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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196K5421999-03-22022 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 ML20117F2811996-02-29029 February 1996 Non-proprietary, VC Summer Residual Heat Removal Data Review & Monitoring Criteria Development ML20094C4691995-06-30030 June 1995 Seismic Activity Near VC Summer Nuclear Station, for Perid Period of Apr-June 1995 ML20094C4591995-03-31031 March 1995 Seismic Activity Near VC Summer Station, for Period of Jan-Mar 1995 ML20081J0901995-03-23023 March 1995 VC Summer Training Simulator Quadrennial Certification Rept 1992-1995 ML20064H4551994-03-0707 March 1994 Rev 2 to VC Summer Charging/Safety Injection Pump Runout Flow Evaluation L-93-036, Licensing Submittal to Support Replacement SG TS Changes for Vsns1993-10-31031 October 1993 Licensing Submittal to Support Replacement SG TS Changes for Vsns ML20062K6441993-04-30030 April 1993 VC Summer Spent Fuel Rack Criticality Analysis Considering Boraflex Shrinkage & Gaps ML20045F9561993-01-14014 January 1993 Non-Proprietary, VC Summer Nuclear Station SG TSP Interim Tube Plugging Criteria. Presentation Matls for Nrc/Sce&G/ Westinghouse Meeting on 930114 ML20090G9101992-02-29029 February 1992 Application for Approval to Incinerate Oil Contaminated W/ Very Low Levels of Licensed Radioactive Matl ML20082P2431991-07-31031 July 1991 Nuclear Physics Methodology for Reload Design ML20070R6561991-03-26026 March 1991 VC Summer Training Simulator Initial Certification Rept ML20062G1031990-10-31031 October 1990 Safety Evaluation for VC Summer Nuclear Station Upgrade to Westinghouse 17X17 Vantage+ Fuel ML20059D7021990-06-30030 June 1990 Technical Rept 90-02, Seismic Activity Near VC Summer Nuclear Station for Apr-June 1990 ML20005F4551990-01-0202 January 1990 Application for Approval to Incinerate Oil Contaminated W/ Very Low Levels of Licensed Radioactive Matls. ML19351A6741989-08-25025 August 1989 Cycle 5 Core Operating Limits Rept. ML20246C7731989-05-0202 May 1989 1988 Computer Mathematical Study of Thermal Plume in Monticello Reservoir Generated by VC Summer Station ML20154J5251988-05-31031 May 1988 Safety Evaluation for VC Summer Nuclear Station Transition to Westinghouse 17x17 Vantage 5 Fuel ML20148L3261987-12-31031 December 1987 Seismic Activity Near VC Summer Nuclear Station for Period Oct-Dec 1987 ML20214P2081987-03-0303 March 1987 Rev 1 to Crdr Summary Rept ML20135G6001985-09-16016 September 1985 Discussion of Proposed Control Logic Change for Steam Generator Power-Operated Relief Valves ML20135C0551985-09-0404 September 1985 Method of Analysis & Safe Shutdown Philosophy, 10CFR50, App R Compliance Review ML20115G4031985-04-15015 April 1985 Control Room Design Review Program Plan Rept for VC Summer Nuclear Station ML20115G4231985-04-15015 April 1985 Summary Rept on Reg Guide 1.97,Rev 3,Post-Accident Monitoring Sys ML20101S4381985-01-21021 January 1985 Rev 2 to Control of Heavy Loads at VC Summer Nuclear Station ML20091A8051984-04-30030 April 1984 Virgil Summer Deletion of Reactor Trip on Turbine Trip Below 50% Power,Apr 1984 ML20083Q0641984-04-0909 April 1984 Rev 1 to Licensing Rept on Spent Fuel Storage Racks ML20083H6381983-12-31031 December 1983 Draft Licensing Rept on High Density Spent Fuel Racks for VC Summer Nuclear Station ML20079P4051983-12-31031 December 1983 Licensing Rept on New Fuel Storage Racks ML20081M5301983-11-30030 November 1983 Seismic Confirmatory Program Equipment Margin Study, Final Rept ML20078R4761983-11-30030 November 1983 Draft Final Rept, Seismic Confirmatory Program - Equipment Margin Study ML20081H7281983-10-18018 October 1983 Draft Equipment Required