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ML12160A169 +
Information Notice 2005-23, Vibration-Induced Degradation of Butterfly Valves +, ML031060370 +, Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing +, Information Notice 2004-06, Loss of Feedwater Isokinetic Sampling Probes at Dresden Units 2 and 3 +, Information Notice 2004-01, Auxiliary Feedwater Pump Recirculation Line Orifice Fouling - Potential Common Cause Failure +, Information Notice 1991-38, Thermal Stratification in Feedwater System Piping +, Information Notice 1989-80, Potential for Water Hammer, Thermal Strafication, and Steam Binding in High-Pressure Coolant Injection Piping +, Information Notice 1985-76, Recent Water Hammer Events +, Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox +, Information Notice 1979-29, Loss of Nonsafety-Related Reactor Coolant System Instrumentation During Operation +, Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors +, Information Notice 1988-71, Possible Environmental Effect of the Reentry of Cosmos 1900 and Request for Collection of Licensee Radioactivity Measurements Attributed to That Event +, Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems +, Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines +, Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage +, Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources +, Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil +, Information Notice 1993-51, Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps +, Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels +, Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve +, Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device +, Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation +, Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick +, Information Notice 1999-19, Rupture of the Shell Side of a Feedwater Heater at the Point Beach Nuclear Plant +, Information Notice 2002-18, Effect of Adding Gas Into Water Storage Tanks on the Net Positive Suction Head for Pumps +, Information Notice 2001-09, Main Feedwater System Degradation in Safety-Related ASME Code Class 2 Piping Inside the Containment of a Pressurized Water Reactor +, Information Notice 2000-01, Operational Issues Identified in Boiling Water Reactor Trip and Atransient +, NRC Generic Letter 1988-03 +, NRC Generic Letter 1985-13 +, ML12160A169 +...
NRC/RES/DE + and Cozens K +
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September 6, 2012 +
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06:44:33, 12 January 2025 +
Information Notice 94-66 +, Information Notice 80-07 +, Information Notice 90-45 +, Information Notice 99-19 +, Information Notice 06-15 +, Information Notice 87-40 +, Information Notice 91-50 +, Information Notice 84-06 +, Information Notice 05-23 +, Information Notice 01-09 +, Information Notice 88-70 +, Information Notice 85-96 +, Information Notice 02-18 +, Information Notice 93-51 +, Information Notice 95-11 +, Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines +, Information Notice 91-38 +, Information Notice 87-36 +, Information Notice 84-87 +, Information Notice 89-80 +, Information Notice 91-58 +, Information Notice 85-76 +, Information Notice 85-50 +, Information Notice 88-09 +, Information Notice 87-34 +, Information Notice 83-77 +, Information Notice 93-12 +, Information Notice 93-48 +, Information Notice 93-62 +, Information Notice 94-08 +...
NUREG-1409, 4/28/2020, Recording of Summary of Category 3 Meeting Regarding Draft NUREG-1409, Revision 1, Backfitting Guidelines.Pdf +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting + and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
16 +
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September 6, 2012 +
Washington + and Arkansas +
Regulatory Guide (RG) 1.68.1, Revision 2, Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors +
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