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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
'
[ ,, , , , , 10CFR2.201 l . '. .,
., to th Carolina Electric & Gas Cornpany Da Jenkinsville. SC 29065 Nuchar Operations SCE&G """
> =a - May 25, 1988 Dr. J. Nelson Grace Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Response to Notice of Violation NRC Inspection Report 88-01 Gear Dr. Grace:
Enclosed is the South Carolina Electric & Gas Company (SCE&G) response to the violations addressed in Enclosure 1 of NRC Inspection Report 50-395/88-01.
SCE&G is in agreement with the alleged violations, and the enclosed response addresses the reasons for the violation and corrective actions taken to prevent recurrence. In addition, and updated Equipment Qualification Enhancement Program schedule is enclosed as discussed during a conversation with Mr. A. Ruff on May 18, 1988.
If you should have any questions, please advise. \A
~
S Very truly yours, ,
Y! gw
. . an _
HIO:0AN/bgh Enclosures c: J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts W. A. Williams, Jr. G. O. Percival General Managers R. L. Prevatte L. A. Blue J. B. Knotts, Jr.
C. A. Price M. D. Blue R. B. Clary B. L. Johnson W. R. Higgins NSRC J. R. Proper RTS (IE 88001, 04, 05)
R. M. Campbell, Jr. NPCF K. E. Nodland file (815.01)
J. C. Snelson
\
8806200027 880525 l l PDR ADOCK 05000395 0 .
DCD , , , ,
^ '.'...'.
~'
' Enclosure I to Dr. J. Nelson Grace Letter May 25, 1988 "
Page 1 of 1 ENCLOSURE I RESPONSE TO NOTICE OF VIOLATION VIOLATION NUMBER 50-395/88-01-01
- 1. ADMISSION OR DENIAL OF THE ALLEGF0 VIOLATION South Carolina Electric & Gas Company (SCE&G) is in agreement with ,
the alleged violation.
II. REASON FOR THE VIOLATION ,
A grace period was incorrectly applied to the lubrication schedule of the Emergency Feedwater (EFW) Pump, MPP0021A. This improper input into the "CHAMPS" program allowed a 25% grace period to be applied to the lubrication schedule for the EFW pump motor which requires lubrication every 12 months. This three (3) month grace period extended the maximum period to 15 months. Justification was provided to show that the motor remained qualified until the lubrication maintenance was performed. .
L III. CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVE 0 The identified EFW Pump motor was lubricated on January 21, 1988.
IV. CORRECTIVE ACTION TAKEN TO AV0!D FURTHER VIOLATION SCE&G is in the process of reviewing the maintenance history of all 10 CFR 50.40 qualified equipment. In addition, SCE&G has reviewed the required maintenance for EQ equipment. Upon completion of these reviews, a comparison will be made between the maintenance that is required and the maintenance that has been performed. Any l discrepancies will be resolved.
V. -DATE OF FULL COMPLIANCE The identification of all I.Q equipment requiring maintenance was completed on May 15, 1988. The maintenance history review of 50.49 equipment and the incorporttion of the requirements into an EQ maintenance manual is sch'sculed to be completed by August 15, 1988.
l l
' Enc 1csure II to Dr. J. Nelson Grace Letter May 25. 1988 Page 1 of 1-ENCLOSURE II RESPONSE TO NOTICE OF VIOLATION VIOLATION NUMBER 50-395/88-01-04 I. ADMISSION OR DENIAL OF THE ALLEGE 0 VIOLATION South Carolina Electric & Gas Company (SCE&G) is in agreement with the alleged violation.
II. REASON FOR THE VIOLATION Ouring a review of the lubricant grease Equipment Qualification (EQ) file, the NRC inspection teu noted a lack of documentation with respect to similarity between the Gulf lubricants and the other lubricants that replaced the Gulf lubricants. In addition, other lubricants were also omitted from the EQ file. The lack of programmatic controls allowed the EQ file to be affected by equal-to-or-better-than evaluations without being properly revised.
Supporting documentation existed, but had not been properly incorporatea into the EQ file.
III. CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVE 0
, The lubricant EQ file has been reviewed and will be revised to include the proper documentation.
IV. CORRECTIVE ACTION TAKEN TO AVOIO FURTHER VIOLATION Engineering procedures now provide for proper programmatic EQ file input and review. In addition, the Virgil C. Summer EQ file is being reconfigured/ reformatted to make it more accessible.
