ML20266E445 + (IC-POOL Zusammenstellung Plangrundlage Giovanola Hoehenfixpunkte)
- ML20217C785 + (ICAVP Project)
- ML20079H252 + (ICE-CONDENSER Aerosol Tests)
- ML22031A187 + (ICP/EXT-06-01204, Rev 1, Response to Requests for Additional Information on the Draft Section 3116 Determination for the INL Intec Tff, April 21, 2006)
- ML20205K247 + (IDCOR-85 Program Plan. W/870313 Release Memo)
- ML24270A118 + (IDHEAS Suite for Human Reliability Analysis- an Overview and Recent Developmental Focuses (Presentation Slides for PSAM17/ASRAM2024 Conference))
- ML23010A191 + (IDHEAS-DEP for EPRI HRA Ug Jan 2023)
- ML12235A363 + (IE 05000280-12-301 and 05000281-12-301, on 08/13/2012, Surry Nuclear Power Plant-Operator Licensing-Written Examination Approval)
- ML13010A573 + (IE 05000327/13-301, 05000328/13-301, on 01/04/2013, Sequoyah Nuclear Plant - Notification of Licensed Operator Initial Examination)
- ML20085G571 + (IE Bulletin 73-5, Mfg Defects in BWR Control Rods)
- ML19256E077 + (IE Bulletin 74-10B, Failures in 4-inch Bypass Piping at Dresden-2)
- ML17054D074 + (IE Bulletin 75-01A, Through-Wall Cracks in Core Spray Piping at Dresden-2)
- ML17054D006 + (IE Bulletin 75-04, Cable Fire at Browns Ferry Nuclear Power Plant)
- ML17054D012 + (IE Bulletin 75-04A, Cable Fire at Browns Ferry Nuclear Plant)
- ML17054D015 + (IE Bulletin 75-05, Operability of Category I Hydraulic Shock & Sway Suppressors)
- ML17054D289 + (IE Bulletin 76-01, BWR Isolation Condenser Tube Failure)
- ML17054D020 + (IE Bulletin 76-02, Relay Coil Failures-GE Type Hfa,Hga,Hka & Hma Relays)