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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 j TRlFUNAC REPORT i
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VIRGIL C. SUMMER NUCLEAR STATION 1
DOCKET No. 50/395 j SOUTH CAROLINA ELEC RIC & GAS COMPANY
- OCTOBER, 1981
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4 APPLICANT EVALUATION OF TRIFUNAC REPORT ON VIRGIL C. SUMMER NUCLEAR STATION SEISMICITY STUDIES INTRODUCTION Prof'essor M.D. Trifunac has written comments on seismic studies erformed in connection with the Virgil C. Summer Nuc1*.r Station, dated September, 1981. Trifunac's comments are based, in large part, on studies that ate not applicable to the site, or on a misunderstanding of the bases for the seismic studies submitted by the Applicant. In order to clarify these issues, the Applicant addresses the points that Tr funac rair.es.
INSTRUMENTAL VERSUS DESIGN ACCELERATION Trifunac's comments imply that design or effective acceleration (the acceleration at zero period in a spectral response diagram; i.e.,
the acceleration used to " anchor" the design spectrum) c&n be compared directly with the peak instrumental acceleration. For example , in his Figure 1, which is referred to repeatedly, the OBE and SSE vertical lines at 0.10g and 0.15g, respectively, are compared, or mingled with, .s ,
the peak " instrumental" acceleration. Because strong motion accelero-graphs may record high frequency ace *leration pulses that have no effect on structures, particularly for ground motions close to the causative fault, the two are not equivalent. The Diablo Caayon plant, as a recent example, uses 1.15g instrumental acceleration and 0.75g effective or design accele:.stion, which value was upheld after years of hearings. The Diablo Canyon ratio is 0.75/1.15 or 0.65. Trifunac generally has agreed with such concepts as can be inferred from statements in his scientific papers , e.g. : ... serious damage to structures comes predominantly from long shaking and not from one or two high-frequency, high-accelera-tion pulses which, because of their short duration, may represent only small, impulsive excitation." (from Trifunac, 1971). Also: " Fin-ally, it should be pointed out here that from the practical earthquake engineering point of view, high acceleration amplitudes should not l
l 1
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4
_2-secessarily be associated with a proportionally higher destructive po-tential. An extended daration of strong ground motion and high ac-celeration amplitudes characterize destructive earthquake shaking, schile one or several b53 h -frequency high-accleration peaks may, in fact, constitute only minor excitation because of the short duration involved and may lead to only moderate or small impulses when applied to struc-tural system." (from Trifunac, 1976).
ESTIMATES OF PEAK ACCELERATION Trifunac's commentary rests very largely on regression anelv es performed by himself, either individually or with associates. Work by other authors on regression analysis of strong motion data is ignored.
On the second page of the section entitled " General Considerations,"
Trifunac begins the first full paragraph with the following statement:
"The body of the strong motion data which is now available is not ade-quate to find the form of the distribution functions of the amplitudes ci!
peak recorded ground accelerations." Concerning this statement, there are two pertinent comments. First, in making this statement, Tri.enac renders his commentary unexaminable. Second, the statement is not correct. For example, the distribution of peak ground accelerations, for given levels of HM intensity, was studied by Murphy and O'Brien (1977). .
Attached is Figure 1 from Murphy and O'Brien, showing distributions of a set of 67 pairs (two horizontal components) of peak ground acelerations corresponding to MM intensity VI. These data are from a study by Trifu-nac and Brady (1975). Two distributions are shown: one about the arith-2 metic mean (82.46 cm/sec ) and the other about the geometric mean (51.98 cm/sec ) , The distribution about the geometric mean matches the normal distribution quite well, i.e., peak ground accelerations are approximately lognormally distributed. This refutes Trifunac's claim that the d.ita now available are not adequate to find the form of the distribution function.
Note that the arithmetic.mean exceeds the geometric mean by a substantial margin. This largely accounts for the difference between the Trifunac and Brady (1975) and Murphy and O'Brien (1977) int,ensity-acceleration cortelations. Trifunac and Brady computed arithmetic means
. _ _ ~ _ _ . _ _ _ _ __ _
4 -
3-of peak accelerations for each intensity level (their Table 3) and then fitted these means with a linear equation relating the log, eithm of peak acceleration with intensity (their equation 1). Because Trifunac and ,
Brady assumed normal cather than lognormal distribution o - peak accelera-tions, the results of their regression analysis are seriously biased, as shown by Murphy and O'Brien (1977).