for Cold Shutdown Aslb/Acrs Active Balance of Plant Equipment & Westinghouse Supplied Valves on Piping ML20071F1371983-03-31031 March 1983 Addendum to Experimental Investigation of Relative Response of Accelerograph Pad,Free Field & Structural Foundations at Virgil C Summer Nuclear Station ML20071F5071983-01-17017 January 1983 Divers Rept:Svc Water Intake Tunnel Insp ML20027C6011982-10-15015 October 1982 Independent Seismic Design Verification:Turbine Driven Portion Emergency Feedwater Sys, Final Rept.One Oversize Drawing Encl.Aperture Card Is Available in PDR ML20065G2581982-09-30030 September 1982 Independent Seismic Design Verification Turbine Driven Section Emergency Feedwater Sys,Vc Summer Nuclear Station, Draft Final Rept ML20063P0591982-09-30030 September 1982 Nonproprietary Version of Interim Power Operation Evaluation Rept ML20062D6601982-07-30030 July 1982 Pressurizer Relief Sys Piping & Support Evaluation Rept for VC Summer Nuclear Station,Sc Electric & Gas Co in Response to NUREG-0737,Item II.D.1 ML20054M4751982-07-0909 July 1982 Independent Seismic Design Verification,Turbine Driven Section Emergency Feedwater Sys, Status Rept ML20050B3541982-03-26026 March 1982 Revised Pages to Human Factors Engineering Evaluation & Improvement of VC Summer Nuclear Station Control Room,Phase 1. ML20041C6121982-02-23023 February 1982 to Fire Protection Evaluation ML20041C9171982-02-19019 February 1982 Nonproprietary Version of Revision 4 to Environ Qualification of Safety-Related Electrical Equipment Per NUREG-0588. ML20039F5591982-01-0707 January 1982 Floor Response Spectra from 1979 Monticello Reservoir Event Vs Original SSE Floor Spectra. ML20038A6621981-10-30030 October 1981 Control of Heavy Loads at Nuclear Power Plants. ML20009G0991981-07-31031 July 1981 Model Study of Reactor Containment Sump Flow Characteristics. ML20009G1511981-07-29029 July 1981 Corrected Pages to Control of Heavy Loads at Virgil C Summer Nuclear Station Unit 1, Revision 1 to 6-month Rept on NUREG-0612 ML20005A9841981-06-26026 June 1981 Control of Heavy Loads at Virgil C Summer Nuclear Station Unit 1. ML20126J8671981-03-18018 March 1981 Reactor Bldg Integrated Leak Rate Test (Type a) Final Technical Rept ML19351F4931981-01-31031 January 1981 Comparison of Mgt/Technical Resources to Regulatory Guidance. ML19341A1661981-01-31031 January 1981 Human Factors Engineering Evaluation & Improvement of VC Summer Nuclear Station Control Room,Phase 1. Prepared for Util 1999-03-22
[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] |
Text
_ __ ._ .
l TECHNICAL REPORT 87-4
- SEISMIC ACTIVITY NEAR THE V.C. SUMMER NUCLEAR STATION For the Period October - December 1987 ,
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! . Pradeep Taiwani Principal Investigator Department of Geological Sciences
!- University of South Carolina l} Columbia, S.C. 29208
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TECHNICAL REPORT 87-4 ,
SEISMIC ACTIVITY NEAR THE V.C. SUMMER NUCLEAR STATION FOR THE PERIOD OCTOBER-DECEMBER 1997 BY PRADEEP TALWANI PRINCIPAL INVESTIGATOR STEVE ACREE KEVIN SEVERANCE DEPARTMENT OF GEOLOGICAL SCIENCES UNIVERSITY OF SOUTH CAROLINA COLUMBIA, S.C. 29208 s
CONTRACT No. N449678
INTRODUCTION Analysis of the seismic activity near the V.C. Summer Nuclear Station in South Carolina between October 1 and December 31, 1987 is presented in this report. During this period a total of' twenty-four events were recorded, fourteen of which were located. The largest chock was of magnitude 2.0 (October 4 - 1830 UTC). Seventeen percent (4) of the earthquakes were of magnitudes greater than zero. Two shocks were of B quality and were located at depths of 0.3 and 0.4 km.
