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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3141999-10-15015 October 1999 Requests Emergency Publication of Document Entitled South Carolina Electric & Gas Co;Vc Summer Nuclear Station,Environ Assessment Transmitted on 991015 to Ofc of Fr for Publication ML20217J3281999-10-15015 October 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re Application for Exemption from Requiremets of 10CFR50,Section 50.60(a) for VC Summer Nuclear Station ML20217F8851999-10-0808 October 1999 Forwards Insp Rept 50-395/99-06 on 990801-0911.One Violation Occurred Being Treated as NCV RC-99-0192, Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models1999-09-28028 September 1999 Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models RC-99-0181, Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment1999-09-21021 September 1999 Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment ML20212C5091999-09-15015 September 1999 Forwards Anticipated Schedule for Operator Licensing Exams for Sce&G.Util Requests That NRC Prepare Exams on Encl RC-99-0184, Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety1999-09-15015 September 1999 Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211Q8911999-09-0101 September 1999 Sumbits Summary of Training Managers Conference on Recent Changes to Operator Licensing Program.Meeting Covered Changes to Regulations,Exam Stds,New Insp Program & Other Training Issues.List of Attendees Encl RC-99-0177, Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.111999-08-31031 August 1999 Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.11 RC-99-0173, Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr1999-08-31031 August 1999 Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr ML20211L5181999-08-30030 August 1999 Forwards Insp Rept 50-395/99-05 on 990620-0731.One Violation Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20211H2481999-08-25025 August 1999 Forwards Four Controlled Copies of Amend 43 to Physcial Security Plan. Summary of Plan Changes, Are Included as Part of Each Controlled Copy.Encls Withheld Per 10CFR73.21 05000395/LER-1999-004, Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Complet1999-08-24024 August 1999 Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Completed RC-99-0171, Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors1999-08-23023 August 1999 Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors RC-99-0152, Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G1999-08-19019 August 1999 Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G RC-99-0164, Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d)1999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d) ML20210Q4851999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at VC Summer.Requests Info Re Individuals Who Will Take Exam,Personnel Who Will Have Access to Exam.Sample Registration Ltr Encl ML20210R5501999-08-0505 August 1999 Ack Receipt of 990707 Response to NCVs Identified on 990607 Re Activities Conducted at VC Summer.Informs That After Consideration of Basis for Denial of NCV 50-395/99-03, Concluded,For Reasons Stated,That NCV Occurred RC-99-0156, Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm1999-08-0404 August 1999 Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-19881999-07-26026 July 1999 Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988 ML20210B7451999-07-22022 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1 & Rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210E3771999-07-16016 July 1999 Forwards Insp Rept 50-395/99-04 on 990509-0619.One Violation Being Treated as Noncited Violation RC-99-0127, Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-021999-07-0707 July 1999 Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-02 RC-99-0129, Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist1999-07-0707 July 1999 Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist RC-99-0131, Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld1999-07-0707 July 1999 Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld ML20210B7111999-07-0606 July 1999 Provides Summary of 990701 Meeting with Sce&G in Atlanta, Georgia Re Recent Virgil C Summer Refueling Outage & Other Items of Interest.List of Meeting Attendees & Licensee Presentation Handouts Encl RC-99-0114, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation1999-06-30030 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation ML20195H5861999-06-0707 June 1999 Confirms 990604 Telcon Between J Proper & R Haag Re Meeting Scheduled for 990701 in Atlanta,Ga,To Discuss Plant Refueling Outage & Items of Interest ML20207H5241999-06-0707 June 1999 Forwards Insp Rept 50-395/99-03 on 990328-0508.