Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045H0941993-07-0808 July 1993 Special Rept Spr 930006:on 930609,discovered Mechanical Penetration in fire-rated Barrier Unsealed.Caused by Unique Configuration of Fire Barrier Penetration Located Near Ceiling.Penetrations Visually Inspected ML20024H7261991-05-24024 May 1991 Special Rept Spr 910003:on 910429,electric-driven Fire Pump Removed from Svc for 10.5 Days as Result of Surveillance Testing Which Indicated Pump Wear or Fouling.New Pump Installed,Tested & Declared Operable on 910509 ML20028H2341990-11-0606 November 1990 Special Rept Spr 90-015:on 900925 & 1014,reactor Bldg hi- Range Area Monitor Declared Inoperable.Caused by Contamination on Connector in Circuit.Repairs Scheduled for Next Refueling Outage ML20043F7511990-05-29029 May 1990 Special Rept Spr 90-006:all Tech Spec Reporting Requirements Resulting from Measured Forces Below Current Acceptable Values During Fourth Tendon Surveillance.No Abnormal Degradation of Containment Tendons Occurred.W/O Rept ML20043D3471990-05-16016 May 1990 Special Rept Spr 90-005:on 900416,B Diesel Generator Tripped Due to High Crankcase Pressure.Caused by Level of Lube Oil Being Higher than Normal.Adjustments Made to Procedures ML20043A5791990-05-15015 May 1990 Special Rept Spr 90-004:on 900414,fire/pressure Barrier for Trace 168 in Room Cb 36-11 Removed from Svc to Facilitate Testing.Fire Barrier Restored to Svc on 900421 ML20042E4201990-04-0505 April 1990 Special Rept Spr 90-001:on 900322,main Plant vent,high-range Radiation Monitor Began to Alarm Spuriously,Declared Inoperable & Removed from Svc.Caused by Failed Readout Module.Alarm Repaired & Returned to Svc on 900402 ML19332D6011989-11-16016 November 1989 Special Rept Spr 89-010:on 891020,smoke Detector 6 RB in Reactor Bldg Spuriously Alarmed & Could Not Be Reset from Outside Bldg Due to Restricted Bldg Entry While Unit at 100% Power.Containment Air Temp Monitored Hourly ML19325D5951989-10-17017 October 1989 Special Rept Spr 89-009:on 890927,diesel Fire Pump Remained Inoperable in Excess of 7 Days.Caused by Defective Cooling Water Pump.Replacement of Pump & post-maint Testing Completed ML19325D8791989-10-0606 October 1989 Special Rept Spr 89-008:on 890904,smoke Detector Alarms in Zone Ppp of Reactor Bldg Spuriously Alarmed & Failed to Remain Clear.Damaged Base Assembly of Detector Replaced. Hourly Bldg Temp Reading Taken.Work Request Initiated ML20028B6391982-11-23023 November 1982 Ro:On 821110,during Mode 2 Operation,Radiation Monitor RM-G19C (Main Steam Line C Monitor) Declared Inoperable Due to Erratic Indications.Caused by Moisture Accumulation. Monitor Will Be Changed Prior to 830101 ML20003D6461981-03-23023 March 1981 Ro:Recently,Insufficient Time Noted for Operators to Take Required Actions in Two Boron Dilution Events.Cause Not Stated.Shutdown Margin for Modes 4 & 5 Will Be Changed. Source Range Setpoint Will Be Changed to 2 Times Background ML19276E6581979-02-0707 February 1979 Telcon Rept:Notification of Discrepancies in Radiographic Technique & Potential Relevant Defects in ASME Code Radiography of Class 2 & 3 Pipe Welds Which Had Been Previously Reviewed & Accepted 1993-07-08
[Table view] Category:LER)
MONTHYEARML20045H0941993-07-0808 July 1993 Special Rept Spr 930006:on 930609,discovered Mechanical Penetration in fire-rated Barrier Unsealed.Caused by Unique Configuration of Fire Barrier Penetration Located Near Ceiling.Penetrations Visually Inspected ML20024H7261991-05-24024 May 1991 Special Rept Spr 910003:on 910429,electric-driven Fire Pump Removed from Svc for 10.5 Days as Result of Surveillance Testing Which Indicated Pump Wear or Fouling.New Pump Installed,Tested & Declared Operable on 910509 ML20028H2341990-11-0606 November 1990 Special Rept Spr 90-015:on 900925 & 1014,reactor Bldg hi- Range Area Monitor Declared Inoperable.Caused by Contamination on Connector in Circuit.Repairs Scheduled for Next Refueling Outage ML20043F7511990-05-29029 May 1990 Special Rept Spr 90-006:all Tech Spec Reporting Requirements Resulting from Measured Forces Below Current Acceptable Values During Fourth Tendon Surveillance.No Abnormal Degradation of Containment Tendons Occurred.W/O Rept ML20043D3471990-05-16016 May 1990 Special Rept Spr 90-005:on 900416,B Diesel Generator Tripped Due to High Crankcase Pressure.Caused by Level of Lube Oil Being Higher than Normal.Adjustments Made to Procedures ML20043A5791990-05-15015 May 1990 Special Rept Spr 90-004:on 900414,fire/pressure Barrier for Trace 168 in Room Cb 36-11 Removed from Svc to Facilitate Testing.Fire Barrier Restored to Svc on 900421 ML20042E4201990-04-0505 April 1990 Special Rept Spr 90-001:on 900322,main Plant vent,high-range Radiation Monitor Began to Alarm Spuriously,Declared Inoperable & Removed from Svc.Caused by Failed Readout Module.Alarm Repaired & Returned to Svc on 900402 ML19332D6011989-11-16016 November 1989 Special Rept Spr 89-010:on 891020,smoke Detector 6 RB in Reactor Bldg Spuriously Alarmed & Could Not Be Reset from Outside Bldg Due to Restricted Bldg Entry While Unit at 100% Power.Containment Air Temp Monitored Hourly ML19325D5951989-10-17017 October 1989 Special Rept Spr 89-009:on 890927,diesel Fire Pump Remained Inoperable in Excess of 7 Days.Caused by Defective Cooling Water Pump.Replacement of Pump & post-maint Testing Completed ML19325D8791989-10-0606 October 1989 Special Rept Spr 89-008:on 890904,smoke Detector Alarms in Zone Ppp of Reactor Bldg Spuriously Alarmed & Failed to Remain Clear.Damaged Base Assembly of Detector Replaced. Hourly Bldg Temp Reading Taken.Work Request Initiated ML20028B6391982-11-23023 November 1982 Ro:On 821110,during Mode 2 Operation,Radiation Monitor RM-G19C (Main Steam Line C Monitor) Declared Inoperable Due to Erratic Indications.Caused by Moisture Accumulation. Monitor Will Be Changed Prior to 830101 ML20003D6461981-03-23023 March 1981 Ro:Recently,Insufficient Time Noted for Operators to Take Required Actions in Two Boron Dilution Events.Cause Not Stated.Shutdown Margin for Modes 4 & 5 Will Be Changed. Source Range Setpoint Will Be Changed to 2 Times Background ML19276E6581979-02-0707 February 1979 Telcon Rept:Notification of Discrepancies in Radiographic Technique & Potential Relevant Defects in ASME Code Radiography of Class 2 & 3 Pipe Welds Which Had Been Previously Reviewed & Accepted 1993-07-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D6401999-10-31031 October 1999 Rev 2 to WCAP-15102, VC Summer Unit 1 Heatup & Cooldown Limit Curves for Normal Operation RC-99-0202, Monthly Operating Rept for Sept 1999 for VC Summer Nuclear Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for VC Summer Nuclear Station.With ML20216J4191999-09-24024 September 1999 Part 21 Rept Re 990806 Abb K-Line Breaker Defect After Repair.Vendor Notified of Shunt Trip Wiring Problem & Agreed to Modify Procedure for Refurbishment of Breakers RC-99-0180, Special Rept on 990807,electric Driven Fire Pump XPP0134A Was Declared Inoperable.Caused by Pump Discharge Relief Valve Failing to Open as Normally Expected.Two Temporary Fire Pumps Were Installed to Provide Backup Suppression1999-09-0808 September 1999 Special Rept on 990807,electric Driven Fire Pump XPP0134A Was Declared Inoperable.Caused by Pump Discharge Relief Valve Failing to Open as Normally Expected.Two Temporary Fire Pumps Were Installed to Provide Backup Suppression RC-99-0183, Monthly Operating Rept for Aug 1999 for Virgil C Summer Nuclear Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Virgil C Summer Nuclear Station,Unit 1.With ML20211K6161999-08-31031 August 1999 Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, Dtd Aug 1999 RC-99-0168, Special Rept:On 990804,electric Driven Fire Pump XPP0134A & Diesel Driven Fire Pump XPP0134B,were Removed from Svc to Allow for Plant Mod.Fire Pumps Were Returned to Operable Condition on 990818,after Mod Was Completed1999-08-19019 August 1999 Special Rept:On 990804,electric Driven Fire Pump XPP0134A & Diesel Driven Fire Pump XPP0134B,were Removed from Svc to Allow for Plant Mod.Fire Pumps Were Returned to Operable Condition on 990818,after Mod Was Completed ML20210M7071999-07-31031 July 1999 Rev 1 to VC Summer Nuclear Station COLR for Cycle 12 ML20211C2201999-07-31031 July 1999 Rev 1 to WCAP-15102, VC Summer Unit 1 Heatup & Cooldown Limit Curves for Normal Operation RC-99-0163, Monthly Operating Rept for July 1999 for VC Summer Nuclear Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0137, Monthly Operating Rept for June 1999 for VC Summer Nuclear Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0122, Monthly Operating Rept for May 1999 for VC Summer Nuclear Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for VC Summer Nuclear Station.With ML20206H2971999-05-0505 May 1999 Part 21 Rept Re Common Mode Failure for magne-blast Breakers.Vc Summer Nuclear Station Utilizes These Breakers in Many Applications,Including 7.2-kV EDG Electrical Buses RC-99-0103, Monthly Operating Rept for Apr 1999 for VC Summer Nuclear Station.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for VC Summer Nuclear Station.With ML20206K2421999-04-30030 April 1999 Rev 0 to COLR for Cycle 12 for Summer Nuclear Station RC-99-0087, Part 21 Interim Rept (SSH 99-0001) Re 990218 Failure of Circuit Breaker Located in Cubicle 14 of XSW1DB to Close During Surveillance Testing.Caused by Positive Interlock Angle Was Incorrect.Breaker Was Returned to GE Factory1999-04-15015 April 1999 Part 21 Interim Rept (SSH 99-0001) Re 990218 Failure of Circuit Breaker Located in Cubicle 14 of XSW1DB to Close During Surveillance Testing.Caused by Positive Interlock Angle Was Incorrect.Breaker Was Returned to GE Factory RC-99-0083, Monthly Operating Rept for Mar 1999 for VC Summer Nuclear Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0063, Special Rept:On 990302 & 16,meteorological Site Number One 10 Meter Temp Element Was Declared Inoperable.Caused by Erratic Operation.Cabling & 10 Meter Electrical Connectors Were Replaced1999-03-26026 March 1999 Special Rept:On 990302 & 16,meteorological Site Number One 10 Meter Temp Element Was Declared Inoperable.Caused by Erratic Operation.Cabling & 10 Meter Electrical Connectors Were Replaced ML20196K5421999-03-22022 March 1999 Rev 2 to VC Summer Nuclear Station,Training Simulator Quadrennial Certification Rept,1996-99, Books 1 & 2. Page 2 of 2 Section 2.4.4 (Rev 2) of Incoming Submittal Were Not Included RC-99-0055, Special Rept:On 990302,Meteorological Site Number One 10 Meter Temp Element (RTD) Was Declared Inoperable Due to Erratic Operation.Cause of Original RTD Failure Is Unknown. Equipment Was Declared Operable on 9903121999-03-16016 March 1999 Special Rept:On 990302,Meteorological Site Number One 10 Meter Temp Element (RTD) Was Declared Inoperable Due to Erratic Operation.Cause of Original RTD Failure Is Unknown. Equipment Was Declared Operable on 990312 RC-99-0050, Monthly Operating Rept for Feb 1999 for VC Summer Nuclear Station,Units 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for VC Summer Nuclear Station,Units 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML20203F4511999-02-12012 February 1999 SER Finding Licensee Adequately Addressed GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Virgil C Summer Nuclear Station ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20206R5241998-12-31031 December 1998 Santee Cooper 1998 Annual Rept RC-99-0052, Vsns 1998 Annual Operating Rept. with1998-12-31031 December 1998 Vsns 1998 Annual Operating Rept. with RC-99-0004, Monthly Operating Rept for Dec 1998 for VC Summer Nuclear Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for VC Summer Nuclear Station,Unit 1.With ML20206R5191998-12-31031 December 1998 Scana Corp 1998 Annual Rept ML20198F4241998-12-18018 December 1998 Safety Evaluation Granting