In subsequent work, both with intensity and magnitude data, Trifunac (1976a, b) performed regressions using the logarithms of peak ground accelerations, but adopted an unorthodox regression scheme, the statis-tical-meaning of which cannot be ascertained. In his work on intensity, Trifunac (1976a) used the same data set as did Trifunac and Brady (1975). Comparison of the results of these studies shows that Trifuna:
(!!76a) obtained practically the same mean values as Tri.N ac and Brady (1975), indicating that he again usci arit.hmetic rather than geometric averaging. The results are not directly comparable because Trifunac (1976a) includes site geology as a regression parameter. In doing so, he reduces the population of his data cells considerably.
Tables 1, 2, and 3 compare various estimates of peak horizontal ground acceleratiin for Modified Mercalli intensities VI, VII, and VIII.
Estimates are given according to Murphy and O'Brien (1977; equation 9),
Trifunac anel Brady (1975; e quation 1 and Te.ble 3), and Trifunac (1976a; Table III). The means given in Figure ' of the Trifunac report corres-pond to Trifunac (1976a) for s = 2 (rock sites). These exceed the
~
expectations given by Murpay and O'Brien (1977) by f actors of about 2.
2 The s:celeration given by Trifunac for intensity VII (177.8 cm/sec ) l equals the expectation of Murphy and O'Brien (1977) for intensity VIII.
The results of regression analysis similarly performed by Trifunac (1976b) using magnitude data are likewise marred by erroneous statistical treatment. Such work should not be used in appraising peak ground accelerations for the Virgil C. Summer Nuclear Station.
As noted above, a further difficulty in applying Figure 1 of Tri-funac in assessing design accelerations is that the difference between
-w e-- ,- - ---y w y w. -,y y v --,-~w- ----r - s- w - - - - - - ,
peak instrumental acceleration and design acceleration is overlooked. If adjusted for statistical error and far the difference between design and free-field instrument accele.ation. Trifunac's Figure 1 would indicate enat the SSE design acceleration is appropriate for ground shaking of MM intensity VII, or ="und motion due to an earthquake of magnitude 5 to 5.5 occurring in the immediate vicinity of the site.
In summary, the methodology used by Trifunac in estimating peak accelerations for given intensities and magnitudes leads to over-estimation of acceleration. Thus conclusions regarding the inadequacy of -
the SSE are inappropriate.
VERfICAL ACCELERATIONS Trift.nac suggests that the ratio of peak vertical accelerations to peak horizontal accelerations should be close to 1, and cites a
" number of recent recordings" to substantiate this view. These record-ings are apparently from magnitudes greater than 6. For smaller mag-nitudes in the range 4 to 6, the vertical-to'-horizontal acceleration ratio is closer to 0.5. This was documented by the Applicant in section 361 of the FSAR, Figures 361.17.4-20 through 361.17.4-23. The data from the Monticello accelerograph support this: The ratio for the 27 August 1978 earthquake, computed as the vertical peak divided by the average of the two horizontal peaks, is 0.34.
SOIL AMPLIFICATION Trifunac questions the Applicant's and NRC staff
- a conclusion that the August 27, 1978, earthquake recording on a soil site represents an amplification of wave motion through the soil. To support his argument he cites Trifunac and Brady (1975) to assert that " average of peak accelerations recorded on rock is higher than the average of acceleration recorded on soil and alluvium." More recent -studies, by Campbell (1981) and Joyner and Boore (1981), which include c >nsideration of near-field records, conclude that level of accelerations recorded on soil and rock are similar. The accelerations discussed above refer to free-field accelerations. The potential that the SMA recording represents on amplified response of a natural hill-like structure is discussed below.
The SMA instrument ir 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 almost at the top of a hillock that is partly man-made and partly natural. The surrounding region slopes down rapidly around the area formed by the dam crests and the abutment area with the surface elevation of 300' in the region of epicenter.
Thus, the SMA recording, in all liklihood, does represent an amplifica-tion of the hillock responding to the free field acceleration. Nonethe-less, the Applican; has conservatively assumed that no such amplification has occurred in its use of the SMA recording of the August 27, 1978, earthquake to evaluate earthquake source parameters.
EARTHQUAKE STRESS DROPS Trifunac states that stress drop estimates in California are highly variable; this is certainly true when these estimates are made in the frequency domain from long period level and corner frequency obser-vations. However, when stress drop estimates are'made from time domain data (specifically, observations of n ), they are quite stable and invariant for California earthquakes (Hanks and McGuire, 1981). The latter is the methodology used in deriving an appropriate stress drop value 'ot charact'rize reservoir-induced eart.iquakes at Monticello.
The comparisons of pe ak-ac cele ratio n-t o-s t res s-d '. op ratio by Trifunac is invalid. The stress drops used by the Applicant are derived from a ; those cited in Trifunac's references are determined by spectral methods, which are often one-tenth the value determined by a for the same earthquake (Hanks and McGuire, 1981). Thus the dis-crepancy found by Trifunac is easily explained by the factor of ten difference in stress drop estimates by various metheds, and does not imply that the Applicant's peak a::celeration estimates are low.
PROBABILITY STUDIES .
Trifunac finds, in his Tables 1 and 2, return periods for the SSE that are substantially different from those presented by the Appli-cant in Tables 361.19-1 and 351.19-2. The Applicant's analysis was based
I on several sets of seiscogenic zones: the enas used for the FSAR are available in that document and are shown in Figure 2, and the zones proposed by Algermissen and Perkins (1976) are reproduced in Figure 3.
Both allow tectonic events to occur at the site.
There are several reasons why Trifunac finds larger probabilities than those of the Applicant. First, he uses the recurrence curve of Chinnery (1979) for the southeastern United States. This is a combina-tion of Bollinger's (1973) South Carolina-Georgia seismic zone and Southern Appalachian seismic zone Since the latter has more historical seismicity than the former (see Figure 4), combining the two increases the perceived hazard for any site within the former zone (such as the Virgil C. Summer Nuclear Plant). No ' vestigator, to the Applicant's knowledge, has proposed combining thes .,nes for the purposes of deter-mining seismic hazard; Chinnery's (1979) investigation had the purpose of comparing general saismicity characteristics in different parts of the eastern United States, not calculating seismic hazard at sites.
The second difference is in the attenuation curves that ne nad to estimate ground motion characteristics. The Applicant has used, for Modiffed Mercalli (HM) intansity, an equation based on MM intensity observed during the 1886 Charleston earthquake, which is the most exten-sive data base available for the southeastern United States. For accel-eration an equation developed by Nuttli for the central United States was used. These attenuation functions are described in section 361.19-4 of the FSAR, and are the most site-specific, least interpretive attenuation equations available. Those used by Trifunac are described in NUREG/CR-689 and estimate spectral velocities as a function of earthquake inten-sity and distance. While this is a novel approach, there are no eastern U.S. earthquake data with which to judge its appropriateness, nor has this methodology received substantial peer review. Thus the uae of this equation to make probability calculations and statements r 'ts in highly tenuous conclusions that should be viewed with caution.
STRUCTURAL DAMPING The primary reason for using 7 percent, instead of 2 percent, damping is due to the fact that 7 percent is more realistic than 2
percent during a 0.22g near-field earthquake for structures originally designed for a 0.15g far-field earthquake, and not solely because it is permitted by the Regulatory Guide. The 7 percent damping was verified by test data that were discussed extensively in the Diablo Canyon ALAB hearings. The decision of the same ALAB hearings acknowledged that 7 percent damping is appropriate.
The effect of structural damping used in the analysis is to control the amplified motion from the input to the top of the building such that the amplification factor matches the recorded data in general. In the reevaluation of the Virgil C. Summer St.atiot design, the resulting amplification factor based on 7 percent damping was 3.0, which is gen-erally higher than recorded amplifica'; ions. In the original design with 2 percent damping, an amplification of 4.75 was obtained. This large amplification factor is totall uccealistic. The value-of 7 percent was used to provide calculation of realistic, but still conservative, struc-tural response. .
- ~'
EFFECTIVE ACCELERATION Trifunac disputes the SER statement that "the finite size of large strurrures would attenuate high frequencies" claiming that it has not been demonstrated so far, and that it w sa not reduce the high frequency input motions significantly and systematically to wartant its use in design calculations. The reference cited for this claim (Feng, et al.,
1982) is unavailable to the Applicant. However, in a recent study.
Campbell (1981) reports comparisons between small building / free-field recordings (115 components) at ground level, and recordings obtained in the lowest basement of large buildings (40 components). Campbell found that peak acceleration recorded in the basement of large buildings was on the 24 percent lower than that recorded at ground level. This result was found to be significant at the 90 percent confidence level.
