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United States Nuclear Regulatory Commission - Protecting People and the Environment

Generic Letters - 1988

File NameDateDescription
gl8802011/23/1988 Individual Plant Examination for Severe Accident Vulnerabilities
gl8801910/28/1988 Use of Deadly Force by Licensee Guards to Prevent Theft of Special Nuclear Material
gl8801810/20/1988 Plant Record Storage on Optical Disks
gl8801710/17/1988Loss of Decay Heat Removal
gl8801610/03/1988 Removal of Cycle-Specific Parameter Limits from Technical Specifications
gl8801509/12/1988Electric Power Systems - Inadequate Control Over Design Process
gl88020s509/08/1995Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - 10 CFR 50.54(f)
gl88020s108/29/1989 Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54
gl8801408/08/1988Instrument Air Supply System Problems Affecting Safety-Related Equipment
gl8801308/08/1988Operator Licensing Examinations
gl88012 PDF Icon08/02/1988 Removal of Fire Protection Requirements from Technical Specification
gl8801107/12/1988 NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations
gl88020s307/06/1990Completion of Containment Performance Improvement Program and Forwarding of Insights for Use in the IPE for SAV
gl8801007/01/1988Purchase of GSA Approved Security Containers
gl88020s406/28/1991Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities
gl8800905/17/1988Pilot Testing of Fundamentals Examination
gl8800805/03/1988 Mail Sent or Delivered to the Office of Nuclear Reactor Regulation
gl8800704/07/1988 Modified Enforcement Policy ... 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety"
gl88020s204/04/1990Accident Management Stratagies for Consideration in the Individual Plant Examination Process
gl8800603/22/1988 Removal of Organization Charts from Technical Specification Administrative Control Requirements
gl8800503/17/1988 Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants
gl8800402/23/1988 Distribution of Gems Irradiated in Research Reactors
gl8800302/17/1988Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps"
gl88001s102/04/1992NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping
gl8800101/25/1988NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
gl8800201/20/1988Integrated Safety Assessment Program II (ISAP II)
Page Last Reviewed/Updated Thursday, March 29, 2012