Relief Request for Approval to Repair ASME Code Class 3 Service Water Piping Flaws in Accordance with GL 90-05 for VC Summer Nuclear Station RC-98-0223, Special Rept 98-001:on 981130,steam Line High Range Gamma Monitor (RMG-19C) Was Declared Inoperable Due to Indeterminate Alarm.Caused by Failures in Detector & Meter Reset Circuitry.Established Preplanned Alternate Method1998-12-16016 December 1998 Special Rept 98-001:on 981130,steam Line High Range Gamma Monitor (RMG-19C) Was Declared Inoperable Due to Indeterminate Alarm.Caused by Failures in Detector & Meter Reset Circuitry.Established Preplanned Alternate Method RC-98-0222, Monthly Operating Rept for Nov 1998 for VC Summer Nuclear Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for VC Summer Nuclear Station,Unit 1.With ML20155G4551998-11-0404 November 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Use Code Case N-416-1 with Licensee Proposed Addl Exams RC-98-0208, Monthly Operating Rept for Oct 1998 for VC Summer Nuclear Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for VC Summer Nuclear Station,Unit 1.With ML20207J5701998-10-31031 October 1998 Non-proprietary Rev 1 to WCAP-14955, Probabilistic & Economic Evaluation of Rv Closure Head Penetration Integrity for VC Summer Nuclear Plant ML20154Q9571998-10-21021 October 1998 SER Accepting Request Seeking Approval to Use Alternative Rules of ASME Code Case N-498-1 for Class 1,2 or 3 Sys ML20154K7901998-09-30030 September 1998 Non-proprietary Rev 0 to WCAP-15101, Analysis of Capsule W from Sceg VC Summer Unit 1 Rv Radiation Surveillance Program RC-98-0184, Monthly Operating Rept for Sept 1998 for VC Summer Nuclear Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for VC Summer Nuclear Station.With ML20154K8041998-09-30030 September 1998 Non-proprietary Rev 0 to WCAP-15103, Evaluation of Pressurized Thermal Shock for VC Summer Unit 1 RC-98-0166, Monthly Operating Rept for Aug 1998 for VC Summer Nuclear Station,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for VC Summer Nuclear Station,Unit 1.With ML20237A7181998-08-13013 August 1998 SER Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RC-98-0153, Monthly Operating Rept for July 1998 for VC Summer Nuclear Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for VC Summer Nuclear Station,Unit 1 RC-98-0131, Monthly Operating Rept for June 1998 for VC Summer Nuclear Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for VC Summer Nuclear Station ML20248J0191998-06-0404 June 1998 Safety Evaluation Accepting Licensee Inservice Testing Program Interim Pump Relief Request Per 10CFR50.55a(a)(3) (II) RC-98-0113, Monthly Operating Rept for May 1998 for VC Summer Nuclear Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for VC Summer Nuclear Station,Unit 1 RC-98-0100, Monthly Operating Rept for Apr 1998 for VC Summer Nuclear Station,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for VC Summer Nuclear Station,Unit 1 ML20217G7411998-04-22022 April 1998 Rev 1 to VC Summer Nuclear Station COLR for Cycle 11 RC-98-0076, Final Part 21 Rept Re a DG EG-B for Vsns,As Followup to .Power Control Svcs of Engine Sys,Inc Provided Response on 980318.Evaluation Concludes That Failure of EG-B Is one-time non-repeatable Failure1998-04-17017 April 1998 Final Part 21 Rept Re a DG EG-B for Vsns,As Followup to .Power Control Svcs of Engine Sys,Inc Provided Response on 980318.Evaluation Concludes That Failure of EG-B Is one-time non-repeatable Failure RC-98-0084, Monthly Operating Rept for Mar 1998 for Virgil C Summer Nuclear Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Virgil C Summer Nuclear Station,Unit 1 ML20212H1421998-03-0202 March 1998 Interim Part 21 Rept SSH 98-002 Re EG-B Unit That Was Sent to Power Control Svcs for Determination of Instability & Refurbishment of a Dg.Cause of Speed Oscillations Unknown. Completed Hot Bore Checks on Power Case 1999-09-08
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