V. DATE OF FULL COMPLIANCE The lubricant EQ file will be revised by September 2, 1988. The programmatic controls for proper EQ file input and review are in place. The EQ procedure was created on March 1, 1988. The proper instructions for EQ input for equal-to-better-than evaluations was proceduralized on February 21, 1988
Enclosure III to Dr. J. Nelson Grace Letter ,
May 25, 1988 Page 1 of 1 ENCLOSURE III RESPONSE TO NOTICE OF VIOLATION
-VIOLATION NUMBER 50-395/88-01-05
- 1. ADMISSION OR DENIAL OF THE ALLEGE 0 VIOLATION South Carolina Electric & Gas Company (SCE&G) is in agreement with the alleged violation.
II. REASON FOR THE V!OLATION The cause of the violation, relative to the D. G. O'Brien penetrations, was due to an incorrect assumption made during the insulation resistance (IR) calculations. It was assumed that the -
straight line extrapolation of test data would provide a valid result. This was later found to be incorrect. The use of incorrect IR values for the Conax penetrations was due to the incorrect report being referenced in the EQ file. This report did not contain the post LOCA data.
III. CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVE 0 SCE&G has elected to pursue additional test reports which provide IR readings taken during LOCA test conditions for both the Conax and 0.G. O'Brien penetrations. These reports are being used for the basis in determining the IR values used in the instrument loop accuracy calculations. These reports will be entered and referenced in the EQ program. In cases where test reports were obtained from other utilities, a commonality analysis was performed to augment the EQ file to reflect the similarity of penetration connections and terminal blocks. The bounding document which provides analysis, calculations, and justification for the affect of IR on instrument loop accuracies will be the Instrument Loop Insulation Resistance (IR)calculationsdocument(VCS-0423-0C15).
IV. CORRECTIVE ACTION TAKEN TO AVOID FURTHER VIOLATION IR values used for calculations will be documented and controlled through the Instrument Loop Insulation Resistance (IR) calculations document (VCS-0423-DC15). The additional reports used in determining IR values during LOCA conditions will also be added to the EQ file.
V. DATE OF FULL COMPLIANCE SCE&G will be in compliance with respect to the corrective actions as stated no later than September 15, 1988.
I
Enclosure IV to Dr. J. Nelson Grace Letter May 25,1988 -
i i
ENVIRONMENTAL QUALIFICATION ENCHANCEMENT PROGRAM '
ACTIVITIES AND SCHEDULE 1
4
A. TRAINING REsPON$lBM ACTIVITY PERSON 348 4/88 s/88 6/88 7/88 8/88 9/88 10/89, ' STATUS 11/88 12/88 If ' 39 3/89 I I I I I I I I I I T i
- 1. Upgrade EQ Training Program for Jim Loftin l,
Maintenance and QC Personnel + (Completed)
(40) Complete s/1
- 2. Establish EQ Training Program for Jim Loftin l Bids recieve week Er.gineering + Steve Carrol!
6/30 f 5/23/88. Under evaluation 3 Complete initial Train ng For i
Jim Loftin Erigmeenng + Steve Carroll ) g, See item A.2 ggo). above t
4 Complete Initia! Training for Jim L ftin Training in g
( 40)"
Maintenance and QC + progress 5 Develop Program for Continuing EQ Training on a Regular Periodic Basis Later i
Total Manhours: 1200 Includes cours2 preparation time by training and manhours of course participants
- Inctodes course preparation time for training and manhours of course participants
+ Activity associated with a NRC Commitment legend: > x/yy = Wojected
. - -- - - - - -- - - - -- - - - -- - - - - + Co m plet ed Task (55) completion (zz-c) date estimated estimated contractor SCE8G Manhours manhours
B. MAINTENANCE -
Activity Responsible Person 3ess 4/8a s/88 6/86 7/e8 828 938 10/88 11/88 12/88 1/89 2/89 3/89 Status i I I I I I I I I I I I I
- 1. Completeinspectionsof J. Yon harsh environment equip. + > complete du ing refuel *4 gii,7is) 12/15
- 2. Continueinspection of riild J. Yon (4.455) progress to be evaluated environment splices y 9/16 pnor to RF #4
- 3. Continueinspection of mild J~ Yon a" environ equip for other "' 9'*"* * ***'""d enwironmental qual. concerns > 9n6 ""
- 4. Issue M51s for Instrumentation + J. Yon (60) completed 2/11 8"alissuecomplete Revision in croc<ess 5 'teview Maint. history of J. Yon --f (100) Complete for Electrical all 50 49 qualified equip. &
forward results to Engineen_ng +
46
- group.1&C Review in progress 6 issue M5is for future disposition J. Yon N contmuing as Required of NCN 2852 (40) 6n
- 7. Implement future disposition J. Yon F j yji5 Complete during RF #4 af NCN 2852 as issued ' ( , , ,)
8 Complete evaluation of J. Yon I C *0' d""ng RF # 4 potential mixed grease and (40) for s remainmg vivs that are repor t results to Engineering +
inauen.ble dunng ops
- 9. Revise EMPs, eCPs, & MMPs to J. Yon >
incorporate EQ Concerns (220) 8/1 in progress See Engineer Activity 1-3 Total Manhours: 16,670
+ Activity associated with a NRC commitment
B. MAINTENANCE (CONT *D.) .
Responsible ACTIVITY Per;on 3/88 4/88 sees sees 7/88 8/88 9/88 io/88 11/88 12/88 i/89 2/89 3/89 Status
- 10. Develop temp. control I I I I I I I I I I I I i J. Yon ,
methods to ensure maint. is done ' MSI-34. Rev. O issued for on qualified equip. or the (40) review & comment 3/30 &
6/1 replacement of qualified equip. I&C comments being is reflected in EQ files resolved
- 11. Gen /Rev. Maint. Proc. to J. Yon Later "Close Documentation Loop" to ensure EQ files are kept up to date
- See Engineer Activity 1-3 Total Manhours: 16.670
,C. ENGINEERING
- 1. Field Walkdowns .
Activity Responsible Person 3/88 4/88 5/88 6/88 7/88 8/88 9,88 Status 10/88 11/88 12/88 1/89 2/89 3/89 E 5 E B B B B 5 5
'****+
5 5 5 5 i c lanf y insp (ntena for J. Mundy Complete mst r umentation +
(32) Completed 2/11 c Determine need to continue B. waselus > Initial determination to nJd E Q insp (other than (40) 8/15 Continue inspections; will
.pi,c es) re-eva'uate by 8/15 3 ev av.ae insp cntena for re-riaining stems (7.2KV mtrs.
- 5. Carroll ) 7.2 kv motor NCN disp.
(41) (160-C) 7/1 issued: Rotork MOV 1:otor k vivs. etc ) Review M515.
Criteria 10 follow 4 Add motor drain infor. J. Mundy --
--- 4 Complete en.in..n for unws to NC N (4)(16-C) Completed 4/6 s u.ma e Rwsi Pit Spli(e J. Mundy ) G/C MRF issued for I/R on so ri.w.a.ng (120) (240-C) 6/15 5/2/88 6 Pniv.de ingr support for eval B. Waselus -
l Field walk downs dunng RF #4 + (680) (1,020 20 m/h per day @ 85 days) 12/31 7 Generate simple /(oncise status hst refle(ting (ompleted (40) woe k & insting implementing 6/15 dot umerits MSI. T 5. etc )
of work lett to be done
" 9 we* Ms's & P"> vide input J. Mundy i,vn va t..mment ,esolution ..........4 (Comple ted) Complete S. Carroil (60) Sfg
+ Activity associated with NRC commitment
l lI. EQUIPMENT QUALIFICATION FILE WORK -
.~.
Responsible ACTIVITY Person 3/88 4/88 5/88 6/88 7/88 8/88 948 10/88 11/88 12/88 1/89 2/89 3/89 Status i
3 I I I I I il l I I I I I
- 1. Complete file revisions required To be completed B W asetus asa result of followup action of the (35) (250-C) 9/2 during impell EQ EQ Audit + File Upgrade
- 2. Add field walkdowninformation 8 waselus ; To b(. completed during
- to EQ Files (75) (750-C) 2/28 Impell EQ File Upgrade for available data - remainder to be added later 3 incorporate summary evals. into files and consider reconfiguring B. wasetus l To be completed during (710) (1500-C)(75 @ 20 hr) 9/2 Impell EQ File Upgrade files. As a min. include a summary of qual. parameters, req. installa-tion parameters, & delete / relocate history data. +
4 Resolve Impell "Open items" 8. wasetus To be completed during c>n EQ Files (100) (1000-C)(50 @ 20 hr) l 9/2 Impeli EQ File Upgrade
- 5. Identify all required maint. for - - - -
- t Completed 5/15 Preliminary data base environmental qualified equip. 8 * ' *'u' complete; see item C.llt.3 not just that above the normal (40) (400-C) maint specified elsewhere +
- 6. Add seismic test reports to 9/2 a wasetus To be completed EQ files (100) (1500-C) (150 @ 10 hr) during Impell EQ File Upgrade
- 7. Incorporate item B-12 tater (maint feedback of field work) into E..g proc. & EQ files 8 Develop generic issues file Later
- 9. Rev equip. class. based on actual tater environmental data & zone maps deveioped as part of Eng. Item Vil-2
- 10. Establish seismic files for NSR toter equip. without existing EQ files
111. EQUIPMENT QUALIFICATION INDEX AND MAINTENANCE MANUAL ..
REsPONs!BLE PERSON 3/88 4/89 $/88 6/E8 7/88 8/88 9/88 10/88 11/88 12/98 1/89 2/89 3/89 STATUS I I l I a a a g g g i a
- 1. Determine desirability to continue Prelim. position B. Waselus l to maintain mild environment equip. in is to maintain the the equip. qual. index & maint. manual. (24) 6/15 Mild files; Consider archiving mild evaluate environment equip. qualification files cost / benefits by 6/15 2 Resolve disagreements between S. Crumbo in progress, also the index & Champs, Master List, 6/15 associated with (60) (100-C)
FSAR, etc. "9' 05 -
Two (2) discrepancies still need resolution
- 3. Incorporate identified maint. +
- 5. Crumbo > Impell Prelim.
requirements from Task 11-5 int manual & issue to Maintenance; Maint. Manual review results of item B5 and (40) (80-C) 8/15 received 5/16/88; disposition as required. Reviewin progress
- 4. Resolve discrepanciesidentified +
by review of PM tasksin CHAMPS S. Crumbo y unnpared to recommend vendor tasks (100) (200-C) 9/2
- 5. Incorporate Maintenance Require.
Later into CHAMPS or Master List data base
+ Activity associated with a NRC commitment
IV. OPERABILITY REVIEWS,JCOs AND WALKDOWN EVALUATIONS '-
Responsible ACTIVITY Person ima 4ma s/88 6/88 7m8 8m8 9/88 10/88 11/88 1248 1/89 2/89 3/89 Status
' ' ' ' I I I I I I I ' I
- 1. Revise JCO for splice list + Complete items to include new circuits from J. Mundy --- -f G/C (10) (32-c) Completed 3/15
- 2. Complete Review of field +
- 5. Carroll I
Wa downs of harsh equip. for t
Impell to provide C tra tor Services for
- 1. Complete evaluation of 81 + J. Mundy --+ Completed 3/15 complete additional potentially spliced terminations locludein Disp. to (40) (160-C) .
NCN 2852.
- 4. Complete evaluation of group S. Crumbo .........y Completed 4/22 10 valves & include in disp. t Complete j NCN 2852 (Six valves) (40)
- 5. Evaluate timitorque Bolt S. Crumbo m Discrepancies r On schedule (60) (200-C) 6/15
- 6. Complete review of field walk 5. Carroll (160) (1.610-C) downs of mild equip. for (10 hr per pkg) reportability later
+ Activity associated with a NRC commitment
V. EQUIPMENT QUALIFICATION MASTER LIST ' '
t' Responsible ACTIVITY Person 3/88 4$8 5/88 6/88 7/88 8/88 9/88 10/88 11/88 12/88 1/89 2/89 3/89 - bIOIUS a I s a a a a a a a a i s
- 1. Update FSAR, Resolve R.G. + F.
& G/C scope document to be 1.97 Category 2 items Thompson '
- 9) g c) issued by 6/3.
- 2. Complete & verify data base for S. Crumbo t G/C developing data base.
new Master List (including sub '
components & sealin9 5g 9 requirements
- 8/1
- 3. Resolve disagreements between S. Crumbo data base and CHAMPS, FSAR.
Associated with Eng. Item
& G/C List V.2 (80) 8/1
- 4. Develop procedure to control S. Crumbo > Not yet started new Master List & issue as a (80) controlled document 9f3
- 5. Rewrite FSAR Section 3.11 to be Later (onsistant with current regutations
- 6. Tie essential equipment list to Later data base 7 Tie Master List Data Base to Later CHAMPS
+ Activity associated with a NRC commitment i
I
V
I. PROCEDURE
REVISIONS ., .