_g_
REFERENCES Algermissen, S.T., and D.M. Perkins (1976), "A Probabilistic Estimate of Maximum Acceleration in Rock in the Contiguous United States,"
USGS Open-File Report 76-416, 45 pp.
Bollinger, G.A. (1973), " Seismicity and Crustal Uplift in the South- ,
I eastern United States," Ae rican Journal of Science, Cooper vol.
273-A, pp. 39C-408.
J Campbell, Kenneth W. (1981), "Near-Source A,ttenuation of Peak Horizontal Acceleration," submitted to the Bulletin of the Seismological Society of America.
(1981), "Near-source Attenuation of Peak Horizontal Acceleration, submitted to the Bulletin of the Seismological Society of America.
Chinnery, M.A. (1979), "A Comparison of Seismicity of Three Regions of cl.: .Mstern United States," Bulletin of the Seismological Society of Ameri:a, vol. 69, pp. 757-772.
Hanks, T.C., and R.K. McGuire (1981), "The Characte. of High Frequency Strong Ground Motion," Bulletin of the Seismological Society of America, vol. 71, Dec. (in press).
Joyner, William B. , and David M. Boore (1981), " Peak Horizontal Accel-eration and Velocity from Strong Motion Records, including Records from the 1979 Imperial ValJ ay, California, Earthquake," submitted to the Bulletin of the Seismological Society of America.
Murphy , J.R. , and O' Brien , L.J. (1977), "The Correlation of Peak Ground Acceleration with Seismic . Intensity and Other Physical Parameters."
Bulletin of the Seismological Society of America, vol. 67, pp.
877-915.
Trifunac, M.D. (1972), " Stress Estimates for the San Fernando, Cali-
!ornia, Earthquake of February 9, 1971: Main Event and Thirteen Aftershocks," Bulletin of the Seismological Society of America, vol.
62, pp. 721-750.
(1976a), "A Note on the Range of Peak Amplitudes of Recorded Accelerations, Velocities and Displacements with respect to the Modified Mercalli Intensity, Zarthquaka Notes, vol. 47, no. 2, pp.
9-24.
(1976b), " Preliminary Analysis of the Peaks of Strong Earthquake Ground Motion - Dependence of Peaks on Earthquake Magnitude, Epi ,
central Distance and the Recording Site Conditions," Bulletin of the Seismological Society of America, vol. 66, pp. 189-219.
Trifunac, M.D., and A.C. Brady (1975), "On the Correlation of Seismic Intensity Scales with the Peaks of Recorded Strong Ground Motion,"
Bulletin of the Seismological Society of America, v. 65, pp.
139-162.
TABLE 1 PEAK HORIZONTAL GROUND ACCELERATION ESTIMATES FOR MM INTENSITY VI Accelerations for -/+
Assumed Expected 1 standard distribution acceleragion deviatign Author function (cm/sec ) (cm/sec )
M trphy & 0'Brien (1977): Eq. (9) Lognormal 56.23 24.55/128.78 Trifunac & Brady (1975): Eq. (1) Normal 65.16 Table 3 S2.46 4.79/160.13 i
4 Trifunac (1976a)
S=0 (alluvium) ? 46.77 S=1 (intermediate) 66.07 S=2 (rock) 91.02 4
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TABLE 2 PEAK HORIZONTAL GROUND ACCELERATION ESTIMATES FOR MM INTENSITY VII Accelerations for -/+
Assumed Expected I standard distribution acceleragion deviatign Author function (cm/sec ) (cm/see )
Murphy & O'Brien '
(1977): Eq. (9) Lognormal 100.00 43.67/229.09 Trifunac & Brady (1975): Eq. (1) Normal 130.02 Table 3 131.29 69.99/192.59 Trifunac (1976a)
S=0 (alluvium) ? 93.33 .
S=1 (intermediate) 128.82 E=? (rock) 177.83 1
4
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PEAK HORIZONTAL GROUND ACCELERATION ESTIMATES FOR MM INTENSITY VIII Accelerations for -/+
Assumed Expected 1 standard distribution acceleragion deviatiga Author function (em/sse ) (cm/sec )
Eurphy & 0'Brien (1977): Eq. (9) Iugnormal 177.83 77.65/407.23 Trifunac & Brady (1975): Eq. (1) Normal 259.42 Table 3 166.67 82.61/250.73 Trifunac (1976a)
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S=2 (rock) 346.74 9
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