ML19347E084
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| ML19347E084 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/08/1981 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8104150405 | |
| Download: ML19347E084 (1) | |
Similar Documents at Summer | |
|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20216J4191999-09-24024 September 1999
[Table view]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 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-99-0087, 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 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 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 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 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 ML20199E6391998-01-28028 January 1998 Part 21 Rept Re Failure of EG-A Control Serial Number 1425251 on 980109.Engine System Incorporated Has Been Notified of Situation & Understands That Part 21 Notification Being Submitted Based on Coc RC-97-0253, Follow-up Part 21 Rept SSH 960004 Re Defect Determined Not to Be Potentially Associated W/Substantial Safety Hazard (Ssh).Westinghouse Determined That SSH Reportable Under 10CFR21 Does Not Exist Based on Listed Info1997-12-15015 December 1997 Follow-up Part 21 Rept SSH 960004 Re Defect Determined Not to Be Potentially Associated W/Substantial Safety Hazard (Ssh).Westinghouse Determined That SSH Reportable Under 10CFR21 Does Not Exist Based on Listed Info ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20138Q2791996-12-13013 December 1996 Part 21 Rept Re Notification on Model 763 Wire Failures.Itt Barton Presently Investigating Understanding of Situation & Intends to Identify Suitable Repair,Can Be Implemented in Field ML20134L1681996-07-31031 July 1996 Part 21 Rept Re Failure of Itt Barton Model 763 Pressure Transmitters.Itt Barton Has Not Established Root Cause But Is in Process of Evaluating Failure ML20115F7081996-07-15015 July 1996 Part 21 Rept Re Failures of Abb/Ite 27N Relays.Abb Has Not Established Root Cause for What Appears to Be Repetitive Failure of U5 Timer RC-96-0157, Part 21 Rept Re Nozzle Weld Defects in Chemical & Vol Control Sys Connections at RCP Seal Injection Nozzles & Ccws Connections at RCP Thermal Barrier Heat Exchanger Inlet & Outlet Nozzles Supplied by W1996-06-17017 June 1996 Part 21 Rept Re Nozzle Weld Defects in Chemical & Vol Control Sys Connections at RCP Seal Injection Nozzles & Ccws Connections at RCP Thermal Barrier Heat Exchanger Inlet & Outlet Nozzles Supplied by W ML20116C9811996-05-20020 May 1996 Part 21 Rept Re Defective Welds Originally Specified & Performed by W on Component Cooling Water Nozzles for RCP Seal Injection Lines RC-95-0040, Interim Part 21 Rept (SSH 940002) Re Failure of 27N Degraded Voltage Relay Mfg by Asea Brown Boveri1995-02-15015 February 1995 Interim Part 21 Rept (SSH 940002) Re Failure of 27N Degraded Voltage Relay Mfg by Asea Brown Boveri RC-94-0308, Interim Part 21 Rept (SSH 940002) Re Failure of 27N Degraded Voltage Relay.Degraded Voltage Relay Returned to Mfg for Further Evaluation & Repair.Sc&G Expects to Complete Evaluation of 10CFR21 Reportability by 9502171994-12-0202 December 1994 Interim Part 21 Rept (SSH 940002) Re Failure of 27N Degraded Voltage Relay.Degraded Voltage Relay Returned to Mfg for Further Evaluation & Repair.Sc&G Expects to Complete Evaluation of 10CFR21 Reportability by 950217 RC-93-0251, Follow-up to 930521 Interim Part 21 Rept SSH 930003 Re Spare Model D26 Type M Relays Mfg by Cutler-Hammer & Supplied by Vitro Corp.All Affected Relays in storage,35 Rejected & Will Not Be Used in Any in-plant Application1993-09-28028 September 1993 Follow-up to 930521 Interim Part 21 Rept SSH 930003 Re Spare Model D26 Type M Relays Mfg by Cutler-Hammer & Supplied by Vitro Corp.All Affected Relays in storage,35 Rejected & Will Not Be Used in Any in-plant Application ML20046C6611993-08-0505 August 1993 Follow-up to 930226 Interim Part 21 Rept.Part 21 Evaluations for Reportability for Nonconformances Ncn 452 & Ncn 4555 Completed W/Determination That Neither Nonconformance Reportable ML20046C3251993-07-28028 July 1993 Part 21 Rept Re Failure of 27N Undervoltage Relay Mfg by Asea Brown Boveri.Subsequent Evaluation by Licensee, Folowing Insp by Vendor,Determined Item Not Reportable,Per 10CFR21 ML20044G3161993-05-25025 May 1993 Interim Part 21 Rept Re Failure of 27N Undervoltage Relay Discovered During Bench Testing Performed Prior to Installation.Relay Returned to Mfg for Repair.Relay Replaced ML20044E7531993-05-21021 May 1993 Interim Part 21 Rept SSH 930003 Re Three Defective Spare Model D26MR31A Type M Relays Mfg by Cutler-Hammer & Supplied by Automation Ind/Vitro Labs.All Vitro Supplied C-H Relays Placed on Hold & Two Relays Sent Off Site for Evaluation ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20102B1211992-07-10010 July 1992 Part 21 Rept Re 911107 C Feedwater Isolation Valve Actuator Failure Due to Defect in Poppet Seal.Seal Replaced & Testing by Independent Lab Being Performed to Determine Physical Properties of Original Poppet Seals ML20087B3211992-01-0606 January 1992 Part 21 Rept Re C Feedwater Isolation Valve Actuator Failure During Testing.Caused by Poppet Seal in Control Valve Assembly.New Design Poppet Seal Extensively Tested & Placed Into Svc,Resolving Problem ML20058F4791990-10-30030 October 1990 Part 21 Rept Re Design of Chilled Water Sys & Postulated Seismic Events Leading to Rupture of Nonsafety Piping ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011E8411990-02-13013 February 1990 Part 21 Rept Re Possible Rise in Chiller Water Temp When Svc Water Flow Valve Opened to Increase Flow.Initially Reported on 900209.Revised Guidelines Issued for Min Chiller Load Operation by Selectively Isolating Cooling Coils ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20245K2411989-08-11011 August 1989 Part 21 Rept Re Error in Design of Nonsafety,Nonseismic Portion of Svc Water Pump House HVAC Sys.Situation Will Be Reviewed & Determined to Be Unique to Mod for Plant.Training Will Be Conducted Re Consideration of Flood Paths ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20151E7221988-07-15015 July 1988 Part 21 Rept Re Steam Propagation Path Affecting Unqualified Equipment.Applicable Scenario Involved Main Steamline Break Which Occurs on 436 Ft Elevation of Intermediate Bldg.Plant Shutdown Initiated.Doors to Room Ib 63-03 Opened ML20237J5081987-08-12012 August 1987 Part 21 Rept Re Design of Control Room Ventilation Sys Not in Compliance W/Sys Requirements Identified in FSAR & W/Single Failure Criteria.Initially Reported on 870807. Licensee Committed to Make Permanent Mod to Intake Dampers ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20210U3821986-10-0303 October 1986 Part 21 Rept Re Swing Chiller Control Circuit.Initially Reported on 861003.Circuit Found to Have Deficiency Which Would Prevent Chiller from Starting.Util Informed of Condition & Implemented Appropriate Administrative Controls ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder NRC-86-3095, Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified1986-01-0909 January 1986 Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20101P9361984-12-20020 December 1984 Part 21 Rept Re Fatigue Cracks on Fuel Injection Pump Delivery Valve Holders of PC-2 & PC-2.3 Emergency Diesel Generators.All Valve Holders W/Improper Radius Will Be Replaced ST-HL-AE-1141, Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors1984-09-14014 September 1984 Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors ML20087F8681984-03-0808 March 1984 Supplemental Part 21 Rept Re Failed Engine Thrust Bearing. Plugs Properly Installed in Both Units.Units Free of Potential Defect ML20079H3241984-01-17017 January 1984 Deficiency Rept Re Broken Strand Wires on Auxiliary Switch Mounted on GE Air Magnetic Circuit Breakers.Investigation Determined Defect Not Reportable Per 10CFR21 ML20081K1551983-10-31031 October 1983 Part 21 Rept Re Failure to Meet Separation Criteria on Main Control Board Defined in IEEE 384-1974,Section 5.6.2. Initially Reported on 830922.DC Power Circuit Reworked Ensuring Protection Against Electrically Generated Fire 1999-09-24 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 |
Text
SOUTH CAROLINA ELECTRIC a gas COMPANY c.l.e.'.
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COLUMBIA SOuTM CAROUNA 29218
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T. C. NicMo ts. J a. $'
April 8, 1981 v,ce ......, . 2 o.. c. com.
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%% _;'s Mr. James P. O'Reilly, Director t N' U. S. Nuclear Regulatory Commission g Region II, Suite 3100 101 Marietta Street, N. W.
Atlanta, Georgia 30303
Subject:
Virgil C. Sutmer Nuclear Station Docket No. 50/395 Potential Substantial Safety Hazard or Potential Significant Deficiency Interim Report Nuclear Eng. File 3.1051
Dear Mr. O'Reilly:
On Thursday, February 19, 1981, Mr. Paul Kellog of NRC Region II was notified 3
of a potential significant deficiency or potential substantial safety hazard con-cerning corroded plug assemblies associated with soleniod valves.
SCE&G Nuclear Engineering had the corroded connectors inspected by a metal-lurgist. He has been instructed to identify the cause of the corrosion and to help Nuclear Engineering arrive at a corrective action to eliminate the conditions for corrosion.
Tha final report is not expected until two months.
Very truly yours, ,
T. C. Nichols, Jr.
TB:TCN:glb cc: V. C. Summer J. L. Skolds G. H. Fischer B. A. Bursey T. C. Nichols, Jr. O. S. Bradham O. W. Dixon, Jr. Document Management Branch C. A. Price (55e/21/LER Only)
D. A. Nauman I&E (Washington)
W. A. Williams, Jr. ISEG R. B. Clary PRS A. R. Koon H. Boreson A. A. Smith H. Hillberg H. N. C;rus NPCF gf J. B. Knotts, Jr. File 68 0 ,
8104150 @
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