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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
[Table view] |
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O APPENDIX X EFFECTS OF NEAR-FIELD EARTIIQUAKE GROUND MOTION ON STRUCTURE AND EQUIPIENT DESIGN 8103120 3 M Re s on
, t9Sl
EFFECTS OF NEAR-FIELD EARTHQUAKE CROUND MOTION ON STRUCTURE AND EQUIPMENT DESIGN The extensive body of site-specific observational evidence pre-sented elsewhere in this report shows that in this highly heterogeneous envi ronment there is a_ limit of approximately one kilometer to the maximum fault dimension for any single -earthquake occurrence. This corresponds to a limiting magnitude of ML = 4.0. The calculations of ground motion presented in this Appendix were carried out both for this limiting magnitude event and for a larger assumed magnitude of ML =.
4.5 which provides a conservative assessment of ground motion effects cnt the -Virgil C. Summer "uclear Station.
The ML = 4.0, stress drop of 25 bars, and R = 2.0 km case gives a zero period acceleration (ZPA) value of 0.14 g, which is less than the Virgil C. Summer SSE ZPA value of 0.15g' for structures on rock.
Therefore, this maximum induced seismic event has no ef fect on struc-
. tures or equipment.
The ML = 4.5, stress drop of 25 bars, and R = 2.0 km case gives .
a ZPA value 'of 0.22 g, which is . higher than ' the Virgil C. Summer SSE 4 ZPA values $f 0.15- g for structures on rock and is lower th'an the SSE
-l ;ZPA value of 0.25 g for structures on soil. In the original seismic analysis, a very conservative 2 percent- damping value was used. NRC Regulatory Guide 1.61 allows a 5 percent damping value for' prestressed
~
concrete and 7 percent damping value for reinforced concrete structures in:the SSE; analysis. Thus,.the Virgil-C. Summer (0.15 g) SSE spectrum at 2: percent damping is compared with the ML = 4.5 (mean value plus' one standard deviation) event' spectra at 5 percent-and 7 percent i
damping in Figure-1.. As shown in'the comparison, the.ML = 4.5 event
- exceeds the Virgil C. Summer (0.15 g) SSE spectrum only in the i
. frequency region higher-than about 9 Hertz..-The dominant frequencies
- of all Seismic Category 1 structures are lower than 9 Hertz except for
,.. the-interior concrete structures of the-Reactor Building.- However,
, :since.the original seismic analysis used.the1 artificial time history.
- . (ATH),as? input and the the ATH's
- response spectrum'always exceeds or 1
een 3 _ _ _ m
e .
j' 4' l equals the Virgil C. Su=cer SSE spectrum, additional conservatism of
. ,- the ATH method can be used to justify the original seismic design of f
the interior concrete structures and the equipment contained therein.
-To remove the conservatism of the ATH method, the Oroville accelerograms were ustd in statistical studies. Four horizontal
. components of two ML = 4.0 aftershocks of the 1975 Oroville, California earthquake, recorded at rock sites, were modified to match the 5 percent damping target spectrum in the mean a's shown in Figures 2 to 5. Four Oroville af tershocks were extended into 36 components by adjusting the time increment, which achieves the effect of shifting the frequency-content of the accelerogram (Tsai, 1969). The original Oroville aftershock accelerograms have time increments of 0.005 second.
Each component was extended into 9 components by using time increments 4 of 0'.0038, 0.0041, 0.0044, 0.0047, 0.005, 0.0053, 0.0056, 0.0059, and e
q 0.0062 second. The 36 accelerograms were used as input to the Reactor N Building seismic analysis. - The mean values -of the 2 percent floor
, response spectra were compared with the original Virgil C. Summer floor
. response spectra used in design (Figures 6'to 20). As shown in the
comparison, the Virgil C. Summer spectra envelop the ML = 4.5 sean v
7- value spectra in_the resonance peak region and almost all other
.n frequency regions. Thus, it is concluded that the original Virgil C.
]{
Summer seismic- design is not exceeded by this ML = 4.5 event.
Some NSSS equipment are designed to floor response. spectra generated at 5 percent structural damping, for loading combinations containing SSE'and LOCA. This set of. Virgil C. Summer floor response
-spectra.is also~ compared with the ML = 4.5 mean value floor response
~
' spectra (Figures - 21i to 35). As shown in the comparison, the original Virgil C.' Summer _ seismic design is not' exceeded - by the ML 4.5 event
~ and continues to be valid'and'a'dequate; W As shown in Figures 6 through 35, the Virgil C. Summer SSE floor response. spectra envelop the M.
g =4.5 event: floor response spectra in the 1 a' '
~
resonance peak' region and in almost all other frequency regions.. The
~
A 4
4
%) . ~
X-2i Revision 1~
,7 March,:1981 x - +
b- ,
only exception is in the frequency region of 20 to 30 Hz, where the Virgil C. Summer response spectra are exceeded by a very small amount. For piping systems and other multiple degree of freedom systems, the frequencies of dominant modes are always lower than 20 Hz. Higher modes have smaller participation factors. Thus, the combined stresses of multiple modes due to the Virgil C. Summer response spectra will always be higher than those due to the Mg=4.5 event spectra. There are a few relatively rigid systems and equipment with frequencies of fundamental modes in the region of 20 to 30 Hz.
These systems and equipment all have high moments of inertia and large section sizes in ord'er to reach high frequencies, and are originally over-designed. 1 Therefore, the slight exceedance of the Virgil C. Summer floor response spectra in the frequency region of 20 to 30 Hz will not cause any overstress problems.
To demonstrate the additional margins available in systems design, the seismic stress, design-stress, and allowable stress are shown in Table 1 for the emergency feedwater and residual heat removal systems. The margins between the required input and the actual input values of equipment seismic qualification are also shown in Table 1. As shown in the table, ample margins are availabic in the original design to accommodate the reservoir induced seismicity.
Revision 1
~
X - 2a March, 1981-
..--a -
.~
Y , . '.
4 TABLE 1 V. C. SUMMER NUCLEAR PLANT SEISMIC BUILT-IN DESIGN MARGINS DESIGN STRESSES ALLOWABLE STRESSES COMPONENT OR REQUIRED SEISMIC STR'ESS OR ACTUAL INPUT G VALUES INPUT G VALUES EMERGENCY FEE 0 WATER 19,000 PSI 12,000 PSI 36,000 PSI l PIPING (T0 DATE)
,000 PSI 11,6@ N M,M N LA (T0 DATE)
TURBINE DRIVEN .36G/.36G/.21G
.5G/.5G/.4G EFW TURBINE TEST 1 TURBINE DRIVEN EFW .36G/.36G/.21G .48G/.48G/0.4G PUMP APPURTENANCES TEST RHR PUMP & MOTOR NL S SAFETY INJECTION .29G/.24G/.19G
- CHARGING PUMP ANALYSIS 3.0G/3.0G/2.0G
Revision 1 March, 1981
REFERENCES Tsai, N.C., 1969. Transforraation of Time Axes of Accelerograms. ASCE Proceedings, Engineering Mechanics Division, vol. 95, no. EM3.
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