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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] |
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, GAR 11 1333 4 MEMORANDUM FOR: Stephan J. Brocoum i Senior Reliability and Risk Analyst Reliability and Risk Assessment Branch Division of Safety Review & Oversight, NRR FROM: Ernst G. Zurflueh, Geophysicist Earth Sciences Branch Division of Radiation Programs &
Earth Sciences, RES
SUBJECT:
REVIEW 0F SEISMIC REFLECTION DATA FOR THE SOUTH TEXAS PROJECT i
! In accordance with your request, I have reviewed seismic reflection data for j '
the South Texas Project. The data and the applicant's interpretation are described in a report by Harding Lawson Associates (HLA) - issued on October l 30, 1985, and entitled " Interpretation of Geophysical Data, South Texas Project, Houston Lighting and Power."
! The description given in the HLA report seems to be correct in general, except l for minor differences in interpretation that could be postulated. A j significant conclusion of the report is that there are two faults, designated A
- and I, that come close to the surface. Although the report only lists the shallowest fault picks and does not describe the possible extent of these faults towards the surface, the applicant stated during a meeting on October 23, 1985 that, for the purposes of the FSAR, it will be assumed that those two faults extend to the surface.
It is my conclusion that the shallowest fault picks given by HLA for faults A i
and I are indeed correct. However, suggestions of even shallower faulting can be found on the seismic records, and the assumption that they may go through to the surface should definitely be used in considering the site. In this respect I would like to remark, although this is not the central theme of this rev!ew, that I cannot disagree with the assumption stated by the applicant in the October meeting, that a magnitude 4 earthquake is the maximum hazard that can be expected from movement on one of these faults. This is based on the observed seismicity of the gulf coast, which has produced only two earthquakes with a magnitude of 3.5.
- A second form of hazard that results from the presence of these faults is
- surface displacement. For instance, fault I crosses the area proposed for the l l cooling pond. However, given an approximate surface trace of the fault from l the seismic data, it should not be difficult to design the embankments of the !
l I
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l Stephan J. Brocoum 2 g ;J pond so that they will safely accommodate both anticipated seismic motion and a small vertical offset along the fault (if loss of coolant is critical). For comparison, several earth- or rockfill dams of considerable height have been designed and built to accommodate such hazards.
The next shallowest fault, J, appears to be capped at about 3850' as stated in the HLA report. There are indications of possible additional faults not shown on the HLA interpretations, but all of those faults would also be capped at considerable depth, if indeed they exist. Therefore, these possible additional faults do not pose a hazard to the plant.
Following are some more detailed comments on the analysis of the seismic data:
Fault A is most clearly seen on lines Jaecon 2M, 4M and GUS-A. The shallowest clear indication of faulting is at 0.16s or 490' depth as described in the HLA report. Indications of possible faulting can be found as shallow as 0.11s or at a depth of 310', and on the GUS-A line there are suggestions that the fault may continue upward towards the surface. Given the applicant's position that the fault is assumed to go through to the surface, this interpretation does not affect the status of the site.
Fault I is found on lines Jaecon 2M and Conoco 3. On line 2M clear fault indications are visible up to about 0.3s or 915' depth. No capping layers can be found, and possible changes in layering along the fault trace can be seen closer to the surface. Therefore, the assumption that fault I may continue to the surface seems reasonable.
A fault that is subparallel to fault I and about one mile north of it can also be seen on lines Jaecon 2M and Conoco 3. The fault may be designated fault I';
it has an ESE trend and extends to approximately 1.45s or 5450' depth. Line 2M shows that the fault is capped at this level, and the fault must be considered inactive. Conoco line 3 shows less definite information on capping of this fault, but this line does not have good shallow data.
Other faults can be inferred at various locations, but none of these possible faults are significant in that, if they exist, they all terminate at depths of several thousand feet.
In sumary, the HLA interpretation is essentially correct, and faults A and I are the only ones that may continue to the surface. The fault locations, shallowest picks and offsets identified by HLA are approximately correct; minor variations in interpretation are possible. Indications of possible faults in
r "t Y Stephan J. Brocoum 3 MAR 11 195 addition to those interpreted by HLA can be found, but these faults do not extend to the surface, are clearly inactive, and therefore pose no hazard to the site.
Ernst G. Zurflueh, Geophysicist Earth Sciences Branch Division of Radiation Programs &
Earth Sciences, RES cc: F. Congel J. Rosenstiel G. Giese-Koch P. Kadambi Distribution /R-2811:
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g;T 11 G 3 MEMORANDUM FOR: Stephan J. Erocoum Senior Reliability and Risk Analyst Reliability ed Risk Assessment Branch Division of Safety Review & Oversight, NRR FROM: Ernst G. Zurflueh,-Geophysicist Earth Sciences Branch Division of Radiation Programs &
Earth Sciences, RES
SUBJECT:
REVIEW 0F SEISMIC REFLECTION DATA FOR THE SOUTH TEXAS PROJECT In accordance with your request, I have reviewed seismic reflection data for the South Texas Project. The data and the applicant's interpretation are described in a report by Harding Lawson Associates (HLA) - issued on October 30, 1985, and entitled " Interpretation of Geophysical Data, South Texas Project, Houston Lighting and Power."
The description given in the tiLA report seems to be correct in general, except for minor differences in interpretation that could be postulated. A significant conclusion of the report is that there are two faults, designated A and I, that come close to the surface. Although the report only lists the shallowest fault picks and does not describe the possible extent of these faults towards the surface, the applicant stated during a meeting on October 23, 1985 that, for the purposes of the FSAR, it will be assumed that those two faults extend to the surface.
It is my conclusion that the shallowest fault picks given by HLA for faults A and I are indeed correct. However, suggestions of even shallower faulting can be found on the seismic records, and the assumption that they may go through to the surface should definitely be used in considering the site. In this respect I would like to remark, although this is not the central theme of this review, that I cannot disagree with the assumption stated by the applicant in the October meeting, that a magnitude 4 earthquake is the maximum hazard that can be expected from movement on one of these faults. This is based on the observed seismicity of the gulf coast, which has produced only two earthquakes with a magnitude of 3.5.
A second form of hazard that results from the presence of these faults is surface displacement. For instance, fault I crosses the area proposed for the cooling pond. However, given an approximate surface trace of the fault from .
the seismic data, it should not be difficult to design the embankments of the l l
l 1
Stephan J. Brocoum 2 g6 ;i i
pond so that they will safely accommodate both anticipated seismic motion and a small vertical offset along the fault (if loss of coolant is critical). For comparison, several earth- or rockfill dams of considerable height have been designed and built to accommodate such hazards.
The next shallowest fault, J, appears to be capped at about 3850' as stated in the HLA report. There are indications of possible additional faults not shown on the HLA interpretations, but all of those faults would also be capped at considerable depth, if indeed they exist. Therefore, these possible additional faults do not pose a hazard to the plant.
Following are some more detailed comments on the analysis of the seismic data:
Fault A is most clearly seen on lines Jaecon 2M, 4M and GUS-A. The shallowest l clear indication of faulting is at 0.16s or 490' depth as described.in the HLA report. Indications of possible faulting can be found as shallow aC 0.11s or at a depth of 310', and on the GUS-A line there are suggestions that the fault may continue upward towards the surface. Given the applicant's position that the fault is assumed to go through to the surface, this interpretation does not affect the status of the site.
Fault I is found on lines Jaecon 2M and Conoco 3. On line 2M clear fault indications are visible up to about 0.3s or 915' depth. No capping layers can be found, and possible changes in layering along the fault trace can be seen closer to the surface. Therefore, the assumption that fault I may continue to the surface seems reasonable.
A fault that is subparallel to fault I and about one mile north of it can also be seen on lines Jaecon 2M and Conoco 3. The fault may be designated fault I';
it has an ESE trend and extends to approximately 1.45s or 5450' depth. Line 2M shows that the fault is capped at this level, arid the fault must be considered ,
inactive. Conoco line 3 shows less definits information on capping of this fault, but this line does not have good shallow data.
Other faults can be inferred at various locations, but none of these possible "
faults are significant in that, if they exist, they all terminate at depths of several thousand feet. <
x In summary, the HLA interpretation is essentially correct, and faults A and I are the only ones that may continue to the surface. The fault locations, shallowest picks and offsets identified by HLA are approximately correct; minor variations in interpretation are possible. Indications of possible faults in
.w Stephan J. Brocoum 3 g,qg 1 7 jgg3 J
addition to those interpreted by HLA can be found, but these faults do not extend to the surface, are clearly inactive, and therefore pose no hazard to the site.
- Ernst G. Zurflueh, Geophysicist Earth Sciences Branch Division of Radiation Programs &
Earth Sciences, RES cc: F. Congel J. Rosenstiel G. Giese-Koch P. Kadambi Distribution /R-2811:
Circ /,Chron RMinogue Econti DCS/RQ3) Dross LBeratan ESB Sbj/Rd KGoller AMurphy EZurflueh i
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