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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
[Table view] |
See also: IR 05000395/1999003
Text
,./_
August 5, 1999
EA 99-204
South Carolina Electric & Gas Company
ATTN: Mr. Gary J. Taylor
Vice President, Nuclear Operations
Virgil C. Summer Nuclear Station
P. O. Box 88 -
- Jenkinsville, SC 29065
Dear Mr. Taylor:
SUBJECT: NRC INTEGRATED INSPECTION REPORT NO. 50-395/99-03
Thank you for your response of July 7,1999, to our Non-Cited Violations (NCVs) identified on
. June 7,1999, concoming activities conducted at your facility, in your response, you denied
NCV 50-395/99003-01, " failure to remove loose debris from the reactor building," and requested
reclassification of NCV 50-395/99003-06, " failure to properly control access to a high radiation
area."
After careful consideration of the basis for your denial of NCV 50-395/99003-01, we have
concluded, for the reasons presented in the enclosure to this letter, that the NCV occurred as
stated in NRC Integrated Inspection Report No. 50-395/99-03.
NCV 50-395/99003-06 stated that you failed to properly control access to a high radiation area
in accordance with 10 CFR 20.1601, " Control of access to high radiation areas." You did not
deny the violation, but rather stated that the violation should be cited against 10 CFR 20.1501
since Health Physics did not perform surveys, reasonable under the circumstances, to evaluate
the extent of radiation levels and the potential radiological hazards that could be present during
fuel movement.
We carefully reviewed the material you provided in support of your request for reclassification
and material that was gathered during the onsite inspection. The reviewed material included
Condition Evaluation Report (CER) 99-0520, the Regulatory Assessment of CER 99-0520, and
Technical Specification 6.12, "High Radiation Areas." We agree that failure to do an adequate
-
survey was an issue in this event; however, we have elected to focus on the control of the high
radiation area in our regulatory action because that control represents a more direct risk for an
individual.
We disagree with your position that extreme measures would have been needed to access the
drained pit area.' ' A Radiation Work Permit already existed for entry into the pit and it would not
have been difficult for Health Physics Technicians and other workers to utilize it again.
. Additionally, we do not view a ladder located just a few feet below the accessible floor level as a
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OFFICIAL COPY
9908170138 990805
PDR ADOCK 05000395
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situation requiring extreme measures to gain access to the drained pit. An extreme measure
could have existed if the ladder had not been in the pit.
Therefore, it is our conclusion that your request for reclassification was not supported and that
NCV 50-395/99003-06 will remain as stated in NRC Integrated Inspection Report No.
50-395/99-03.
We appreciate your cooperation in this matter.
Sincerely,
Orig signed by Charles A. Casto for
Loren R. Plisco, Director
Division of Reactor Projects
Docket No.: 50-395
License No.: NPF-12
Enclosure:
Evaluations and Conclusion (NCV 50-395/99003-01)
'
.
SCE&G: 3
cc w/ encl:
R. J. White
Nuclear Coordinator (Mail Code 802)
' S.C. Public Service Authority
Virgil C. Summer Nuclear Station -
P. O. Box 88
Jenkinsville, SC 29065
' J. B. Knotts, Jr., Esq.
Winston and Strawn
1400 L Street, NW
Washington, D. C. 20005-3502
Chairman
Fairfield County Council
P. O. Box 60 -
Winnsboro, SC 29180
.
Virgil R. Autry,' Director
Radioactive Waste Management l
Bureau of Solid and Hazardous
Waste Management -
S, C. Department of Health
.
and Environmental Control-
2600 Bull Street
Columbia, SC 29201
- R. M, Fowlkes, Manager
Operations (Mail Code 303)
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
P-. O. Box 88
Jenkinsville, SC 20065
April Rice, Manager
Nuclear Licensing & Operating
l
Experience (Mail Code 830)
Virgil C. Summer Nuclear Station
j
P. O. Box 88
Jenkinsville;SC 29065
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L. Plisco, Ril
K. Cotton, NRR
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L. Hayes,Ril
G. Kuzo, Ril ,
R. Gibbs, Ril
P. Fillion, Ril
S. Sparks, Ril
R. Borchardt, OE
B. Summens, OE (Letterhead copie) -
PUBLIC
NRC Resident inspector
. U.S. Nuclear Regulatory Commission
Route 1, Box 64 .
