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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
- FOIA/PA-2008-0016 +
- IR 05000397/2007403 +
- Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment +
- ML072700254 +
- ML072540597 +
- ML072050488 +
- ML072610107 +
- TAC:MD4590 +
- ML072920214 +
- ML072600112 +
- ML073090199 +
- ML072400092 +
- ML072920216 +
- ML072920196 +
- L-07-129, Discharge Monitoring Report (NPDES) Permit No. PA0025615 +
- NL-07-074, Request for Extension of Completion Date for Corrective Actions and Modifications Required by GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +
- BVY 07-066, License Renewal Application, Amendment 31 +
- ML072620352 +
- ML072620177 +
- L-PI-07-068, Comments on Safety Evaluation and License Amendment to Incorporate Large-Break Loss-of-Coolant Accident (LBLOCA) Analysis Using ASTRUM +
- L-MT-07-046, License Amendment Request: Application for Technical Specification Change TSTF-477, Add Action for Two Inoperable Control Room Air Conditioning Subsystems to the Technical Specifications Using the Consolidated Line Item Improvement Proce +
- RS-07-128, Additional Information Supporting Second Ten-Year Interval Inservice Inspection Relief Requests +
- ML072610565 +
- ML072600694 +
- ML072600312 +
- NL-07-1760, J. M. Farley, Units 1 and 2 - Relief Request Q1/2B13-RR-V-2, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) +
- Press Release-II-07-045, - NRC Sets Public Meeting with Farley on Sept. 20 in Dothan to Discuss Inspection of Cooling Water System Breaker Failures +
- ML072550030 +
- ML072530972 +
- ML072490602 +
- ML072430034 +
- TSTF-07-28, Comment (1) of the Technical Specification Task Force Response on August 16, 2007 Federal Register Notice, Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement to Revise Control Rod Notch +
- 05000219/LER-2007-001, Automatic Reactor Scram Following Trip of Reactor Feed Pump +
- ML072680835 +