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Category:Inspection Plan
MONTHYEARIR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23131A1492023-05-10010 May 2023 2023 V.C. Summer Commercial Grade Dedication Inspection Information Request IR 05000395/20220062023-03-0101 March 2023 Annual Assessment Letter for Virgil C. Summer Nuclear Station (Report 05000395/2022006) ML23055A0992023-02-24024 February 2023 Final - Virgil C. Summer - Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000395/20220052022-08-26026 August 2022 Updated Inspection Plan for Virgil C. Summer - Report 05000395/2022005 ML22075A0482022-03-16016 March 2022 V.C. Summer Nuclear Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000395/2022401 IR 05000395/20210062022-03-0202 March 2022 Annual Assessment Letter for Virgil C. Summer Unit 1 (Report No 05000395/2021006) ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections IR 05000395/20200062021-03-0303 March 2021 Annual Assessment Letter for Virgil C. Summer Station, Unit 1 Report 05000395/2020006 ML21050A0012021-02-18018 February 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML21043A1402021-02-11011 February 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000395/20190062020-03-0303 March 2020 Annual Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 - NRC Report 05000395/2019006 IR 05000395/20190052019-08-28028 August 2019 Updated Inspection Plan for Virgil C. Summer Nuclear Station, Unit 1 - (Report 05000395/2019005) ML19155A2752019-06-0404 June 2019 VC Summer 2019003 Rad Safety Inspection Document Request ML19066A3792019-03-0707 March 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000395/20180062019-03-0404 March 2019 Annual Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 Report 05000395/2018006, Report 05000395/2018402, Report 05000395/2018501 ML18240A2122018-08-27027 August 2018 VC Summer Emailed Information Request EB3 RP 2018004 IR 05000395/20180052018-08-23023 August 2018 Updated Inspection Plan for Virgil C. Summer Nuclear Station, Unit 1, (Report 05000395/2018005) IR 05000395/20170062018-02-28028 February 2018 Annual Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 - Report 05000395/2017006, Report 05000395/2017402, Report 05000395/2017501 ML17234A2422017-08-21021 August 2017 Updated Inspection Plan ML17150A4552017-05-30030 May 2017 Notification of Virgil C. Summer Design Bases Assurance Inspection - NRC Inspection Report 05000395/2017007 ML17142A1882017-05-19019 May 2017 Virgil C.Summer Emergency Preparedness Inspection and Request for Information Dated: May 19, 2017 IR 05000395/20160062017-03-0101 March 2017 Annual Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 - Report 05000395/2016006 IR 05000395/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 - NRC Inspection Report 05000395/2016005 ML16130A8192016-05-0404 May 2016 Notification of Inspection and Request for Information IR 05000395/20150052015-09-0101 September 2015 Mid-Cycle Letter for Virgil C. Summer Generating Station Unit 1 - NRC Assessment Report 05000395/2015005 IR 05000395/20140012015-03-0404 March 2015 Annual Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 - Report 05000395/2014001 ML14245A2002014-09-0202 September 2014 V.C. Summer Mid-Cycle Ltr 2014 ML14175A5762014-06-24024 June 2014 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000395/20130012014-03-0404 March 2014 Annual Assessment Letter for Virgil C. Summer Nuclear Station, Unit 1 - Report 05000395/2013001 ML13246A1412013-09-0303 September 2013 Mid Cycle Assessment Letter IR 05000395/20120012013-03-0404 March 2013 Annual Assessment Letter for Summer Nuclear Station, Unit 1, Report 05000395/2012001 ML12248A1172012-09-0404 September 2012 Mid Cycle Assessment Letter Summer 2012 ML1206505962012-03-0505 March 2012 EOC Report 22 ML1124400632011-09-0101 September 2011 Report 22 - Summer ML1106304142011-03-0404 March 2011 V. C. Summer, Inspection/Activity Plan, 03/01/2011 - 06/30/2012, Report 22 ML1024403162010-09-0101 September 2010 Report 22 - 2010 Mid Cycle Inspection/Activity Plan ML1006208862010-03-0303 March 2010 Report 22 - 2010001, Inspection/Activity Plan ML0924403682009-09-0101 September 2009 Inspection/Activity Plan, 09/01/2009 - 12/31/2010 ML0906304762009-03-0404 March 2009 Enclosure - Summer Inspection / Activity Plan (03/01/2009 - 06/30/2010) ML0824609582008-09-0202 September 2008 Inspection Activity Plan - 09/02/2008 - 12/31/2009 IR 05000395/20080012008-03-0303 March 2008 Annual Assessment Letter (IR 05000395-08-001) ML0724802462007-08-31031 August 2007 Inspection / Activity Plan 09/01/2007 - 03/31/2009, Report 22 ML0706003462007-03-0101 March 2007 Inspection / Activity Plan for 03/01/2007 - 09/30/2007 RC-07-0021, Inspection and Mitigation Plan/Schedule of Alloy 82/182 Pressurizer Butt Welds (C-04-1719)2007-01-31031 January 2007 Inspection and Mitigation Plan/Schedule of Alloy 82/182 Pressurizer Butt Welds (C-04-1719) ML0624303732006-08-31031 August 2006 Mid-Cycle Performance Review and Inspection Plan, 09/01/06 - 03/31/08 ML0606104122006-03-0202 March 2006 Inspection / Activity Plan, 03/01/2006 - 09/30/2007 2024-08-22
[Table view] Category:Letter type:RC
