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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML20150F2941988-05-31031 May 1988 Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20155K1391987-12-30030 December 1987 Final Rept MSIV 3-Way Dual Solenoid Valve Failures ML20235F0881987-12-17017 December 1987 Marked-up Draft Seismological Analysis of Bodega Head,Ca ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235G3041987-09-29029 September 1987 Partially Withheld, Preliminary Investigation of Enrico Fermi II Nuclear Power Plant ML20235B3121987-08-31031 August 1987 Comparison of Monticello & Brunswick Recirculation Pump Trip ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20237K8201987-08-26026 August 1987 TVA Employee Concerns Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-2, Review of Nuclear Safety Review Staff Non-Startup Items at Bellefonte ML20237K7691987-08-0606 August 1987 Rev 3 to TVA Employee Concern Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-1, Review of Nuclear Safety Review Staff Restart Items at Browns Ferry ML20236N2591987-07-31031 July 1987 Final Summary Rept of Human Factors Engineering Review for Byron & Braidwood Stations Spds ML20237K7981987-07-28028 July 1987 Rev 1 to TVA Employee Concerns Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-2, Review of Nuclear Safety Review Staff Non-Restart Items at Browns Ferry ML20237K8081987-07-23023 July 1987 Rev 0 to TVA Employee Concern Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-1, Review of Nuclear Safety Review Staff Startup Items at Bellefonte ML18093A1791987-06-19019 June 1987 Installation of Trip-A-Unit Protection Scheme Suppl Info Salem & Hope Creek Generating Stations. ML20214S3081987-05-28028 May 1987 Weekly Status Rept,Assessment of Embedment Plates Status as of 870528 ML20214T2941987-05-27027 May 1987 Comm Ed Final Summary Rept on Human Factors Review for Byron/Braidwood Stations Emergency Response Facilities ML20215K2441987-04-30030 April 1987 Assessment of Embedment Plates Status as of 870430, Weekly Status Rept 1999-07-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20141M0471991-12-31031 December 1991 Pge Annual Rept - 1991 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20085D2951991-08-21021 August 1991 Field Exercise Scenario,Aug 1991 ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20065R8731990-11-30030 November 1990 Monthly Operating Repts for Diablo Canyon Units 1 & 2 for Nov 1990 ML20058P5181990-05-11011 May 1990 Accident Sequence Precursor Program Event Analysis 323/87-005 R2, Loss of RHR Cooling Results in Reactor Vessel Bulk Boiling ML20058P5131990-04-0505 April 1990 Accident Sequence Precursor Program Event Analysis 424/PNO-IIT-90-02A, Loop,Diesel Generator Failure & 36 Min Interruption of SDC During Mid-Loop Operation ML18094B3211990-02-28028 February 1990 Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20058P5221990-02-0303 February 1990 Accident Sequence Precursor Program Event Analysis Loss of Reactor Protection Sys Bus B Causes Loss of Shutdown Cooling ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML18094B1471989-10-25025 October 1989 Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment 1999-07-12
[Table view] |
Text
- - - - - - -
geWatory Docket Filt Seismic Reflection Data from the Offshore Region Between Point Estero and Point Arguello:
Interpretive Data and Discussion .
-M.7g Contents i
I. Note on the structure of the East Boundary zone of the offshore Santa Maria Basin and the Hosgri fault, as observed on Western Geophysical Company line W74-12.
Introduction i Discussion Illustrations:
Figure 1 Plot of reflectors and other features on Western Geophysical Company line W74-12 (migrated).
2 Geologic section through the Diablo Canyon Power Plant Site and Adjacent I Area II. Note on Comparison of Fault Locations near the Diablo Canyon Site as Observed on Seismic Reflection Records from Different Surveys Introduction Discussion Table A. Seismic Reflection Lines Surveyed in the Offshore Area Between Estero Bay and Point San Luis Hlustrations:
Plate II(N) Map showing geology and structural relationships v/ithin the coastal and offshore region between Port San Luis and Lopez Point, California, i
annotated to show location of Western Geophysical Company seismic re- l flection lines, and location of the Figure 2 cross section from I, above.
Plate II Map showing geology and structural relationships within the coastal and I
offshore region between Point Conception and Arroyo Grande, California, annotated to show location of Western Geophysical Company scismic reflection lines.
8707290342 870721 PDR FOIA CONNORB7-214 PDR ggg gggg, g g gggg j~
l l
.. ; 1 is juxtaposed to the east against Acoustic Unit A3 s smic nturns, wM an Mu-preted to represent an upraised block of basement Acoustic Unit A3* * ^ ""
tic Unit A - quivalent rock. The boundary between the basal Acoustic Unit A E #t f 2 2 the offshore section and the inferred A2 -A3 n ar-s n sedon is MerpmW to upm-sent an east-dipping reverse fault. The inference that this boundary represents a fault contact is based on the apparent abrupt large vertical separation across it, and on the I
interpretation that the prominent diffractions present on the unmigrated line W74-12 j record are associated with a fault surface. The reverse fault contact is overlapped I
without break by the upper, Acoustic Unit Ay , part of the offshore basin section. ]
The part of the offshore Santa Maria Basin East Boundary zone that has been 1
affected by post-Pliocene fault movements is referred to as the Hosgri fault or' fault zone. The outer, main break along the post-Pliocene fault zone is indicated on the un-migrated line W74-12 record only by vague diffractions (since it is not well displayed in the acoustic frequency range used to produce the Western seismic lines), but it is clear- l 1
ly identifiable on most sparker seismic reflection lines. Likewise, the details of struc- l l
tural deformation adjacent to this fault are observable on sparker lines (e.g., Figures l 9A,12A,13A, and 14A of Appendix A to Appendix 2.5D to the Diablo FSAR), but not on ]
the Western Geophysical lines. Features appearing on the two versions of line W74-12 that are considered to be artifacts of the data recording and/or processing operations include two water-bottom multiples (on both unmigrated and migrated versions), diffrac-tionr from the Hosgri and the buried fault planes on the unmigrated record, and arcuate ,
patterns of alignments referred tobyWestern Geophysical 'as " velocity diffraction pat-terns" on the migrated record. These latter features are important because they could, i
if confused with true bedding reflections, be the cause of a misleading interpretation of the geologic structure. The velocity diffraction patterns appear as partly overlapping concentric arcuate lines that are centered about point sources located at intervals of about 16,000 feet, ground distance. They are most prominent near the ends of lines, in areas of data dropout, and in zones where slight velocity errors occur in the migra-tion process. These conditions mostly exist where Acoustic Unit A3" "*
Acoustic Unit A2parts of the section are represented in the record. In general, the i velocity diffraction patterns have a much lower degree of coherency than reflections i
I.
from bedded strata, e re -ca h a-m Amm m oma
The apparent geologic significance of the information contained in the line W74-12 record is that evidence of a pre-upper-Pliocene episode of compressional def-ormation is indicated there. This episode of tectonism probably corresponds to the comprest?onal deformation represented by the deep synclinal folding of the San Luis Range. The evidence from other, higher resolution records showing the upper several j thousand feet of the present Hosgri fault zone indicates that its post-mid-Pliocene history has been characterized by extensional and probably also by Ir.teral slip movements rather than the reverse movements shown at depth on line W74-12.
i
- 3. Earth Sciences Associates
II Note on Comparison of Fault Locations near the Diablu Canyon Site as Observed on Seismic Reflection Records from Different Surveys Introduction itecords and post-plot track charts from four different seismic reflection surveys of the offshore area near the Diablo Canyon site are available. The track charts and records from three of these surveys (USGS Kelez,1973; BBN,1973-74; Aquatronics, 1974) have been submitted as part of the documentation of geologic interpretations for the Diablo Canyon FSAR. Recordr and track charts for a survey conducted by Western i Geophysical Co. , Inc. In 1974 have also been used for the interpretations presented, but the records themselves, being proprietary, have not been subtitted directly.
Discussion The offshore area near Diablo Canyon has been intensively surveyed by seismic reflection techniques. Within the reach extending about 12 miles from Point San Luis north to the southerly part of Estero Bay, some 55 separate lines have been surveyed and are available for interpretation, as shown on the track chart base to Plate II(N) and in Table A.
These lines were all run in 1973 and 1974. The USGS Kelez and Western records were from parts of regional coastal surveys, while the BBN and Aquatronics surveys were concerned specifically with the area offshore from Diablo Canyon. The Western, BBN, and Aquatronics surveys were all navigationally controlled and post-plotted by Navigation Services, Inc. , using computer-reduced plots of continuous radio-transponder records of the survey ship's position. This system is said to be accurate to within a few feet when good station control is available, as it was in the Diablo area. )
l The original FSAR map of the position of faults in the Diablo offshore area was {
based on interpretation of records from the BBN, Aquatronics, and Kelez surveys. These I l
records were all obtained using sparker type energy sources, which varied in resolution l and penetration from the very high resolution .5 second penetration 3 Kj Aquatronics system to the intermediate resolution 1.5 second penetration 90 Kj Kelez system. The )
latter system achieved nearly 10,000 feet of penetration.
i l
t u m e a seme aeeee w me
Interpretation of these data resulted in a map showing four main breaks within the Hosgri fault zone. Directly opposite from Diablo Canyon, these breaks ranged from about 2.7 to 4.7 miles distance offshore. The outermost break was seen only in the deeper part of the section, and was mapped as a buried fault.
The records obtained from Western Geophysical were of the computer-processed deep seismic type. These records register to 5.0 seconds penetration, but are of much lower resolution than the sparker records. Because of the nature of the recording and the computer processing, which are designed to maximize the return of information from the deeper part of the section, the Western records show no usable information in the uppermost 500 to 1000 feet of the section. Consequently, faults of small displacement in the near surface part of the section are in many cases difficult or impossible to detect I in such records.
In the case of Western line W74-12, run nearly opposite Diablo Canyon, the chief feature that relates to faulting is a deeply buried steep reverse fault that corresponds to the outermost buried fault shown on Plate U(N). This fault truncates the easterly end of .j the deeper (Lower Pliocene-Miocene Acoustic Unit A ) part of the offshore Santa Maria 2 !
Basin section against Mesozoic basement and upraised Acoustic Uni! A r ek, but is I 2
overlapped by the shallow Upper Pliocene Acoustic Unit A section without break. Smaller breaks that extend to the surface at points closer to shore are only vaguely suggested in the Western records.
Line W74-12 was obtained both in standard format and also with computer migra-tion processing, the latter in order to determine whether significant errors of subsurface geometry and position could be present in the unprocessed record. It was found that the migration caused little change in the apparent position of the buried fault, and that it re-sulted in appreciable degradation of the nearer surface part of the record.
It is considered significant that the major fault break seen on line W74-12 is a deeply buried feature, and that it corresponds to a similar feature mapped at the same location using the three sets of sparker records available previously. These higher resolution records clearly show an unbroken Pliocene section several hundred feet thick extending across this fault, e re woo e gu m m m m /Ammmenomm
1
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Table A !
l Seismic Reflection Lines Surveyed i
in the Offshore Area Between Estero Bay and Point San Luis Kelez BBN Aquatronics Western 50 123 SS-1 W74-14 27 SS-2 SS-3 125 48 25-26 46 127 l 23 PB-1 W74-80 l 129 21 l 19 44 17 PB-2 131 15 42 13 PB-3 133 11 VV74-12 38 PB-4 135 9 2
137 4 6 36 8
10 139 12 14 16 18 20 34 141 W74-82 22 32 30 fierrRh federnlreme AeeeentaRee
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