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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
- ML23207A059 + (ML23207A059)
- ML23207A073 + (ML23207A073)
- ML23207A074 + (ML23207A074)
- ML23207A076 + (ML23207A076)
- ML23207A110 + (ML23207A110)
- ML23207A111 + (ML23207A111)
- ML23207A112 + (ML23207A112)
- ML23207A114 + (ML23207A114)
- ML23207A115 + (ML23207A115)
- ML23207A119 + (ML23207A119)
- ML23207A121 + (ML23207A121)
- DCL-23-064, Nuclear Material Transaction Report for New Fuel + (ML23207A122)
- CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills + (ML23207A126)
- NL-23-0628, Readiness for Supplemental Inspection EA-22-101 + (ML23207A131)
- NLS2023047, Licensee Guarantees of Payment of Deferred Premiums + (ML23207A140)
- ML23207A151 + (ML23207A151)
- LR-N23-0054, In-Service Inspection Activities + (ML23207A156)
- L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches + (ML23207A157)
- PMNS20230863, Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Relocate Refueling Operations Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual + (ML23207A162)
- PMNS20230867, Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Extend the Diesel Generator Allowed Outage Time from 3 Days to 14 Days at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 + (ML23207A170)
- ML23207A174 + (ML23207A174)
- ML23207A176 + (ML23207A176)
- ML23207A178 + (ML23207A178)
- ML23207A180 + (ML23207A180)
- PMNS20230838, Meeting to Discuss Sections of the National Organization of Test, Research and Training Reactors, Inc. (Trtr) Proposed Guidance on the 50.59 Process for Digital Applications (NEI 23-03) with the U. S. Nuclear Regulatory Commission (NRC) + (ML23207A186)
- ML23207A188 + (ML23207A188)
- ML23207A189 + (ML23207A189)
- ML23207A193 + (ML23207A193)
- ML23207A194 + (ML23207A194)
- ML23207A195 + (ML23207A195)
- ML23207A196 + (ML23207A196)
- ML23207A198 + (ML23207A198)
- ML23207A199 + (ML23207A199)
- ML23207A201 + (ML23207A201)
- ML23207A202 + (ML23207A202)
- STC-23-035, Notification of Proposed Integrated Materials Performance Evaluation Program Schedules for NRC Fiscal Years 2024-2026 + (ML23207A203)
- ML23207A204 + (ML23207A204)
- 05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open + (ML23207A220)
- ML23207A230 + (ML23207A230)
- IR 05000382/2023402 + (ML23207A231)
- IR 05000298/2023402 + (ML23207A242)
- ML23207A248 + (ML23207A248)
- ML23207A249 + (ML23207A249)
- ML23207A252 + (ML23207A252)
- ML23208A002 + (ML23208A002)
- ML23208A009 + (ML23208A009)
- L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump + (ML23208A057)
- RA-23-0150, End of Cycle 28 (M2R28) Inservice Inspection Summary Report + (ML23208A058)
- ML23208A059 + (ML23208A059)
- ML23208A060 + (ML23208A060)
- ML23208A062 + (ML23208A062)