Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARLR-N980537, Special Rept:On 981006,train B of Reactor Vessel Level Indicating Sys Was Indicating Malfunction.Caused by Loss of Fill in Capillary Sensing Line.Extensive Troubleshooting Was Performed on Sys1998-11-16016 November 1998 Special Rept:On 981006,train B of Reactor Vessel Level Indicating Sys Was Indicating Malfunction.Caused by Loss of Fill in Capillary Sensing Line.Extensive Troubleshooting Was Performed on Sys LR-N980422, Special Rept:On 980816,RMS Channel 1R15 Inoperable for Greater than Seven Days.Cause Is Under Investigation. Replacement of Detector Assembly W/Higher Temperature Rated Detector to Mitigate Effects to Be Completed by 9810191998-08-31031 August 1998 Special Rept:On 980816,RMS Channel 1R15 Inoperable for Greater than Seven Days.Cause Is Under Investigation. Replacement of Detector Assembly W/Higher Temperature Rated Detector to Mitigate Effects to Be Completed by 981019 LR-N970729, Special Rept 97-15,on 971022,2A EDG Declared Inoperable. Caused by Moisture Build Up in Starting Air headers.2A EDG Equipment Inspected Just Subsequent to Aborted Start1997-11-21021 November 1997 Special Rept 97-15,on 971022,2A EDG Declared Inoperable. Caused by Moisture Build Up in Starting Air headers.2A EDG Equipment Inspected Just Subsequent to Aborted Start LR-N970649, Special Rept 97-02:on 970909,isolation of Fire Protection Water to Plant Auxiliary Bldgs & Containments Occurred Due to Closure of Valves 1PF186 & 1PF187.Valves Opened on 970916 & Locally Verified Open by Loss Prevention Personnel1997-09-30030 September 1997 Special Rept 97-02:on 970909,isolation of Fire Protection Water to Plant Auxiliary Bldgs & Containments Occurred Due to Closure of Valves 1PF186 & 1PF187.Valves Opened on 970916 & Locally Verified Open by Loss Prevention Personnel LR-N970418, Special Rept 97-01:on 970615,radiation Monitoring Sys Channel 1R15 Was Inoperable for More than Seven Days.Caused by Configuration of Plant.Required Operational Surveillances Will Be Completed on 2R15 & Channel Restored1997-06-30030 June 1997 Special Rept 97-01:on 970615,radiation Monitoring Sys Channel 1R15 Was Inoperable for More than Seven Days.Caused by Configuration of Plant.Required Operational Surveillances Will Be Completed on 2R15 & Channel Restored ML18101B3051996-03-25025 March 1996 Special Rept:On 960224,valid Failure of 1B EDG Was Identified During Surveillance Testing.Caused by Fatigue Due to Normal Machine Vibration.Replaced Threaded Nipple ML18101B1581995-12-29029 December 1995 Special Rept 95-02:on 951207,valid Failure of 1A EDG Identified Approx 23 & 1/2 H Into 24 H Endurance Surveillance Test.Caused by Lubricating Oil Leak at Threaded Piping Nipple.Threaded Nipple Replaced ML18101B1541995-12-27027 December 1995 Special Rept 95-001:on 951129,valid Failure of 1B EDG Identified During Routine Monthly Surveillance Test.Caused by Malfunction of Woodward Electronic Governor Control Unit. Unit Replaced & 1B EDG Tested Satisfactorily on 951214 ML18101A8061995-07-0303 July 1995 Special Rept:On 950607,identified That 950601 Failure of EDG 1B Potential Common Mode Failure.Util Unable to Determine Cause at Present Time.Ler Will Be Submitted to NRC ML18101A7341995-05-19019 May 1995 Special Rept:On 950506,RMS Declared Inoperable Due to Problems Encountered W/Operation of Victoreen Met Package. Caused by Met Package Inconsistencies.Appropriate Computer Software Corrections Being Researched & Will Be Implemented ML18101A5601995-02-15015 February 1995 Special Rept 95-01:on 950125,shortly After RCP Turned Off to Remove RCP from Svc,Momentary RCS Pressure Transient Occurred & Pressure Peaked 365.5 Psig Due to Pressure Equalization Through 21 RCS Loop.Procedures Will Be Changed ML18100B0421994-04-27027 April 1994 Special Rept 94-2:on 940329,valid Failure of 1A Diesel Generator Occurred.Caused by Buildup on Contacts of Breaker Position Switch 52HL,resulting in Excessive Electrical Resistance.Breaker Position Switch Replaced ML18100A8271994-01-20020 January 1994 Special Rept 94-01:on 940106,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable & Exceeded 7-day Time Frame for Restoring Inoperable Channels to Operable Status on 940113.Monitors Returned to Svc on 940118 ML18100A6211993-09-17017 September 1993 Special Rept 93-4:on 930910,radiation Monitoring Channels 2R45B & 2R45C Inoperable Greater than Seven Days.Caused by Design Deficiency.Corrected by Separating Monitors Reference & Chassis Grounds ML18100A4941993-07-21021 July 1993 Special Rept:On 930707,process Monitor - Noble Gas