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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:UTILITY TO NRC
MONTHYEARML20059K4071990-09-17017 September 1990 Advises That Author Succeeded Os Bradham as vice-president, Nuclear Operations,Effective 900915.All Correspondence to Util Should Be Sent to Listed Address ML20059J9141990-09-14014 September 1990 Responds to Violations Noted in Insp Rept 50-395/90-21. Violation Occured,However Description of Violation in Error. Corrective Action:Valve XVT02803B Placed in Proper Position & Verification of Emergency Feedwater Sys Lineup Completed ML20059E2821990-08-30030 August 1990 Advises That Programmed Enhancements Per Generic Ltr 88-17 Re Loss of DHR Implemented & Mods Operable ML20059D6911990-08-29029 August 1990 Forwards Technical Rept 90-02, Seismic Activity Near VC Summer Nuclear Station for Apr-June 1990 ML20059B9541990-08-28028 August 1990 Forwards Semiannual Effluent & Waste Disposal Rept for Jan-June 1990, Per 10CFR50.36a & Sections 6.9.1.8 & 6.9.1.9 of Tech Spec ML20056B4901990-08-22022 August 1990 Discusses NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Decision on Future Insp Frequency &/Or Sys Mods Should Be Deferred Until Internal Components Could Be Inspected ML20059A2041990-08-16016 August 1990 Forwards First Semiannual fitness-for-duty Rept from 900103- 0630.Util Pleased W/Program,However,Concerned About Incorrect Test Results for Blind Performance Specimens Received from Roche Labs ML20058P6581990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 & Rev 13 to ODCM for Virgil C Summer Nuclear Station.Rev Implements Changes Necessary to Permit Removal of Radiological Effluent Specs from Tech Specs as Recommended by Generic Ltr 89-01 ML20058P7681990-08-13013 August 1990 Forwards Mods to 900516 Tech Spec Change Request Re Pressurizer Code Safety Valve Setpoint Tolerance & Mode 3 Exception,Per 900713 Telcon.Changes Do Not Affect Technical Intent of 900516 Submittal Nor Alter Safety Evaluation ML20058N6961990-08-10010 August 1990 Responds to Violations Noted in Insp Rept 50-395/90-18. Corrective Action:Personnel Counseled on Procedural Compliance & Importance of Independent Verification in Maintaining Proper Sys Alignment ML20056A3441990-08-0101 August 1990 Responds to NRC Request for Further Justification Re Relocating Emergency Operations Facility to Corporate Headquarters ML20059A3691990-07-30030 July 1990 Ack Receipt of SALP Rept 50-395/90-11 & Forwards Comments on Rept ML20056A0201990-07-27027 July 1990 Provides Notification That All Actions Re Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment, Completed ML20055H9821990-07-20020 July 1990 Forwards Amend 28 to Physical Security Plan.Amend Withheld (Ref 10CFR73.21) ML17305B7681990-07-19019 July 1990 Responds to NRC NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Transmitters Identified in Item 1 from Suspect Lots Identified by Rosemount ML20044B0241990-07-11011 July 1990 Responds to Violations Noted in Insp Rept 50-395/90-15. Corrective Actions:Relay Rewired & Verified Against Design Drawings ML20055F3631990-07-10010 July 1990 Forwards Rev 1 to Plant Core Operating Limits Rept Cycle 6, as Result of Typo ML20055E0341990-07-0505 July 1990 Forwards Technical Rept 90-1, Seismic Activity Near VC Summer Nuclear Station for Period Jan-Mar 1990 ML20055D4661990-07-0303 July 1990 Forwards Amend 4 to Updated Virgil C Summer Nuclear Station Fire Protection Evaluation Rept, Effective 900301 ML20058K4421990-06-29029 June 1990 Forwards Response to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20043F6621990-06-0707 June 1990 Requests for Change in QA Program 10CFR50.54 & FSAR Biennial Reviews of Plant Procedures Based on Justification Contained in Proposed Change to FSAR.SAP-139 Will Be Revised Immediately Following Approval of Request ML20043D5861990-06-0101 June 1990 Forwards LERs 90-004 & 90-006 Which Respond to Violation Noted in Insp Rept 50-395/90-12.Corrective Actions:Training Conducted & Tech Spec Instruments Evaluated for Adequate Testing ML20043C5001990-05-29029 May 1990 Forwards marked-up Pages to Util 900410 Tech Spec Change Request Indicating Location of Incorrect Std Refs,Per 900419 Telcon W/Jj Hayes ML20043B7351990-05-23023 May 1990 Forwards Rev 0 to Core Operating Limits Rept,Cycle 6. ML20043A9181990-05-17017 May 1990 Forwards List Detailing Tubes in Which F* Criteria Applied During Steam Generator Tube Insp Subsequent to Fifth Inservice Eddy Current Exam.Location of Degradation Measured from Tube End on Hot/Cold Leg Up to Degradation ML20043G4621990-05-0303 May 1990 Advises That Util Will Control Operations to Abide by More Restrictive Required Shutdown Margin Curve While Awaiting NRC Approval to Place Revised Curve in Tech Specs ML20042G4741990-05-0101 May 1990 Special Rept Spr 90-003 Listing Number of Steam Generator Tubes Plugged or Repaired During Fifth Refueling Outage ML20042E1931990-04-11011 April 1990 Forwards Seismic Activity Near VC Summer Nuclear Station, Oct-Dec 1989. Several Seismic Monitoring Stations Inoperable During Reporting Period & Also During First Quarter 1990 ML20012F3551990-04-0303 April 1990 Withdraws 900321 Request for Relief from Testing RHR Containment Isolation Valves Xvg 08701 A/B at Frequency Specified in ASME Section XI Code.Meeting Requested to Discuss Util Interpretation of Testing in 10CFR50,App J ML20012E9061990-03-23023 March 1990 Submits Supplemental Response to Station Blackout Re Proper Documentation & Consistent Implementation of NUMARC 87-00 Guidance.Plant Currently Maintains Targeted Emergency Diesel Generator Reliability by Ensuring Compliance W/Tech Specs ML20012E0431990-03-23023 March 1990 Forwards Corrected Pages to Rev 26 to Radiation Emergency Plan. ML20012D9691990-03-23023 March 1990 Forwards, Sante Cooper 1989 Annual Financial Rept, South Carolina Gas & Electric 1989 Annual Financial Rept Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Plant ML20012E5881990-03-21021 March 1990 Forwards Corrected Slide to Clarify Util Current Plans Re Steam Generator Insp Plan,Per 900312 Meeting W/Nrc ML20012D8271990-03-21021 March 1990 Requests Relief from Testing RHR Containment Isolation Valves Xvg 08701 A/B at Frequency Specified in ASME Section XI Code.Valves Will Be Tested at Frequency Specified for Type a Valves in 10CFR50,App J ML20012D0371990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Design of Steam Generator Overfill Protection.Util Does Not Plan to Implement Physical Mods or Administrative Changes Since Overfill Protection Sys Meets or Exceeds Guidance in Generic Ltr ML20012D4781990-03-16016 March 1990 Forwards First Annual ECCS Evaluation Model Revs Rept,Per 881017 Rev to 10CFR50.46.Rept Identifies Several Mods to Large & Small Break LOCA Evaluation Models Used at Facility & Provides Estimated Effects of Changes on ECCS Analyses ML20012C0661990-03-0909 March 1990 Forwards Addl Info Re Natural Circulation Evaluation Program Rept,Per 900208 Telcon Request ML20012A0921990-03-0101 March 1990 Forwards Response to Generic Ltr 90-01,consisting of Completed NRC Regulatory Impact Survey Questionnaire Sheets Containing Estimates of Time Spent by Managers on Insps & Audits ML20006E3411990-02-0606 February 1990 Forwards Proprietary Addl Info,Per NRC 900104 Request,Re Util Tech Spec Change Request for Elimination of Resistant Temp Detector Bypass Manifold sys,marked-up Tech Spec Pages & Block Diagrams.Encls Withheld ML20006D1241990-02-0101 February 1990 Requests Approval,Per 10CCFR50.55a,for Use of Alloy 690 Matl in Fabricating/Use of Steam Generator Plugs During Upcoming Refueling Outage.Alloy 690 Currently code-approved Matl for Steam Generator Tubing Based on Corrosion Resistance ML20011E1211990-01-31031 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Util Currently Performs Visual Insps & Dredgings of Svc Water & Circulating Water Intake Structures Once Each Refueling Cycle