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
- PLA-4428, Forwards Application for Amends to Licenses NPF-14 & NPF-22, Revising TSs Re HPCI Pump Automatic Transfer to Suppression Pool Logic Elimination +
- ML17158B557 +
- ML17158B558 +
- ML17158B556 +
- ML17264A408 +
- ML17264A407 +
- ML17264A406 +
- ML17333A385 +
- ML17333A384 +
- ML18012A183 +
- ML18012A182 +
- ML17353A609 +
- ML17353A607 +
- ML070440477 +
- ML18101B295 +
- ML18151A187 +
- ML20101L929 +
- ML20101G870 +
- 05000254/LER-1996-003, Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure +
- ML20101F702 +
- ML20101F562 +
- ML20101F428 +
- ML20101F418 +
- ML20101F400 +
- ML20101F389 +
- ML20101F298 +
- ML20117C829 +
- ML20137S077 +
- ML20134B683 +
- ML20133N541 +
- ML20133N607 +
- ML20133F051 +
- ML20129F782 +
- ML20129F770 +
- ML20128H733 +
- ML20128H682 +
- ML20149L639 +
- ML20149L585 +
- ML20149D969 +
- TAC:M93822 +
- NSD-NRC-96-4664, Forwards Proprietary Rev 0 to WCAP-14601, AP600 Accident Analyses - Evaluation Models. Proprietary Rept Withheld (Ref 10CFR2.790) +
- 3F0396-18, Retracts 10CFR50.72 Reportable Event 29998 Re Unacceptable as-found Local Leak Rate Testing Results of Reactor Bldg Purge Inlet Containment Isolation Valves.Addl Data Determined Actual Containment Integrity Maintained +
- ST-HL-AE-5322, Responds to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Reactor Coolant Sys +
- PY-CEI-NRR-2038, Forwards Rev 3 to PDB-F0001, COLR for Perry Nuclear Power Plant Unit 1,Cycle 6 (Reload 5) & Rev 0 to J11-02581SRLR, Supplemental Reload Licensing Rept for Perry Nuclear Power Plant Unit 1,Reload 5,Cycle 6 +
- ML20266F929 +
- 05000254/LER-1996-002-04, :on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans +
- 05000424/LER-1996-001-02, :on 960220,pipe Fatigue Leads to Nuclear Svc Cooling Water Inoperability.Caused by Design That Allows Fatigue Cracks to Develop in Discharge Piping.Indications/ Cracks Repaired +
- 05000324/LER-1996-002-02, :on 960306,SRVs Tested at Wyle Lab Exceeded TS Setpoint Limits Due to Setpoint Drift.Caused by Oxygen Induced Pilot disc-to-seat Bonding.Srv Pilot Valve Assemblies Replaced +
- ML20101E178 +
- ML20101E185 +