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Category:NON-RECURRING TECHNICAL REPORT (ENVIRONMENTAL)
MONTHYEARML20046A0581993-03-31031 March 1993 Technical Rept 93-1, Seismic Activity Near VC Summer Nuclear Station for Jan-Mar 1993. ML20126G9151992-09-30030 September 1992 Technical Rept 92-3, Seismic Activity Near VC Summer Nuclear Station, for Period Jul-Sept 1992 ML20104B8261992-06-30030 June 1992 Technical Rept 92-2, Seismic Activity Near VC Summer Nuclear Station, for Period Apr-June 1992 ML20101L9531992-03-31031 March 1992 Technical Rept 92-1, Seismic Activity Near VC Summer Nuclear Station, for Period Jan-Mar 1992 ML20091N6531992-01-27027 January 1992 Technical Rept 91-3, Seismic Activity Near VC Summer Nuclear Station,Jul-Dec 1991 ML20091D7911991-12-31031 December 1991 Technical Rept 91-4, Seismic Activity Near VC Summer Nuclear Station for Period Oct-Dec 1991 ML20079E7721991-10-0101 October 1991 Technical Rept 91-2, Seismic Activity Near VC Summer Nuclear Station,Apr-June 1991 ML20079C9541991-06-21021 June 1991 Seismic Activity Near VC Summer Nuclear Station,Jan-Mar 1991 ML20072S6471990-12-31031 December 1990 Seismic Activity Near VC Summer Nuclear Station for Oct-Dec 1990, Technical Rept 90-4 ML20006B1241990-01-24024 January 1990 Seismic Activity Near VC Summer Nuclear Station for Period Jul- Sept 1989. ML20245K7231989-03-31031 March 1989 Technical Rept 89-1 Seismic Activity Near VC Summer Nuclear Station, for Jan-Mar 1989 ML20246P2131988-12-31031 December 1988 Seismic Activity Near VC Summer Nuclear Station for Period Oct-Dec 1988 ML20210L3071986-06-30030 June 1986 Seismic Activity Near VC Summer Nuclear Station, for Apr-June 1986 ML20214U4161986-03-31031 March 1986 Seismic Activity Near VC Summer Nuclear Station, for Period Jan-Mar 1986 ML20102C1161985-03-31031 March 1985 316(b),Demonstration for VC Summer Nuclear Station for South Carolina Dept of Health & Environ Control & Nrc ML20116E7821984-12-31031 December 1984 Seismic Activity Near VC Summer Nuclear Station,Oct-Dec 1984 ML20106G2421984-09-30030 September 1984 Seismic Activity Near VC Summer Nuclear Station for Period Jul-Sept,1984, Quarterly Seismic Rept ML20090B1301984-07-0606 July 1984 Seismic Activity Near VC Summer Nuclear Station, Technical Rept 84-1 for Jan-Mar 1984 ML20078C1381983-06-30030 June 1983 Seismic Activity Near Virgil C Summer Nuclear Station Apr-June 1983 ML20078C1521983-03-31031 March 1983 Seismic Activity Near Virgil C Summer Nuclear Station Jan-Mar 1983 ML20083Q5731983-02-22022 February 1983 Seismic Activity Near VC Summer Nuclear Station for Period Apr-June 1982 ML20078C1571982-12-31031 December 1982 Seismic Activity Near Virgil C Summer Nuclear Station Oct-Dec 1982 ML20071D8381982-09-30030 September 1982 Seismic Activity Near VC Summer Nuclear Station,Jul-Sept 1982 ML20065L5321982-06-30030 June 1982 Geologic Studies in Area of Induced Seismicity at Monticello Reservoir,Sc, Fourth Technical Rept.Thirteen Oversize Figures Encl.Aperture Cards Are Available in PDR ML20065L5271982-03-31031 March 1982 Seismic Activity Near VC Summer Nuclear Station,Jan-Mar 1982, Technical Rept 82-1 ML20040G9871982-02-10010 February 1982 Technical Rept 81-3, Seismic Activity Near VC Summer Nuclear Station,Jul-Sept 1981. ML20040G9891981-12-26026 December 1981 Third Technical Rept, Geological Studies in Area of Induced Seismicity at Monticello Reservoir,Sc. ML20011A4461981-10-31031 October 1981 Applicant Evaluation-Luco Rept. ML20011A4251981-10-31031 October 1981 Applicant Evaluation Joyner-Fletcher Rept. ML20011A4231981-10-31031 October 1981 Applicant Evaluation Trifunac Rept. ML19343D5751981-04-30030 April 1981 Supplemental Investigation - Svc Water Pond West Embankment Rept 2. ML20008F1291981-03-31031 March 1981 to App X, Effects of Near-Field Earthquake Ground Motion on Structure & Equipment Design, from Rept Entitled Supplemental Seismologic Investigation. ML19347D0151981-03-0606 March 1981 Supplemental Investigation,Svc Water Pond West Embankment, Virgil C Summer Nuclear Station. ML19345D5961980-12-31031 December 1980 Supplemental Seismologic Investigation. ML19345B6271980-09-30030 September 1980 Seismic Activity Near VC Summer Nuclear Station for Jul-Sept,1980. ML19290E6821980-03-11011 March 1980 Technical Rept 79-4, Seismic Activity Near Facility for Oct-Dec 1979. ML19260A1861979-11-0202 November 1979 Comparison of 780827 Monticello Reservoir Earthquake Response Spectra to OBE Response Spectra. ML19210C9501979-09-30030 September 1979 Technical Rept 79-3, Seismic Activity Near VC Summer Nuclear Station,Jul-Sept 1979. ML19247A5741979-06-30030 June 1979 Technical Rept 79-2, Seismic Activity Near VC Summer Nuclear Station, Apr-June 1979 1993-03-31
[Table view] Category:TEXT-ENVIRONMENTAL REPORTS
MONTHYEARML20217J3431999-10-15015 October 1999 Environ Assessment & Finding of No Significant Impact Re Issuance of Exemption from Certain Provisions of 10CFR50, Section 50.60(a) to Sce&G for Operation of VC Summer Nuclear Station RC-99-0075, 1998 Annual Effluent & Waste Disposal Rept for VC Summer Nuclear Station. with1998-12-31031 December 1998 1998 Annual Effluent & Waste Disposal Rept for VC Summer Nuclear Station. with ML20217F2781998-04-0101 April 1998 Mod to NPDES Permit SC0030856,issued to Sce&G Vsns RC-98-0095, Annual Effluent & Waste Disposal Rept for VC Summer Nuclear Station for Operating Period 970101-12311997-12-31031 December 1997 Annual Effluent & Waste Disposal Rept for VC Summer Nuclear Station for Operating Period 970101-1231 RC-98-0096, Radiological Environmental Monitoring Rept for Period Jan-Dec 19971997-12-31031 December 1997 Radiological Environmental Monitoring Rept for Period Jan-Dec 1997 ML20138H7081996-12-31031 December 1996 Annual Effluent & Waste Disposal Rept for Operating Period Jan-Dec 1996 RC-97-0093, Radiological Environ Monitoring Rept VC Summer Nuclear Station for Operating Period 960101-12311996-12-31031 December 1996 Radiological Environ Monitoring Rept VC Summer Nuclear Station for Operating Period 960101-1231 ML20107L8711995-12-31031 December 1995 Annual Effluent & Waste Disposal Rept for Operating Period Jan-Dec 1995 ML20080H6731995-09-30030 September 1995 Technical Rept 94-3, Seismic Activity Near VC Summer Station for Period Jul-Sept 1994 ML20080P4181994-12-31031 December 1994 Semiannual Effluent & Waste Disposal Rept for Operating Period Jul-Dec 1994 ML20083L6511994-12-31031 December 1994 Seismic Activity Near VC Summer Nuclear Station for Period Oct-Dec 1994 RC-94-0227, Semiannual Effluent & Waste Disposal Rept for Period of Jan-June 19941994-06-30030 June 1994 Semiannual Effluent & Waste Disposal Rept for Period of Jan-June 1994 ML20073A7221994-06-30030 June 1994 Technical Rept 94-2, Seismic Activity Near Vsns for Period Apr-June 1994 RC-94-0052, Semiannual Effluent & Waste Disposal Rept for Operating Period,930701-12311993-12-31031 December 1993 Semiannual Effluent & Waste Disposal Rept for Operating Period,930701-1231 ML20065F3041993-12-31031 December 1993 Technical Rept 93-4, Seismic Activity Near Vsns for Period Oct-Dec 1993 ML20065F2981993-09-30030 September 1993 Technical Rept 93-3, Seismic Activity Near VC Summer Nuclear Station for Period Jul-Sept 1993 ML20056G5471993-06-30030 June 1993 Semiannual Effluent & Waste Disposal Rept for Operating Period Jan-June 1993 ML20046A0581993-03-31031 March 1993 Technical Rept 93-1, Seismic Activity Near VC Summer Nuclear Station for Jan-Mar 1993. RC-93-0116, Radiological Environ Monitoring Rept for VC Summer Nuclear Station for Operating Period 920101-12311992-12-31031 December 1992 Radiological Environ Monitoring Rept for VC Summer Nuclear Station for Operating Period 920101-1231 ML20126G9151992-09-30030 September 1992 Technical Rept 92-3, Seismic Activity Near VC Summer Nuclear Station, for Period Jul-Sept 1992 ML20099G3651992-08-11011 August 1992 NPDES Noncompliance Notification:On 920805,fish Discovered in Circulating Water Discharge Area.Caused by Thermal Stresses Re Plant Circulating Water Discharge Temps.Temp Monitoring Will Continue.Table Re Fish Species Encl ML20101T1111992-07-14014 July 1992 NPDES Noncompliance Notification:On 920708,fish Kill Discovered in Plant Circulating Water Discharge.Caused by Thermal Shock from Increasing Circulating Water Discharge Temps.Addl Info Will Be Included in 1992 Fish Kill Summary ML20104B2661992-06-30030 June 1992 Amended VC Summer Nuclear Station Semiannual Effluent & Waste Disposal Rept,Jan-June 1992 ML20104B8261992-06-30030 June 1992 Technical Rept 92-2, Seismic Activity Near VC Summer Nuclear Station, for Period Apr-June 1992 ML20114C7791992-06-30030 June 1992 VC Summer Nuclear Station Semiannual Effluent & Waste Disposal Rept for Operating Period 920101 Through 920630 ML20101L9531992-03-31031 March 1992 Technical Rept 92-1, Seismic Activity Near VC Summer Nuclear Station, for Period Jan-Mar 1992 ML20091N6531992-01-27027 January 1992 Technical Rept 91-3, Seismic Activity Near VC Summer Nuclear Station,Jul-Dec 1991 ML20094H0561991-12-31031 December 1991 Semi-Annual Effluent & Waste Disposal Rept for Jul-Dec 1991 ML20091D7911991-12-31031 December 1991 Technical Rept 91-4, Seismic Activity Near VC Summer Nuclear Station for Period Oct-Dec 1991 ML20079E7721991-10-0101 October 1991 Technical Rept 91-2, Seismic Activity Near VC Summer Nuclear Station,Apr-June 1991 ML20082N1231991-06-30030 June 1991 Semiannual Effluent & Waste Disposal Rept for Jan-June 1991 for VC Summer Nuclear Station ML20079C9541991-06-21021 June 1991 Seismic Activity Near VC Summer Nuclear Station,Jan-Mar 1991 ML20072S6471990-12-31031 December 1990 Seismic Activity Near VC Summer Nuclear Station for Oct-Dec 1990, Technical Rept 90-4 ML20086R9571990-12-31031 December 1990 Radiological Environ Monitoring Rept,Jan-Dec 1990 ML20029A8221990-12-31031 December 1990 Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1990. ML20029A4271990-09-30030 September 1990 Seismic Activity Near VC Summer Nuclear Station,Jul-Sept 1990. ML20059G3861990-09-0404 September 1990 NPDES Noncompliance Notification:On 900828,29 & 30,limited Fish Kills Discovered in Circulating Water Discharge Bay. Caused by Thermal Shock from Increasing Discharge Temps Combined W/Fluctuating Water Levels in Reservoir ML20059B5041990-08-20020 August 1990 NPDES Noncompliance Notification:On 900815 & 16,limited Fish Kills Discovered in Plant Circulating Water Discharge Bay. Caused by Thermal Shock from Increasing Discharge Temps Combined W/Fluctuating Water Levels ML20055G3951990-07-16016 July 1990 NPDES Noncompliance Notification:On 900711,limited Fish Kill Discovered in Plant Circulating Water Discharge Bay.Caused by Thermal Shock from Increasing Discharge Temp & Fluctuating Water Levels in Reservoir ML20044B0181990-07-11011 July 1990 NPDES Noncompliance Notification:On 900706,limited Fish Kill Discovered in Plant Circulating Water Discharge Bay.Caused by Thermal Shock from Increasing Discharge Temps Combined W/Fluctuating Water Levels in Facility Reservoir ML20059C0041990-06-30030 June 1990 Semiannual Effluent & Waste Disposal Rept for Jan-June 1990 ML20085M5841990-06-14014 June 1990 NPDES Noncompliance Notification:Chronic Problem W/Ph Values Exceeding Limit of 9.0 at Outfalls 005,006A & 006B ML20085M5811990-03-31031 March 1990 Status Rept-Fish Kill Action Plan 1st Quarter 1990 ML20006B1241990-01-24024 January 1990 Seismic Activity Near VC Summer Nuclear Station for Period Jul- Sept 1989. ML20042E1961989-12-31031 December 1989 Seismic Activity Near VC Summer Nuclear Station,Oct-Dec 1989. ML20246K2581989-08-28028 August 1989 NPDES Noncompliance Notification:On 890822,fish Kill Discovered in Circulating Water Discharge Bay.Caused by Temp Fluctuation in Circulating Water Discharge Bay ML20245J4581989-08-0909 August 1989 NPDES Noncompliance Notification:On 890804,89 Dead Fish Discovered in Circulating Water Discharge Bay.Possibly Caused by Temp Fluctuations at Bottom of Discharge Bay on 890803 ML20247F7111989-07-20020 July 1989 NPDES Noncompliance Notification:On 890626,dead Catfish Discovered in Circulating Water Discharge Bay & Canal at Plant.During 890626-0710,167 Dead Fish Noted in Discharge Area.Fish Kill Suspected to Have Occurred Late on 890624 ML20247E9961989-07-20020 July 1989 NPDES Noncompliance Notification:On 890715,fish Kill Discovered at Plant Circulating Water Discharge Canal.Caused by Thermal Shock ML20246J6371989-06-30030 June 1989 Nonproprietary Semiannual Effluent & Waste Disposal Rept for Operating Period Jan-June 1989 1999-10-15
[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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APPLICANT EVALUATION LUC 0 REPORT 4
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VIRGIL C. SUMMER NUCLEAR STATION DOCKET No. 50/395 SOUTH CAROLINA ELECTRIC & GAS COMPANY OCTOBER, 19El i
i-gOQh[oh p A
APPLICANT EVALUATION OF LUC 0 REPORT ON VIRGIL C. SUMMER NUCLEAR STATION SEISMI'ITY STUDIES Prof. J. Enrique Luco has reviewed the " Supplemental Seismologic Inves-tigation",' including Appendix XI, portions of the FSAR (361.13, 361.17.4, 361.21) and portions of the Safety Evaluation Report. His response is contained la a report entitled, " Comments on Estimates of Scrong Ground Motion for the V. C. Summer Nuclear Station, Unit I", dated September 23, 1981. The issues raised by Luco result from misinterpretations of the studies which have been performed by the Applicant or from the use of incorrect parameter values in his analyses. This deserves a direct response; the form of the response follows the issues raised by Luco, in order.
ON THE HANKS - MCGUIRE METHOD TO ESTIMATE PEAK ACCELERATION Luco 1.s correct ia pointing out that in the usual characterization of earthquakes via the Brune model (which is done through observations of spectral amplitudes in the frequency domain), stress drops vary greatly and corner frequency and spectral decay at high frequencies are the subject of current discussions. However, the Applicant is not using the Brune model in this usual, frequency-domain application but in the method propostu 'oy Hanks and McGuire (1981). This method (which uses observa-j ti .ans of ground accelerations in the time domain) provides remarkably stable 1stimates of stress drops for past earthquakes (in fact, this is one of the major points of Hanks and McGuire, 1981). That this is the case is recognized later in Luco's report when he states, "The stress drop paramet.er appearing in the estimate of peak acceleration obtained by Hanks and McGuire has no relation with the stress drop determined by standard seismologic methods. In particular, Hanks and McGuire found that the peak accelerations for events in California could be approx-imated by a constant stress drop of 100 bars, independent of the stress i
drops calculated for these events by standard seismological methods."
Hanks and McGuire also point out that, regardless of the accuracy or 1
E
-- -ww-, - . -..---,y ~-..,.-,-v,--.~,,-r.----e+.. -,.-c.,-.-- ..--.-e _ _ - - - - . - - -
insecuracy of this methodolcgy in characterizing corner frequency and high frequency spectral decay, the model works in predicting both root-mean-square (r=s) and peak acceleration. Thus Luco's concerns about uncertainties in str'ess drop, corner frequency, and spectral decay are applicable to frequercy domain methods, not to the Applicants' time domain method. Applicants' method does not lead to estimates of peak acceleration which are highly uncertain, as Luco implies, but rather leads to peak acceleration estimates with confidence as high as available by using other state-of-the-art methods.
ESTIMATES OF STRESS Dr.0P Luco implies that stress drops estimated (in the frequency domain) by standard seismological methods and presented by the Applicant are irrelevant. This is not the case. The Applicant has presented such data in Appendix VII of the Supplemental Seismologic Investigat. ion to give as complete a picture as possible about the data which have been gathered at the site. In the context in which Luco views these data (that of the experience of Hanks and McGuire with California data), the standard stress drop data presented in Appendix VII are entirely consistent. In California, standard stress drop values range from 6 to 140 bars, and the values appropriate for ras acceleration estimates is 100 bars; at Monticello, standard stress drop values range from 1 to 5 bars and the value appropriate for rms acceleration is 25 bars.
The derivation of rms acceleration a by Luco is slightly differ-ent from that of the Applicant because Luco explicitly ine.ludes the term (1 + (f,/f)2)-1 in the integral, whereas the Applicant does not. The Applicant's derivation, which was und to calculate values of a and peak acceleration presented to the ACRS Seismic Subcommittee on February 26, 1981, is given in the attached Appendix. To be sure, the term (1+(f /f) )~
9 appears in equations in the Applicants' FSAR section 361.17.4, but the question of whether more accuracy is gained by discarding the term and integrating from f=f , or including the term and integrating from f=o, is moot:
the available spectra from Monticello can be fit either way with equal accuracy. The more important point is that it makes little difference
to conclusions gained by comparison of estimates to data at high digi-tization rates (e.g. 500 points per second, which are presumably most accurate) where fu=40 or 50 hz is appropriate. This is shown in the attach-ed Appendix (a typical effect on stress drop estimates for these records is 15%). At lower digitization rates there is more effect which accounts in part for the results Luco obtains in comparison to data presented by the Applicant in FSAR Table 361.17.4-1. In any event, conclusions from FSAR Table 36'. 17.4-1 are obsolete: relocation of the August 27, 1978 earthquake now indicates a source-to-site distance of 0.67 km rather than 0.8 km, and digitization at 500 points per-second have brcome available. A more enlightened conclusion is obtained by comparison of predictions with records digitized at 500 points per second. Table I shows the appro-priate parameters, observations, and predictions made by the Applicant that were presented at the ACRS Subcommittee meeting February 26, 1981.
It also shows estimates made by Luco's equation (2) which indicate that a stress drop of 26 bars explains the observations (using Luco's preferred value of f =50 u hz) . Thus the analysis sad equations developed by Luco fully support the stress drop value of 25 bars used by the Applicant for the most recent accurate data available on the August 27, 1978 earth-quake. The value of 100 bars obtained by Luco in his report is based on an erroneous source-to-site distance (calculated from preliminary depth estimate) of 1.6 km; all investigators familiar with the data includ-ing USGS (Fletcher, personal communication,1981) now agree that a source-to-site distance of about 0.67 km (as used in Table 1) is accurate.
Luco's calculation of stress drop for earthquakes at Hsinfengkiang Reservoir (his Table 2) is incorrect on two counts, thus rendering his con-clusions invalid. First, Luco uses an upper frequency of 20 hz, whereas the Chinese strong motion instruments provide linear response up to 35 hz (the Applicant states this in its Appendix XI). Thus f u=35 hz or I greater would be more appropriate. Second, Luco used surface-wave magnitude M, in place of local magnitude g . For the Chinese data j (M
L = 3 to 5 ) , M, is less than g by about one unit. As a result, smaller source sizes and larger stress dror: are obtained than is correct l 1
1
.. ~4 for thaso dete. In cny ccao, tha important ras.nlt from tha Chin 2co data is that stress drops determined from peak acceleration do not increase with magnitude; the Applicant made this point in Appendix XI, and Luco apparently agrees with this conclusion. One further point is that the seismological stress drop calculated for the M,=6.1 main shock. of Hsinfengkiang was 7.5 bars (Sheng et al., 1973), a value which is not inconsistent (given the above discussion) with the ras acceleration stress drops reported by the Applicant in Appendix XI.
Luco conclades that a stress drop of 150 bars is appropriate. Not onl:, is this view unsupported by data, it is contradicted by data at Monticello, at Hsinfengkiang, and in California. For the firs t two locations, stress drops less than 25 bars are indicated; California data .
are irrelevant to the issue of very shallow induced seismicity and, in any case, indicate a stress drop for ras accelerations of 100 bars. Luco has presented no data which indicate that a stress drop of 150 bars is appropriate to use with the Hanks and McGuire method.
ESTIMATES OF PEAK GROUND ACCELERATION The peak acceleration values shown by Luco in his Table 3 are invalid for the Virgil C. Summer Nuclear Station because they are based on a 100 bar stress drop. It is not surprising that Luco's Table 3 values agrees with the equations of Joyner et al. (1981) at R=7.3 km (zero epicentral distance)* because these equations are bas d on Californic data and Hanks and McGuire have shown that 100 bars e appropriate for Cali-fornia earthquakes.
- Data shown by Luco in his Table 4 and his Figure 1 are misleading.
He states, that "This sample may be biased towards the largest peak accelerations," (emphasis added), but in fact the sample g biased. For the Oroville data which Luco finds of particular interest, the average of the larger peak accelerations on each record for 4.0 < g < 5 is 382 _
cm/sec , whereas, the mean of the Oroville af tershock peak accelera-tiona on bedrock sites for the same magnitude range is 164 cm/sec (Seekins and Hanks, 1978). Thus th= data presented by Luco are very much It appears that Luco has misinterpreted the meaning of the parameter R=7.3 km used by Joyner et al (1981); this le not a depth estimate, so that R is not hypocentral distance as Luco states. Joyner et al (1981) simply use constant R as a parameter to fit their data.
l- . _ - - - - . - - . ~ . - - - - -- - -- -- - - - - - -~ ~ '~"
biased toward higher accelerations and should not be used to determine peak acceleratior levels. Further, the Oroville af tershocks are charac-terized by an ras-acceleration determined stress drop of 100 bars which the Applicant has shown is inappropriate for Monticello Reservoir earth-quakes.
VERTICAL PEAK ACCELERATIONS l
The Applicant agrees with Luco's observation that vertical peak accel- '
erations are generally less than horizontal peak accelerations during earth-quakes of magnitude less than 6. Data supporting this have been presented by the Applicant in Section 361.17.4 of the FSAR.
ROCK VERSUS SOIL SITES The SMA instrument is located on the abutment between Monticello Dams B and C. An examination of the topography of this region indicates that the instrument site is located a1.most at the top of a hillock that is partly man-made and partly natural. The SMA recording, in all likeli-hood, represents amplification of the motion of the hillock relative to motion that would be observed in the free-field at either a soil or rock site. Nonetheless, the Applicant has conservatively assumed that no such amplification has occurred in its use of the SMA recording of the A2 gust 27, 1978, earthquake to evaluate seismic source parameters. The Applicant maintains, however, that the accelerograph records are not' strictly repre-sentative of free-field motion, a distinction that Luco fails to draw.
In the free-field, and for short epicentral distances, peak ground accelerations are comparable for rock and soil sites (Campbell, 1981; Joyner and Boore,'1981).
RESPONSE SPECTRUM AT FOUNDATION LEVEL Luco states that it is not appropriate to compare the 5% and 7% SSE i spectra with the 2% M =4.5 spectrum to study the effects on equipment at the louer levels of the plant. This statement (which points to the lack of effect of structural damping for fcunlation equipment) would be true if a fixed base model were used in the analysis. Since foundation compliance was taken into account in the soil structure interaction analysis and the base mat response was amplified 10% relative to the input motion, it is appropriate to compare the 5% and 7% SSE spectra with the 2% M =4.5 spectrum for the effects on equipmant at the lower levels of the plant.
