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 Report dateSiteEvent description
05000382/LER-1985-006, Discusses 850220 Inadvertent Containment Spray Actuation & Subsequent Evaluation in Light of Reactor Coolant Pump Seal Degradation (Ref LER-85-006).Insp Shows,Despite Seal Degradation,Vapor Seal Integrity MaintainedWaterford
05000382/LER-1985-057, Forwards LER 85-057-00.Event Analysis & Reporting Group Established to Improve Plant Safety & Reliability & Ensure That Causes of Significant Events Identified & Corrected,As of Sept 1986Waterford
05000382/LER-1986-011, Forwards LER 86-011-01,revised Per Determination That Deviations to App R Requirements for Fire Barriers w/228 Seals Identified to Have Sleeve Type Configuration as Described in LER Not RequiredWaterford
05000382/LER-1990-009Waterford
05000382/LER-1995-002, Forwards LER 95-002-01 Providing Details of Design Change 3448 Installed During Refueling Outage 8 as Result of 950610 Reactor Trip,Partial Loss of Offsite Power & Fire.Revised Info Identified by Vertical Line in right-hand MarWaterford
05000382/LER-1995-005, Forwards Attachment a Inadvertently Omitted from LER 95-005-00 Package Submitted on 951204Waterford
05000382/LER-1996-013, Advises That LER 96-013-00 Cancelled Based on Root Cause Analysis Results Concluding That Facility Did Not Operate in Excess of 100% Licensed Reactor PowerWaterford
05000382/LER-1996-015, Forwards LER 96-015-02 Which Revises Previous Submittal by Deleting Info Re long-term Corrective Action for Event.Info Deleted Has Been Annotated by Vertical Line in right-hand MarginWaterford
05000382/LER-1997-011, Forwards LER 97-011-01,revising Previous Submittal Re Water Level Maintained in Containment Spray Risers That May Have Been Less than Required by Ts.Commitments DiscussedWaterford
05000382/LER-1997-013, Forwards LER 97-013-00,reporting Discovery That Refueling Machines Overload Protection Features Had Not Been Fully Operable & Surveillance Procedure for Testing Lift Capacity of CEA Hoist,DeficientWaterford
05000382/LER-1997-014, Forwards LER 97-014-01 Which Provides Details of Reportable Deficiencies in Testing of Logic Circuits Identified During GL 96-01 Reviews & EvaluationsWaterford
05000382/LER-1997-016, Forwards LER 97-016-01 Which Repts Similar Potential as That Contained in LER 97-016-00,that Existed for SG Differential Pressure Instrumentation Associated W/EfasWaterford
05000382/LER-1997-020, Forwards Results of Util Assessment Re Potential Common Mode Failure of safety-related Static Uninterruptible Power Supply Units,Initially Reported in LER 97-020-00Waterford
05000382/LER-1997-021, Forwards LER 97-021-01,revising Details of Rept Submitted 970711 Re Primary Containment Integrity Having Been Found to Be DegradedWaterford
05000382/LER-1997-023, Forwards LER 97-023-00,which Provides Details of Failure to Perform TS SR 4.8.1.1.2.h.2 within Required Surveillance IntervalWaterford
05000382/LER-1997-027, Forwards LER 97-027-01,providing Updated Info Re Reportable Condition for AccwsWaterford
05000382/LER-1997-028, Forwards LER 97-028-00 Which Provides Details Re Loss of Power to 3A Safety Bus Resulting in Automatic Start of EDG aWaterford
05000382/LER-1997-029, Forwards LER 97-029-00 Which Provides Details on Testing Deficiencies of Relay Contacts in safety-related Logic CircuitsWaterford
05000382/LER-1997-030, Forwards LER 97-030-01,which Documents Condition Wherein Normally Closed Inside & Outside Ci Valves for Containment Atmosphere Release Sys Were Subject to Single Failure Which Could Result in Failure of Isolation Valves to ClosWaterford
05000382/LER-1997-031, Forwards LER 97-031-00,re Inadequate Valve Position Indication in HR Analyzer SysWaterford
05000382/LER-1997-032, Forwards LER 97-032-00,providing Details of Noncompliance W/Plant TS Due to Failure to Meet General Design Criteria 54Waterford
05000382/LER-1997-033, Informs That LER 97-033-00 Did Not Include Proposed Schedule for Providing Reanalysis to Show Compliance,Per Util 980105 Submittal.Completion Date of 980430 ProposedWaterford
05000382/LER-1997-034, Forwards LER 97-034-00 IAW 10CFR50.73(a)(2)(i)(B) Due to Failure to Perform Snubber Functional Test as Required by TSWaterford