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207D1881999-05-28028 May 1999 Informs That Effective 990524,K Cotton Assigned as Project Manager,Project Directorate II-1,for Virgil C Summer Nuclear Station 05000395/LER-1999-006, Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1)1999-05-17017 May 1999 Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1) RC-99-0104, Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy1999-05-13013 May 1999 Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy RC-99-0105, Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station1999-05-13013 May 1999 Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station 05000395/LER-1999-005, Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components1999-05-12012 May 1999 Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components ML20206L5121999-05-11011 May 1999 Informs That NRC Reorganized,Effective 990328.Reorganization Chart Encl ML20206P5771999-05-0707 May 1999 Informs That During 980519 Telcon Between T Matlosz & G Hopper,Arrangements Were Made for Administration of Licensing Exam at Virgil C Summer Nuclear Station During Wk of 990927 RC-99-0080, Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective1999-05-0606 May 1999 Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective RC-99-0097, Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.111999-05-0606 May 1999 Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.11 RC-99-0092, Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI1999-05-0303 May 1999 Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI RC-99-0090, Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b1999-04-29029 April 1999 Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b ML20206E1681999-04-29029 April 1999 Informs That FERC & NRC Will Conduct Category I Svc Water Pond (Swp) Dam Insp at Facility on 990610 ML20206P5021999-04-26026 April 1999 Forwards Insp Rept 50-395/99-02 on 990214-0327.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR 05000395/LER-1999-002, Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl1999-04-12012 April 1999 Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl ML20205T2311999-04-0909 April 1999 Informs That on 990318,A Koon & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Schedules for Wk of 000807 for Approx Eight Candidates ML20205G4181999-04-0101 April 1999 Advises That 970725 Application & Affidavit Which Submitted, WCAP-14932, Probabilistic & Economic Evaluation of Reactor Vessel Closure Head Penetration Integrity for Plant, Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(4) RC-99-0078, Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e)1999-04-0101 April 1999 Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARRC-99-0192, Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models1999-09-28028 September 1999 Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models RC-99-0181, Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment1999-09-21021 September 1999 Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment ML20212C5091999-09-15015 September 1999 Forwards Anticipated Schedule for Operator Licensing Exams for Sce&G.Util Requests That NRC Prepare Exams on Encl RC-99-0184, Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety1999-09-15015 September 1999 Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety RC-99-0177, Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.111999-08-31031 August 1999 Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.11 RC-99-0173, Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr1999-08-31031 August 1999 Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr ML20211H2481999-08-25025 August 1999 Forwards Four Controlled Copies of Amend 43 to Physcial Security Plan. Summary of Plan Changes, Are Included as Part of Each Controlled Copy.Encls Withheld Per 10CFR73.21 05000395/LER-1999-004, Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Complet1999-08-24024 August 1999 Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Completed RC-99-0171, Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors1999-08-23023 August 1999 Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors RC-99-0152, Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G1999-08-19019 August 1999 Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G RC-99-0164, Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d)1999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d) RC-99-0156, Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm1999-08-0404 August 1999 Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-19881999-07-26026 July 1999 Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988 RC-99-0129, Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist1999-07-0707 July 1999 Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist RC-99-0131, Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld1999-07-0707 July 1999 Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld RC-99-0127, Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-021999-07-0707 July 1999 Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-02 RC-99-0114, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation1999-06-30030 