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| provide your best estimate when WEC will complete these tasks. Also, describe how these activities relate to, and will be used to, update the probabilistic susceptibility assessment of VHP nonles at Summer. | | provide your best estimate when WEC will complete these tasks. Also, describe how these activities relate to, and will be used to, update the probabilistic susceptibility assessment of VHP nonles at Summer. |
| : 3. The Nuclear Energy Institute indicated in their January 29,1998, and April 1,1998, letters (Refs.1 and 2), that VHP noule Inspection plans have been developed for inspecting the Farley Unit 2 plant in the year 2002, and the Diablo Canyon Unit 2 plant in the year 2001. We noted that although you have endorsed the probabilistic susceptibility model described in WCAP-14901, Revision 0, other WOG member licensees have endorsed a probabilistic susceptibility model an altemate vendor developed. The WOG's proposal to inspect the VHP nozzles at the Farley Unit 2 and Diablo Canyon Unit 2 plants appea.s to be based on a composite assessment of the VHP nozzles at all WOG member plants. Verify that such a composite ranking assessment has been applied to the evaluation of VHP nozzles at Summer, if composite rankings were obtained for all of WOG member plants, justify why applying one model would yield the same comparable relative rankings as would applying the other model. Comment on the susceptibility rankings of the VHP nozzles at Summer relative to the susceptibility rankings of the VHP nozzles at the Farley Unit 2 and Diablo Canyon Unit 2 planta. | | : 3. The Nuclear Energy Institute indicated in their January 29,1998, and {{letter dated|date=April 1, 1998|text=April 1,1998, letter}}s (Refs.1 and 2), that VHP noule Inspection plans have been developed for inspecting the Farley Unit 2 plant in the year 2002, and the Diablo Canyon Unit 2 plant in the year 2001. We noted that although you have endorsed the probabilistic susceptibility model described in WCAP-14901, Revision 0, other WOG member licensees have endorsed a probabilistic susceptibility model an altemate vendor developed. The WOG's proposal to inspect the VHP nozzles at the Farley Unit 2 and Diablo Canyon Unit 2 plants appea.s to be based on a composite assessment of the VHP nozzles at all WOG member plants. Verify that such a composite ranking assessment has been applied to the evaluation of VHP nozzles at Summer, if composite rankings were obtained for all of WOG member plants, justify why applying one model would yield the same comparable relative rankings as would applying the other model. Comment on the susceptibility rankings of the VHP nozzles at Summer relative to the susceptibility rankings of the VHP nozzles at the Farley Unit 2 and Diablo Canyon Unit 2 planta. |
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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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- W4 9 p' \ UNITED STATES 4
g j NUCLEAR REGULATORY COMMISSION o, WASHINGTON, D.C. 206&M001
'% .. Septe m ber 8,1998 Mr. Gary J. Taylor Vice President, Nuclear Operations l South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station l
Post Office Box 88 I Jenkinsville, South Carolina 29065 l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 97-01, (TAC NO. M98602) l
Dear Mr. Taylor:
On April 1,1997, we issued Generic Letter (GL) 97-01, " Degradation of Control Rod Drive l Mechanism Nozzle and Other Vessel Closure Head Penetrations." Our GL requested, in part, l that licensees describe their plans to inspect the vessel head penetration (VHP) nozzles at their '
respective pressurized water reactor (PWR) designed plants. We required addressees to submit an initial response within 30 days of the GL issuance informing us of their intent to comply with our request. A follow-up response was also due within 120 days of the GL issuance containing the technical response details to our information requests. In the discussion section of the GL, we stated that "individuallicensees may wish to determine their inspection activities based on an integrated industry inspection program. " We also indicated that we did not object to individual PWR licensees basing their inspection activities on an integrated industry inspection program.
As a result, the Westinghouse Owner's Group (WOG) determined that it was appropriate for its members to develop a cooperative, integrated inspection program in response to GL 97-01.
The WOG program is documented in two Westinghouse Electric Corporation (WEC) Topical Reports, WCAP-14901, Revision 0, " Background and Methodology for Evaluation of Reactor Vessel Closure Head Penetration Integrity for the Westinghouse Owners Group," and WCAP-14902,' Revision 0, " Background Material for Response to NRC Generic Letter 97-01:
Reactor Vessel Closure Head Penetration integrity for the Westinghouse Owners Group." The WOG submitted the integrated programs described in WCAP-14901 and WCAP-14902 to us on July 25,1997.
We have reviewed your May 1,1997, and July 30,1997, responses to GL 97-01. We determined that you are a member of the WOG, and are a participant in the WOG integrated program that was developed to address our GL 97-01 requests. In your responses to GL 97-01, you also indicated that the information in WEC Topical Report WCAP-14901 applies to the assessment of VHP nozzles at the Summer plant. In addition, we noted that you indicated in your 120-day response that WCAP-14932, "Probabilistic and Economic Evaluation of Reactor Vessel Closure Head Penetration Integrity for Virgil C. Summer Nuclear Plant," also applied to evaluating VHPs at your plant.
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P 9809140145 980908 PDR ADOCK 05000395 Ok (
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! 4 2-a Our request for additional information (RAl) is enclosed. Our RAI questions mainly pertain to Topical Report WCAP-14901. However, we request that you generally apply the information requests to WCAP-14932 as well. Please note that we have issued similar requests to other WOG member utilities. As before, we encourage you to address these inquiries in an i
integrated fashion with the WOG and the Nucle'ar Energy institute. However, we request that 4
you identify any deviations from the WOG's integrated program that may be specific to the Summer plant.
I discussed this RAI with Mr. Jim Turkett of your staff on September 1,1998. We mutually agreed that the SCE&G target date to respond to this RAI is within 90 days of the date of this letter. Please call me at (301) 415-1423 if you need to revise the target date.
! Sincerely, i . bd M l L. Mark Padovan, Project Manager j Project Directorate 11-1 Division of Reactor Projects - 1/11
- Office of Nuclear Reactor Regulation i
Docket No. 50-395
Enclosure:
Request for Additional Information
}
. cc w/ encl: See next page i
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4 4
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September 8 1998 0 1
0 1 1
Our request for additional information (RAl) is enclosed. Our RAI questions mainly pertain to Topical Report WCAP-14901. However, we request that you generally apply the information I requests to WCAP-14932 as well. Please note that we have issued similar requests to other l WOG member utilities. As before, we encourage you to address these inquiries in an integrated fashion with the WOG and the Nucle'ar Energy Institute. However, we request that you identify any deviations from the WOG's integrated program that may be specific to the Summer plant.
l l
l discussed this RAI with Mr. Jim Turkett of your staff on September 1,1998. We mutually agreed that the SCE&G target date to respond to this RAI is within 90 days of the date of this I letter. Please call me at (301) 415-1423 if you need to revise the target date.
Sincerely, Original Signed by:
l L. Mark Padovan, Project Manager Project Directorate 11-1 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Request for Additional Information cc w/ encl: See next page Distribution Docket File PUBLIC PD li-1 Reading OGC ACRS J. Zwolinski L. Plisco, Ril J. Harold J. Medoff DOCUMENT NAME: G:\ SUMMER \ SUM 98602.RAI To receive a copy of this document, indicate in the box: "C" a Copy without auchment/ enclosure "E" a Copy wrth attachtnant/endosure "N" a No copy ///
OFFICE PDil 1/PM _, /-) lEI Poll 1/LA l6l l l PO!!-1/D f)'((,V l NAME MPadovan D EDunnint; ton f6'7h P2 T. Kuo f 8 DAVE 09/ 1 /98 09/ j)98 $/1998 i 0FFICIAL RECORD COPY
September 8.1998 I
l Our request for additional information (RAI) is enclosed. Our RAI questions mainly pertain to Topical Report WCAP-14901. However, we request that you generally apply the infcrmation 1 requests to WCAP-14932 as well. Please note that we have issued similar requests to other i WOG member utilities. As before, we encourage you to address these inquiries in an '
integrated fashion with the WOG and the Nuclear Energy Institute. However, we request that
{
you identify any deviations from the WOG's integrated program that may be specific to the Summer plant.
1 I discussed this RAI with Mr. Jim Turkett of your staff on September 1,1998. We mutually
, agreed that the SCE&G target date to respond to this RAI is within 90 days of the date of this i letter. Please call me at (301) 415-1423 if you need to revise the target date. !
I Sincerely,
)
Onginal Signed by:
L. Mark Padovan, Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/II
- Office of Nuclear Reactor Regulation l Docket No. 50-395 i l
Enclosure:
Request for 1
Additional Information cc w/ encl: See next page Distribution !
' Docket FiW !
PUBLIC l PD 11-1 Reading OGC ACRS J. Zwotinski l L. Plisco, Ril l
J. Harold J. Medoff DOCUMENT NAME: G:\ SUMMER \ SUM 98602.RAI l Ta receive a copy of this document. Indicate in the box: "C" = Copy without attachment / enclosure "E' = Copy with attachtnent/ enclosure "N" = No copy / /7 0FFICE POII-1/PM ,O lE PDil 1/LA lE l PDil-1/D [M[,V l NAME MPadovan 'M EDunnington ((h P2 T. Kuo Il
~3 DATE 09/ A/98 09/ '/J98 5/ M98 4 0FFICIAL RECORD COPY
Mr. Grry J. Taylor VIRGIL C. SUMMER NUCLEAR STATION i South Carolina Elsetric & Gas Company cc:
Mr. R. J. Whito J. B. Knotts, Jr., Esquire Nuclear Coordinator Winston & Strawn Law Firm S.C. Public Service Authority 1400 L Street, N.W.
c/o Virgil _ C. Summer Nuclear Station Washington, D.C. 20005-3502 Post Office Box 88, Mail Code 802 ~
Jeiikinsville, South Carolina 29065 l
Resident inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 J+nkinsville, South Carolina 29065 l
Figional Administrator, Region 11 1
!! S. Nuclear Regulatory Commission Ailanta Federal Center 6' Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Cnairman, Fairfield County Council-Drawer 60
%1nnsboro, South Carolina 29180 Mr. Virgil R. Autry, Director D! vision of Radioactive Waste Management Bureau of Land & Waste Management Department of Health & Environmental Control 2 BOO Bull Street Columbia, South Carolina 29201 Mr. Robert M. Fowlkes, Manager Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 303 Post Office Box 88 Jenkinsville, South Carolina 29065 Ms. April R. Rice, Manager Nuclear Licensing & Operating Experience South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 830 Post Office Box 88 Jenkinsville, South Carolina 29065
a
' r e
~
i Enclosure
] Reauest for AdditionalInformation I
in Resoonse to Generic Letter (GL) 97-01 1
4 The technical content provided in WCAP-14901', Revision 0, is basically the same as that I provided in WCAP-14902. The difference is that WOG member plants subscribing to i
WCAP-14901 opted to rank the susceptibility of their vessel head penetrations (VHPs) according to a probabilistic Weibull analysis method. In contrast, the WOG member plants j subscribing to WCAP-14902, Revision 0, opted to rank the VHPs for their facilities according to a probabilistic methodology that another vendor developed.
- j. We have reviewed your May 1,1997, and July 30,1997, responses to GL 97-01. We need the l following information to complete our review of your responses. The requested information relates to the WOG's integrated program for assessing VHP nozzles at WOG member plants,
- and to the contents of Topical Report No. WCAP-14901 as it relates to these responses
4 i 1. In WCAP-14901, WEC did not determine what the probabilistic failure model would lead
. the WOG to conclude with respect to assessing Primary Water Stress Corrosion i Cracking (PWSCC) in WEC-designed VHPs. With respect to the probabilistic
! susceptibility model (i.e., probabilistic failure model) provided in WCAP-14901:
1
- a. Provide the susceptibility rankings compiled for the WOG member plants for which
, WCAP-14901 applies. In regard to other WOG member plants to which WCAP-14901 applies, include the basis for establishing the ranking of your plant
, relative to the others.
l b. Describe how the probabilistic failure model in WCAP-14901 for assessing VHP i postulated flaws was benchmarked, and list and discuss the standards the model
! was benchmarked against.
- c. Provide additionalinformation regarding how the probabilistic failure models in WCAP-14901 will be refined to allow the input of plant-specific inspection data into the model analysis methodology.
{ d. Describe how variability in product forms, material specifications, and heat treatments used to fabricate each control rod drive mechanism penetration nozzle at j WOG member plants are addressed in the probabilistic crack initiation and growth models described or referenced in Topical Report No. WCAP-14901.
t
- 2. Table 1-2 in WCAP-14901 summarizes key tasks in WEC's VHP assessment program.
The table indicates that the tasks for (1) Evaluation of PWSCC Mitigation Methods, (2)
Crack Growth Data and Testing, and (3) Crack initiation Characterization Studies are not complete and are stillin progress. Since the probabilistic susceptibility models
- appear to be dependent, in part, on PWSCC crack initiation and growth estimates, a
t d
provide your best estimate when WEC will complete these tasks. Also, describe how these activities relate to, and will be used to, update the probabilistic susceptibility assessment of VHP nonles at Summer.
- 3. The Nuclear Energy Institute indicated in their January 29,1998, and April 1,1998, letters (Refs.1 and 2), that VHP noule Inspection plans have been developed for inspecting the Farley Unit 2 plant in the year 2002, and the Diablo Canyon Unit 2 plant in the year 2001. We noted that although you have endorsed the probabilistic susceptibility model described in WCAP-14901, Revision 0, other WOG member licensees have endorsed a probabilistic susceptibility model an altemate vendor developed. The WOG's proposal to inspect the VHP nozzles at the Farley Unit 2 and Diablo Canyon Unit 2 plants appea.s to be based on a composite assessment of the VHP nozzles at all WOG member plants. Verify that such a composite ranking assessment has been applied to the evaluation of VHP nozzles at Summer, if composite rankings were obtained for all of WOG member plants, justify why applying one model would yield the same comparable relative rankings as would applying the other model. Comment on the susceptibility rankings of the VHP nozzles at Summer relative to the susceptibility rankings of the VHP nozzles at the Farley Unit 2 and Diablo Canyon Unit 2 planta.
References:
l
- 1. David J. Modeen, Director of Engineering, Nuclear Generation Division, Nuclear Energy l Institute, letter to G. C. Lainas, Acting Director, Division of Engineering, Office of Nuclear I Reactor Regulation, U.S. Nuclear Regulatory Commission, (Untitled), January 19,1998. I
- 2. David J. Modeen, Director of Engineering, Nuclear Generation Division, Nuclear Energy Institute, letter to G. C. Lainas, Acting Director, Division of Engineering, Office of Nuclear l Reactor Regulation, U.S. Nuclear Regulatory Commission, "
Subject:
Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Head Penetrations,"
April 1,1995.
1 i