Responsible ACTIVITY Person 348 4/88 s/88 6/88 7/88 848 9/88 10/88 11788 12/88 t/89 2/89 3/89 Status
. I I I ! I I I I I I I I i 1 Revise TS-301 toinclude EQ M. Curtiss ) issued for comment concerns 7/1 2 ReviseTS-137,114, & 144 T. Curtin to ensure EQ concerns
) T5-13 7 issue for comment-S. Carroll (90) are addressed & proper interfaces 7/31 TS-144 issued for comment at e covered 15-114 issued for comment
- 3. Revise MD-#31 to better address B. Waselus t Not yet started EQ interfaces and functional r 7/31 responsibilities (30)
+ Activity associated with a NRC comment
9 Vll. ENVIRONMENTAL PARAMETERS . - -
Responsible AGIVITY Person 3/88 4e8 se8s 6/88 7/88 8/88 9/88 10/88 11/88 12/88 1/89 2io9 3/89 Status I i i I i i i i i i I I i
- 1. Complete MRF on correcting G. Baker )
over temperature conditions in MRF written; G/C preparing poo) (soo-c) 7/1 scope to perform design IB 436 2 Develop Environment zone B Waselus '
maps ' 8/1 G/C Performing Task (4g3 g433.c3
- 3. Issue TRP on NNS HVAC Systems 5. Crumbo servicing areas containin9 ) 8/1 G/C 5 cope estimate expected (60) (300-c) by 5/31/88 environmental qualified equip.
2 4 Review other parameters (radia- S. Crumbo tion, humidity, etc.) to determine l /1 Y' (59) pon_c) need for field verification of 1
design basis & log term monitoring program
- 5. Obtain results of one year temp. 5. Crumbo monitoring program per G. Baker Monitoring program i
MSI- 87T0293. Complete / evaluate > continuing. G/C (300) (loss-C) reviewingMSI and will data & continue or close monitor 4/15/89 program correlate / evaluate results 6 Retest E&W PA temp S. Cr umbo > WPA 436' el, test successful. -
(75) 7fj HVAC damper problems creating setback. MWR written to rework.
- 7. Review effects of temp. on 22 B. Waselus ;;
items identified in CGGS-37197 6/15 Impell performing review (10) (80-C) 1
Vill OTHERS ,
.2 Responsible ^
ACTIVITY Person Status 3ms 4:88 saa 6/88 7/88 8/88 9/88 10/88 11/88 12/88 U8) 2/89 3/89 5 I i i i 1 i i i i
- 1. Complete list of hermetic con- J. Mundy i
& List is complete - 5 hermetic nectors & decideif additional (5) connectors to be added -
need to be added + (25) (250 0 6/15 will request G/C for scope doc.
- 2. Process all analysis work done S. Crumbo 4
in preparation for & during the EQ ) Non Formal EQ File
- 0C Calculations / Analysis will be Audit as formal calculations (G/C or5CE8G as appropriate) processed formally under Impell's EQ File Upgrade
- Task. NCN 2852 Calc / analysis l requiring formal processing have been identified (5).
i Of these,4 calc. have been processed. 2 await assump-tion verification.
i .
a
- 3. Resolve seismic concern with B. Waselus - - - -
+
condulets mounted on ASCO vivs T. Lovett Completed Complete. NCN 2852 (ioo) (coo.c) 4/28 Disp. # 58 issued.
4 Review results of Maintenance T. Ef finger ;
item #4 Mixed greaseissue + e a nt. Item B 8 (40) 2/1 S Oose NCN 2661 + F. Thompson --- -----
-+
(m) 5/1 Completed Complete 6 Complete & verify loop accuracy T. Wessner calculations + G/C calcs. complete - E5 I
(s00) U134 c) 6/1 reviewing for approval 7 Review Impell Supplementary
- Evaluations & EQ Update for 5. Carroll '
r I
inpact onG/C Design Records To be completed as part of EQ (25) (100 0 10/1 File Upgrade project
- 8. Resolve Impell identified IMS vendor manual concerns F. Thompson I Not yet started (60) 8/l
, --N Vill. OTHERS (CONT'D) *
.?
s ;
e Responsible -
ACTIVITY Person was 4S8 s/sa 6ma 7/88 8/88 9/88 10/88 11/88 12sa 1/89 2/89 3mg Status
- 9. Define long te 'urces & Later program needet. .ntain ef fective EQ Prca
- 10. Generate EQ DBD Later
- 11. Consider establishing separate Later EQ screen on Champs
'12 Develop EQ DG Coordinate Later with Training Dept include History from TS-137
+ Activity associated with a NRC Commitment .
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