Search by property
Jump to navigation
Jump to search
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
- ML19325E447 + (ML19325E447)
- ML19325E449 + (ML19325E449)
- ML19325E450 + (ML19325E450)
- ML19325E451 + (ML19325E451)
- ML19325E452 + (ML19325E452)
- ML19325E453 + (ML19325E453)
- ML19325E454 + (ML19325E454)
- ML19325E455 + (ML19325E455)
- ML19325E456 + (ML19325E456)
- ML19325E457 + (ML19325E457)
- W3P89-2125, Responds to 891031 Request for Addl Info Re Revised Tech Spec 3.2.1.9, Boron Dilution. Tech Spec Should Explicitly State That Requirement Does Not Apply in Mode 3 While Shutdown Less than 145 Inches + (ML19325E460)
- ML19325E461 + (ML19325E461)
- ML19325E462 + (ML19325E462)
- W3P89-2100, Responds to NRC Bulletin 88-004 Re Two mini-flow Design Concerns.Concerns Involves Potential for dead-heading of One or More Pumps in safety-related Sys & Whether Installed mini-flow Capacity Adequate for Single Pump in Operation + (ML19325E463)
- W3P89-2109, Forwards Change 2 to Rev 6 to, Pump & Valve Inservice Test Plan. Change Adds Four Valves to Scope of Testing Under Plan.Summary of Changes to Plan Encl + (ML19325E465)
- ML19325E466 + (ML19325E466)
- ML19325E467 + (ML19325E467)
- ML19325E468 + (ML19325E468)
- ML19325E469 + (ML19325E469)
- ML19325E470 + (ML19325E470)
- ML19325E471 + (ML19325E471)
- ML19325E473 + (ML19325E473)
- ML19325E474 + (ML19325E474)
- ML19325E476 + (ML19325E476)
- ML19325E477 + (ML19325E477)
- IR 05000309/1989017 + (ML19325E479)
- ML19325E480 + (ML19325E480)
- ML19325E482 + (ML19325E482)
- ML19325E484 + (ML19325E484)
- ML19325E485 + (ML19325E485)
- ML19325E486 + (ML19325E486)
- PNO-III-89-068, on 891026,radiographer & Assistant Received whole-body Overexposure of 4.9 & 1.02 Mrems,Respectively. Caused by Failure to Lock Device After Each Exposure & to Perform Adequate Radiation Surveys.Event Reenacted + (ML19325E488)
- ML19325E489 + (ML19325E489)
- ML19325E491 + (ML19325E491)
- ML19325E492 + (ML19325E492)
- ML19325E493 + (ML19325E493)
- ML19325E494 + (ML19325E494)
- RBG-31692, Responds to Generic Ltr 88-20 & Suppl 1 Re Individual Plant Exam.Util Has Established in-house Group to Perform Individual Plant Exam & Addl Support Will Be Provided by PRA Consultants + (ML19325E495)
- ML19325E496 + (ML19325E496)
- IR 05000331/1989025 + (ML19325E498)
- ML19325E499 + (ML19325E499)
- NUREG/CR-5432, Forwards Draft NUREG/CR-5432, Scoping Study of Potential Impacts of Inadvertent Fire Suppression Sys Actuations in Commercial Nuclear Power Plants, for Comment + (ML19325E502)
- ML19325E503 + (ML19325E503)
- ML19325E504 + (ML19325E504)
- ML19325E505 + (ML19325E505)
- ML19325E507 + (ML19325E507)
- ML19325E508 + (ML19325E508)
- ML19325E509 + (ML19325E509)
- 3F1089-17, Provides Rev to Util 890722 Schedule Milestones for Addition of Auxiliary Feedwater Pump at Facility Due to Changed Dates for Plant Refuelings & Design Effort for Mod More Complex than Anticipated + (ML19325E512)
- ML19325E515 + (ML19325E515)
- ML19325E517 + (ML19325E517)