effluent- Condenser Exhaust Sys Was Removed from Svc Due to Observed Water in Its Sample Line.Sample Line 2R15 Drained & Dried ML18096B3511993-03-23023 March 1993 Special Rept 93-2:on 930310,RMS Channels 2R45B & 2R45C Removed from Svc to Functionally Test Low Flow Differential Pressure.Test Results Showed That Switch Inoperable.Caused by Design Deficiency.Design Mod Being Prepared ML20138H1741993-02-0909 February 1993 RO 25043:on 930208,PSE&G Reported That CRT Associated W/Salem Unit 1 Overhead Annunciator Sys Was Found to Be Inoperable for Approx 23 Minutes ML18096B2571993-02-0404 February 1993 Special Rept 93-1:on 930104,fire Barrier Penetration Seal Impaired to Support Welding of RHR Sys Drain Piping.Barrier Inoperable for More than 7 Days.Cables Removed & Access Hatch Closed to Restore Penetration to Operability ML18096B2331993-01-28028 January 1993 Special Rept 93-1:on 930114,RMS Channels 1R45B & 1R45C Declared Inoperable Upon Annuciation of External Fail Alarm.Cause Not Determined.Upon Completion,Corrective Actions Will Be Taken & Channels Will Return to Svc ML18096B1701992-12-21021 December 1992 Special Rept 92-9:on 921208,chilled Water Supply Could Not Be Restored Following Completion of RMS Channel Functional Surveillance.Caused by Blow Indication Panel Circuit Fuse. New Solenoid Valve Operator Ordered ML18096B1601992-12-18018 December 1992 Special Rept 92-9:on 921112,fire Barrier Impairment Initiated to Support Svc Water Sys Design Changes & Penetration Inoperable for More than 7 Days Through 921119. Penetrations Will Be Sealed Upon Completion of Work ML18096B1171992-11-23023 November 1992 Special Rept 92-8:on 921116,RMS Channels Declared Inoperable & Removed from Svc for More than 7 Days.Caused by Bad Ground Wire Connection on Three Wire Power Cable.Connector Repaired & post-maint Testing Successfully Completed ML18096B0861992-11-0505 November 1992 Special Rept 92-7:on 921008,discovered Door Misaligned & Would Not Close & Latch.Caused by Equipment Failure.Fire Door Declared Functional Upon Completion of Repairs & Testing ML18096B0731992-10-30030 October 1992 Special Rept 92-8:on 920924,fire Barrier Penetrations Impaired to Support Design Change Work.On 921001, Penetrations Exceeded seven-day Limit,Per TS 3.7.11.a. Impaired Penetrations Resealed & Inspected ML18096B0591992-10-23023 October 1992 Special Rept 92-6:on 920924,valid Failure,Involving DG 2B, Occurred During Monthly Surveillance Testing & Exhaust Smoke Observed Rising from Around Turbocharger.Caused by Loose Pipe Fasteners.Fasteners Torqued Appropriately ML18096B0021992-09-24024 September 1992 Special Rept 92-7:on 920826,auxiliary Bldg 100-ft Elevation Corridor Fire Door Found Impaired & Not Returned to Operability within 7 Days.Caused by Broken Internal Hinge Plate Welds.Damaged Door Will Be Replaced ML18096A9151992-08-21021 August 1992 Special Rept 92-6:on 920814,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable for More than 7 Days. Caused by Degradation on Impellers of Two Sample Pumps. Preventive Maint Applicability Review Will Be Performed ML18096A8841992-08-0707 August 1992 Special Rept 92-4-1:on 920430,fire Pump 1 Started Knocking 10 Minutes Into half-hour Run.Caused by sheared-off Follower Guide Pin.On 920514,fire Pump Developed Severe Oil Leak.Caused by Piston Failing to Contact Cylinder Head ML20099C1471992-07-23023 July 1992 Special Rept 92-5:on 920713,radiation Monitoring Sys Channels 2R45B & 2R45C Declared Inoperable & Removed from Svc.Caused by Equipment Failure.Channel Repairs Will Be Tested Upon Completion of Mod ML18096A8261992-07-0909 July 1992 Special Rept 92-5:on 920623,actuation Capability of 78-ft Lower Electrical Penetration CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Maint Work.Sys Returned to Svc on 920702 ML18096A7431992-05-22022 May 1992 Special Rept 92-4:on 920430 & 0514,fire Pumps 1 & 2, Respectively,Inoperable for More than 7 Days.Caused by Sheared Cam Follower Pin & Severe Oil Leak.Fire Protection Sys cross-tie Valve Opened to Provide Backup Protection ML18096A7281992-05-22022 May 1992 Special Rept 92-3,on 920422,discovered That CO2 Sys Was Inoperable.Caused by Maint Work Activities.Upon Completion of Maint Diesel Generator Area CO2 Sys Will Be Returned to Svc ML18096A7351992-05-15015 May 1992 Ro:On 920423,fire Pump 1 Declared Inoperable & Remains Inoperable Due to Broken Crankshaft.Both Fire Suppression Sys Inoperable.On 920515,fire Pump 2 Declared Inoperable Due to Severe Oil Leak.Written Rept to Be Provided in 14 Days ML18096A7021992-05-11011 May 1992 Special Rept 92-2-1:on 