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MONTHYEARML20059J3371993-11-0505 November 1993 Discusses 930217 Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers & Requests That Util Review Results of NUMARC Program &,Within 30 Days of Completion,Inform NRC of Required Actions for Restoring Operability to Fire Barriers Project stage: Other ML20059A5931993-12-22022 December 1993 Forwards Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) Project stage: RAI RC-94-0321, Forwards Response to NRC 940923 follow-up to 941222 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers1994-12-21021 December 1994 Forwards Response to NRC 940923 follow-up to 941222 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other RC-95-0076, Forwards Response to Follow Up Request for Addl Info Re GL 92-081995-03-23023 March 1995 Forwards Response to Follow Up Request for Addl Info Re GL 92-08 Project stage: Request ML20101J7231996-03-29029 March 1996 Forwards follow-up to 951006 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other RC-96-0186, Clarifies Info Provided to NRC in Util Ltr Re Response to Question 1.d of NRC RAI .Response to RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Encl1996-07-29029 July 1996 Clarifies Info Provided to NRC in Util Ltr Re Response to Question 1.d of NRC RAI .Response to RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Encl Project stage: Response to RAI RC-96-0216, Forwards Follow Up to RAI Re GL 92-08 Per 10CFR50.54(f) 931222.Detail Description of Two Separate Exemption Requests to Requirements of Section III.G.2 of App R to 10CFR50 Encl1996-08-23023 August 1996 Forwards Follow Up to RAI Re GL 92-08 Per 10CFR50.54(f) 931222.Detail Description of Two Separate Exemption Requests to Requirements of Section III.G.2 of App R to 10CFR50 Encl Project stage: Other 1995-03-23
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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 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 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) ML20196K9771999-03-25025 March 1999 Refers to Open Meeting Conducted at Licensee Request at NRC Region II Offices in Atlanta,Ga on 990315 Re Upcoming April 1999 Refueling Outage,Back Leakage Into Residual Heat Removal Sys & Licensee Position on Hazard Barriers ML20205D7981999-03-23023 March 1999 Advises of NRC Planned Insp Effort Resulting from Summer Plant Performance Review for Period July 1998 Through Jan 1999.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next Eight Months Encl ML20204J7201999-03-15015 March 1999 Forwards Insp Rept 50-395/99-01 on 990103-0213.No Violations Noted.Sce&G Conduct of Activities During Insp Period Generally Characterized by Safety Conscious Operations & Conservative Decision Making ML20207J0661999-03-0303 March 1999 Confirms 990226 Telephone Conversation Between a Rice & M Widman Re Meeting Scheduled for 990315.Purpose of Meeting Will Be to Discuss VC Summer Upcoming Refueling Outage & Items of Interest ML20203F4351999-02-12012 February 1999 Forwards SER Finding Licensee Adequately Addressed GL 96-05 Requested Actions & Have Acceptable Program to Periodically Verify safety-related MOV design-basis Capability at Virgil C Summer Nuclear Station ML20203G5751999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20203G4091999-02-0101 February 1999 Forwards Insp Rept 50-395/98-10 on 981122-990102.No Violations Noted.Licensee Conduct of Activities at VC Summer Facility Was Generally Characterized by Safety Conscious Operations & Conservative Decision Making ML20199J0571999-01-21021 January 1999 Forwards RAI Re 980918 Request for Amend to Plant Ts.Amend Would Incorporate New Best Estimate Analyze for Core Operations Core Power Distribution Monitoring & Support Sys Into Ts.Response Requested within 15 Days of Receipt of Ltr ML20199K0281999-01-13013 January 1999 Discusses NRC Organization Charts to Be Implemented by Region 2 on 990117.Forwards Organization Charts for Info ML20198Q7471999-01-0505 January 1999 Informs That 981204 Request to Extend RAI Response Period Re GL 97-01 to 990115 Has Been Accepted ML20199E5971998-12-23023 December 1998 Provides Summary of Training Manager Conference Conducted on 981105.Forwards Agenda,List of Attendees,Handouts & Preliminary Schedule for FY99 & FY00.Goal of Providing Open Forum of Operator Licensing Issues Met ML20198N8341998-12-21021 December 1998 Forwards Insp Rept 50-395/98-09 on 981011-1121 & NOV Re Failure to Follow Procedures During Snubber Testing ML20198F4181998-12-18018 December 1998 Forwards SER Granting Licensee 980513 Request for Approval to Temporarily Repair ASME Code Class 3 Piping at VC Summer Nuclear Station Pursuant to 10CFR50.55a(g)(6)(i) ML20198B7611998-12-0303 December 1998 Informs That on 981007,generic Fundamentals Exam Was Administered to 148 Candidates at 21 Facilities.Summary of Statistical Results of Exam Listed.Contents of Exam Along with Associated Input Data Needed for Updating Catalog Encl ML20196G0981998-12-0303 December 1998 Requests Proposed Alternatives to Confirm That Listed Structures Free from Gross Erosion or Other Effects That Could Impair Structures Stability,Per NRC Category I SW Pond Dam Insp ML20198A7711998-12-0202 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Details of Insp Plan for Next 4 Months & Historical Listing of Plant Issues,Called Plant Issues Matrix Encl ML20196D5831998-11-12012 November 1998 Informs That on 981007,NRC Administered Gfes of Written Operator Licensing Examination.Copies of Both Forms of Exam Including Answer Keys,Grading Results for Facility & Copies of Indivividual Answer Sheets Encl.Without Encl ML20195E9761998-11-0909 November 1998 Forwards Insp Rept 50-395/98-08 on 980906-1010.No Violations Noted.Conduct of Activities at VC Summer Facility Was Generally Characterized by Safety Conscious Operations & Conservative Decision Making ML20155G4451998-11-0404 November 1998 Forwards Safety Evaluation Re Relief Request to ASME Code Case N-416-1,for Class 1,2 & 3 Piping & Components.Proposed Alternative with Addl Exams Proposed,In Lieu of Performing Sys Hydrostatic Test Provides Acceptable Level of Safety ML20154Q9451998-10-21021 October 1998 Forwards SE Re Approval to Use ASME Code Case N-498-1 for Periodic Hydrostatic Testing of ASME Class 3 Piping at Plant ML20155B8071998-10-0909 October 1998 Extends Invitation to Attend Training Managers Conference on 981105 in Atlanta,Georgia.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators ML20155B1561998-10-0505 October 1998 Forwards Insp Repts 50-395/98-07 on 980726-0905.No Violations Noted ML20239A3671998-09-24024 September 1998 Forwards Insp Rept 50-395/98-06 on 980628-0725.No Violations Noted.During Insp Period,Nrc Received Response to NOV 50-395/98002-01.Response Meets Requirements of 10CFR2.201 ML20151V1911998-09-0808 September 1998 Forwards Request for Addl Info Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations. Response Requested within 90 Days of Date of Ltr ML20153F0261998-09-0202 September 1998 Refers to Insp Rept 50-395/98-06 Issued on 980824.Ltr Transmitting Insp Rept Referred to Wrong Violation Number in Paragraph Three.Corrected Page with Violation Number 50-395/98004-01 Encl ML20151T9241998-08-27027 August 1998 Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Novs. Licensee NOV Responses Which Accept Violations & Require No Addl Communication to Be Ack in Cover Ltr of Next Insp Rept ML20239A4521998-08-26026 August 1998 Forwards SALP Insp Rept 50-395/98-99 for Period of 961027- 980725 1999-09-09
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__o . ._ . _ __ __ _
t t
- $pawagb*. UNITED STATES j NUCLEAR REGULATORY COMMISSION ,
[g[*2 g C WASHINGTON, D.C. 20E0001 ]
\..... December 22, 1993 i Docket No. 50-395 i
Mr. John L. Skolds Vice President, Nuclear Operations l South Carolina Electric & Gas Company ;
Virgil C. Summer Nuclear Station '
P.O. Box 88 :
Jenkinsville,- South Carolina 29065 l
Dear Mr. Skolds:
l
SUBJECT:
REQUEST FOR ADDITIONAL INFORr4ATION REGARDING GENERIC LETTER 92-08,
" THERM 0-LAG 330-1 FIRE BARRIERS," PURSUANT TO 10 CFR 50.54(f) -
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 (TAC NO. M85610) i In your response of February 17, 1993, to Generic Letter (GL) 92-08, i "Thermo-Lag 330-1 Fire Barriers," you indicated that actions necessary to restore the operability of these barriers at Virgil C. Summer Nuclear Station, Unit No.1 (Summer Station), would be based on the results of the industry test program being coordinated by the Nuclear Management and Resources Council -
(NUMARC). During recent meetings with U.S. Nuclear Regulatory Commission l (NRC) staff, the Executive Director for Operations'and the Commission, NUMARC i described the scope of its Thermo-Lag fire barrier program, the results of the i Phase I fire tests, and planned Phase 2 tests. The program is limited to ,
certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the development of guidance for applying the test results to plant .
specific fire barrier configurations. However, NUMARC's program is not
?
intended to bound all in-plant Thermo-Lag fire barrier configurations. During a NUMARC-sponsored industry workshop on December 1 and 2, 1993, NUMARC .
presented the scope of its program and the Phase 1 test results to the j licensees. '
In view of the limited scope of the NUMARC program and the limited success of the Phase 1 tests, it is clear to the staff that the NUMARC program will not be sufficient to resolve all Thermo-Lag fire barrier issues identified in GL 92-08. Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with their in-plant Thermo-Lag barriers.
To help ensure timely resolution of the fire barrier issues at Summer Station, the' staff requires additional information on- the configurations and amounts of Thermo-Lag fire barriers installed in the plant and the cable loadings within particular Thermo-Lag configurations. This information is necessary to review NUMARC's guidance for applying the test results to plant-specific barrier configurations and to identify configurations that are outside the scope of .
NUMARC's test program. For those configurations that are outside the scope of i the program or for.those configurations that you deem are impractical to upgrade, we request that you provide plans and schedules for resolving the technical issues identified in GL 92-08. You are required, pursuant to Section 182(a) of.the Atomic Energy Act of 1954, as amended, and 9401030049 931222 '
PDR- ADOCK 05000395'
~
2900m '
A iEC RLE CENTER GWY l
Y December 22, 1993 I Mr. John L. Skolds :
10 CFR 50.54(f), to' submit a. written report that contains the information !
specified in the_ enclosure to this letter within_45 days from receipt of this !
letter. Your response must be submitted under oath or_ affirmation. Please 4 submit your response to the undersigned, with a copy to the appropriate i Regional Administrator. Please retain all; information and' documentation' used 't to respond to this request on site for future NRC audits or inspections. -!
This request is covered by Office of Management' and Budget Clearance Number i 3150-0011, which expires June 30, 1994. The estimated average number of; ;
burden hours of 300 person-hours is anticipated to increase by an. additional .i 120 person-hours for'each addressee's response, includirig th'e time required to
- assess the requirements for information, . search data-sources, gather and analyze the data, and prepare the required. letters. This revised estimated i average number of burden hours pertains only to the.' identified response - :
related matters and does not include the time to implement the actions "
required to comply with the applicable regulations, license conditions, or commitments. Comments on the accuracy of this estimate and suggestions to. !
reduce the burden may be directed to _the Office of Information and Regulatory !
Affairs (3150-0011), NE0B-3019, Office of Management and Budget, Washington',
D.C. 20503, and to the U.S. Nuclear Regulatory Commission,-Information and l Records Management Branch (MNBB-7714), Division of Information Support .
Services, Office of Information and Resources Management, Washington, D.C. !
20555. :
1 If you have any questions about this matter, please contact George Wunder at '
301-504-1455 or Patrick Madden at 301-504-2854. ,
Sincerely, !
ORIGINAL SIGNED BY:
L. J. Callan !
Acting Associate Director for Projects. j Office of Nuclear Reactor Regulation ,
l Enclosure- -
Request for Additional Information ,
cc w/ enclosure: [
See next page g i
DISTRIBUTION: I See attached page .;
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rim t 0FFICE LA:PDII-lrw PM:FDII-l PD:PDII-1,/ (A)ADP j NAME PAndersob .dIfdr SB d h LJ b n- !
DATE 12/M/93 12'[20/93 12/P/k 12/Z[/93 COPY Yes/No gh/No Yes/d M/No Yes/No ;
' ~
0FFICIAL RECORD COPY '/ l DOCUMENT NAME: G:\ SUMMER \85610.RAI .
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Mr. John L. Skolds ,
1
! 10 CFR 50.54(f), to submit a written report that contains the information l specified in the enclosure to this letter within 45 days from receipt of this
- letter. Your response must be submitted under oath or affirmation. Please ,
i submit your response to the undersigned, with a copy to the appropriate Regional Administrator. Please retain all information and documentation used to respond to this request on site for future NRC audits or inspections.
This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994. The estimated average number of-burden hours of 300 person-hours is anticipated to increase by an additional '
i 120 person-hours for each addressee's response, including the time required to 1 assess the requirements for information, search data sources, gather and analyze the data, and prepare the required letters. This revised estimated average number of burden hours pertains only to the identified response-related matters and does not include the time to implement the actions '
required to comply with the applicable regulations, license conditions, or comitments. Comments on the accuracy of this estimate and suggestions to l reduce the burden may be directed to the Office of Information and Regulatory Affairs (3150-0011), NE0B-3019, Office of Management and Budget, Washington, D.C. 20503, and to the U.S. Nuclear Regulatory Comission, Information and Records Management Branch (MNBB-7714), Division of Information Support Services, Office of Information and Resources Management, Washington, D.C.
20555.
l l If you have any questions about this matter, pleEse contact George Wunder at 1
301-504-1455 or Patrick Madden at 301-504-2854.
Sincerely, l
l l L. . a lan Ac ing Associate Director for Projects Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information 1
cc w/ enclosure:
See next page l
t
4-Mr. John L. Skolds Virgil C. Summer Nuclear Station South Carolina Electric & Gas Company cc:
Mr. R. J. White Nuclear Coordinator S.C. Public Service Authority c/o Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 802 Jenkinsville, South Carolina 29065 J. B. Knotts, Jr., Esquire Winston & Strawn Law Firm 1400 L Street, N.W.
Washington, D.C. 20005-3502 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Comnission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., N.W., Ste. 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Mr. R. M. Fowlkes, Manager Nuclear Licensing & Operating Experience South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065
I DISTRIBUTION:
l-netDocket! File?O- CMcCracken MGamberoni GWunder NRC PDR PMadden- RIngram, PMSB PAnderson Local PDR CBerlinger Region II- PDII-1 R/F RJenkins OGC RII/01 GMulley (0IG) ACRS (10) Glainas LCallan :
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i ENCLOSURE REQUEST.FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-08
" THERM 0-LAG 330-1 FIRE BARRIERS" PURSUANT TO 10 CFR 50.54(f) i I. Thermo-Lag Fire Barrier Configurations and Amounts A. Discussion Generic Letter (GL) 92-08,"Thermo-Lag 330-1 Fire Barriers," applied to all 1-hour and all 3-hour Thermo-Lag 330-1 materials and barrier systems constructed by any assembly method, such as by joining preformed panels and conduit preshapes, and trowel, spray, and brush-on applications. This includes all fire barriers, all barriers to achieve physical independence of electrical systems, radiant energy heat shields, and barriers installed to enclose intervening combustibles.
B. Required Information
- 1. Describe the Thermo-Lag 330-1 barriers installed in the ;
plant to
- a. meet 10 CFR 50.48 or Appendix R to 10 CFR Part 50,
- b. support an exemption from Appendix R.
- c. achieve physical independence of electrical systems,
- d. meet a condition of the plant operating license,
- e. satisfy licensing commitments.
The descriptions should include the following information:
the intended purpose and fire rating of the barrier (for example, 3-hour fire barrier, 1-hour fire barrier, radiant energy heat shield), and the type and dimension of the barrier (for example, 8-ft by 10-ft wall, 4-ft by 3-ft by 2-ft equipment enclosure, 36-inch-wide cable tray, or 3-inch-diameter conduit). l
- 2. For the total population of Thermo-Lag fire barriers described under Item I.B.1, submit an approximation of:
- a. For cable tray barriers: the total-linear feet and square feet of 1-hour barriers and the total linear feet and square feet of 3-hour barriers.
- b. For conduit barriers: the total linear feet of 1-hour barriers and the total linear feet of 3-hour barriers.
- c. For all other fire barriers: the total square feet of !
1-hour barriers and the total square feet of 3-hour !
barriers. i
- d. For all other barriers and radiant energy heat l shields: the total linear or square feet of 1-hour barriers and the total linear or square feet of 3-hour j barriers, as appropriate for the barrier configuration I or type.
< , I II. Important Barrier Parameters A. Discussion In a letter of July 29, 1993, from A. Marion, NUMARC, to C. McCracken, NRC, NUMARC stated: " Relative to bounded configurations, ... [i]t will be the utilities' responsibility to verify their baseline installations are bounded." Furthermore, NUMARC stated that the parameters of importance for utility use of data from the industry Thermo-Lag fire barrier test program are:
- 1. Raceway orientation (horizontal, vertical, radial bends)
- 2. Conduit
- 3. Junction boxes and lateral bends
- 4. Ladder-back cable tray with single layer cable fill
- 5. Cable tray with T-Section
- 6. Raceway material (aluminum, steel)
- 7. Support protection, thermal shorts (penetrating elements)
- 8. Air drops
- 9. Baseline fire barrier panel thickness
- 10. Preformed conduit panels
- 11. Panel rib orientation (parallel or perpendicular to the raceway)
- 12. Unsupported spans ,
- 13. Stress skin orientation (inside or outside)
- 14. Stress skin over joints or no stress skin over joints
- 15. Stress skin ties or no stress skin ties
- 16. Dry-fit, post-buttered joints or prebuttered joints
- 17. Joint gap width
. 18. Butt joints or grooved and scored joints
- 19. Steel bands or tie wires
- 20. Band / wire spacing l
- 21. Band / wire distance to joints
- 22. No internal bands in trays
- 23. No additional trowel material over sections and joints or additional trowel material applied
- 24. No edge guards or edge guain Each NUMARC cable tray fire test specimen includes 15 percent cable fills (i.e., a single layer of cables uniformly distributed across the bottom of the cable tray). This approach requires consideration of plant-specific cable information during the assessments of tested
.y configurations and ' '.st results. in relation to plant-specific l Thermo-Lag configurations. For example, cable trays with less ;
thermal mass (cable fill) than the NUMARC test specimens, different ;
cable types, and the proximity of the cables to the Thermo-Lag 1 (e.g., cables may be installed in contact with the unexposed surface .l of the Thermo-Lag or may come into contact during a fire if the i Thermo-Lag material sags). In its letter of July 29, 1993, NUMARC i stated: " Utilities using the results of the NUMARC testing will )
need to evaluate their installed cable fill and ensure that it is i bounded by the tested cable fill." NUMARC is not conducting any cable functionality tests or evaluations and stated that cable functionality evaluations will be performed by utilities using data from the generic program.
The parameters of importance concerning cables protected by fire barriers are:
- 1. Cable size and type (power, control, or instrumentation). l
- 2. Cable jacket type (thermoplastic, thermoset) and materials.
- 3. Cable conductor insulation type (thermoplastic, thermoset plastic) and materials.
- 4. Cable fill and distribution of cables within the protected conduit or cable tray.
- 5. Proximity of cables to the unexposed (inside) surfaces of the fire barrier. ;
- 6. Presence of materials between the cables and the unexposed side of the fire barrier material (for example, Sealtemp cloth, which is used in the NUMARC test specimens).
- 7. Cable operating temperature.
- 8. Temperatures at which the cables can no longer perform their intended function when energized at rated voltage and current.
Other parameters that are unique to particular barriers, such as interfaces between Thermo-Lag materials and other fire barrier materials or building features (walls, etc.) and internal supports, are also important. In addition, because of questions about the uniformity of the Thermo-Lag fire barrier materials produced over time, NUMARC stated in its letter of July 29, 1993, that "[c]hemical analysis of Thermo-lag materials provided for the program, as well as samples from utility stock, will be performed, and a test report prepared comparing the chemical composition of the respective s ampl es . " The results of the chemical analyses may indicate that variations in the chemical properties of Thermo-Lag are significant and may require additional plant-specific information in the future.
B. Required Information l
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- 1. State whether or not you have obtained and verified each of the aforementioned parameters for each Thermo-Lag barrier installed in the plant. If not, discuss the parameters you l have not obtained or verified. Retain detailed information l
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on site for NRC audit where the aforementioned parameters i are known.
- 2. For any parameter that is not known or has not been verified, describe how you will evaluate the in-plant I barrier for acceptability.
- 3. To evaluate NUMARC's application guidance, an understanding of the types and extent of the unknown parameters is needed.
Describe the type and extent of the unknown parameters at your plant in this context.
III. Thermo-Lag Fire Barriers Outside the Scope of the NUMARC Program A. Discussion In your response of to GL 92-08, you indicated that actions necessary to restore the operability of these barriers would be '
based on the results of the NUMARC test prograt.. During recent meetings with the NRC staff, the Executive Director for Operations and the Commission, NUMARC described the scope of its Thermo-Lag fire barrier program, the results of the Phase 1 fire tests, and planned Phase 2 tests. The program is limited to certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the deveicpment of guidanca for applying the test results to plant-specific fire barrier configurations. However, NUMARC's. program is not intended to bound all in-plant Thermo-Lag fire barrier configurations. In view of the scope of the NUMARC program and the limited success of the Phase I tests, it is clear that the NUMARC program will not be sufficient to resolve all Thermo-Lag fire barrier issues identified in GL 92-08. Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with in-plant Thermo-Lag barriers.
B. P.equired information
- 1. Describe the barriers discussed under Item I.B.1 that you have determined will not be bounded by the NUMARC test program.
- 2. Describe the plant-specific corrective action program or plan you expect to use to evaluate the fire barrier configurations particular to the plant. This description should include a discussion of the evaluations and tests being considered to resolve the fire barrier issues identified in GL 92-08 and to demonstrate the adequacy of existing in-plant barriers.
- 3. If a plant-specific fire endurance test program is anticipated, describe the following:
- a. Anticipated test specimens.
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- b. Test methodology and acceptance criteria including ]
cable functionality.
IV. Ampacity Derating l A. Discussion NUMARC has informed the staff that it intends to use the Texas Utilities (TV) Electric Company and Tennessee Valley Authority (TVA) ampacity derating test results to develop an electrical raceway component model for the industry. Additional information is needed to determine whether or not your Thermo-Lag barrier configurations (to protect the safe-shutdown capability from fire cr to achieve physical independence of electrical systems) are within the scope of the NUMARC program and, if not, how the in-plant barriers will be evaluated for the ampacity derating concerns identified in GL 92-08.
B. Required Information
- 1. For the barriers described under Item I.B.1, describe those that you have determined will fall within the scope of the NUMARC program for ampacity derating, those that will not be bounded by the NUMARC program, and those for which ampacity derating does not apply.
- 2. For the barriers you have determined fall within the scope of the NUMARC program, describe what additional testing or evaluation you will need to perform to derive valid ampacity derating factors.
- 3. For the barrier configurations that you have determined will not be bounded by the NUMARC test program, describe your plan for evaluating whether or not the ampacity derating tests relied upon for the ampacity derating factors used for those electrical components protected by Thermo-Lag 330-1 (for protecting the safe-shutdown capability from fire or to achieve physical independence of electrical systems) are correct and applicable to the plant design. Describe all corrective actions needed and submit the schedule for completing such actions.
- 4. In the event that the NUMARC fire barrier tests indicate the need to upgrade existing in-plant barriers or to replace existing Thermo-Lag barriers with another fire barrier system, describe the alternative actions you will take (and the schedule for performing those actions) to confirm that the ampacity derating factors were derived by valid tests and are applicable to the modified plant design.
Your response to Section IV.B may depend on unknown specifics of the NUMARC ampacity derating test program (for example, the final barrier upgrades). However, your response should be as complete as
e-t possible. In addition, your response should be updated as additional information becomes available on the NUMARC program.
V. Alternatives A. Discussion On the basis of testing of Thermo-Lag fire barriers to date, it is not clear that generic upgrades (using additional Thermo-Lag materials) can be developed for many 3-hour barrier configurations or for some 1-hour barriers (for example, 1-hour barriers on wide cable trays, with post-buttered joints and no internal supports).
Moreover, some upgrades that rely on additional thicknesses of Thermo-Lag material (or other fire barrier materials) may not be practical due to the effects of ampacity derating or clearance problems.
B. Required Information Describe the specific alternatives available to you for achieving compliance with NRC fire protection requirements in plant areas that contain Thermo-Lag fire barriers. Examples of possible alternatives to Thermo-Lag-based upgrades include the following:
- 1. Upgrade existing in-plant barriers using other materials.
- 2. Replace Thermo-Lag barriers with other fire barrier materials or systems.
- 3. Reroute cables or relocate other protected components.
- 4. Qualify 3-hour barriers as 1-hour barriers and install detection and suppression systems to satisfy NRC fire protection requirements. !
l VI. Schedules ,
A. Discussion )
The staff expects the licensees to resolve the Thermo-Lag fire !
barrier issues identified in GL 92-08 or to propose alternative fire i protection measures to be implemented to bring plants into compliance with NRC fire protection requirements. Specifically, as ,
test data becomes available, licensees should begin upgrades for !
Thermo-Lag barrier configurations bounded by the test results.
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- 8. Required Information Submit an integrated schedule that addresses the overall corrective action schedule for the plant. At a minimum, the schedule should address the following aspects for the plant:
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- 1. implementation and completion of corrective actions and fire l barrier upgrades for fire barrier configurations within the '
scope of the NUMARC program,
- 2. implementation and completion of plant-specific analyses, testing, or alternative actions for fire barriers outside the scope of the NUMARC program.
VII. Sources and Correctness of Information Describe the sources of the information provided in response to this ;
request for information (for example, from plant drawings, quality assurance documentation, walk downs or inspections) and how the accuracy and validity of the information was verified.
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