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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
- IR 05000298/1999012 +
- Press Release-II-99-051, NRC Region II Issues Mid-Cycle Plant Performance Review Results +
- Press Release-99-225, NRC to Hold Meetin in Rockville, Maryland, on Control of Sold Materials from Licensed Facilities +
- ML18152B357 +
- ML20112F420 +
- NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl +
- ML20217P512 +
- ML20217P355 +
- NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed +
- TAC:MA1769 +
- ML20217N586 +
- ML20217N461 +
- ML20217N193 +
- ML20217M893 +
- ML20217M757 +
- ML20217M679 +
- ML20217M671 +
- ML20217L717 +
- ML20217K955 +
- ML20217J987 +
- ML20217J961 +
- PNO-I-99-048, on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H +
- PNO-IV-99-046, on 991020,State of Wa Notified NRC Operations Ctr by e-mail of Transportation Event Involving Shipment of Poly Liners Originally Used to Contain Condensate Resin from Nuclear Power Plants.Resin Hold Fission & Activation +
- PLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl +
- ML23018A116 +
- TXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span +
- ML20217M999 +
- 05000424/LER-1999-003-02, :on 990922,CR Door Painting Resulted in Loss of Positive Pressure Boundary.Caused by Inadequate pre-job Briefing.Doors Were Closed Upon Discovery by CR Personnel. with +
- 05000317/LER-1999-006, :on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With +
- ML20217N219 +
- ML20217K882 +
- ML20217N686 +
- ML20217J837 +
- ML20217N501 +