920324,0414,15 & 25,fire Barriers Impaired for More than 7 Days to Support Planned Work in SW Sys,Sw Project Support & SW Pipe Replacement.Hourly Fire Watch Will Continue Until All Concerns Resolved ML18096A6501992-04-23023 April 1992 Special Rept 92-2:on 920324,0414 & 15,fire Barriers Impaired for Greater than Seven Days in Support of Planned Work. Hourly Fire Watch Will Continue Until Fire Protection Concerns Associated W/Areas Resolved ML18096A6491992-04-23023 April 1992 Special Rept 92-4:on 920318,two Fire Barrier Penetrations Were Impaired to Support Turbine/Generator Design Change Work for Greater than Seven Days.Caused by Outage Related Activities.Penetrations Were Resealed on 920326 ML18096A6051992-03-26026 March 1992 Special Rept 92-3:on 920302,jacket Water Leakage Developed After Loading DG 2A.On 920305,DG 2A Tripped on Low Lube Oil Pressure.Both Events Caused by Equipment Failure.Tube Connector Compression Fitting Replaced & Diesel Retested ML18096A5891992-03-23023 March 1992 Special Rept 92-2:on 920302 & 21,fire Barriers Impaired for More than 7 Days to Support Design Changes & outage-related Activities.Hourly Fire Watch Established & Fire Penetrations Will Be Sealed ML18096A5671992-03-12012 March 1992 Special Rept 92-1:on 920223,fire Barriers Found Impaired for Greater than Seven Days.Caused by Equipment Failure.Fire Door Will Be Replaced Upon Receipt of New Door ML18096A5101992-02-0606 February 1992 Special Rept 92-1 on 920104,06 & 25,fire Barriers Impaired for Greater than Seven Days in Support of Outage Related Activities Due to Time Required to Complete Work.Hourly Fire Watch Will Continue Until Concerns Re Areas Are Resolved ML18096A4231992-01-0909 January 1992 Special Rept 91-3,on 911210,26 & 27:fire Barriers Found Impaired for Greater than 7 Days.Cause of Occurrence Due to Support Outage Related Activities.Penetrations Will Be Sealed ML18096A4001991-12-23023 December 1991 Special Rept 91-4 Re Valid Failure of Diesel Generator 2B on 911122.Cause Unknown.Surveillance Procedure SP(O)4.8.1.1.2 Performed Satisfactorily ML18096A2301991-08-22022 August 1991 Special Rept 91-02:on 910725,reactor Trip Breaker Failure Occurred Duing Surveillance Testing of Reactor Trip Bypass Breaker.Detailed Investigation Rept Being Prepared & Breaker Being Replaced ML18096A0841991-06-20020 June 1991 Special Rept:On 910523 & 910525,valid Failure Re 2B Diesel Generator Occurred When pre-lube Pump Heater Circuit de-energized & non-valid Failure Occurred on 910525 Re Jacket Water Leak ML18095A8901991-04-17017 April 1991 Special Rept 91-1-1:on 910218,910220,910224 & 910322 Fire Barrier Penetration Seals Impaired for Greater than Seven Days.Cause of Impairment Was to Support Outage Activities. Hourly Fire Watch Will Continue ML18095A8111991-03-20020 March 1991 Special Rept:On 910211,910213 & 910217 Fire Barrier Impairments Greater than Seven Days in Support of Planned Work.Cause of Impairment of Fire Barrier Penetrations Was to Support Outage Related Activities ML18095A7831991-03-0707 March 1991 Special Rept 91-1:on 910211,Elevation 64 & 84 Ft Switchgear Rooms & Elevation 78 Ft Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Design Work.Continuous Fire Watch Established ML18095A7521991-02-20020 February 1991 Special Rept 88-3-28:from 880720-910122,listed Fire Barrier Penetration Seal Impairments Occurred.Cause Not Positively Determined.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18095A6751990-12-26026 December 1990 Special Rept 90-7:on 901210,switchgear Rooms & Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days to Support Design Change Work on 901126. Adequate Precautions Taken to Ensure Design Capability ML18095A7511990-12-0505 December 1990 Revised Special Rept 90-10-1:on 900707,TS Action Statement 3.7.10.3c.a Entered When 64 Ft & 84 Ft Elevation Switchgear Room CO2 Fire Protection Sys Declared Inoperable.Caused by Equipment Failure.Sys Design Drawing Revised 1998-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARLR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With LR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 05000272/LER-1999-006-02, :on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With1999-08-26026 August 1999
- on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With
ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 9) Second Interval,Second Period, First Outage (96RF) LR-N99-0380, Monthly Operating Rept for July 1999 for Salem,Unit 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With LR-N99-0379, Monthly Operating Rept for July 1999 for Salem,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 05000311/LER-1999-008, :on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With1999-07-28028 July 1999