05000382/LER-1998-001, Forwards LER 98-001-00,providing Details of TS 3.0.3 Condition Experienced During Plant Malfunction When LCO Section 3.1.2.4 Was Not MetWaterford
05000382/LER-1998-002, Forwards LER 98-002-00 Providing Details of Condition Involving Brief Loss of Command Function in CR in Violation of Administrative TS 6.2.2.Condition Being Reported Per 10CFR50.73(a)(2)(i)(B)Waterford
05000382/LER-1998-003, Forwards LER 98-003-00 Providing Details of Both Hydrogen Analyzers Being Inoperable Due to Undersized Thermal Overloads.Condition Being Reported Per 10CFR50.73(a)(2)(i) (B) & 10CFR50.36(c)(2) Prohibited by TSsWaterford
05000382/LER-1998-004, Forwards LER 98-004-00,providing Details of TS 4.0.3 Condition That Existed W/Ts 4.3.1.1,Table 4.3-1,refueling Interval Channel Functional Test for Core Protection Calculator SysWaterford
05000382/LER-1998-005, Forwards LER 98-005-00,re Details of Missed TS 3.8.4.2 Surveillance Test for Thermal Overloads of Eight motor-operated Valves.Condition Being Reported Pursuant to 10CFR50.73(a)(2)(i)(B)Waterford
05000382/LER-1998-006, Forwards LER 98-006-00 Re Discovery of Feedwater Isolation Valves Being Inoperable in Excess of TS Allowed Outage Time. Condition Being Reported Pursuant to 10CFR50.73(a)(2)(i)(B)Waterford
05000382/LER-1998-008, Forwards LER 98-008-00,re Degraded Condition in Both Trains a & B of Ecw Sys.No New Commitments Made within LtrWaterford
05000382/LER-1998-009, Forwards LER 98-009-00,providing Details of Inadvertent ESF Actuation Which Started CCS Components.Rept Submitted Per, 10CFR50.73(a)(2)(iv)Waterford
05000382/LER-1998-010, Forwards LER 98-010-00,re Potential Overpressurization of Nitrogen Sys Possibly Rendering Multiple Safety Sys InoperableWaterford
05000382/LER-1998-011, Forwards LER 98-011-00,providing Details of Condition Wherein Plant Entered TS 3.0.3 for Having Both Trains of Component Cooling Water Declared Inoperable ConcurrentlyWaterford
05000382/LER-1998-012, Forwards LER 98-012-00,re Details of Condition Which Constituted Violation of TS 3.3.1 Because TS Channel Check Was Not Performed,Per TS Requirement 4.3.1.1Waterford
05000382/LER-1998-014, Forwards LER 98-014-00 for Waterford Steam Electric Station, Unit 3.Rept Provides Details of Manual Reactor Trip,Followed by Actuation of EFW Actuation Sys That Initiated EFW Flow to Both SGsWaterford
05000382/LER-1998-015, Forwards LER 98-015-00,providing Details of Incorrect Installation of T-ring Rubber Seals on CR Normal Outside Air Intake Upstream & Downstream Isolation Valves HVC-101 & HVC-102Waterford
05000382/LER-1998-017, Forwards LER 98-017-00,re Error in Energy Redistribution Factors Used in LOCA Analysis.Condition Was Also Reported to NRC Via Telcon 980803Waterford
05000382/LER-1998-018, Forwards LER 98-018-00 for Waterford Steam Electric Station, Unit 3.Rept Provides Details of Situation in Which TS 3.0.3 Entered,Due to Both Trains of Shield Bldg Ventilation Being Inoperable SimultaneouslyWaterford
05000382/LER-1998-019, Forwards LER 98-019-01,IAW 10CFR50.73(a)(2)(ii). LER 98-019-00,discussed.Refs to Feedwater Valves Have Been Deleted in Revised LERWaterford
05000382/LER-1998-021, Forwards LER 98-021-00,providing Details of Condition in Which Plant Was Operated with B Concentration in One of SITs Potentially Below TS Limits.Reasonable Assurance Exists That Condition Existed Over Period of Time Greater thWaterford
05000382/LER-1999-002, Forwards LER 99-002-00 Re Leaks Discovered on Instrument Nozzles in Rcs.Event Being Reported Per 10CFR50.73(a)(2)(ii) & 10CFR50.73(a)(2)(i)(B)Waterford
05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3Waterford
05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic CircuitsWaterford
05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on AttachedWaterford
05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also EnclWaterford
05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established ImmediatelyWaterford
05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement FormWaterford
05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement FormWaterford
05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement FormWaterford
05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in SubmittalWaterford