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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
- ML20077J113 + (ML20077J113)
- ML20077J120 + (ML20077J120)
- ML20077J121 + (ML20077J121)
- ML20077J122 + (ML20077J122)
- NLS2020014, Nebraska Public Power District - Report of Changes to Emergency Plan Implementing Procedure Cooper Nuclear Station, Docket No. 50-298, DPR-46 + (ML20077J126)
- ML20077J131 + (ML20077J131)
- ML20077J135 + (ML20077J135)
- 05000311/LER-1983-035-01, /01T-0:on 830725,flux Map Results Indicated That Tech Spec Limits for Enthalpy Hot Channel Factor Would Be Exceeded During Low Power Operation W/Control Rods Near Insertion Limits.Caused by Improper Modeling + (ML20077J147)
- ML20077J149 + (ML20077J149)
- ML20077J150 + (ML20077J150)
- ML20077J151 + (ML20077J151)
- ML20077J161 + (ML20077J161)
- ML20077J171 + (ML20077J171)
- ML20077J172 + (ML20077J172)
- ML20077J173 + (ML20077J173)
- ML20077J174 + (ML20077J174)
- ML20077J175 + (ML20077J175)
- ML20077J177 + (ML20077J177)
- ML20077J178 + (ML20077J178)
- ML20077J179 + (ML20077J179)
- ML20077J180 + (ML20077J180)
- ML20077J182 + (ML20077J182)
- ML20077J185 + (ML20077J185)
- ML20077J187 + (ML20077J187)
- ML20077J188 + (ML20077J188)
- PLA-7848, Submittal of Unit 1 Cycle 21 Core Operating Limits Report, Revision 1 PLA-7848 + (ML20077J211)
- ML20077J221 + (ML20077J221)
- ML20077J229 + (ML20077J229)
- ML20077J233 + (ML20077J233)
- ML20077J236 + (ML20077J236)
- ML20077J241 + (ML20077J241)
- ML20077J242 + (ML20077J242)
- ML20077J246 + (ML20077J246)
- L-83-438, Forwards Excerpt from Rev F to 830801 Physical Security Plan Re Control of Access to Containment During Shutdown, Per NRC 830630 Request.Excerpt Withheld (Ref 10CFR73.21) + (ML20077J259)
- ML20077J260 + (ML20077J260)
- ML20077J268 + (ML20077J268)
- ML20077J287 + (ML20077J287)
- ML20077J303 + (ML20077J303)
- ML20077J305 + (ML20077J305)
- ML20077J309 + (ML20077J309)
- ML20077J312 + (ML20077J312)
- ML20077J314 + (ML20077J314)
- ML20077J322 + (ML20077J322)
- ML20077J328 + (ML20077J328)
- ML20077J334 + (ML20077J334)
- ML20077J337 + (ML20077J337)
- ML20077J338 + (ML20077J338)
- 05000313/LER-1983-018-03, /03L-0:on 830726,emergency Feedwater Bypass Valve CV-2626 to Steam Generator B Failed to Open from Control Room During Surveillance Test.Caused by Failure of Interlock Contact Preventing Reverse Contactor to Open + (ML20077J339)
- 2CAN088310, Submits Plan for Addressing Criteria Outlined in Generic Ltr 83-10B Re Reactor Coolant Pump Trip.Program to Establish Proper Setpoints Initiated & Justification for Manual Trip Will Be Performed.Final Submittal Expected by Jan 1984 + (ML20077J340)
- 05000285/LER-1983-006-03, /03L-0:on 830714,reactor Protective Sys Channel D Axial Shape Index Internal Tilt Pretrip Setpoint Drifted Out of Spec.Caused by Faulty Bell & Howell Dual Potentiometer Module.Module Replaced + (ML20077J341)
- ML20077J356 + (ML20077J356)