- on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With
ML20210B7371999-07-21021 July 1999 Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively ML18107A4411999-07-0909 July 1999 SER Denying Licensee 980730 & 990222 Requests to Revise TS 3/4.7.6, Control Room Emergency Air Conditioning Sys, & Associated Bases to Change Acceptable Criteria for Control Room Emergency Air Conditioning System 05000311/LER-1999-007, :on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With1999-07-0606 July 1999
- on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With
05000272/LER-1999-005-02, :on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With1999-07-0202 July 1999
- on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With
05000311/LER-1999-006, :on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With1999-07-0101 July 1999
- on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With
05000311/LER-1999-002, :on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With1999-07-0101 July 1999
- on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With
ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF) LR-N99-0324, Monthly Operating Rept for June 1999 for Salem,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept LR-N99-0325, Monthly Operating Rept for June 1999 for Salem,Unit 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With ML18107A3931999-06-23023 June 1999 Safety Evaluation Supporting Licensee Response to GL 95-07 ML18107A4161999-06-23023 June 1999 Safety Evaluation Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000272/LER-1999-004-02, :on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With1999-06-17017 June 1999
- on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With
ML18107A3751999-06-15015 June 1999 Safety Evaluation Accepting Licensee Request for Approval of Proposed Changes to Nuclear Business Unit EP for Hope Creek & Salem Generating Stations,Iaw 10CFR50.54(q) 05000272/LER-1999-003-02, :on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With1999-06-0909 June 1999
- on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With
05000311/LER-1999-005-01, :on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With1999-06-0202 June 1999
- on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With
ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 LR-N99-0278, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With LR-N99-0275, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With ML18107A3111999-05-21021 May 1999 SER Accepting GL-88-20,suppl 4, IPEEEs for Severe Accident Vulnerabilities, for Plant,Units 1 & 2 05000272/LER-1999-002-02, :on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With1999-05-12012 May 1999
- on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With
05000311/LER-1999-004-01, :on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With1999-05-10010 May 1999
- on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With
05000311/LER-1999-003-01, :on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With1999-05-0404 May 1999
- on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With
ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With
ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 LR-N99-0225, Monthly Operating Rept for Apr 1999 for Salem Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 LR-N99-0226, Monthly Operating Rept for Apr 1999 for Salem Unit 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With ML20206B4761999-04-26026 April 1999 Safety Evaluation Supporting Amends 220 & 202 to Licenses DPR-70 & DPR-75,respectively 05000311/LER-1999-001-03, :on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With1999-04-23023 April 1999
- on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With
ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18106B1461999-04-0101 April 1999 SER Accepting Util Proposed Request to Use 1992 Edition of ASME Boiler & Pressure Vessel Code,Section Xi,Article, IWA-4500,for Potential Repair of Feedwater Nozzles for Salem Nuclear Generating Station,Unit 2 LR-N99-0176, Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With LR-N99-0177, Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 05000272/LER-1999-001-02, :on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with
05000272/LER-1999-001-01, :on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with
1999-09-30
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