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation 05000395/LER-1999-006, Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1)1999-05-17017 May 1999 Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1) RC-99-0104, Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy1999-05-13013 May 1999 Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy RC-99-0105, Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station1999-05-13013 May 1999 Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station 05000395/LER-1999-005, Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components1999-05-12012 May 1999 Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components RC-99-0097, Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.111999-05-0606 May 1999 Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.11 RC-99-0080, Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective1999-05-0606 May 1999 Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective RC-99-0092, Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI1999-05-0303 May 1999 Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI RC-99-0090, Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b1999-04-29029 April 1999 Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b 05000395/LER-1999-002, Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl1999-04-12012 April 1999 Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl RC-99-0078, Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e)1999-04-0101 April 1999 Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e) RC-99-0066, Submits Rept of Status of Decommissioning Funding (RR-1950), for Vsns Per 10CFR50.751999-03-31031 March 1999 Submits Rept of Status of Decommissioning Funding (RR-1950), for Vsns Per 10CFR50.75 ML20205B9981999-03-29029 March 1999 Informs That Authority & Sce&G Has Ownership Interests of one-third & two-thirds,respectively in VC Summer Nuclear Station.Operating License Scheduled to Expire in 2022.Rept Addresses Decommissioning Cost Estimates & Financing RC-99-0054, Forwards Rev 2 to VC Summer Nuclear Station Training Simulator Quadrennial Certification Rept,1996-99, Per 10CFR55.45(b)(5)(ii)1999-03-22022 March 1999 Forwards Rev 2 to VC Summer Nuclear Station Training Simulator Quadrennial Certification Rept,1996-99, Per 10CFR55.45(b)(5)(ii) RC-99-0053, Requests That Implementation Date of Proposed TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear (Beacon) Be Extended. Util Requests 120 Day Time Frame to Perform Initial Beacon Calibrs During Cycle 121999-03-22022 March 1999 Requests That Implementation Date of Proposed TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear (Beacon) Be Extended. Util Requests 120 Day Time Frame to Perform Initial Beacon Calibrs During Cycle 12 RC-99-0048, Informs That Util Has Implemented Policy That Requires All Personnel Granted Unescorted Access to Vsns Satisfactorily Complete Test on Site Specific Info1999-03-10010 March 1999 Informs That Util Has Implemented Policy That Requires All Personnel Granted Unescorted Access to Vsns Satisfactorily Complete Test on Site Specific Info ML20207J5661999-02-16016 February 1999 Requests That Proprietary Rev 1 to WCAP-14932 Re Rv Closure Head Penetrations Integrity for VC Summer Nuclear Plant,Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4) RC-99-0026, Provides Response to NRC RAI Re TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear1999-02-0505 February 1999 Provides Response to NRC RAI Re TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear RC-99-0023, Informs That in Response to GL 97-06,SCE&G Informed NRC of Plan to Perform Secondary Side Examination Scheduled for Refueling Outage RF-11.SCE&G Has Decided to Defer Secondary Side Insp of Sg.Reasons for Change of Plan Listed1999-02-0101 February 1999 Informs That in Response to GL 97-06,SCE&G Informed NRC of Plan to Perform Secondary Side Examination Scheduled for Refueling Outage RF-11.SCE&G Has Decided to Defer Secondary Side Insp of Sg.Reasons for Change of Plan Listed 05000395/LER-1998-009, Forwards LER 98-009-01 for VC Summer Nuclear Station.Rept Describes Unanalyzed Condition for non-safety Related Component for Which All Failure Mechanisms Had Not Been Evaluated1999-01-28028 January 1999 Forwards LER 98-009-01 for VC Summer Nuclear Station.Rept Describes Unanalyzed Condition for non-safety Related Component for Which All Failure Mechanisms Had Not Been Evaluated RC-99-0015, Forwards Amend 16 to Training & Qualification Plan,Per 10CFR50.54(p).Summary of Changes,Encl1999-01-22022 January 1999 Forwards Amend 16 to Training & Qualification Plan,Per 10CFR50.54(p).Summary of Changes,Encl RC-99-0005, Responds to 980908 RAI Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations1999-01-15015 January 1999 Responds to 980908 RAI Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations RC-98-0225, Forwards Rev 41 to EP-100, Radiation Emergency Plan. List of Changes by Page Number Affected by Rev 41 Also Encl1998-12-14014 December 1998 Forwards Rev 41 to EP-100, Radiation Emergency Plan. List of Changes by Page Number Affected by Rev 41 Also Encl RC-98-0226, Forwards Amend 42 to Psp.Changes Do Not Degrade Safeguards Effectiveness in PSP or Safeguards Contingency Plan,As Described in 10CFR50.54(p).Without Encl1998-12-14014 December 1998 Forwards Amend 42 to Psp.Changes Do Not Degrade Safeguards Effectiveness in PSP or Safeguards Contingency Plan,As Described in 10CFR50.54(p).Without Encl RC-98-0216, Requests Extension of Response Period to 990115 to Respond to NRC 980908 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Util Intends to Utilize Industry Generic RAI Response1998-12-0404 December 1998 Requests Extension of Response Period to 990115 to Respond to NRC 980908 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Util Intends to Utilize Industry Generic RAI Response RC-98-0189, Provides Assessment Results of GL 98-02, Loss of Rc Inventory & Associated Potential for Loss of Emergency Mitigation Functions While in Shutdown Condition, Per 10CFR50.54f1998-11-24024 November 1998 Provides Assessment Results of GL 98-02, Loss of Rc Inventory & Associated Potential for Loss of Emergency Mitigation Functions While in Shutdown Condition, Per 10CFR50.54f RC-98-0207, Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment1998-11-11011 November 1998 Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment RC-98-0177, Informs That Sce&G Will Classify as Moderate Any Stratification Condition That Results in Total Cuf,Based on Design Basis Values Plus Any Contribution from Stratification,Of Between 0.1 & 0.71998-11-0909 November 1998 Informs That Sce&G Will Classify as Moderate Any Stratification Condition That Results in Total Cuf,Based on Design Basis Values Plus Any Contribution from Stratification,Of Between 0.1 & 0.7 RC-98-0194, Provides Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs1998-11-0202 November 1998 Provides Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs RC-98-0202, Forwards Response to RAI Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1998-10-30030 October 1998 Forwards Response to RAI Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions RC-98-0186, Expresses Appreciation for Opportunity to Present Topical Rept TR-104965, On-Line Monitoring of Instrument Channel Performance1998-10-26026 October 1998 Expresses Appreciation for Opportunity to Present Topical Rept TR-104965, On-Line Monitoring of Instrument Channel Performance RC-98-0185, Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 11998-10-0909 October 1998 Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 1 RC-98-0182, Responds to 980402 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs1998-10-0808 October 1998 Responds to 980402 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs RC-98-0178, Provides Comments on SALP Insp Rept 50-395/98-99.Util Ack That Station Can Enhance Future Performance Further with More Focus & Attention on Change Mgt Practices Re Plant & Procedure Changes1998-10-0505 October 1998 Provides Comments on SALP Insp Rept 50-395/98-99.Util Ack That Station Can Enhance Future Performance Further with More Focus & Attention on Change Mgt Practices Re Plant & Procedure Changes 1999-09-28
[Table view] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20043A3741990-05-0707 May 1990 Forwards Final VC Summer Nuclear Station Exercise on 890606-07. No Deficiencies Identified During Exercise & Thirteen Areas Requiring Corrective Actions Noted ML20214P4181987-05-22022 May 1987 Forwards VC Summer Nuclear Power Plant Exercise, Conducted on 870204.No Deficiencies Identified.Six Areas Requiring Corrective Actions & Several Areas Recommended for Improvement Discussed ML20138R9841985-11-0606 November 1985 Forwards Exercise Rept for 850424-25 Exercise of Offsite Radiological Emergency Preparedness Plans ML20080J6081984-02-0808 February 1984 Forwards Request That full-scale Participation by Affected Local Govts & Substantial Participation by State of Sc Not Be Required.Fema Will Support Exemption from 10CFR50,App E, Section IV.F.1 ML20080G9611983-08-15015 August 1983 Forwards VC Summer Nuclear Power Plant Full-Scale Local Exercise Conducted on 830316, Final Rept.Deficiency Noted at Reception Ctr in Newberry County Corrected ML20073Q4521983-04-25025 April 1983 Forwards Ltr Repts Re Seismic Confirmatory Program, Explosion & Vibration Tests & Computer Program for Evaluating Equation 58 ML20073Q4551983-04-12012 April 1983 Informs That Error Found in Computer Program for Evaluating Equation 58 Re R Factor.Analytical Approach Used Entirely Different from Model Approach But Gives Similar Results. Results of Model Approach Justified ML20073B3971983-04-0808 April 1983 Submits Comments on Seismic Confirmatory Program,Vc Summer Station Unit 1, in Preparation for Meeting W/Licensee.Rept Fails to Demonstrate Applicability of Explosion Tests to Earthquakes ML20073B3941983-04-0808 April 1983 Discusses Review of Forced Vibration Tests on Pad.Results of Stiffness Method Invalid.Results of Modal Method Appear Entirely Acceptable ML20005B8251981-08-25025 August 1981 Forwards Us Court of Appeals,Fourth Circuit Notification of Petition for Review of NRC 810626 Order.All Related Cases Will Be Consolidated & Briefing Schedule Established ML20009B0021981-07-0808 July 1981 Comments on Fes for Facility.Discussion & Comparison of Radiological Risks from Accident & Normal Operation Releases Are Significant Improvements Over Des Info ML20004E4721981-06-10010 June 1981 Ack Receipt of EIS on 810603.FR Publication Scheduled for 810612,w/public Review Period to Terminate 810713 ML20004D0661981-06-0101 June 1981 Submits Addl Info Re Status of State & Local Emergency Preparedness for Facility,Per NRC 810310 Request.Mods Needed.Sc & Affected Areas Could Be Expected to Execute site-specific Radiological Emergency Preparedness Plans ML19352A9221981-05-21021 May 1981 Comments on Util Public Info Brochure Re Facility,Per NRC 810508 Request.Plan Is Workable.Util Overstates Level of Cleanliness Re Contamination Levels in Secondary Loop ML20003B1741981-02-0505 February 1981 Requests Extension Until 810206 to File Comments on NRC 810115 Order ML19339D0811981-02-0404 February 1981 Forwards Comments on Approach & Format of Accident Analysis Presented in Facility DES,NUREG-0534.Potential Impact of Serious Accident on Human Health & Environ Not Described in Manner Understandable to Public ML19341B4391981-01-28028 January 1981 Requests Extension Until 810205 to Comment on Matters Raised by Commission 810115 Order.Other Parties Do Not Object to Extension ML20002E1821981-01-19019 January 1981 Comments on Des for Facility Re Possible Impacts of Class 9 Accidents,In Response to NRC Request.Discussion of Probabilities of Occurrence,Magnitude of Consequences & Risk Considerations Should Be Given Separate Attention ML20002D6351981-01-12012 January 1981 Applauds NRC Decision to Prepare Suppl to Des for Evaluation of Environ Impacts from Different LWR Accident Scenarios Including Class 9 Accidents.Technical Comments on Des Encl ML20002C1661981-01-0505 January 1981 Ack Receipt of 801110 Ltr Transmitting Suppl to Draft Eis. Provides Detailed Comments on Sections Re Groundwater & Uncertainties.Finding of Lewis Rept W/Respect to Uncertainty in Risk of Reactor Accidents Should Be Discussed in Fes ML17209A7711980-12-30030 December 1980 Responds to NRC Request for Updated Info Re Occurrence of Earthquakes Similar to 1886 Event in Charleston,Sc.Similar Earthquakes Have Potential to Occur in Vicinity.Seismic Engineering Parameters Should Be Carefully Considered ML19347C6511980-12-24024 December 1980 Forwards Nasa Comments on Draft EIS for Facility.Questions Why Wind Rose Data Was Not Taken Into Account in Determining Probability of Total Population Exposure.Ten Copies of Final EIS Requested ML19340D4061980-12-23023 December 1980 Requests 15-day Extension for Review of Suppl to Facility Des,Per 801223 Telcon ML19345D6391980-12-10010 December 1980 Reviews Facility Des Per 801110 Request.Draft Appears Acceptable in Areas Reviewed ML19345B4351980-12-0101 December 1980 Ack Receipt of Draft EIS Which Will Be Forwarded to Responsible Environ Officer for Review & Comment.Provides Procedures & Addressees for Subsequent EIS Reviews ML19339C5261980-11-12012 November 1980 Determines That EIS Received on 801107 Meets Requirements of Section 1506.9 of Ceq Regulations.Fr Publication of Availability Scheduled for 801114.Public Review Period Will Terminate on 801229 ML19347A6901980-09-24024 September 1980 Requests Extension Until 801010 to Respond to Commisison 800630 Memorandum & Order.Careful Analysis & Evaluation of Issues Required ML19332A6461980-09-10010 September 1980 Informs of Actions Initiated to Assist Sc & Local Govt in Development of Radiological Emergency Response Plans Consistent w/NRC-FEMA Criteria ML19254C6551979-09-18018 September 1979 Submits Comments Re Des as Requested in NRC 790629 Ltr. Statement Generally Adequate But Assessment of Aquatic Impacts in Monticello Reservoir Is Unsupported by Baseline Data for New Aquatic Sys ML19208D4451979-09-18018 September 1979 Comments on Des:More Detailed Discussions Needed Re Prediked Limnology of Monticello Reservoir,Impacts on Biota & Effects of Thermal Discharge on Phytoplankton ML19275A0511979-08-24024 August 1979 Comments on Draft EIS Re Operation of Nuclear Station. Wetlands Data Should Be Included in Fes.States Should Develop or Update Emergency Response Preparations ML19242A3131979-07-23023 July 1979 Responds to 790629 Ltr.Offers No Comments on Des 1990-05-07
[Table view] |
Text
.-.- .__.. . _ . . . .
t y-f United States Department of the Interior H gl-.
=
_._ j GEOLOGICAL SURVEY BOX 250-16 '- M.S o DENVER FEDERAL CENTER DENVER, COLORADO 80225
. IN Rt Pl.T Rtti R 'In Branch of Engineering' Geology and Tectonics Mail Stop-966 April 25, 1983-p .67' N Dr. Robert E. Jackson, Chief Geosciences Branch Division-of Engineering .
Office of-Nuclear Reactor Regulation Nuclear Regulatory Commission' Washington, D.C.'.20555
Dear Bob:
Enclosed are three letter reports, one from W. B. Joyner and two from Noel Bycroft, concerning the. Virgil C. Summer Nuclear Station Unit 1.
Please let me know if you have any questions regarding these reports.
Sincerely, 1
S. T. Algeraissen 1 Enclosures 1.
J 4
i
@D7 s ,
- c. 8304290126 830425 PDR ADOCK O$000395
- p. PDR w-
- ~ . . _ _ . . _ _ _ - .. . _ . - _ . . ~ . . , _ . . . _ . . . . - . . _ . . . - . . . _ . _ _ . _ _ . _ _ _ . _ . _ . _ . _ . _ ,
/,bl's
. ., 1 United States Department of the Interior
- h. GE01DGICAL SURVEY OFFICE OF EARTHOUAKES, VOLCAN0ES. . AND Ef'GIf;EERIPG Eranch of Engineering Seismology and Geology 345 Middlefield Road, MS 77 Henlo Park, CA 94025 April 8,1983 Dr. Jerry L. King U. S. fiuclear Regulatory Cmmission Mail Stop P-514 Washington, D. C. 20555
Dear Jerry:
In preparation for our scheduled neeting with the Licensee later this month, I am setting down ny preliminary comnents on the report " Seismic Confirnatory Program, Virgil C. Summer Nuclear Station Unit 1", including the Adder: dun to Appendix B, dated March 1993.
floel Bycrof t will cement on the theory used in interpreting the pad tests, and I will leave that subject largely to him. I.wauld like to suggest, however, that since the modal anproach, which was used to get the final answer, is not conpletely rigorous, it would be of great interest to see a comparison between the observed displacement anolitude and phase frm the low-force-level test (e.g., Figure 4 of Appendix A) and the predictions of the model obtained by the modal analysis. That should be a relatively simple thing to do.
With respect to the explosion tests as a means of determining foundation ef fects, I don't believe the submissions demonstrate the applicability of the explosion tests to earthquakes. They show that the explosion seisnograms are dominated by what they call S-wave and higher node surface waves. They claim to show that the spectral ratios are similar whether cmputed for a P-wave window, an S-wave window (including the surface waves), or for the whole record. They show that fundamental node surface waves do not contribute to the spectral ratios. All of this, however, does not demonstrate that the relative response of foundation and free-field sites is the same for earthquakes as for explosions. If we accept the description of the dominant portion of the selsnograms as a cmbination of S-waves and higher node surface waves, we have to presume that the relative excitation of the various components of this cmbination is sensitive to the depth of the source, and further, that the relative response of foundation and free-field sites is sensitive to the relative excitation of the coeponents. Looked at from a s - dif ferent point of view, it ray be more realistic to consider the dominant portion of the seismogram to be a combination of scattered S-waves, scattered not only in the vicinity of the recording site, but also in the vicinity of the source a in the vicinity of any surface reflection points between the f .
pr go
source and the recording site. _ From this point of view, one would expect the character of the motion, and in particular, the relative response at
. - foundation and free-field sites to be sensitive to the depth of the source.
- Either way, the source depth may be a significant variable. The average depth of the explosions must be significantly less than the average depth of the earthquakes, and all of the. explosion depths may in fact be less than all of g : the earthquake depths. Two _ shots were at depths comparable to the computed l hypocentral' depth of the October 1979 earthquake, but no data from those shots
- - is shown and, as I interpret Table V.C.I. no data from those shots was. used in cmputing horizontal spectral ratios. In any case, the uncertainty of the computed hypocentral depth forces us to acknowledge that the real depth could be substantially greater than that for all 'of the explosions. This leaves me with substantial doubt concerning the applicability of the explosion tests for determining relative. response in an earthquake. (My conern on this point is increased by comparing Figure IV.C.1 with Figures IV.C.3 and IV.C.6.. The comparison is difficult to make because of the scale change, but the' records-
, of the shots seem to _ have higher coda amplitudes at free-field sites than the L record of the earthquake, and the particle-motion diagrams show a different
[ pattern for the earthquare compared to the explosions.)
l I am-also concerned about the use of a zero-phase-shift filter to L represent the transfer function!between foundation and free-field sites. The i effect of this 'is difficult to assess and could be quite significant, Relative _ phase controls the. extent to which 'an increase in modulus represents an : increase in peak amplitude and the extent to which it represents an increase in duration. The effect of an increase in amplitude on damped response spectra may-'be very different from the effect of an increase in l duration, depending on ae character of the signal. To help us assess this
- aspect of their work, I think the Licensee should be asked to show comparisons of typical observed free-field records with synthatic free-field records formed by filtering Auxiliary Building records with the corresponding zero-phase-shift filter.
Another major problon in the interpretation of the explosion tests is the treatment of variablility, The consultants use the-mean spectral ratio. I question this cnoice in spite of the ingenious argument offered by Robin McGuire. As you remember, he argued that, if the mean ratio had turned out to be 1.0, NRC would not have required that the spectrum be raised; so no extra margin over the mean ought to be required in the case of a nean less than i 1.0. I disagree. I think ti',4t if the mean had (surprisingly) turned out to be I.0, prudence would have required giving serious consideration to raising the spectrum.- From the standpoint of safety, the question is not whether the i spectrum is exceeded on the average, but, rather, whether it is exceeded anywhere. If the Envelope Spectrum embodied a large degree of conservatism, it might be argued that the use of the mean spectral ratio was justified, but
- i. the envelope of all events recorded in approximately a five-year period cannot be considered conservative without some debatable assumption about the rate at which the earthquake sequence is dying off.
4 e mee e-+e ,---v
-. . ?.
.t- ;a.
. I cannot find a clear explanation of how the " band pass spectral ~ ratios"-
for the various windows were calculated. I'may just.have missed it,but, if
- not', the consultants should supply it. -In comparing the band pass ratios-shown in Figures VI.C.55 and _VI.C.58 with the ratios in Figures VI.C.20 and VI.C.24, it does not seem to me that-the comparison is very good,-particularly L in the; vicinity of 20 Hz. Similarly, I don't think the agreement -is very good '
between the ratios shown in Figures VI.C.47 and VI.C.48. .The consultants apparently consider disagreerents by a factor of two as matters of trivial
.importance. That being the case, they will presumably not object to raising _
their final answer by a factor of two.
The problems discussed.above are the most important issues I see at this time. -In going through the report I noted some minor. problems. At the bottom of page 1, it _is stated that the results of the pad tests comfirm testimony at the 1982 ASI.B hearings. -I do not.believe that is the -case. You-have access
.to the transcripts and _could check. If the statement is .not correct, perhaps
- it should be deleted; otherwise, the record gives a false impression of consistency. I don't understand the last paragraph on page 8.- I expect you "do. but, if not, it should be clarified.
It is not clear to me that the reasons they give on page 9 (paragraph 1) are adequate to'show that the Auxiliary Bullding motions-are representative _of motions in the Intemediate Building; an engineer should look at this. On page 10, paragraph 2, -I don't .
understand why motions recorded in the sump would overestimate motions
- expected on the main floor of the Diesel. Generator Building. Either Figures
! IV.A.7 and -IV.A.8 are mislabeled or Figure IV.C.3 is mislabeled. The labeling ,
i . of Figure V.C.1'.is inconsistent. Does it represent data recorded at site F3 '
or' site FR7 In Table C.V.1 the tem " Code Revision #" should be defined. On
,, page 43 of Appendix B, line 13 up from the bottom, a reference is made to Figure _VI.C.7' when Figure VI.C.6. is obviously intended. The discussion in the first paragraph'of page _43 of the differences between spectral ratios
-computed for different time _ windows is entirely in terms of the vertical
, component. It-would have been more relevant if it have been done for the horizontal components.
If you want to discuss any of these problems before the meting, give me a cal l .
Best regards, William B. Joyner Geophysicist Copy to:
yMed Algemissen
r
/s.A~s United States Department of the Interior
- GEOLOGICAL SURVEY OFFICE OF EARTHQtlAKES, VOLCAN0ES ' AND ENGINEERING '
Branch of Engineering Seistology and Geology 345 Middlefield Road, MS 77
'Fenlo Park, CA 94025 April 8, 19P.3 Dr. Jerry L. King U. S. Nuclear Regulatory Commission Mail Stop P-514 Washington, D. C. 20555
Dear Jerry:
Bill Joyner and I agreed that he would review the explosion tests, and I would review the forced vibration tests on the pad.
I have found no analytical errors in either the stiffness or r'odal approach. The stif fness rethod which was correctly elected to be the h
fundamental nethod of analysis is a rigorous method and ivolves no assumptions, except that of linearity. However, it is obvious from the-results that something is amiss. This is shown by the neaative damping obtained, by the large value of the transfer functions, by the fact that the resonance of the hut appears in the value of toe stiffness functions Kyg, K12' K21, and especially in K22, by the strange behavior of K12 and K21, and by the fact that the real part of K, should be approximately a constant value. It is hard to suggest why this is all so. Suggestions about the phases being difficult to determine are a possibility. Certainly, it is difficult to l
separate out the needed information from cmplex data where all the modes are I
being excited at the same time, unless the reasurements are very clean and the equations well conditioned. Possibly, it would be better experimentally if i-
~
the hut was removed and treated separately and a pure torque obtained from two l
out of phase vibrators, symnetrically placed, be applied. Similarly, a translation notion with ninimum rotation could be obtained by exciting the pad
(
through its center of gravity by a horizontal rod connected to a vibrator j 1 hk L
=
. N ,
a 6
placed on the adjacent ground. This would be experimentally more difficult, but may praduce more tractable measurements.
The essential assumption in the modal approach is that classic normal modes exist. This is' not strictly the case in this application because the
~
compliance. functions are frequency dependent.- This frequency dependence is shown-in Figures 4 and 5 of the enclosed paper for the case of translation and rotation of a circular plate' on the surface of an elastic halfspace. If we assume a shear wave velocity of 600 ft/sec then for an effective r value o of 2.3 ft., the value of tha non-dimensional frequency factor a o is 'about 1.2 for the resonant frequency of, say, 50 Hz. For this value of ao it is to be noticed that.the values of fj -and fj are not too different from their values at a o= 0 and consequently, the modal approach is a reasonable approxi-mation. C. B. Crouse, in a private communication, has pointed out that-this is an embedded foundation (18" embedment) and that Dominguez (referenced in the Ertex Appendix A) has shown that this degree of embedment substantially l' changes the compliance functions- from those of a foundation on the surface. I l have not yet seen this reference. Presumably Dominguez assumes that the l
sides of the foundation can take tension as well as compression. I assume
-that compaction takes place at the sides and so the effective embedment is somewhat less than 9" and that the plate on the surface is'a reasonable approximation ~. The results obtained from the modal approach appear entirely feasible. We have programmed Eq. 58 of the enclosed paper in order to nake an l analytical assessment of the problem and initially obtained values of the I free-field similar to those of Appendix A. The effect of the hut was not included on the assumption that we-are most interested in the region of the second resonance. However, at the last minute of writing this note, we suspect our computer program and are currently checking it out. We used the following values of the parameters:
e r- ,- ,,m-r l.,-,..,-e- - - , , - - - . . - , - ,,-,a - ,en- , , - - - - - , ~ -e-, , , -- ,
Shear wave velocity = 600 ft/sec by = 3.0 b2 = 1.0 A y = 0.45 A2 " 1*2 The value of R discussed in the enclosed paper for these parameters has not yet been calculated. Figure 8 in the enclosed paper shows R for values of t'.e r parameters somewhat. different from the above values but roughly in the ,
same region. Remembering that a, = 1.2 corresponds to' about 50 Hz a comparison between Figures 8 and 9 of the enclosed paper and Figures 4 and 13' of Appendix A shows that they fall in the same ballpark for the second
- resonance. The relevant larger value of by = 3.0 will increase the value of R shown in Figure 8.
Bill Joyner notes that as the modal approach is not completely rigorous, it would be useful to make a comparison between the observed displacement amplitude and phase such as shown in Figure 4 of Appendix A and the predictions of the model obtained by the modal approach.
. Conclusions
- 1. The results of the stiffness method are invalid.
- 2. The results of the modal method appear entirely acceptable.
Sincerely, G. N. Bycroft Physical Scientist topy to:
T. Algenaissen