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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
- ML18036A475 +
- ML18036A474 +
- ML18036A473 +
- Information Notice 1991-79, Deficiencies in the Procedures for Installing Thermo-Lag Fire Barrier Materials +
- ML18153C839 +
- ML20086N228 +
- ML20086M546 +
- ML20086M388 +
- ML20086M373 +
- ML20086M302 +
- ML20086L820 +
- ML20086L724 +
- ML20086L502 +
- ML20086L283 +
- ML20086L259 +
- ML20086L264 +
- NRC-91-0154, Forwards Rev 17 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld +
- ML20086K389 +
- ML20086K214 +
- ML20086K175 +
- ML20086J820 +
- ML20086J787 +
- ML20086J541 +
- ML20086J052 +
- ML20086J001 +
- ML20086H968 +
- ML20086H946 +
- ML20086H941 +
- ML20091H046 +
- ML20091G672 +
- ML20091G359 +
- ML20126L226 +
- TAC:M77946 +
- TAC:M73648 +
- ET-NRC-91-3642, Requests That Encl Rept NSD-TAP-1131, Response to NRC Questions on Steam Generator Operating Cycle Evaluation for North Anna 1, Be Withheld (Ref 10CFR2.790) +
- NLS9100783, Notifies of Schedule Extension for Completing Upgrades to Safety Parameter Display Sys (Spds),Per Response to Generic Ltr 89-06.Requests Addl 6 Months to Complete Two Remaining SPDS Upgrades +
- TAC:M72166 +
- SNRC-1874, Forwards Response to Request for Addl Info During 911126-27 Telcons Re Decommissioning Plan.Jib Cranes Will Be Installed in Reactor Bldg to Facilitate Matl Handling During Decommissioning,Per NUREG-0612 +
- BECO-91-150, Revised Proposed Tech Spec Re Auxiliary Electrical Sys +
- 2CAN129104, Forwards Arkansas Nuclear One,Unit 2 Simulator Performance Testing Rept. New Malfunctions Incorporated Into Simulator During Past 4 Yrs +
- PY-CEI-NRR-1418, Suppls 910628 Submittal of Form 474, Simulation Facility Certification, Including Supporting Documentation to Inform NRC That on 911111 Subj Facility Declared Ready for Training, Per Completion of Initial Performance Testing +
- PY-CEI-NRR-1417, Suppls 900717 & 1221 Responses to NRC Bulletin 90-001. Potential Loss of Fill-Oil in Rosemount Transmitters +
- 05000301/LER-1991-005-02, :on 911111,discovered Both High Head saftey- Injection Pump Breakers Were Racked In,Making Both Pumps Cognitive Errror.Review Conducted +
- 05000278/LER-1991-017-02, :on 910924,Automatic Depressurization Sys Discovered Inoperable Due to Components Being Unqualified. Caused by MSRV Thermal Insulation Being Improperly Installed.Subj Insulation Properly Reinstalled +
- 05000336/LER-1991-012-01, :on 911106,8-inch Diameter Pipe Ruptured in Reheater Drain Tank to High Pressure Feedwater Heater Pipe, Resulting in Manual Reactor Trip.Caused by Erosion/Corrosion in Elbow.Ruptured Pipe Replaced +
- 05000301/LER-1991-005-01, :on 911111,determined That Both Safety Injection Pump Breakers Racked in W/Rcs Temperature Less than 270 F.Caused by Procedural Inadequacy.Operator Aids Will Be Installed in Vicinity of Subj Breakers +
- 05000373/LER-1991-015-03, :on 911107,determined That Certain ESF Bus Under Voltage Relay Contacts Were Not Functionally Tested. Caused by Inadequate Testing Procedures.Undervoltage Trip Paths Tested & Test Procedures Will Be Revised +
- 05000285/LER-1991-024, :on 911106,ventilation Isolation Actuation Signal Received When Electrician Removed Wrong Fuse Block from Control Panel.Caused by Personnel Error.Standing Order Revised Re Pulling Fuses or Lifting Leads +
- 05000362/LER-1991-007-02, :on 911107,fuel Handling Bldg Train a Spuriously Actuated as Radiation Monitor 3RI-7822 Returned to Svc.Caused by Intermittent Failure of Internal to Normal/ Bypass Switch.Handswitch Replaced +
- 05000334/LER-1991-029, :on 911106,AFW Pump Actuated Due to low-level Steam Generator Level.Caused by Lack of Secondary Flow to Steam Generators.Steam Generator Levels Stabilized & AFW Pump Secured +