ML20006D2951990-01-26026 January 1990 Forwards WCAP-12464, VC Summer Nuclear Station Natural Circulation Evaluation Program Rept. Rept Provides Info to Resolve Branch Technical Position Rsb 5-1, Design Requirements for RHR Sys for Facility,Per 890719 Telcon ML20006B1211990-01-24024 January 1990 Forwards Technical Rept 89-3, Seismic Activity Near VC Summer Nuclear Station for Period Jul-Sept 1989. ML20006A7191990-01-19019 January 1990 Provides Update of long-term Corrective Action for 890711 Loss of Offsite Power.Installation of Voltage Regulator on 230/7.2 Kv Emergency Auxiliary Transformer Neither Required Nor Any Appreciable Benefit Derived from Installation ML20006A5521990-01-16016 January 1990 Advises That Util Will Validate Adequacy of Any Sys Used for Periodic Inservice Insp & Will Upgrade,As Required,Eddy Current Test Methods Used as Better Methods Developed & Validated for Commercial Use,Per 900111 Discussion ML20005H0791990-01-12012 January 1990 Advises That Response to NRC Request for Addl Info Re L* Implementation Will Be Submitted by 900801 Due to Refueling Outage Schedule ML20005F1191990-01-0505 January 1990 Forwards Description of F* Application at Plant & Sample Eddy Current Lissajous Figures for 12 Steam Generator Tubes, Per 891218 Request for Extension of Application of F* Tube Plugging Criterion for Life of Steam Generators ML20005G4921990-01-0505 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Bulletin & Core Shuffle Procedure Will Be Discussed Among Core Engineering Personnel in Documented Training Session ML20005F4531990-01-0404 January 1990 Forwards Application for Approval to Incinerate Oil Contaminated W/Very Low Levels of Licensed Radioactive Matls within Site Boundary of Facility ML20005F0601990-01-0303 January 1990 Forwards Justification for Continued Operation Re Pressurizer Surge Line Thermal Stratification,Per NRC Bulletin 88-011.Util Believes That Plant Can Continue Operation for at Least 20 Addl Heatup/Cooldown Cycles 1990-09-17
[Table view] |
Text
4 south CAROLINA ELECTRIC a gas COMPANY ] ~
.os, orrice so. ve. r_ [
COLUMBIA. SOUTH CAROLS?.A 29216 _- ., g q r.)
E. H. Ca tw s. J n. _
July 5. 1979 'm v,cc , ..
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. c . . '.'. .
p w.
co cc Mr." James P. O'Reilly, Director United States Nuclear Regulatory Commission -
Region II 101 Marietta Street, N. W.
Atlanta, Georgia 30303 Subj ect: Virgil C. Summer Nuclear Station Inspection & Enforcement Bulletin 79-02/79-02 Rev. 1 Docket No. 50-395 Nuclear Engineering File 2.8950
Dear Mr. O'Reilly:
South Carolina Electric & Gas Company has reviewed IE Bulletin 79-02 dated March 8, 1979, and IE Bulletin 79-02 Revision 1 dated June 21, 1979, and submits the attached written response as required.
Should you have further quest nq concerning this matter, please contact us.
Ve 1 ly yours, i
/ rews, Jr.
E. H.
RW:EHC:md CC: Office of Inspection & Enforcement Washington, D. C.
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70 08310lli g[05/8
.- AL COPr
V. C. SUMMER NUCLEAR STATION
. UNIT 1 NRC IE BULLETIN 79-02 XEVISION 1
1.0 INTRODUCTION
A design review was performed in response to the United States Nuclear Regulatory Commission (NRC) request, IE Bulletin No. 79-02, " Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts," dated March 8, 1979, and Revision 1, dated June 21, 1979, for Virgil C. Summer Nuclear Station, Unit 1, Docket No. 50-395. The review was performed on a repre-sentative sample of safety-related supports (Seismic Category I). Possible effects of base plate flexibility on base plate anchors were considered.
This report presents the methods and results of the review.
2.0
SUMMARY
AND CONCLUSION 2.1 Summary of Design Review
- 1. Most p3..es were determined to be flexible as defined by the NRC 2:1 ratio criteria. Therefore, plates were reanalyzed using a method in which the effects of plate flexibility, anchor preload, and shear-tension interaction were considered.
- 2. A representative sample totaling ninety-six (96) pipe support base plates for pipe of a diameter 2 1/2" and larger, all anchored with Hilti " Kwik Bolts", was reanalyzed. Of the ninety-six (96) supports studied, cue (1) had a factor of safety less than 3.0 (actual value = 2.98), three (3) had a factor of safety between 3.0 ar.d 3.5, and six (6) exhibited a factor of safety between 3.5 snd 4.0. The factors of safety less than 4.0 were determined to exist only for the faulted and upset load combinations.
- 3. All Seismic Category I supports are potentially subject to a relatively low number of seismic loading cycles which can be accommodated by the design. Operational loads which could, during the lifetime of the plant, undergo a large number of load cycles will be identified during 2035 i95 1 ,
- + '
, - , ,i, ,
('
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e
- " 4 startup (est.ing, and modifications co the pipe support syste.n will be ,
made as requ1 red tk assure that such loads are eliminated.
7 ;
2.2 Summary of QC ikgumentation OR of In-Place Inspection QC procedures provide for inspac: ion requirements as discussed in Section 3.4.
t At the Virgil C.' Summer Nuclear Station', QC documentation that design re-qui,rements have been met exists for 100% of the expansion bolts.
2.3 Conclusion s
The results of the inveMigation for the effects of plate flexibility on
- s pipe support base plate anchors indicate that, for mo.t plates anchored to concrete surf aces with Hilti " Kwik Bolts", pryins 2arcas did not exist.
Prying forces were f ound to be present on four (4) of the ninetvysix (96) plates considered and in tho e cases the prying was ret.ponsible for an average increase in the bolt tension of Jess than lDT. It is also seen that the factors of safety of the swqures reanaly,ted meet the minimum .
established by IE Bt11etin 79-02 in mort cases, with ihe vnly exceptions > ,
existing for the faulted and upset load combinations. Under these condi-tions, the factors of. 'sahty are conservativ'e. Since QC inspection is made on 100% of all expansion bolts, the resulte of this reanalysis confirm the adequacy of the original design. \
q 3.0 REVIEW RESULTS'I In consideration of the 'rsquested action, a representative sampling of base plates for large bore'(2 1/2" and larger) Seismic Category 7 pipes was re-analyzed. There are appro'xIm. ely seven hundred (700) base plates in the plant which fit this c'ategory, a'n4 ninety-six (96) have been investigated.
/'
Small bore (2" and smaller diameter) pipe was originally designed using a seismic support spacing er teria. That c:1:eria were developed based on a
? I i
\
conservative pipe stre.-ss snd a multi-span model for each pipe si.:e and
( ,'
\ <
2035 196 s 2 ,
Q -f
schedule. The model analysis provides pipe spans and support loads. This approach has been verified by sample computer analyses to be conservative relative to applicC le Code requirements. -
A serier of typical support designs was generated and load rated by analy-tical techniques. The supports were analyzed for structural adequacy for all-members, welds and the expansion anchor bolts. In generating the load rating, the most conservative combination of the maximum distance from the pipe to the structure and the smallest allowed spacing between expansion anchor bolts was used.
As a result of this conservative approach, if 15% or more of the supports on any of the small bore piping runs would fail, the piping stresses would still remain within Code allowables. Therefore, detailed analyses and in-spection of these expansion anchor bolts is considered unnecessary.
3.1 Response to NRC Item 1 Base plates were considered rigid in the original design. For reexamination of the base plates considering plate flexibility, procedures were developed for the analysis of the plates and anchorages for moment and axial load ap-plied to the plate surfaces (Figures 1, 2, 3 and 4).
Wedge anchors were installed in accordance with manufacturer's recommendations.
Bolts were torqued to the degree necessary to ensure a preload equal to or Breater than the allowable working load on the bolt. A field test program was conducted to establish for each bolt size the torque value required to ensure the required level of bolt tension.
The magnitude of the residual preload directly influences the plate rotation at the anchor, and full fixity against anchor rotation is obtained when:
(Tg -V) (L) = V
?035 197 3
Where Tg = Anchor residual preload V = Plate shear L = Effective edge distance of the plate from the tensile anchors e = Distance from the edge of the attachment to the tensile anchors With full fixity against nachor rotatir... the plate deflection transverse to the surface of the plate at the face of the attachment is the same as
~
support settlement of a member fixed at both ends.
As long as preload exceeds plate shear, some resistance to anchor rotation exists. When T < V, there is free rotation of the plate at the anchor, and the plate deflects as a cantilever.
Preloaded wedge anchors have a remory of their ma imum load and will not experience inelastic displacements until a load larger than the installation preload occurs. At loadings less than the installation preload, the anchors will function essentially elastically even though the actual loading exceeds the residual prelond on the anchor. If the actual load is less than the residual preload, the bolt is essentially prestressed, and the stress re-mains approximately constant under this load. The performance of a pre-loaded wedge anchor is the same under dynamic as under static loadings; that is, the anchor will not experience inelastic displacements (1. addition to that which occurs during installation) until the anchor is subjected to a load greater than the installation preload.
Based on the plate and anchor response as described above, procedures were developed to determine tensile forces in the anchors, as shown in Figures 1, 2, 3 and 4. Shear and tension effects were combined directly to evaluate the factor of safety of the anchors, with the shear force being distributed equally to all anchors in the connection. The method of combining these effects is described in Section 3.2.
. 03.5 l98 4 ,
3.2 Response to NRC Item 2 The concrete expansion anchor bolts used at V. C. Summer, Unit 1, are the
" Kwik Bolts" as manufactured by Hilti, Inc. This is a wedge type anchor for which NRC Item 2(a) specifies a minimum factor of safety of four (4). The results of the reanalysis are su=marized in attached Tables 1 & 2.
The f actor of safety against failure (F.S.) is conservatively determined using the following shear-tension interaction equation:
(F.S.) (T ) (F.S.) (Sg )
+ = 1 (T,) (S,)
Where: F.S. = factor of safety against failure T = Tension force induced into an anchor (considering 0 plate flexibility)
T e ultimate tension capacity of an anchor
= Shear force induced into an anchor S, = ultimate shear capacity of an anchor *
- From manufacturer's static load tests Expansion boS placement in the structure is governed by the following criteria:
- a. A minimum edge distance between the bolt centerline and the edge of a concrete member equal to 5d or 4 inches, whichever is greater.
- b. A minimum spacing between adjacent bolts on each base plate of 10d, where d is the diameter of the bolt, unless otherwise approved by the Engineer. Also, due to various field installation problems udth locations of adjacent base plates, there is a small percentage (estimated at less than 3% of all cttachments) of occurrences where the minimum spacing of 10d has not been maintained between anchor bolts of adjacent plates. This situation is presently being investigated and such occutrences will be evaluated on a case by 7035 199
case basis for design adequacy.
3.3 Response to NRC Item 3 Pipe support reactions are generated as an output of a dynamic analysis and are utilized for the design of the individual pipe supports. Therefore, theoretically, a dynamic amplification factor was not required.
However, to provide for the effects of hardware and erection tolerances, the OBE seismic part of the reaction is multiplied by a factor of 1.5 to produce a design load. This factor provides additional design margin on the dynamic part of the loads.
The governing load combination including the 1.5 factor is:
Deadweight + Thermal + (1.5) OBE + Occasional 5 Allowable Seismic Mechanical Anchor Loads Bolt Load In order to ensure cyclic load carrying capability, wedge type anchors are installed by applying a torque of sufficiant magnitude to set the wedges at a bolt preload equal to or greater *.han the maximum allowable working load.
3.4 Response to NRC Item 4 (a) As described in Section 3.3, in order to ensure cyclic load carrying capability, vedge type anchors are installed by applying a torque of suf ficient magnitude to set the wedges at a bolt preload equal to or greater than the maximum allowable working load. Also, a field test program was conducted which established for each bolt size the torque value required to ensure the required level of bolt tension. The QC inspection requirements are described in sub-item (b) below where it is stated that documentation exists for 100% of the expansion bolts on the torque value applied in the field. This level of inspection verifies that the design requirements have been met for each anchor bolt.
It is also noted that there are no shell type anchor bolts being used at the Virgil C. Summer Nuclear Station.
703S 200 6 '
(b) The design specification and associated QC procedures require inspection In addition, of expansion bolts relative to the installation criteria.
all bolts in one out of every ten connections, but not less than 10%
of the connections made by each crew, shall be inspected for compliance with skewness. Connections shall also be inspected for bolt tightness with a calibrated manual torque wrench in not less than 10% of the con-nections made by each crew.