SEISMIC NETWORK Earthquakes recorded during this period were located using stations of the SCE&G and USGS/USC networks. The configuration of the stations utilized to locate the events in this report is shown in Figure 1 and station coordinates are listed in Appendix I.
DATA ANALYSIS Hypocentral locations of the events were determined using the computer program HYP071 (Lee and Lahr, 1972) and the velocity model listed in Appendix II. The event magnitude (M g) was determined from the signal duration at station JSC, using the following relation:
Mg = -1.83 + 2.04 Log D
- where D is the signal duration (seconds).
An estimate of daily energy release is determined using a
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3 simplified magnitude (Mg) energy (E) relation by Gutenberg and Richter (1956).
log 10 E = 11.8 + 1.5 M g .
j OBSERVED SEISMICITY FOR THE PERIOD OCTOBER-DECEMBER 1987 During this period twenty-four events were recorded and fourteen were located (see Appendix III). This level of activitf was slightly greater than that observed during the previous reporting period, but the overall decline in seismicity is continuing as shown in Figure 2. The largest event of this quarter (M g=1.0) occurred on October 4 at 1830 UTC. Four shocks (17%) were of magnitudes greater than zero.
The epicenters of earthquakes located during this quarter and during each month are presented in Flgure 3 and Figures 4, 5, and 6, respectively. Most epicenters are located on the western shore of the reservoir. Only two earthquake locations were of quality B or better. These events were located at depths of 0.3 km and 0.4 km, respectively.
CORRELATION OF RESERVOIR MATER LEVEL WITH SEISMIOITY Monticello Reservoir is a pumped storage facility. Any decrease in reservoir level associated with power generation is recovered when water is pumped back into the reservoir. There can be normal variations up to approximately five feet per day between the maximum and miniarm water level. We have been monitoring the water level to see if there is any correlation
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6 MONTICELLO EARTHOUAKES OCTOBER 1987 ,
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between the daily or seasonal changes in the reservoir level ,
. and the local seismicity. Water level was compared with seismicity j in Figure 7. The top two plots show the median water level and [
the change in water level each day. The number of events per day and the log of the energy released per day are shown in the lower two histograms which reveal four small earthquake swarms. These charts include both located and unlocated events around the reservoir. There is a possible correlation between the drop in l median water level and higher daily fluctuation on November 1 - 6 l (days 87.305 - 87.310) and seismicity.
1 CONCLUSIONS 1 The level of activity observed during the fourth quarter of J
{ 1987 was not significantly higher than that observed during the third quarter. No event was of a magnitude greater than 1.0.
Four of the twenty-four earthquakes were of magnitudes greater than 0.0. Depths of both quality B earthquake locations were J
1ess than 0.5 km.
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SosMARY OF 1987 SEISMICITY i
Seismic activity during 1987 (177 events) was not significantly greater than that recorded during 1986 (144 events)
. (Figure 2). The number of events per day rect.ded during 1987 is shown in Figure 8. The majority of the activity occurred during the f2rst quarter of the year. A total of 177 earthquakes were recorded, 147 of which were located (83%). The majority of the
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la earthquakes were concentrated beneath the center of the reservoir (Figure 9). Thirty-seven percent (65) of the located events were of B quality. Depths calculated for the B quality events all were within 3.5 km of the surface. The majority of the B quality earthquakes were located at depths between 1.5 and 2.0 km (Figure 10). ,
t The largest earthquake of the year was of magnitude Mg = 1.9 (January 13 - 0545 UTC). Only four events were of magnitudes greater than or equal to 1.0.
In summary, seismicity at Monticello Reservoir was of low magnitude during 1987. With the exception of earthquake awarms in January and February, the activity rate was low throughout the year.
REFERENCES Gutenberg, B. and Richter, C.F. (1956). Magnitude and energy of earthquakes, Ann. Geof. 9, p. 1-15.
Lee, W.H.K. and Lahr, J.C. (1972). A computer program for determining hypocenter, magnitude and first notion pattern of local earthquakes, Revisions of HYP071, U.S. Geolosteal Survey. Open-File Report, 100 pp.
13 i
MONTICELLO EARTHOUAKES JANUARY - DECEMBER 1987 ,
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- t 0 1 3 3 4 0 I 3 3 4 8 8 MAGNITUDE DEPTH (KM) 2 Figure 9. Seismic activity at Monticello Reservoir during 1987.
