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David Kern
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Engineering Region 1 Branch 2 false
Engineering Region 1 Branch 2 true
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NRC Region 1
David Kern# QUERY59c3810780856e029cd7dfa108afdbf5
Press Release-I-10-045, NRC Assigns New Resident Inspector to Three Mile Island Nuclear Power Plant
Press Release-I-03-076, New NRC Resident Inspector Assigned to Three Mile Island Nuclear Plant
Press Release-I-03-067, NRC Assigns New Senior Resident Inspector to Beaver Valley
PNO-I-97-077, on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown
PNO-I-98-002, on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.3
PNO-I-97-017, on 970319,Units 1 & 2 Experienced Dual Unit Reactor Trip from Full Power Due to Electrical Fault Protection Signal from 345 Kv Bus in Onsite Switchyard. Signal Tripped Both Main Generators
L-97-056, Submits Special Rept Documenting Results of ISI of SG Tubes, Performed During Unit 1 Twelfth Refueling Outage on 971026. Number of Tubes Inspected & Breakdown of Tubes Removed from Svc for Each SG Documented in Table 1
05000334/LER-1997-029, :on 970907,discovery of de-energized Chart Recorder Leads to Missed RWST Level Check Surveillance. Caused by Operator error.Re-energized Level Recorder & Performed RWST Level Channel Operability Check
05000334/LER-1997-017, :on 970701,ESFA of P-12 Interlock Occurred Due to Decreasing Reactor Water Temperature.Caused by Human Performance Problems.Provided Training for All Planners
05000412/LER-1997-001-01, :on 970106,reactor Trip Occurred Due to Main Transformer Ground Protection.Caused by Inadequate Design Implementation.Procedure 10M-35.3C & Elementary Diagram Was Revised
05000334/LER-1997-024, :on 970805,TS 3.0.3 Was Entered as Result of Failure of RWST Level Transmitter.Caused by Crack in Ferrite Block for Level Transmitter LT-QS-100B.Replaced Transmitter W/Foxboro Model 827DF-IS1SHSA1
05000334/LER-1997-032, :on 970927,automatic Start of EDG Occurred During Bus Transfer from Unit to Sys Station Transformer. Caused by Conservative Setpoints for Starting EDGs at Unit 1.Restored CR Ventilation
05000334/LER-1997-028, :on 970825,SFP Crane Interlocks & Physical Stops Were Not Tested Prior to Use IAW Ts.Caused by Procedures,Program/Process/Equipment Labeling & Training/ Qualification.Performed Surveillance Test
05000334/LER-1997-027, :on 970817,surveillance of Refueling Water Storage Tank Boron Concentration Was Missed.Caused by Inattention to Detail & Lack of Self Checking by Daylight Chemistry Specialist.Counseled Personnel
05000334/LER-1997-026, :on 970814,CR Ventilation Isolation Dampers & Containment Isolation Valves Did Not Meet TS ESF Response Time Srs.Caused by Inadequate Surveillance Test Procedures. Reviewed Surveillance Test Data
05000412/LER-1997-005-01, :on 971015,conditions Prohibited by TS During Routine 4.16kV & 480 Volt Emergency Bus Surveillance Testing,Was Determined.Caused by Inadequate Design.Testing Performed Using Other Existing Procedures
05000334/LER-1997-034, :on 971008,identified That Rhrs TS Requirements Were Not Satisfied During Refueling Cavity Draining.Caused by Inadequate Procedures.Revised Procedure 1OM-20.4.E, Draining Refueling Cavity, to Satisfy TS
05000334/LER-1997-020, :on 970724,identified Pressure Switch Contact, Installed in Control Circuit,Had Unqualified Level Category. Caused by Deficiency in Original Design of Ventilation Sys. Installed Qualified Replacement Switches
05000412/LER-1997-007-01, :on 971205,routine Surveillance Testing of Pr Neutron Flux High Positive Rate RT Function Was Inadequate. Caused by Lack of Awareness During Procedural Development to Ensure Adequate Overlap.Procedure Revised
05000412/LER-1997-006-01, :on 971201,TS Requirements for 4.16 Kv Bus Undervoltage Trip Feeder Breaker Function ESF Response Time Were Not Met.Caused by Inadequate Relay Calibr Procedures. Recalibrated Time Delays
05000334/LER-1997-037, :on 971120,inadequate Ssps Automatic Logic Functions Testing Noted.Caused by Procedural Deficiencies. Revised Applicable Procedures & Completed Addl Surveillance Testing to Adequately Verify Two Functions
05000334/LER-1997-036, :on 971113,inadequate Channel Check for Meteorological Monitoring Instrumentation Was Noted.Caused by Inadequate Change Mgt.Hp Was Requested to Perform Channel Checks & Rept Results to CR
05000334/LER-1997-018, :on 970705,potential for Spurious Seismically Induced FPS Sys Activation Affecting EDG Was Noted.Caused by Deficiency in Original Design.Established Fire Watch
05000334/LER-1997-015, :on 970501,voluntary Entry Was Proceduralized Into TS 3.0.3 by Allowing Bypass of Source Range Channels Input to High Flux Trip.Caused by Misinterpretation of TS 3.3.1.1,Table 3.3-1,Item 6.Changed Procedure