The above are the minimum inspection requirements; however, for the Virgil C. Summer Nuclear Station, QC documentation that design require-ments have been met exists for 100% of the expansion bolts as follows:
bolt hole location, cleanliness of hole, depth of hole, bolt size and length, depth of grout, bolt torque and skewness.
Based upon the requirements of IE Bulletin 79-02, for all subsequent expansion bolt installations the QC inspection checklist will include bolt spacing within the plate and to adjacent holes, minimum embedment depth and thread engagement. We do not feel that it is necessary to verify the embedment depth and thread engagement for existing instal-lations due to the 100% inspection program already in effect.
At the Virgil C. Summer Nuclear Station, base plates which have been grouted were raised from the supporting surface by shims and washers. Leveling nuts were not used.
2035 20l 7
TABLE 1 RESULTS OF BASE PLATE ANCHOR REANALYSIS UPSET LOAD COMBINATION Anchor Factor of Anchor Factor of Mark Size O Safety Mark Size 0 Safety Smi-220 5/8 19.3 RHH-215 Dia. Leg 3/4 4.25 CCH-474 Vert. Leg 5/8 10.7 RHH-233 3/4 10.28 CCll-474 Dia. Leg 5/8 7.7 RHH-125 3/4 35.9 CSH-185 5/8 10.2 Smi-116 Ver t. Leg 3/4 15.84 SPil-291- 5/8 8.0 SLH-116 Dia. Leg 3/4 9.00 CCH-475 5/8 10.1 SMI-139 3/4 10.9 SMI-203 5/8 11.9 SkT-078 3/4 24.43 FMi-225 5/8 11.2 SWH-067 3/4 5.7 CCH-773 3/4 6.2 SWH-065 3/4 11.13 CSH-196 3/4 14.3 RHH-281 3/4 7.6 SWH-204 3/4 3.28* RHH-105 3/4 12.2 CCH-297 3/4 22.4 RHH-108 Vert. Leg 1 9.14 SMI-207 3/4 5.67 RHH-108 Dia. Leg 1 4.96 CCH-473 3/4 12.3 RHH-216 Vert. Leg 1 7.47 Smi-114 Vert. Leg 3/4 5.7 RHH-216 Dia. Leg 1 4.39 SMI-ll4 Dia. Leg 3/4 6.5 RHH-267 1 21.6 FMi-253 1 13.4 RHH-280 1 33.6 FMi-218 1 9.0 SWH-138 Vert. Leg 1 4.05 SWH-218 1 3.52* SWH-133 Dia. Leg 1 4.19 FMi-262 1 3.57
- SMi-124 1 6.5 Fmi-255 1 5.10 RHH-283 Vert. Leg 1 35.11 Smi-138 Vert. Leg 1 5.20 RHH-283 Dia. Leg 1 52.66 SWH-138 Dia. Leg 1 6.00 RHH-185 Vert. Leg 1 7.12 RHH-263 Vert. Leg 1-1/4 12.5 RHH-185 Dia. Leg 1 3.79*
RHH-263 Dia. Leg 1-1/4 9.2 RHH-268 1 9.56 MSH-226 5/8 23.92 RHH-263 Vert. Leg 1-1/4 11.97 MSH-244 5/8 38.27 RHH-263 Dia. Leg 1-1/4 9.18 MSH-207 5/8 21.99 RHH-204 Vert. Leg 1-1/4 9.1 MSH-216 5/8 27.17 RHH-204 Dia. Leg 1-1/4 4.95 MSH-167 5/8 15.53 RHH-173 1-1/4 5.07 MSH-272 5/8 5.89 MSH-218 3/4 27.25 MSH-057 3/4 5.82 MSH-062 3/4 2.98*
70.42 r ')
MSH-246 Vert. Leg MSH-246 Dia. Leg 1
1 39.5