Jenkinsville, SC 29065
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PUBLIC l
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NRC Resident inspector
U.S. Nuclear Regulatory Com sion
Route 1, Box 64
Jenkinsville, SC 29065
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SCE&G 4
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J. Lieberman, OE
PUBUC
NRC Residentinspector
U.S. Nuclear Regulatory Commission
Route 1, Box 64
Jenkinsville,SC 29066
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EVALUATIONS AND CONCLUSION (NCV 50-395/99003-01)
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On June 7,1999, a Non-Cited Violation (NCV) was identified during a routine NRC inspection for
failure to adequately remove loose debris from the reactor building in accordance with Technical
Specification surveillance requirement 4.5.3.1.1 South Carolina Electric & Gas Company
responded to the NCV on July 7,1999. The licensee contends that the amount of debris found
by the inspectors represented a negligible challenge to Emergency Core Cooling System
(ECCS) sump performance and therefore performance of the surveillance requirement was
ac; equate. The NRC's evaluations and conclusion regarding the licensee's arguments are as
follows:
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Restatement of NCV 50-395/99003-01
On May 7, the inspectors conducted an inspection of containment to assess mMerial
condition and general area housekeeping prior to reactor startup. At the time of this
inspection the licensee had completed a reactor building closeout visual inspection per
Quality Systems Procedure (QSP)-208, ' Inspection of Housekeeping and items in ,
Storage," Revision 9 and had entered Mode 4. In general, the material condition of the - l
! containment was satisfactory. However, the inspectors identified debris and tools, such
as a rubber shoe, a plastic bag, a cloth booty and other small items within accessible
areas of containment. The debris identified by the inspectors was subsequently
removed from the reactor building. The inspectors estimated the total amount of debris
to be approximately two square feet. The inspectors were informed by engineering
personnel that the transportable debris could block approximately two percent of one
train's sump suction screen and therefore this debris represented a negligible challenge j
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to sump performance. The inspectors agreed with this assessment.
TS Surveillance Requirement 4.5.3.1, " Emergency Core Cooling Systems," which is
, applicable for Mode 4, requires that the licensee perform a visual inspection per TS ,
4.5.2.c, to verify that no loose debris is present in the reactor building. Section 8.2.1.B of !
QSP-208, which implements the requirements of surveillance requirement 4.5.2.c, '
requires, in part, that the licensee identify and correct reactor building housekeeping
discrepancies prior to reactor building closeout. The failure to adequately remove loose
debris from the reactor building is a violation of TS 4.5.3.1. This Severity Level IV ;
violation is being treated as a Non-Cited Violation (NCV), consistent with Appendix C of -
the NRC Enforcement Policy. This violation is in the licensee's corrective action program
as CER 99-0748 and is identified as NCV 50-395/99003-01.
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Summary of Licensee's Response to NCV 50-395/99003-01 4
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The licensee contends the following:
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The purpose of surveillance requirement 4.5.2.c is to ensure that the required number of ,
trains of the Emergency Core Cooling System (ECCS) are operable and that there is not !
sufficient debris inside the reactor building that can be transported to the sumps and
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Enclosure
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degrade ECCS performance to a level that its design basis functions can no longer be
performed.
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The design of the ECCS sumps complies with the recommendations of Regulatory Guide
(RG) 1.82, " Water Sources for Long-Term Recirculation Cooling Following a Loss of
Coolant Accident," Revision 0, dated 6/74. Under the recommendations of this RG,
cump blockage from debris up to 50% is assumed. The design of the Virgil C. Summer
. Nuclear Station (VCSNS) sumps was verified as adequate for the 50% blockage criteria
by scale model testing conducted at the Alden Research Laboratory during the initial
plant licensing phase. -
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The potential sources of LOCA generated debris were also investigated during the
original plant licensing phase. Section 6.3.2.6.1 of the VCSNS FSAR describes the
potential sources of LOCA generated and other types of debris present inside the reactor
building. The NRC reviewed this investigation and concluded that the sumps could
perform their design function considering the debris blockage criteria of RG 1.82.
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Subsequent to the NRC inspection of the reactor building, Engineering personnel ,
performed an evaluation and determined that the transportable debris found inside the j
reactor building could block approximately two percent of one train's sump suction
screen and that this represented a negligible challenge to ECCS sump performance.
The inspectors agreed with this assessment. Therefore, it is SCE&G's position that the
- Technical Specification surveillance was adequate.
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During conversations between plant staff and the inspectors, it was inferred that the ease
in which the debris was found was a contributing factor to issuance of the violation. It is
SCE&G's position that, although the presence of debris in the reactor building after
establishment of containment integrity was undesirable and showed lack of attention to
detail, the ease with which the debris was located is not a valid basis for a violation.
NRC Evaluation of Licensee's Response
The NRC staff has carefully reviewed your response and considered the following items:
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Technical Specification surveillance requirement (SR) 4.5.2.c, which is referenced by TS
4.5.3.1, requires, in part, that the ECCS subsystem be demonstrated operable *by a
visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present j
in the reactor building which could be transported to the RHR [ residual heat removal] and !
Spray Recirculation sumps and cause restriction of the pump suctions during LOCA
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conditions." Contrary to your position that the purpose of SR 4.5.2.c is to ensure debris '
is not present that could prevent the ECCS sumps from performing their design basis
function, the SR does not reference a quantity of debris relative to ECCS sumps being !
able to perform their function. The NRC recognizes that minor debris such as tie wraps, '
small pieces of paper, etc., which remained in the reactor building following the visual
inspection of SR 4.5.2.c would not necessarily cause the SR to be viewed as
inadequate. However, the NRC considers that the type ofloose debris found by the
inspectors (e.g. rubber shoe, plastic bag, and cloth booty) was not minor and could
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reasonably be transported to the RHR and Spray Recirculation sumps and cause
restriction of the ECCS pump suctions.
_ Our interpretation of SR 4.5.2.c requirements is consistent with your response to NRC
Bulletin 93-02," Debris Plugging of Emergency Core Cooling Suction Strainers." In this
Bulletin, the NRC requested licensees to identify temporary sources of fibrous materials
which are installed or stored in containment. In your June 10,1993, response to Bulletin
93-02, you stated that "all temporary material used during an outage inside containment
is removed so as to not reduce the performance of the emergency sumps." Your letter
further stated that the " Quality Control organization performs a reactor building closeout
inspection (each outage) which assures miscellaneous equipment / debris is removed
from the building." We believe that your response to Bulletin 93-02 is consistent with our
interpretation that the intent of SR 4.5.2.c is to remove all loose debris from the reactor
building.
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Your engineering evaluation concluded that the transportable debris found in the reactor
building could block approximately two percent of one train's sump suction screen.
Although the NRC agrees that a two percent blockage of the ECCS sump represents a
negligible challenge to sump performance, your response did not consider the aggregate
effects of the debris identified by the inspectors with other potential sources of debris in
the reactor building. VCSNS Final Safety Analysis Report (FSAR) section 6.3.2.6.1,
" Containment Sump and its Effect on Long Term Cooling Following a LOCA," discusses
other potential sources of debris within the reactor building. FSAR section 6.3.2.6.1
does not identify loose debris of the type identified by the inspectors as potential
blockage sources for the ECCS sumps. Therefore, this debris represents an additional
two percent blockage beyond the sump debris loading assumed in the safety analysis.
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The NRC considered the quantity of loose debris in the reactor building, including the
potential for ECCS sump screen blockage, when evaluating the severity level of the
violation. Although you failed to comply with TS 4.5.2.c, the NRC agrees that the
additional challenge created by the loose debris would not result in the ECCS system
being unable to perform its intended function. Therefore, based on guidance contained
in NUREG-1600, Rev.1, " General Statement of Policy and Procedure for NRC
Enforcement Actions," the NRC characterized the violation at a Severity Level IV.
Violations at Severity Level IV, the least significant of the four severity levels established
in the NRC Enforcement Policy, involve noncompliances with NRC requirements for
which the associated risks are not significant. Consistent with Appendix C of the
Enforcement Policy, the NRC treated this Severity Level IV violation as an NCV.
With regard to your comment concerning the ease in which the debris was found and the
inference that this was'a contributing factor to the issuance of the violation, the NRC did
consider the fact that the debris was located within readily accessible areas of the
reactor building. Based on the type of debris and its location in readily accessible areas,
it is reasonable to believe that the debris could have been transported to the reactor
building sump. In dispositioning this violation, the NRC considered the ease of the
inspectors' identification in the evaluation of the accessibility and transportability of the 1
loose debris.' I
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NRC Conclusion
For the above reasons, the NRC staff concludes that the NCV 50-396/99003-01, " failure to
remove loose debris from the reactor building," occurred as stated,
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