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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
- 05000482/LER-2010-002, Regarding Turbine Trip Function of Reactor Trip P-4 Interlock Defeated During Entry Into and in Mode 3 +
- ML17010A361 +
- ML15132A569 +
- ML11188A108 +
- CNS-16-015, Technical Specification Bases Changes +
- ML16049A495 +
- IR 05000348/2015301 +
- ML12299A229 +
- ML16021A501 +
- ML15356A365 +
- CNS-15-098, Technical Specification Bases Changes +
- ML15337A271 +
- ML15223A945 +
- NLS2105025, 10 CFR 50.55a Requests for Fifth Ten-Year Inservice Inspection Interval +
- ML15140A277 +
- ML15140A126 +
- ML15022A653 +
- ML14363A499 +
- NL-14-1385, Basis for Proposed Changes. Part 1 of 2 +
- ML14242A021 +
- ML14240A660 +
- L-14-206, License Renewal Application Amendment No. 50 - Annual Update +
- ML100550501 +
- ML13004A051 +
- ML12356A448 +
- ML12340A518 +
- ML12299A182 +
- ML12297A152 +
- ML12297A084 +
- ML11215A059 +
- CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation +
- ML12251A359 +
- ML120030235 +
- ML120720212 +
- ML12083A123 +
- ML12080A216 +
- ML11363A038 +
- ML110550846 +
- ML11311A162 +
- ML102571779 +
- ML110871250 +
- ML103300242 +
- NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change +
- ML16132A400 +
- NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases +
- NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 6 Through Chapter 7 +
- NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications +
- RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors +
- RS-14-338, Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Appendix C - Turbine Missile Study +
- NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9 +