05000267/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl
NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904
RBG-35756, Provides Util Response to Generic Ltr 91-06, Resolution of Generic Issue A-30,Adequacy of Safety-Related DC Power Supplies
05000445/LER-1999-003-01, :on 990519,discovered Battery Surveillances Were Not Performed with Proper Periodicity as Required by Ts.Caused by Misinterpretation of Sr.Resistance Readings Taken,Noed Requested & LAR Requested.With
05000267/LER-1983-010-03, /03L-0:on 830302,during Release of Radioactive Liquid Effluent from Reactor Bldg Sump,Overflow from Liquid Waste Sump Drained Into Reactor Bldg Sump.Caused by Personnel Error.Release Terminated
05000267/LER-1982-004-01, /01T-0:on 820202,inadvertent Radioactive Liquid Waste Release Occurred from Receiver a During Plant Shutdown for Design Mods to Circulator Auxiliary Sys.Caused by Improper Valve Lineup.Event Reviewed W/Operators
05000267/LER-1982-004, Forwards LER 82-004/01T-0.Detailed Event Analysis Encl
05000267/LER-1982-041, Forwards LER 82-041/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-034-03, /03L-0:on 810504,equipment Necessary to Terminate Release from Liquid Waste Sys & Reactor Sump Found Not Operating Properly.Caused by Plugged Sense Lines on Flow Element Associated W/Control Valve
05000267/LER-1981-013, Forwards LER 81-013/01T-0.Detailed Event Analysis Submitted
05000267/LER-1980-067-01, /01T-0:on 801107,tritium Concentration Exceeded Limit Specified in LC04.8.24.8.2(a).Caused by Inadequate Deviation 80-445 to Surveillance Procedure SR 5.8.2bc-M. Procedure & Design Changes Under Investigation
HNP-94-098, Responds to NRC Re Violations Noted in Insp Rept 50-400/94-22.Corrective Actions:Revised Plant Administrative Procedure AP-002, Plant Conduct of Operations, to Include Section Entitled, Control of Designated Vehicles
GO2-90-036, Application for Amend to License NPF-21,revising Battery Load Profiles in Surveillance Requirement 4.8.2.1.d.2 to Reflect Results of Recent Reviews of Battery Capabilities
GO2-90-070, Application for Amend to License NPF-21,revising Tech Spec 3.8.2.1 to Reflect Plan to Add Addl Load to Battery During Spring 1990 Refueling Outage
GO2-92-200, Forwards Amend 45 to FSAR Section Fire Protection Evaluation
05000267/LER-1981-013-01, /01T-0:on 810203,following Liquid Waste Release 429,tritium Concentration Exceeded Tech Spec.Caused by Sys Design Inadequacy W/Oil Separator on Liquid Waste Discharge Line.Bypass Installed Around Oil Separator