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Issue date | Title | |
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Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures | 9 July 1997 | Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
NRC Generic Letter 1992-02 | 6 March 1992 | NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown. |
ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability |
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping | 13 June 1991 | Thermal Stratification in Feedwater System Piping |
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break | 30 June 1989 | Degradation of Containment Isolation Capability by a High-Energy Line Break |
ML18041A187 | 10 February 1989 | LER 89-002-00:on 890111,reactor Protection Sys Automatically Actuated.Caused by Voltage Fluctuation on Vital Bus Which Induced False High Startup Rate Scram Signal.Conditional Precautions Added to Operating procedures.W/890210 Ltr |
IR 05000029/1988009 | 21 June 1988 | Onsite Regular & Backshift Insp Rept 50-029/88-09.Violations Noted.Major Areas Inspected:Previous Insp Findings,Bimonthly Safety Sys Verification,Operational Safety Verification, Radiological Controls & Emergency Exercise |
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 |
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 |
NRC Generic Letter 1987-12 | 9 July 1987 | NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled |
Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System | 2 February 1987 | Miswiring in a Westinghouse Rod Control System |
ML18041A135 | 1 July 1986 | LER 86-004-00:on 860601,heater Drain Tank Level Control Channel Failed & Both Heater Drain Pumps Tripped.Caused by Severe Lightning Storm.Heater Drain Tank Level Control Channel Power Supply replaced.W/860701 Ltr |
Information Notice 1986-53, Improper Installation of Heat Shrinkable Tubing | 26 June 1986 | Improper Installation of Heat Shrinkable Tubing |
NRC Generic Letter 1983-43 | 19 December 1983 | NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications |