ML20111B783
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| ML20111B783 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/03/1985 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RO-SPR-84-018, NUDOCS 8501090073 | |
| Download: ML20111B783 (2) | |
Similar Documents at Summer | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARRC-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
[Table view]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-99-0168, 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 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 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-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-98-0014, Special Rept (Spr 970003):on 971230,declared a EDG Inoperable Due to Frequency Oscillations.Developed & Implemented Troubleshooting Plan on Electronic Governor Control Unit & Mechanical Speed Control Governor Unit1998-01-29029 January 1998 Special Rept (Spr 970003):on 971230,declared a EDG Inoperable Due to Frequency Oscillations.Developed & Implemented Troubleshooting Plan on Electronic Governor Control Unit & Mechanical Speed Control Governor Unit RC-97-0251, Special Rept (Spr 970002):on 971111, a EDG Declared Inoperable After Oscillations Occurred During Performance of Monthly Surveillance Test.Erratic Fuel Rack Movement Continued After Engine Unloaded1997-12-11011 December 1997 Special Rept (Spr 970002):on 971111, a EDG Declared Inoperable After Oscillations Occurred During Performance of Monthly Surveillance Test.Erratic Fuel Rack Movement Continued After Engine Unloaded RC-96-0150, Rev 1 to Special Rept Spr 960004,including Info Re Imperfection in SG B,For ISI Activity Completed on 9604291996-07-10010 July 1996 Rev 1 to Special Rept Spr 960004,including Info Re Imperfection in SG B,For ISI Activity Completed on 960429 RC-96-0152, Special Rept (Spr 960005):on 960512,Channel B EFW Flow Indications for Accident Monitoring Declared Inoperable Due to Incorrect Calibr Range for Flow Transmitters.Replacement Transmitters Not Arrive on Site Until Aug 19961996-06-17017 June 1996 Special Rept (Spr 960005):on 960512,Channel B EFW Flow Indications for Accident Monitoring Declared Inoperable Due to Incorrect Calibr Range for Flow Transmitters.Replacement Transmitters Not Arrive on Site Until Aug 1996 RC-96-0138, Special Rept:On 960425,fire Door DRIB/310 Inoperable for More than 7 Days.Caused by High Energy Electrical Arc When Speed Switch on Operating Pump Opened.New Door Ordered & Fire Barrier Will Be Restored within Week of Door Arrival1996-05-20020 May 1996 Special Rept:On 960425,fire Door DRIB/310 Inoperable for More than 7 Days.Caused by High Energy Electrical Arc When Speed Switch on Operating Pump Opened.New Door Ordered & Fire Barrier Will Be Restored within Week of Door Arrival ML20101Q7521996-04-11011 April 1996 Special Rept Spr 9600022:on 960305,loose Parts Monitoring panel,XPN6042 Declared Inoperable.Digital Metal Impact Monitoring Sys Currently Being Replaced.Operability Will Be re-established at End of Refueling Outage ML20100R5781996-03-0404 March 1996 Special Rept Spr 960001:on 960211,electric Driven Fire Pump XPP0134A Declared Inoperable Due to Intermitten Tripping of Local Circuit Breaker in Panel XPN7075A on Pump Start Due to Overcurrent RC-95-0313, Special Rept Spr 950003:on 951121,noted That Hydrostatic Pressure Testing & Flow Verifications Had Not Been Conducted for Test Performed in 1991 & 1994.Changed Task Description on Surveillance Task Sheet1995-12-20020 December 1995 Special Rept Spr 950003:on 951121,noted That Hydrostatic Pressure Testing & Flow Verifications Had Not Been Conducted for Test Performed in 1991 & 1994.Changed Task Description on Surveillance Task Sheet RC-95-0288, Suppl 1 to Special Rept Spr 94-005 Submitted on 940718 Re Inoperability of Main Plant Vent High Range Process Monitor RMA-13 Due to Spiking & Spurious Alarms.Installed Weather Shield Over Opening of Detector Housing1995-11-10010 November 1995 Suppl 1 to Special Rept Spr 94-005 Submitted on 940718 Re Inoperability of Main Plant Vent High Range Process Monitor RMA-13 Due to Spiking & Spurious Alarms.Installed Weather Shield Over Opening of Detector Housing RC-95-0275, Special Rept Spr 950002:on 951013,main Steam Radiation monitor,RMG-19B,declared Inoperable Due to Spiking Above High Radiation Setpoint Four Times within Thirty Minutes1995-10-27027 October 1995 Special Rept Spr 950002:on 951013,main Steam Radiation monitor,RMG-19B,declared Inoperable Due to Spiking Above High Radiation Setpoint Four Times within Thirty Minutes RC-95-0208, Special Rept (Spr 950001):on 950627,portion of Fire Svc Computer Sys Placed in by-pass to Isolate Malfunction.Hourly Fire Watch Patrol Began Insp of Affected Zone within One H After Placing Computer in by-pass,as Required1995-08-0404 August 1995 Special Rept (Spr 950001):on 950627,portion of Fire Svc Computer Sys Placed in by-pass to Isolate Malfunction.Hourly Fire Watch Patrol Began Insp of Affected Zone within One H After Placing Computer in by-pass,as Required RC-94-0182, Special Rept Spr 94-005:on 940705,main Plant Vent High Range Radiation Monitor Declared Inoperable Due to Spiking & Spurious Alarms.Established Preplanned Alternate Method of Monitoring Appropriate Parameters1994-07-18018 July 1994 Special Rept Spr 94-005:on 940705,main Plant Vent High Range Radiation Monitor Declared Inoperable Due to Spiking & Spurious Alarms.Established Preplanned Alternate Method of Monitoring Appropriate Parameters ML20113J2051992-07-31031 July 1992 Suppl 1 to Special Rept 92-004:on 920617,25,27 & 0706 & 17, Main Plan Vent High Range Process monitor,RMA-13 Declared Inoperable.Caused by Vibration from Abv Duct.Shock Mounts Installed on Detector Mounting ML20101L1751992-07-0202 July 1992 Special Rept Spr 92-004:on 920617,main Plant Vent high-range Radiation Monitor RMA-13 Declared Inoperable Due to Spiking & Spurious Alarms.Caused by Noise Induced from High Amplifier Circuit Board.New Board Installed ML20101F1261992-06-12012 June 1992 Special Rept Spr 920003:on 920516,smoke Detectors in Zone Ppp of Reactor Bldg Alarmed & Failed to Reset.Caused by High Temp & High Humidity & Detector &/Or Base Damage.Smoke Detector Sys Will Be Replaced in Mar 1993 During Refuel 7 ML20092K2701992-02-19019 February 1992 Special Rept:On 920128,piping Penetration in 3 H Rated Fire Wall Separating a & B Diesel Generator Rooms Identified as Not Listed in Required Fire Barrier Stp.Caused by Inadvertent Ommission of Barrier from Applicable STP ML20086T6331991-12-30030 December 1991 Special Rept Spr 910011:on 911207,smoke Detectors in Zone 000 in RB Spuriously Alarmed & Could Not Be Reset from Outside of Bldg.Compensatory Action & Monitoring of Containment Air Temp Hourly Initiated ML20091F0431991-11-0404 November 1991 Suppl 1 to Special Rept 91-0005:on 910916,main Plant Vent high-range Process Monitor RMA-13 Inoperable Due to Spiking. Caused by Introduction of Noise Via Ground Loop.Field Cable Grounded at One Point & Wiring Drawings Will Be Revised ML20079G5441991-09-30030 September 1991 Special Rept Spr 910006:on 910916,main Steam Line Radiation Monitor Declared Inoperable for More than 72 H Due to Inoperability of Remote Alarm & Horn.Unit Will Be Declared Operable Prior to Entering Mode 4 at End of Outage ML20083C7261991-09-16016 September 1991 Special Rept:On 910828,main Plant Vent High Range Process monitor,RMA-13,declared Inoperable Due to Spiking of Monitor.Extensive Troubleshooting Performed on Monitor. Detector Assembly & Readout Module Replaced ML20077C6971991-05-13013 May 1991 Special Rept Spr 910002:on 910413,area Temp of 102 F Allowed by Tech Spec 3.7.9 Was Exceeded for More than 8 H. Caused by Unavailability of Chilled Water to Room Cooler During Period Emergency Feedwater Pumps Were Used ML20070E2481991-02-12012 February 1991 Special Rept Spr 910001:on 910108,degraded Foam Seal Fire Barrier Identified.Caused by Seal Foam Matl Contracting & Pulling Away at Edges Where Matl Adheres to Fixed,Adjoining Walls.Barrier Reworked to Initial Condition ML20066D0551991-01-0202 January 1991 Special Rept Spr 90-016:on 901203,fire Protection Officer Questioned Position of CO2 Tank Outlet Valve Because of Relationship of Worm Gear & Sector Gear.Caused by Failure to Return Sys to Operable Status on 901031.Valve Repaired ML20065K1211990-10-30030 October 1990 Special Rept 90-014:land Use Census Identified New Location Yielding Calculated Dose Greater than Tech Spec 4.11.2.3 Limit.Odcm Will Be Revised by 901214 to Include New Location & Dispersion Coefficients ML20058B3851990-10-12012 October 1990 Special Rept Spr 90-013:on 900925,reactor Bldg hi-range Alarm Alarmed Spuriously & Declared Inoperable.Caused by Slight Contamination on Connector in Circuit.Monitor Tested & Returned to Svc ML20062A9531990-09-26026 September 1990 Special Rept Spr 90-011,Suppl 1:on 900912,main Plant Vent High Range Process Monitor RM-A13 Inoperability Occurred. Caused by Defective Auxiliary Pre Amp & Low Range Pre Amp Cards.Cards Repaired ML20065D8081990-09-12012 September 1990 Special Rept Spr 90-011:on 900829,main Plant Vent high-range Process Monitor RM-A13 Declared Inoperable.Caused by Spiking of Monitor.Troubleshooting & Component Replacement Unsuccessful.Suppl to Rept to Be Submitted ML20055H3431990-07-16016 July 1990 Special Rept Spr 90-10:on 900702,fire Door DRIB/108 Found Open as Result of Baseplate Becoming Wedged Underneath Door Preventing Closure W/O Assistance.Fire Watch Established. Door Stop Installed on 900709 ML20246K2031989-06-29029 June 1989 Special Rept Spr 89-007:on 890611,smoke Detectors in Reactor Bldg Spurious Alarmed & Could Not Be Reset Outside Bldg. Entry Into Reactor Bldg Restricted Due to Unit Being at 100% Power.Work Request Initiated for Repair During Next Outage ML20245F8951989-06-16016 June 1989 Special Rept Spr 89-006:on 890517,fire Door IB-203 Declared Inoperable Due to Broken Welds & Warping of Door & on 890528,reactor Shut Down & Entered mini-outage for Repairs. Fire Door RB-303 Returned to Svc on 890609 ML20244D3241989-06-0202 June 1989 Special Rept Spr 89-005:on 890516,meteorological Instrumentation Declared Inoperable to Allow for Sys Upgrades Designed to Enhance Reliability.Mods Expected to Be Completed & Sys Returned to Operable Status by 890609 ML20244C1691989-04-0606 April 1989 Special Rept 89-004:on 890310,facility Shutdown to Perform Steam Generator Work Resulting in Fire Barriers Being Inoperable for Greater than 7 Days.Fire Watch Established ML20235J1911989-02-17017 February 1989 Special Rept Spr 89-002:on 890202,Delta T 10-40 Meter Indications Inconsistent W/Actual Environ Conditions.Caused by Failure of 10-meter Aspirator Motor.Rotation Corrected to Move Air Flow Across Element to Aspirator Motor ML20195G5061988-11-10010 November 1988 Special Rept Spr 88-009 Re Inservice Insp of Steam Generator Tubes.Results of Insps Performed During Fourth Refueling Outage Include No Tubes in Any of Three Steam Generators Repaired.Total of 588 Tubes Plugged for Three Generators ML20195B9031988-10-20020 October 1988 Special Rept Spr 88-008:on 880916,Fire Doors PA301,AB401 & RB303 Inoperable for More than 7 Days.Cause Not Stated.Fire Doors Opened to Facilitate Personnel Access to Reactor Bldg. Barriers Expected to Remain Degraded for Duration of Outage ML20154L4171988-09-15015 September 1988 Special Rept Spr 88-007:on 880830,meteorological Tower Took Direct Lightning Strike Resulting in Loss of All Instruments on Tower & Three Dual Pen Recorders.All Repairs Expected to Be Completed & Unit Restored to Operable Status by 880930 ML20151L2971988-07-13013 July 1988 Special Rept:On 880626,diesel Fire Pump Failed to Start in Response to Valid Test Signal.Caused by Some Connectors Not Firmly Seated.Control Panel Removed & Taken to Maint Shop & All Connectors Reworked to Achieve Positive Connection 05000395/LER-1988-006, Special Rept Spr 88-05:on 880512,safety Injection/Reactor Trip Occurred When MSIV a Shut During Testing.Details Described in Encl LER 88-06.Accumulative Usage Factor for Affected Safety Injection Nozzle Did Not Exceed 0.701988-07-0808 July 1988 Special Rept Spr 88-05:on 880512,safety Injection/Reactor Trip Occurred When MSIV a Shut During Testing.Details Described in Encl LER 88-06.Accumulative Usage Factor for Affected Safety Injection Nozzle Did Not Exceed 0.70 ML20154Q6401988-05-23023 May 1988 Special Rept Spr 88-004:on 880506,61 Meter Wind Direction Instruments Declared Inoperable.Caused by Defective Data Logger.New Data Logger Installed & Instrument Will Be Returned to Operable Status on 880524 ML20154P3681988-05-0606 May 1988 Special Rept Spr 88-03:on 880422,reactor Bldg High Range Radiation Monitor RM-G18 Declared Inoperable Due to Erratic Reading.Caused by Faulty Connections.New Coaxial Connectors Installed & Monitor Returned to Svc ML20238C6801987-12-18018 December 1987 Special Rept Spr 87-009:on 871105,Fire Detection Zone F Declared Inoperable Due to Sporadic Integrated Fire Sys Computer Alarms.Caused by Signal Noise in Computer Loop Remote Cabinet.Repairs Reduced Frequency of Problem ML20235V2481987-07-14014 July 1987 Special Rept Spr 87-008:on 870630,Fire Door AB 421 Declared Inoperable to Allow Passage of Air Hoses & Electrical Extensions in Support of Maint in Area.Door Returned to Operable Status on 870708 After Repairs Completed ML20235V2791987-07-13013 July 1987 Special Rept Spr 87-007:on 870630,noble Gas Effluent Monitor RMA-14 on Reactor Bldg Purge Supply & Exhaust Sys Declared Inoperable Due to Spurious Alarms.Caused by Failed Wire on Power Circuit Board.Wire Repaired & Monitor Returned to Svc ML20214R0541987-06-0101 June 1987 Special Rept Spr 87-006:on 870405,both Trains of Gaseous Radwaste Treatment Sys Removed from Svc During Refueling Outage to Perform Sys Mods to Increase Sys Reliability & Reduce Sys Downtime.Mods Completed on 870525 ML20214J5171987-05-11011 May 1987 Special Rept Spr 87-005:third Inservice Eddy Current Exam of Steam Generator Tubing Completed on 870426.Encl Provides Info on Number of Tubes Plugged in Each Steam Generator During Insp & Submitted in Accordance W/Tech Spec 4.4.5.5.a 1999-09-08 Category:TEXT-SAFETY REPORT MONTHYEARML20217D6401999-10-31031 October 1999
[Table view]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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sucu.. o.... .o~ s January 3, 1985 40e 4 g,. O S
Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, NW Atlanta, GA 30323
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Special Report (SPR 84-018)
Dear Sir:
Attached is a Special Report for the Virgil C. Summer Nuclear Station.
This Special Report is being submitted pursuant to the requirements of Technical Specification 3.4.9.3, " Reactor Coolant System - Overpressure Protection System."
Should there be any questions, please call us at your convenience.
Very trul yo s, ,
- 0. W. ixon, .
RJB:0WD/dwf Attachment oc: V. C. Summer K. E. Nodland T. C. Nichols,.Jr./O. W. Dixon,lJr. R. A. Stough E. H. Crews, Jr. G. Percival E. C. Roberts C. W. Hehl W. A. Williams , Jr. J. B. Knotts, Jr.
D. A. Nauman I&E Washington Group Managers Document Management Eranch
- 0. S. Bradham INPO Records Center C. A. Price ANI Library D. A. Lavigne NPCF J. F. Heilman File C. L. Ligon (NSRC)
OFRCAL COPX 8501090073 850103 R\
PDR ADOCK 05000395 S PDR s fJM
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3 Mr. James P.-O'Reilly
'SPR 84-018 January 3, 1985 EVENT DESCRlPTION On December 4, 1984, with the Plant in Mode 5, Residual Heat Removal (RHR) "B" Train Suction Relief Valve actuated due to a Reactor Coolant System (RCS) pressure transient resulting from an isolation of letdown flow.
CAUSE OF FAILURE Instrument & Control (I&C) personnel, replacing the power supply-drawer to the Incore Thermocouple Separation Cabinet, inadvertently-pinched a main power lead on the rear of the unit, shorting the lead to ground. The short circuit ultimately resulted in the loss of Inverter XIT-5901, which de-energized the distribution panel providing power:to Letdown Flow Control Valve HCV-142. Loss of power to control valve HCV-142 cauced the valve to fail closed, isolating letdown flow and causing the RCS pressure transient. RHR "B" Train Suction Relief Valve actuation was verified by the observation of the RHR discharge pressure indicator IPI-600B.
ACTION TAKEN The Operator at the Control immediately opened Pressure Control Valves-445 A and B to re-establish letdown flow.
ACTION TAKEN-TO Ph?CLUDE RECURRENCE The lead on the rear of the power supply drawer was replaced with a shorter main power lead to prevent pinching during power supply drawer
-removal and replacement. The Licensee also inspected the other unit ~
and verified that the installed lead was short enough to preclude pinching and subsequent grounding.
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