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! 8 18 28 38 48 58 68 I I I I I I
- 8.25 l 8.75 1
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) 3.88 JANUARY - DECEMBER 1987 N=65 Figure 10. Depth distribution of B quality events at Monticello Reservoir during 1987.
1
'. 15 APPENDIX I STATION LOCATIONS No. STN. LAT.*N LONG.*W 1 JSC 34+ 16.40' 41+ 15.60' 2 001 34+ 19.91' 81+ 17.74' 3 002 34* 11.58' 81+ 13.81' 4 005 34+ 16.05' 81+ 20.05' 5 007 34+ 22.23' 81+ 19.50' 7 010 34+ 20.18' 81+ 20.25'
16
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i APPENDIX II l
1 j MONTICELLO RESERVOIR VELOCITY MODEL Velocity Depth to top km/sec km 1.00 0.00 8.40 0.03 5.90 0.18 4.10 0.46 6.30 0.82 8.10 30.00 4
r - _ ___ ___ _ _ _ _________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
17 :
I APPENDIX III t
MONTICELLO EARTHQUAKES OCTOBER-DECEMBER 1987 MYP071 FORMAT column 1 Date.
Column 2 Origin time (UTC) h.m.sec.
Column 3 Latitude (N) degrees, min.
Column 4 Longitude (W) degrees, min.
Column 5 Depth (km).
Column 6 Local duration magnitude.
Column 7 No. of station readings used to locate event.
P and S arrivals from same stations are regarded as 2 readings.
Column 8 Largest azimuthal separation in degrees between stations.
Column 9 Epicentral distance in km to nearest station.
Column 10 error of time residuals in Root sec. mean RMS =squarg/NO, R where R, is the time residual for tke ith statiog Column 11 Standard error of the epicenter in km*.
- Column 12 Standard error of the focal depth in km*.
' Statistical interpretation of standard errors involves assump-tions which may not be met in earthquake locations. Therefore standard errors may not represent actual error limits.
If ERN or ERZ is blank, this means that it cannot be computed, because of insufficient data.
4
18 NONTICELLO EARTNQUAEES OCTOSER-D8CEMBER 1987 i
.- DATE ORIGIN LAT N LONO W DEPTH NAC N0 GAP DNIN RMS ERH ERZ QN 871003 1138 31.69 34-22.33 81-19.60 1.00 0.01 4 307 0.2 0.06 C1 i 871004 1830 18.45 34-18.08 81-19.89 2.03 0.95 10 210 3.9 0.06 0.5 1.3 C1 871008 853 24.20 34-21.25 81-20.72 1.02 -0.86 7 246 2.1 0.05 0.4 0.8 C1 l 871101 1621 55.99 34-19.27 81-19.09 0.41 0.82 10 163 2.4 0.06 0.2 0.5 81 871104 1123 54.22 34-20.71 81-19.31 0.40 -0.86 5 246 1.7 0.03 0.0 0.0 C1 871105 14 1 1.73 34-20.44 81-20.66 2.10 -0.60 5 257 0.8 0.02 0.5 0.4 C1 871105 14 6 52.81 34-20.57 81-20.77 2.14 -0.24 8 245 1.1 0.09 0.8 0.6 C1 871106 11 1 53.35 34-19.25 81-19.39 0.33 0.82 10 173 2.2 0.06 0.3 0.6 B1 871203 9 8 23.96 34-20.68 81-20.09 1.73 -0.86 7 183 1.0 0.02 0.1 0.2 C1 871214 2346 42.23 34-19.25 81-20.35 0.80 -0.24 5 243 1.7 0.08 2.0 3.2 C1 871216 051 38.68 34-29.28 81-20.35 1.00 -0.86 4 315 0.2 0.09 C1 871217 035 33.07 34-17.33 81-18.98 1.89 -0.24 5 125 2.9 0.07 1.0 3.6 C1 871223 047 49.49 34-19.59 81-21.60 0.14 -0.24 5 274 2.3 0.08 1.6 4.3 C1 871224 1345 47.47 34-20.28 81-21.76 1.81 -0.24 6 240 2.3 n.06 0.8 0.8 C1 l
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