05000334/LER-1997-006, :on 970322,failure to Test Solid State Protection Sys Logic IAW TS Caused by Procedural Deficiencies.Performed Surveillance Testing on 970324
05000334/LER-1997-003, :on 970220,identified RCS Pressure Isolation Valves Were Not Tested.Caused by Operator Error.Affected Valves Declared Inoperable & Verified to Be Closed & Deenergized & Procedures Revised
05000334/LER-1997-002-01, :on 970219,declared EDGs Inoperable Due to Inaccuracies of Watt Meter Instrument Loop.Restored EDG Operability Via Performance of Revised Operating Surveillance Tests
05000412/LER-1996-006-01, :on 961024,determined Potential Control & Protection Sys Interaction in Sgwlcs.Caused by Failure to Adequately Review Steam Flow & SG Level Instrument Design. Implemented Design Mod to Sgwlcs
05000412/LER-1996-010-01, :on 961202,while in Mode 3,maint Crew Completed Leak Repair of Reactor Head Vent Sys Isolation Valve.During Investigation Determined That Leak Sealant Would Prevent Sys from Accomplishing Functions
05000412/LER-1997-002, :on 970111,while in Mode 3 at 0% Reactor Power Plant Entered TS 3.0.3 for Cooldown to Mode 5.Caused by Incomplete Construction Contractor Documentation & Lack of Overall Knowledge of Flood Protection by Crew
05000412/LER-1996-005-01, :on 961011,motor Control Ctr Auxiliary Control Relays Failed Due to Thermal Aging.Replaced 203 Active J12 Relays
05000412/LER-1997-001, :on 970106,reactor Trip Occurred Due to Main Transformer Ground Protection Relay.Caused by Inadequate Design Implementation.Procedures 2OM-35.3C & 2OM-35.4L Revised
05000334/LER-1996-012, :on 961006,entry Into TS 3.0.3 Occurred Due to Isolation of CR Breathing Air Pressurization Sys.Verified Crebaps Actuation Was Inadvertent & Reset Signal at Approximately 1503 Hours on 961006
05000334/LER-1996-009, :on 960731,containment Penetrations Not Designed Accordance with Design Basis.Caused by Inadequate Design.Unit 1 Penetration Numbers 1,2,4,5,TS 3.6.3.1 Were Entered
05000412/LER-1996-003-01, :on 961213,SLCRS Moisture Separator Heaters 2HVS-CH219A & 2HVS-CH219B Were Not Adequately Tested Due to Inadequate Review of GL 96-01.Review of Applicability to Both Units Was Performed
05000334/LER-1996-013, :on 961130,failure to Perform Gaseous Waste Disposal Sys Oxygen Testing as Required by TSs Discovered. Caused by Operator Error & Inadequate Operating Logs. Oxygen Analyzers Were Restored
05000412/LER-1996-009-01, :on 961220,determined That Missed Surveillance Test of Manual Calculation of Quandrant Power Tilt Ration (QPTR) Occurred.Caused by Inadequate Procedures.Qptr Calculation Performed & Procedures Revised
05000412/LER-1996-008-01, :on 961203,manual Reactor Trip Initiated During Core Physics Testing.Manual Trip Was Initiated as Result of Conservative Management Decision to Place Plant in Safe, Shutdown Condition in Order to Perform Testing
05000412/LER-1996-007-01, :on 961015,CR Ventilation Sys Was Operated in Purge Mode to Ventilate Paint Fumes from Cr,Temporarily Rendering CR Emergency Bottled Air Pressurization Subsystem & Esf,Inoperable.Changed Planning Processes
05000412/LER-1996-004-01, :on 960830,bypass Feedwater Regulating Valve Leakage Leads to Manual Reactor Trip During Shutdown for Refueling.Procedures Revised
05000334/LER-1996-003, :on 960322,ESF actuation-feedwater Isolation Occurred,Due to Steam Generator Water Level Transient. Operating Procedures for Unit 1 Will Be Revised
05000334/LER-1997-011, :on 970509,determined Inadequate Testing Was Performed on Solid State Protection Sys Relays K630A & K630B.Caused by Inadequate Procedure.Subject Relays Tested & Verified Operable & Revised Procedures
05000334/LER-1997-022, :on 970730,ESFA of P-12 Interlock Occurred Due to Decreased Reactor Water Temp.Caused by Operator Unfamiliarity W/Level Controller Response in All Situations. Controller Windup Will Be Demonstrated
05000334/LER-1997-023, :on 970801,determined Two Analog Rod Position Indicators (Arpi) Channels Inoperable.Caused by Calibr Drift of Arpi Sys.Will Complete Mod to Upgrade Arpi Sys During Upcoming Unit 1 Refueling Outage
PNO-I-97-020, on 970407,Allegheny Power Sys Inc & Dqe Inc, Parent Co of Duquesne Light Co,Announced Billion Dollar Agreement to Merge Companies.Merger Unanimously Approved by Both Companies Boards of Directors
PNO-I-97-040, on 970627,Unit 1 RPS Trip Functions Did Not Meet Design Requirements & Were Inoperable.Licensee Intends to Install Design Change to Resolve IEEE-279 Postulated Failure Concerns.Operators Began TS Required Shutdown
PNO-I-97-001, on 970106,unit 2 Experienced Reactor Trip from 98% Power Due to Turbine Trip.All Control Rods Inserted Completely.Auxiliary Feedwater Sys Started on Low SG Water Level Signal as Expected.Plant Remains Stable in Mode 3
PNO-I-99-048, on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H
PNO-I-99-036, on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action
PNO-I-99-033, on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault