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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] Category:UTILITY TO NRC
MONTHYEARELV-02056, Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam1990-09-0606 September 1990 Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam ELV-01599, Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator1990-09-0404 September 1990 Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator ELV-02059, Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B1990-08-30030 August 1990 Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B ELV-01956, Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request1990-08-30030 August 1990 Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request ELV-02050, Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required1990-08-30030 August 1990 Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required ELV-02028, Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)1990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d) ELV-02022, Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld1990-08-22022 August 1990 Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld ELV-02027, Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively1990-08-20020 August 1990 Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively ELV-01973, Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical1990-08-14014 August 1990 Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical ELV-01918, Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion1990-08-0303 August 1990 Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion ELV-01943, Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned1990-07-27027 July 1990 Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned ELV-01949, Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable1990-07-26026 July 1990 Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable ELV-01500, Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities ML20055H6441990-07-23023 July 1990 Submits Summary of Snubber Types & Sample Plans for Functional Testing to Be Performed During Sept 1990 Outage ML20044B0311990-07-13013 July 1990 Forwards Vogtle Electric Generating Plant Unit 1 Reactor Containment Bldg 1990 Integrated Leakage Rate Test Final Rept. ML20044B1541990-07-12012 July 1990 Responds to NRC 900612 Ltr Re Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Eop Step Deviation Documents to Be Upgraded,Adding More Justification & Temporary Change Issued to Correct EOP Deficiencies ELV-01867, Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered1990-07-12012 July 1990 Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered ML20055F1651990-07-0909 July 1990 Forwards Comments Re NUREG-1410 ELV-01858, Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete1990-07-0606 July 1990 Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete ML20044A8851990-07-0606 July 1990 Forwards Response to NRC Question on Steam Generator Level Instrumentation Setpoints,Per Revised Instrument Line Tap Locations.Tap Location Will Be Changed from Above Transition Cone to Below Transition Cone ELV-01834, Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21)1990-06-28028 June 1990 Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21) ML20044A2791990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Indicating Status of Each Generic Safety Issue Encl ML20043J0171990-06-22022 June 1990 Discusses Corrective Actions for Plant Site Area Emergency, Per 900514 Ltr.Jacket Water High Temp Switches Calibr for Diesel Generators,Using Revised Calibr Procedure ML20043H3061990-06-15015 June 1990 Forwards Rev 3 to ISI-P-014, Inservice Insp Program, for Review & Approval,Per Tech Spec 4.0.5 Re Surveillance Requirements.Rev Includes Withdrawal of Relief Requests RR-45,47,48 & 54 ML20043G2071990-06-12012 June 1990 Forwards Amend 18 to Physical Security & Contingency Plan. Amend Withheld (Ref 10CFR73.21) ML20043G1021990-06-0606 June 1990 Requests Temporary Waiver of Compliance from Requirements of Action Statement 27 of Tech Spec 3.3.2 for Period of 6 H When Two Operating Control Room Emergency Filtration Sys Trains Shut Down for Required Testing ML20043E6901990-06-0505 June 1990 Forwards Rev 12 to Emergency Plan & Detailed Description & Justification of Changes.W/O Rev ML20043G7651990-06-0505 June 1990 Forwards Rev 13 to Emergency Plan & Description & Justification of Changes ML20043B5991990-05-25025 May 1990 Forwards Scope & Objectives Re 1990 Annual Emergency Preparedness Exercise to Be Conducted on 900801 ML20043B5981990-05-24024 May 1990 Responds to Violations Noted in Insp Rept 50-424/90-05 on 900217-0330.Corrective Actions:Locked Valve Procedure Revised to Eliminate Utilization of Hold Tag on Valves Required by Tech Specs to Be Secured in Position ML20043B6291990-05-22022 May 1990 Forwards Rev 5 to ISI-P-008, Inservice Testing Program, Per Tech Specs 4.0.5 Re Surveillance Requirements & Generic Ltr 89-04 ML20043B6351990-05-22022 May 1990 Forwards Rev 2 to ISI-P-016, Inservice Testing Program, Per Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. ML20042H0601990-05-14014 May 1990 Forwards Summary of Corrective Actions for 900320 Site Area Emergency Due to Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability.Truck Driver Disciplined for Lack of Attention ML20042G7301990-05-11011 May 1990 Forwards Revised Pages for May 1989,Jan & Mar 1990 Monthly Operating Repts for Vogtle Electric Generating Plant,Units 1 & 2.Revs Necessary Due to Errors Discovered in Ref Repts ML20042E2911990-04-18018 April 1990 Forwards Amend 17 to Security Plan.Amend Withheld (Ref 10CFR2.790) ML20042E7481990-04-0909 April 1990 Requests Approval to Return Facility to Mode 2 & Subsequent Power Operation,Per 900320 Event Re Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability ML20012E9001990-03-28028 March 1990 Provides Supplemental Response to Station Blackout Rule,Per NUMARC 900104 Request.Mods & Associated Procedure Changes Identified in Sections B & C W/Exception of Mods to Seals Will Be Completed 1 Yr from Acceptance of Analysis ML20012E8581990-03-28028 March 1990 Suppls Response to NRC Bulletin 88-010,Suppl 1 Re Traceability Reviews on Molded Case Circuit Breakers Installed in safety-related Applications.All Breakers Procured & Installed in Class 1E Equipment Reviewed ML20012E9761990-03-27027 March 1990 Requests Withdrawal of Inservice Insp Relief Requests RR-45, RR-47,RR-48 & Conditional Withdrawal of RR-54 Based on Reasons Discussed in Encl,Per 900206 Conference Call ML20012D8561990-03-22022 March 1990 Submits Special Rept 1-90-02 Re Number of Steam Generator Tubes Plugged During 1R2.One of Four Tubes Exceeded Plugging Limit & Required Plugging.Remaining Three Tubes Plugged as Precautionary Measure.No Defective Tubes Detected ML20012D6641990-03-22022 March 1990 Provides Followup Written Request for Waiver of Compliance to Make Tech Spec 3.04 Inapplicable to Tech Spec 3.8.1.2 to Permit Entry Into Mode 5 W/Operability of Diesel Generator a & Associated Load Sequencer Unverified ML20012D3681990-03-19019 March 1990 Forwards Proprietary & Nonproprietary Suppl 2 to WCAP-12218 & WCAP-12219, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Vogtle Units 1 & 2, Per 900226 Request.Proprietary Rept Withheld (Ref 10CFR2.790) ML20012D3401990-03-19019 March 1990 Submits Response to 891121 Request for Addl Info Re Settlement Monitoring Program.Current Surveying Procedures Used by Plant to Monitor Settlement of Major Structures Outlined in Procedure 84301-C.W/41 Oversize Drawings ML20012D6631990-03-15015 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in Lwrs.Overfill Protection Sys Sufficiently Separate from Control Portion of Main Feedwater Control Sys & Not Powered from Same Source ML20012C4681990-03-0606 March 1990 Provides Summary Rept of Property Damage Insurance Levels, Per 10CFR50.54(w)(1) ML20012B2891990-03-0606 March 1990 Forwards Plant Pipe Break Isometrics,Vols 1 & 2 & Advises That Encl Figures Have Been Revised to Be Consistent W/Pipe Analysis in Effect at Time That Unit 2 Received Ol,Including Revs Through 890930.W/309 Oversize Figures ML20012B2421990-03-0606 March 1990 Forwards Cycle 3 Radial Peaking Factor Limit Rept & Elevation Dependent Peaking Factor Vs Core Height Graph ML20011F5291990-02-26026 February 1990 Withdraws 881107 Proposed Amend to Tech Spec 3.8.1.1, Revising Action Requirements for Inoperable Diesel Generator to Clarify Acceptability of Air Roll Tests on Remaining Operable Diesel Generator ML20011F5261990-02-26026 February 1990 Forwards 1989 Annual Rept - Part 1. Part 2 Will Be Submitted by 900501 ML20011E8911990-02-12012 February 1990 Advises That Hh Butterworth No Longer Employed by Util 1990-09-06
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I November 12, 1982 Director of Nuclear Reactor Regulation Attention: Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Comission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NWBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT POSTULATED MILLETT FAULT STUDY
Dear Mr. Eisenhut:
As requested at the.0ctober 29, 1982 Postulated Millett Fault Study meeting with members of the NRC staff in Bethesda, Georgia Power Company is for-
- i. warding the seismic reflection lines from the Savannah River Plant. Please l find enclosed the replay sections for the refraction lines in the vicinity l of the Postulated Millett Fault, the time cross sections, the top triassic, saprolite, and crystalline rock countour. maps, and the velocity gradient map. Also enclosed are five copies of a report issued as part of the re-l~ flection studies. All this infonnation is available through the Oak Ridge, Tennessee Repository.
Should you have any questions, please inquire.
p ncere i
- l. -
. Doug Dut n Rfn Vice President
- j. Generating Plant Projects DED/ JAB /sw xc: R. A. Thomas G. S. Grainger J. A. Bailey N
- 0. Batum E. L. Doolittle D. O, Foster J. M. Grant
- 1. C. R icClure G. F. Trowbridge 9
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[jh g., UNITED STATES jf . ATOMIC ENERGY COMMISSION
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WASHINGTON, D.C. 20545
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Qhe;N jus a 1g73 Richard C. DeYoung, Assistant Director for Pk 's, ALVIN W. VOCTLE UNITS 1, 2, 3, & 4 PLANT NAME: Alvin W. Vogtle LICENSING STAGE: CP
- l. , DOCKET NUMBERS: 50-424 427
. RESPONSIBLE BRANCH: PUR Branch #2 REQUESTED COMPLETION DATE: 6/8/73 APPLICM;TS RESPONSE DATE NECESSARY FOR NEXT ACTION PLANNED ON PROJECT: NA
.1 DESCRIPTION OF RESPONSE: Answar.to Questions 8
REVIEW STATUS: Site Analysis Branch - CP Enclosed are questions on geology and foundation engineering pertaining to proposed units of the subject plant. A copy of I
questions 1, 2, and 3 were previously provided to L. Crocker, RP
'l Pruject Lumswr, who has . submitted them to the applicant. A
- position paper, which recomends that additional site exploration j work be-done, is concurrently _being prepared for this project.
~
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Harold R. Denton, Assistant Director
_ .,, for Site Safety
! Directorate of Licensing 1
Enclosure:
As stated ,
, cc: w/o enclosure A. Giambusso
'W. Mcdonald
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cc: w/ enclosure S. H. Hanauer J. M. Hendrie V. P. Gamill
.K. Kniel -
L. Crocker l
A. T. Cardone hf? gSC525O/OO 1
31 ALVIN W. VOGTLE QUESTIONS DOCKET NOS. 50-424 - -427
- 1. What is the geologic significance of the clastic dikes mentioned on page 2.5-67
- 2. On pages 2.5-2, 3 the basement complex is described as also including Triassic sediments. What is the configuration and location, with res.pect to the site of the Triassic basin? What is the evidence that the basin is not bounded by faults, in a manner similar to other fault-bounded Triassic basins in the Piedmont.
i
. 3. The cross section (B-B') illustrated in figure 2.5-6 shows a-monoclinal flexure (albeit with vertical exaggeration). Discuss the
' I structural relationship of this flexure and any bounding fault of the Triassic basin.
1- .
Discu'ss possible relationship between the apparently anomalous high
'i seismic response in the zone enclosed by the 8-1/2 value shown on 3_
figure 2.5-26 to basin bounding structures in the basement complex.
- 4. Provide those boring logs of holes drilled in the proposed plant area that were not submitted in the PSAR. For example, the logs for drill holes 101B, 1073, 146, 148, 149, 150, 151, 183, and 184, which are located in the containment buildirgs locations, were not provided in the PSAR.
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- 5. Discuss the significance and magnitude of possible subsidence resulting from fluid withdrawal by means of the proposed uater wells that will supply normal make-up water and cooling water during emergency shutdown conditions. Verify your estimate of the magnitude of subsidence by providing the appropriate analyses.
. 6. In order to complete the geologic and tectonic framework for the proposed site,' describe and discuss the geology to the north of the Savannah River, using as guidelfr.es the " Seismic and Csologic Siting Criteria" and the " Standard Format and Content of SAR's for i
'l Nuclear Power Plants." Show in an appropriate figure the extent and locations of th'e nearby Triassic Basin and clastic dikes l
1, mentioned on page 2.5-6.
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(- AEC Question 2.19 What is the geologic significance of the clastic- dikes mentioned on page 2.5-6?
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The cross section (B-B') illustrated in figure 2.5-6 shows a monoclinal flexure (albeit with vertical exaggeration). Discuss the structural relationship of this flexure and any bounding fault of the Triassic basin.
3
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UMP AEC Question 3.3 The simplified lumped mass and soil spring approach proposed in the PSAR to characterize soil-structure interaction is not appropriate. The use of equivalent soil springs may produce a pronounced filtering of the ground motion response amplitude and response frequencies due to inadequate repre-sentation of soil parameters. Indicate your intent to adopt one of the following methods for soil-structure interaction analysis:
(a) A nonlinear finite element approach with appropriate nonlinear stress-strain and damping relationship for the soil.
3 (b) An iterative linear finite element approach with appropriate nonlinear stress-strain and damping relationship for the soil (pseudo-nonlinear h.,'s approach).
(c) Lumped springs to represent the soil with appropriate dampings (not more than 10% of u-itical damping corresponding to horizontal and vertical springs), uw'lizing a variation in the soil properties corresponding to the span of maximum and minimum strain levels so that the floor response spectra obtained envelop those using the finite element approach. If a pseudo-nonlinear finite element approach is used, identify the manner in which variation in the properties of the soil are accounted for. (Para. 3.7.2.1)
Response
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9 L i-l 3.3 7/6/73 Amendment 3 i
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1 VNP Cretaceous period. Seismic refraction surveys at the site indicate that this basement complex-Cretaceous contact occurs at a depth of approximately 950 feet. More or less constant deposition continued from the Cretaceous through mid-Tertiary i periods in the Savannah River basin area with the youngest identified Tertiary sediments being Miocene in age. Variegated clays and sands lithologically similar to the Miocene Hawthorne I- formation were encountered in the upper portion of one of the
- higher holes drilled at the site, but insufficient exposures of these clays and sands were present to show as a mappable unit.
(S For regional geology map see figure 2.5-3.
Figure 2.5-4, which is a portion of the Tectonic Map of North America, shows the relationship of the site, on the essentially undisturbed sediments of the Coastal Plain, to the Piedmont Province to the north and west with its older and more emplex geologic units. The basement complex, as exposed in the Piedmont Province, has undergone at least two periods of granitic intrusion or granitization as well as well-developed faulting and folding. This activity, however, has been essentially quiescent since the deposition of the Cretaceous .
sediments in the coastal plain. This wedge of Cretaceous and younger sediments, which feather out at the Fall Line near Augusta, is reported to reach depths of approximately 4,000 feet at the coastal line near Savannah, Georgia. The lowest
.( -
member of the sediments appears to represent.an alluvial deposit, possibly of coalescing fans derived from the erosion of the older basement rocks to the west and north. The encroachment of a shallow sea in the Uppermost Cretaceous and Lower Tertiary times resulted in the shoreward migration of estuarine and shallow marine deposits. In the vicinity of the site, lignitic sands and clays are replaced by marls, coquinas, and shallow water sand. These deposits grade coastward into deeper water lithological units of the same age, such as limestone and shales. The present dip seaward of these units is approximately 30 feet per mile at the Cretaceous basement complex contact.
The basement complex is described above as including Triassic-sediments. The location and configuration of these sediments with regard to the VNP is shown on figure 2.5-4A. This Triassic basin, its location, and supporting evidence are discussed in reference 2.5.7.2 (Siple , G. E. , 1967). Here Siple discusses the core obtained in the bottom of the holes 3 drilled on the SRP as lithologically characteristic of "the fanglomerate or conglomerate facies of the Newark group of late Triassic age." The outline of the basin has been determined largely on the basis of aeromagnetic surveys which show the Triassic sediments as " lows" compared to the surrounding igneous-metamorphic Piedmont complex.
i 2.5-3 7/6/73 Amendment 3 l
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VNP Based on what are believed to be similar Triassic basin occur-rences in the Piedmont area and on the steep magnetic gradient' delineating the northwest and southeast edges of the basin, it is assumed that at least these sides are bounded by faults and 3 that the Triassic sediments have been preserved in a down-dropped graben within the basement rock.
2.5.1.3.2 Stratigraphy
/ - The stratigraphy applicable to the Savannah River basin area is I. susanarized in table 2.5-1. Igneous and metamorphic rocks varying in age from Precambrian to Paleozoic form the lowest unit believed to be present at the site.
This material was not encountered during drilling or indicated by the deep refraction seismic work, but is known to form the true basement material by direct or inferred means throughout the Georgia-South Carolina area.
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t 2.5-3a 7/6/73 Amendment 3
VNP
. Deposition of continental sediments during the Triassic is known to have occurred fron samples obtained from drilling through the coastal province. Much of this material was oroded during the post-Triassic, pre-Cretaceous time, but local basins containing Triassic sediments were preserved beneath the peneplain surface formed. Aerial magnetic surveys in the past
. decade have disclosed that one of these Triassic basins extends from bcncath the Atomic Energy Commission's Savannah River Project (S RP) in South Carolina to several miles beyond the site of the Vogtle Nuclear Plant in Georcia. On the SRP, the basin was confirmed by seismic reflection studies and deep core holes. The deposits consist of siltstono, claystones, and
,, sandstones resembling those of the typical Newark Group
( ~
.' fanglomerates of the Upper Triassic period. Measurements made at the Vogtle site indicate that a material with refraction velocity of 12,000 feet per second exists at approximately 950 feet below the plant site', which agrees with the Triassic basin sediment data.
Overlying the peneplained surf ace of the Precambrian-Triassic basement complex is the nonmarino Tuscaloosa Formation. This !
formation is composed largely of detritus derived from the weatheret granitic-metamorphic basement rocks and contains considerable coarse grained quartz, partially altered feldspar, and mica (generally of the muscovite variety) . In gross ap-pearance, it consists of light-grey to light-brown to white, cross-bedded, arkosic to quartzitic sands and gravels inter-
\.
- beuded with lenses of silt and clay, of red, white, brown, or purple color. Tne variegated clays are generally of relatively pure kaolin and are nined extensively in the vicinity of the Fall Line.
Overlying the Lower Cretaceous Tuscaloosa Formation is the Ellenton Formation, which occurs sporadically and locally within the Savannah River basin, but occurs consistently in the plant site area. Originally described by Siple in his work on the S RP , it is believed to be of Upper Cretaceous age. The Ellenton Formation consists of dark-cray to black, sandy, lignitic, micaceous clay interbedded with mediun to coarse-grained quartz sand in its type area. The lower part of the Ellenton Formation is composed generally of a clayey quartz sand varying in texture from medium to coarse-grained, becoming locally gravelly. Deconposed pyrite or marcasite fragments, lignite, muscovite, and kaolinitic aggregates are quite common.
The Ellenton Fornation is distincuished from the Tuscaloosa Fornation by the latter's marked preponderence of muscovite and kaolin as compared to that in the Ellenton Formation.
Above the Lilenton Formation are the Tertiary deposits of the Eocene through Miocene periods. The lowest of these is the
, 2.5-5
,. VNP ;
at least post-Claiborne sediments. Although the second-possibility, seismic activity, is a likely causative force, it also seems probable that the dike itself was formed both by means of infilling, at an equal pace, of overlying material and by the mechanism included in hypothesis 3. So far as is known, there is no material present now in a stratigraphically higher position in the geologic section and similar in composition to the fracture fill that conceivably might have worked down into the fissure as it was being formed. There is, however, greenish-gray clay in the Hawthorne Formation at downdip
( localities that could have been present in this area in the geologic past and would be a likely source for such filling.
There is also similar clay stratigraphically lower in the geologic section - a fact which suggests that possibly some dikes were injected up through the younger Tertiary rocks.
3 Conceivably this injection may have been brought about by the failure of underlying beds to support compressional stresses.
Under such conditions the weight of the overlying material would cause a failure in the substructure brought about by ground water solution of the underlying calcareous beds. , When these beds could no longer support the overlying formations, I fractures would develop as the superstructure collapsed, and l clastic material below would migrate up into the fractures.
Some corroborative evidence for such an origin is indicated by
(, the large number of solution sinks in the vicinity of the dikes, as for example, in the northeastern quarter of the Ellenton quadrangle. , Conversely, dike swarms are indigenous to those areas exhibiting other features of solution and collapse." ,
The Quarternary appears largely represented by the flood plain deposits and valley fill associated with the rivers and larger streams in the area.
2.5.1.3.3 Structure The major structural trend affecting the Georgia-South Carolina region along the southern portion is the pre-Mesozoic Appalachian system. Tectonic activity had ceased on this system before the deposition of the Cretaceous sediments in the Savannah River valley area, as is evidenced by the lack of tectonic folding or documented fault offsets in the sedinents.
Faulting, perhaps of major proportions, appears to have occurred in the basement complex during the pre-Cretaceous, however, to account for the down-warped or down-faulted segments of Triassic sediments found preserved within the basement complex throughout much of the Atlantic Coastal Plain.
The coastal plain sediments indicate une Savannah River basin has remained remarkably stable throughout Upper Pesozoic and .
2.5-6a 7/6/73 Amendment 3
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to 90 feet (+) in Holes 38 and 156, are stratigraphically part of the Oligocene. This is true, also, for the shell bearing horizon in Hole 45 on the SRP.
2.5.1.4.3 Structure The geologic structure in this area is best illustrated by figure 2.5-10 showing the contours on the top of the bearing stratum. Although the surface of this marl bed is believed to
,- be a formational contact, the contours indicate only a minimum amount of differential erosion. The contours were derived from outcrop and drill hole information and indicate a general dip to the south and east of about 30 feet to the mile throughout-the plant site area. The general dip is interrupted on the northeast by a gentle dip to a maximum slope of five percent (3 degrees) to the northwest, and lowers the reversal of the surface of the bearing stratum approximately 50 feet in that direction.
The dip reversal is seen with a 20 to 1 vertical exaggeration on section B-B' of figure 2.5-6. The trend of the axis is approximately northeast-southwest. It is an anomaly that has been the subject of much investigation and discussions.
, Numerous holes were drilled to determine its character, and
\- water pressure tests were made to determine if it affected the ,
watertightness of the bearing stratum. No indication that it I was a . fault controlled feature was found during the extensive l investigations . It does not appear to be an erosional feature i on the top of the unit as it is reflected in both the top and !
bottom of the bearing stratum to an approximately equal extent. 3 ;
It dips in the wrong direction to reflect possible near-surface expression of the underlying Triassic basin boundaries. No relationship to the assumed boundary fault contact at the ;
northern edge of the Triassic basin could be found. As the i assumed northern Triassic basin boundary fault would have to be down-thrown towards the sea, the fact that the flexure in the bearing horizon slopes in the opposite direction, i.e. , to the northwest, seems to negate any genetic relationship. It appears to have been formed previous to and in part possibly during the deposition of the thick shell deposits that roughly coincide with the reversal, as may be seen on figure 2.5-10A.
A local, well developed, striated bedding plane was found in
. one hole (' N o . 246) at the base of the marl. This is near the southwestern or lower side of the anomaly and well away from the plant area. Water losses were also noted related to jointing in the upper 15 feet of the marl during some exploratory drilling investigating this feature. These phenomena were not observed elsewhere throughout the plant site inves tigation. It is believed that the reversal represents 2.5-11 7/6/73 Amendment 3
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deposition on an erosional irregularity on the underlying sands, with the possibility of some local differential compaction during or shortly after deposition of the bearing stratum.
,- Solution depressions are readily apparent on the topographic map of the site and, as the site explorations shown on figure 2.5-1 indicate, they were the subject of considerable f
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t 2.5-ila 7/6/73 Amendment 3l3
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The map divides the coterminous United States into the '
following four zones.
l Areas where there is thought to be no reasonable l
expectancy of earthquake damage - Zone 0 '
Areas of expected minor damage - Zone 1 Areas where moderate damage could be expected - Zone 2.
~ Areas where major destructive earthquakes may occur -
(- , Zone 3 The site lies inside Zone 2 where moderate damage could be expected. According to this map, moderate damage corresponds to intensity VII on the Modified Mercalli Scale.
The zones are based principally on the known distribution. of damaging earthquakes, their intensities and geological considerations. Since the Charleston earthquake of August 31, 1886 resulted in .the greatest intensities in this part of the country, the zones there will be based on data from this shock.
The Dutton isoseismal map most probably forms the basis for the zones in this area therefore, since the Dutton map included i
the site in the VII (MM) area, it appears in this zone of the
(' -
risk map even though the site may never have experienced an intensity this high in historic times.
The high seismic response zone enclosed by the 8-1/2 (Rossi-Forel) isosaismal line shown on figure 2.5-26 has been discussed by C. E. Dutton in "The Charleston Earthquake" (USGS 9th Annual Report, 1887-88).
"......The shocks at Columbia, South Carolina, judging'from all accounts, were more forcible than at Savannah. The first two impulses, which appear to have corresponded to the two maxima already described at Charleston, threw the whole city into a state of terror. The swaying of buildings was very great; the jarring, like that of a wagon rumbling over a stony pavement,
, was excessive, shaking down plaster, chandeliers, crockery and light objects, and producing a 3oud rattle, which, added to the a subterranean roaring, caused th greatest consternation.......
Still no instances have been rev erted of the demolition of any buildings.
The most remarkable circumstance, however, connected with Columbia is the f act that a considerably greater intensity is i indicated for that city than for the localities to the southeast of it nearer to the centrum. There is, indeed, a belt of country along the Piedmont region where the same state 2.5-45 7/6/73 Amendment 3 v -- -,
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'throughout the State of North Carolina the vigor of the shocks was very great. . . . . . . . There is, however, a notable difference as a general rule between the eastern part of 'the State within the coastal region and the Piedmont and mountain region. It was notably less forcible in the coastal plain........ There are many indications that the vast masses of littoral deposits of unconsolidated sands, clays, and marls along the Atlantic 3 border and ooastal plain, especially in the Carolinas, greatly-tempered and modified the force of the earthquake. It may be said that they ' cushioned' the shocks, not alastically, but by actually dissipating in some measure portions of the rays of
( energy which here affected the surface........"
2.5.2.11 Earthquake Frequency Table 2.5-10 shows earthquake frequency in the vicinity of the Vogtle site. It is based on actual data from the historic earthquake record of about 300 years, and shows the shocks which were felt in the site area.
2.5.2.12 Summary and Conclusions The first historical quake felt in the eastern United States is listed as occurring in Canada in 1663, so there is an
(~' historical earthquake record of 300 years for the southeastern United States. This area of the country experiences moderate to low earthquake activity with the exception of the Charleston area. The greatest intensity experienced at the site resulted '
from the August 31, 1886, Charleston earthquake about 104 miles
. east of the site. Considering the reports from nearby towns, j the intensity at the site was no greater than a VII.
The great New Madrid, Mo. 1811-1812 shocks were also felt at the site, but with no greater intensity than VI (MM). Other distant and nearby shocks, however, have been barely felt at the site, probably with no greater intensity than IV.
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. -l0 ::'hn MEliORANDUM FOR: Ina B. Alterman, Geologist Geology Section, GSB, DE FROM: Phyllis A. Sobel, Seismologist Seismology Section, GSB, DE
SUBJECT:
SEISMOLOGY REVIEW 0F BECHTEL REPORT," STUDIES OF POSTULATED MILLETT FAULT" I have reviewed the seismicity information in the Bechtel report on the Millett Fault prepared for the Vogtle applicant. The available seismicity information includes (1) felt earthquakes, (2) reciit instrumentally located events, and (3) data from the Savannaf River 2 1ant array, just across the Savannah River from the Vogtle site. The and I agree, that historic seismicity reveals no applicant evidence of concludes' active faulting in the area. The seismicity near the site has been scat.tered and low level (maximum MM intensity VI). No clustering of earthquakes < occurring near the postulated Millett or Statesboro faults. "
Phyllis Sobel, Seismologist Seismology Section Geosciences Branch cc: R. Jackson L. Reiter S. Brocoum P. Sobel A. K. Ibrahim
.