. The conclusions reached by Luco regarding the level of conservatism of response spectra are incorrect. The velocity amplification factor used by Luco (a value of 1.9) is in fact a mean-plus-one standard-deviation (mean + o) amplification factor, not a mean factor. This is apparent from comparisons with Regulatory Guide 1.60 spectral amplification factors and with the (mean + a) amplification factor deve-loped by the Appifcant for the velocity range (see Table 3). Thus Luco's pseudo-velocity spectral amplitude for 5% damping of 0.29 ft./sec. is a (mean + o) amplitude, not a mean amplitude.
Further documentation of the Applicant's methodology is provided as follows. The response spectra developed to represent vibratory ground motion from reservoir-induced earthquakes at Monticello Reservoir were derived following requirements indicated in Reg. Guide 1. 60, "Desiga Response Spectra for Seismic Design of Nuclear Power Plants." Specifically, Reg. Guide 1.60 staces that the standard design response spectrum procedure ". . .does not apply to sites which (1) are relativtly close to the epicenter of an expected earthquake or (2) which have physical charactcr-istics that could significantly affect the spectral combination of input motion. The Design P.esponse Spectra for such sites should be developed on a case-by-case basis." The Virgil C. Summer Nuclear Station would be close to the epicenter of any reservoir-induced seismicity of concern; hence site-specifie response spectra were developed to represent grcund motion for these events.
This procedure consisted of using response spectrum shapes for earthquake ground motions recorded at magnitudes, distances, and site.
conditions representative of reservoir-induced earthquakes at the Virgil C. Summer facility. These respense spectrum shapes, for magnitutes in the range of interest, were than compared to other available data to ensure their applicability.
The shapes for th*.;e spectra were ta. ken from the publication of Johnson and Traubenik (1978). These spactral shspes reprasent ground motions based on records obtained on rock sites for earthquakes with magnitudes (Q) between 4.7 and 6.5, with source-to-site distances of less than 20 kilometers. The derived spectra for 5 percent de.mping for g = 4.0, 4.5, and 5.3 events scaled to 0.15 g peak acceleration a:w
7-labeled "RIS" in Figure 1. These are mean + c spectra, based on the amplification factors reported by Johnson and Traubenik (1973). Use of the mean + o spectrum is consistent with the procedure defined as accep-table for standard design response spectra in Reg. Guide 1.60.
Also shown in Figure 1 are the Reg. Guide 1.60 spectrum for 5 percent damping, and the Virgil C. Summer Nuclear Station SSE spec-trum for 5 percent damping, both scaled to 0.15 g acceleration (the SSE ar.celeration at the facility). It la apparent that the derived RIS spectra generally match both the Virgil C. Summer spectrum and the RG 1.60 spectrum at the highest frequencies, but deviate at intermediate and low frequencies, the extent depending on both the earthquake magni-tude and the frequency of interest. The reason for this deviation is that broad-banded design spectra typically represent ground motions for earthquakes of magnitude around 6-1/2 (they are derived from recorded ground r9tions during seismic events with an average magnitude of 6-1/2).
The RIS spectra, on the other hand, logically reflect the lack of intermediate and low frequency energy which will be generated during magnitude 4.0 to 5.3 earthquakes with sm 11 source to site distances.
Two steps are required to generate site-specific spectra of the type shown in Figure 1, and in comparing these spectra to other results available it is convenient to break the comparison into these two steps.
The first step is the estimation of a peak velocity and a peak displace-ment which are consistent with the peak acceleration of the earthquake of interest. In the present application, the peak velocity-to-acceleration ratio is most critical because it determines the upper corner frequency of the spectrum. The peak displacement is not important in the present application because the Virgil C. Summer SSE spectrum greatly exceeds the RIS spectra in the displacement-controlled region (at lower frequencies).
To evaluate the peak velocities derived by Johnson and Traubenik (1978), we compare them to results derived from other studies. Table 2 v'-e'- -e-W v'w-'-- -"----*e g' 8P "" - * - ' " " ' irr "----r =w- '
@--"-* - - w'--' *'9"'m' *-=*u"* ' ' -' '
- 7 ri