'T)0 '3 d /02 MSH-158 Vert. Leg 1 47.15 MSH-158 Dia. Leg 1 26.53 MSH-250 Vert. Leg 1 7.75 MSH-250 Dia. Leg 1 6.53 MSH-183 Vert. Leg 1 6.17 MSH-183 Dia. Leg 1 4.58 RHH-102 Vert. Leg 5/8 53.6 RHH-102 Dia. Leg 5/8 39.5 RHH-269 5/8 11.0 RHH-173 Vert. Leg 3/4 13.8 RHH-215 Vert. Leg 3/4 7.78
TABLE 2 RESULTS OF BASE PLATE ANCHOR REANALYSIS FAULTED LOAD COMBINATION Anchor Factor of Mark Size O Safety RHH-263 Vert. Leg 1-1/4 4.00 Rint-263 Dia. Leg 1-1/4 3.7
- MSH-246 Vert. Leg 1 6.04 MSH-246 Dia. Leg 1 3.39*
MSil-158 vert. Leg 1 6.04 MSH-158 Dia. Leg 1 3.39*
RHH-269 5/8 6.99 RHH-173 Vert. Leg 3/4 9.9 RHH-281 3/4 5.54 RHH-267 1 5.6 EHH-280 1 17.6 RHH-283 Vert. Leg 1 28.43 RHH-283 Dia. Leg 1 42.66 RHH-185 Vert. Leg 1 7.73 RHH-185 Dia. Leg 1 4.11 RilH-268 1 4.1 RHH-263 Vert. Leg 1-1/4 4.01 RHil-263 Dia. Leg 1-1/4 3.7
- RHH-173 Dia. Leg 1-1/4 3.64 *
COhJ OITION 1 a
F
-H- -
a v V*I a
V9
\ .= , . * '
x *.._ ~ : ? ; .,
ll . . ,
,, _=i
=.
. .:. s ty ,..
G __L - -
WHEN (Ta -V)L = Vy , ANCHOR LO AD T. T4 = PRELO AD IN THE ANCHOR.
T = TOTA L L O A D I N AN C H O R Ti . PR ELO AD IN ANCHOR llGURE 1 2035 204
- 4F
-p-;
CONDITION 2 ay
~
~
Vf 6 ",..
, .2
.my 'l r
L =
Py = mWG NE WHEN V > Tl 4 h
PROBLEM T=v 4 P y THE PROBLEM 15 SOLVED BY SUPERPOSITION,USING PARTS i AND 2 BELOW AV Ve' 3EI q
^
Ve ('O C
Q ] _Ve' , 33 )
n_ 3El 2e /
o "
k h ul y O '- ve2 g PART I , , . ,
V-Tl 2EI o'
Ve L _ V-Tl ks
~2EI ks 03 I i u u ,I c '
ds 2 i_ __ __ _ - __ _ : - l i o pv a h a b b "
?
o2 py py ks PART 2 3
Pv L 2 , pv L 6 Pv L 03=0 4-0 2 EI SEI + 's" AG 3 Py L Pv Py Py L7e PvL *6S
=
O PV = 0 3+ u EI +3EI AG ks EQUATING o,= o pv ; P v= - ( V-T l ) +h+ +j (EQ.1) ff < No A R YI N G E X t ! T.S AtJO 7
[F $c! >Y SO L U T10M of E Q-1 YEILDS THE PRYIN6 FOR ryr TOTAL B ot.T FORCE IS V
CONDITION 1: NO TENSION ANCHOR ROTAT4ON OR DISPL ACEMENT M e.
G V
LV 1
v u? g ll L 4-W + e 'Li C T T= TOT AL LOAD IN ANCHOR Ti- PRELOAD IN ANCHOR FOR M 6 ( , g ,)( L+W t e) , T=Ti PRYtNG FORCE = 0
035 206 FIGURE 3
CONDITION ?. : TENSION ANCHOR ROTATION AND DISPLACEMENT M 6 M
~
\
v \
' V
- L 3
T-Ti o 00* Ks
@ A h h a ll C L+ W + e Li '
p Pv T=V+ Pv T TOTAL LOAD IN ANCHOR Ti:PRELOAO IN ANCHOR T = V 4- P v a a = T-Ti gg V Lt
- * ?_EIp L: 03- + ggy - & W - O e.
7 M &Pvli v
V-Ti
'Ol i pv. 2EIg,,g Kst,y g,
Ks El SEI 5 AG V-Ti V e* L i
~
18 t
IF V-Ti < Veggy Li -GLi, SIMULTANEOUS SOLOTION OF THE 6 61% EQUATIONS GivEN ABOVE WILL YlELD THE LOCATION OF THE COMPRESSIVE FORCE C AND T HE. M AC,NITUDE OF THE PRYINc, FORCE Pv
'b FIGURE. 4-