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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
- IA-85-123, Transcript of 840713 Meeting W/Util in Bethesda,Md Re Util 840628 Response to Ofc of Investigations Investigation. Pp 1-44 + (ML20137A456)
- PY-CEI-NRR-2138, Provides Comments on Draft NUREG-1560, Individual Plant Exam Program:Perspectives on Reactor Safety & Plant Performance,Summary Rept + (ML20137A459)
- 05000295/LER-1985-046-03, :on 851206,both Source Range Channels Failed Following Reactor Trip.Caused by Faulty Preamplifier & Bad Detector Tube.Preamplifiers & Detector Well Connectors Replaced + (ML20137A460)
- ML20137A462 + (ML20137A462)
- ML20137A465 + (ML20137A465)
- ML20137A466 + (ML20137A466)
- ML20137A467 + (ML20137A467)
- ML20137A469 + (ML20137A469)
- ML20137A471 + (ML20137A471)
- ML20137A475 + (ML20137A475)
- ML20137A479 + (ML20137A479)
- ML20137A480 + (ML20137A480)
- 05000295/LER-1985-044-03, :on 851206,inadvertent Steam Flow/Feedwater Flow Mismatch W/Low Steam Generator Level Reactor Trip Occurred.Caused by Steam Flow Transmitter 1FT-512 Drifting Out of Tolerance.Transmitter Replaced + (ML20137A482)
- ML20137A483 + (ML20137A483)
- ML20137A485 + (ML20137A485)
- ML20137A487 + (ML20137A487)
- ML20137A489 + (ML20137A489)
- ML20137A490 + (ML20137A490)
- ML20137A491 + (ML20137A491)
- PY-CEI-NRR-2142, Provides 180 Day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety Related Movs + (ML20137A492)
- IR 05000523/2006005 + (ML20137A493)
- 05000454/LER-1985-097-01, :on 851208,inadvertent Safety Injection Occurred.Caused by Personnel Procedural Error.Operators Instructed to Independently Verify Steps of Procedure + (ML20137A494)
- ML20137A495 + (ML20137A495)
- ML20137A496 + (ML20137A496)
- ML20137A498 + (ML20137A498)
- ML20137A500 + (ML20137A500)
- 05000364/LER-1985-011-01, :on 850717,reactor Trip Occurred Due to Low Steam Generator Level.Caused by Apparent Failure of Feedwater Regulating Valve a to Respond in Manual Control. Valve Exercised & Checked Thoroughly + (ML20137A501)
- ML20137A502 + (ML20137A502)
- ML20137A506 + (ML20137A506)
- ML20137A507 + (ML20137A507)
- ML20137A510 + (ML20137A510)
- ML20137A513 + (ML20137A513)
- ML20137A515 + (ML20137A515)
- ML20137A517 + (ML20137A517)
- ML20137A521 + (ML20137A521)
- ML20137A524 + (ML20137A524)
- JPN-97-012, Forwards Response to NRC RAI Re EDG TS Change + (ML20137A527)
- ML20137A528 + (ML20137A528)
- IR 05000522/2006005 + (ML20137A530)
- ML20137A533 + (ML20137A533)
- 05000327/LER-1985-042, :on 851020,containment Ventilation Isolation Occurred.Caused by Electrical Failure of Train B Purge Air Exhaust Radiation Monitor Recirculation Pump Motor.Impeller Pump Vanes & Motor Replaced + (ML20137A534)
- ML20137A535 + (ML20137A535)
- ML20137A541 + (ML20137A541)
- ML20137A543 + (ML20137A543)
- 05000269/LER-1985-013-03, :on 851019,gaseous Waste Disposal Tank 1C Pressurized & Isolated W/O Taking Hydrogen Concentration Sample Per Tech Spec 4.1.3.Caused by Personnel Error.Tank Sampled & Analyzed After Discovery + (ML20137A545)
- ML20137A546 + (ML20137A546)
- JPN-97-011, Provides 180 Day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety Related Movs + (ML20137A547)
- ST-HL-AE-1366, Forwards Revised Responses to Questions 250.01N & 250.07N for Use During NRC Review of Preservice Insp Program. Responses Will Be Incorporated in Next FSAR Amend + (ML20137A550)
- ML20137A551 + (ML20137A551)
- ML20137A556 + (ML20137A556)
- 05000237/LER-1985-040-03, :on 851021,during Review of Mar 1978 SER Re Plant Fire Protection Program,Discrepancies Concerning Mods Described in SER Discovered.Caused by Inadequate Documentation of Commitments in SER + (ML20137A557)