MONTHYEARRC-22-0004, (Vcsns), Unit 1 - 2021 Annual Letter of Certification and Testing Results of the Public Alerting System2022-01-14014 January 2022 (Vcsns), Unit 1 - 2021 Annual Letter of Certification and Testing Results of the Public Alerting System RC-18-0157, (Vcsns), Units 1, 2 and 3 Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-12-28028 December 2018 (Vcsns), Units 1, 2 and 3 Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-18-0149, ISFSI - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-12-21021 December 2018 ISFSI - Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-18-0136, (Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683)2018-12-12012 December 2018 (Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683) RC-18-0144, (Vcsns), Unit 1 - Core Operating Limits Report (COLR) for Cycle 252018-11-20020 November 2018 (Vcsns), Unit 1 - Core Operating Limits Report (COLR) for Cycle 25 RC-18-0126, (Vcsns), Unit 1 - Notification of an Intended Change a Commitment Date for Open Phase Condition (OPC) Made in RC-17-01692018-11-0909 November 2018 (Vcsns), Unit 1 - Notification of an Intended Change a Commitment Date for Open Phase Condition (OPC) Made in RC-17-0169 RC-18-0070, (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ...2018-10-0808 October 2018 (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ... RC-18-0067, (Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.22018-10-0808 October 2018 (Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 RC-18-0123, NRC Request for Information Baseline Radiation Safety Inspection2018-10-0404 October 2018 NRC Request for Information Baseline Radiation Safety Inspection RC-18-0117, (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment2018-09-28028 September 2018 (Vcsns), Unit 1 - Fukushima Near-Term Task Force Recommendation 3.1: Seismic Probabilistic Risk Assessment RC-18-0112, (Vcsns), Unit 1 - Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2, D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.B.2 and 4.8.2.1.C.32018-09-27027 September 2018 (Vcsns), Unit 1 - Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2, D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.B.2 and 4.8.2.1.C.3 RC-18-0119, (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422, Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-09-19019 September 2018 (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422, Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation RC-18-0118, (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange2018-09-14014 September 2018 (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange RC-18-0116, (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information2018-09-11011 September 2018 (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information RC-18-0113, (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-08-31031 August 2018 (Vcsns), Unit 1 - Supplement to License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation RC-18-0091, License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions2018-08-29029 August 2018 License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions RC-18-0111, License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation2018-08-24024 August 2018 License Amendment Request LAR-18-03422 Request for a One-Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation RC-18-0100, (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information2018-08-22022 August 2018 (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information RC-18-0105, (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water ..2018-08-14014 August 2018 (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water .. RC-18-0102, Withdrawal of Request to Revise Technical Specifications to Correct an Administrative Error2018-08-10010 August 2018 Withdrawal of Request to Revise Technical Specifications to Correct an Administrative Error RC-18-0098, (Vcsns), Units 1, 2 and 3 - Modification of Requested Latest Completion Date in Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-07-30030 July 2018 (Vcsns), Units 1, 2 and 3 - Modification of Requested Latest Completion Date in Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-18-0085, (Vcsns), Unit 1 - Notification of an Intended Change to a Commitment Made in RC-17-01262018-07-23023 July 2018 (Vcsns), Unit 1 - Notification of an Intended Change to a Commitment Made in RC-17-0126 RC-18-0090, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request...2018-07-12012 July 2018 (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request... RC-18-0089, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping2018-07-11011 July 2018 (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping RC-18-0084, Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Requ2018-07-0303 July 2018 Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Reques RC-18-0082, Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping2018-07-0303 July 2018 Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping RC-18-0079, Vigil C. Summer Nuclear Station (Vcsns), Unit 1 - Request to Revise Technical Specifications to Correct an Administrative Error2018-06-29029 June 2018 Vigil C. Summer Nuclear Station (Vcsns), Unit 1 - Request to Revise Technical Specifications to Correct an Administrative Error RC-18-0074, Change of the Commitment Date of DRIB/105A&B Door Submittal2018-06-18018 June 2018 Change of the Commitment Date of DRIB/105A&B Door Submittal RC-18-0060, (VCSNS) - Request to Revise Technical Specifications to Correct Administrative Error2018-05-30030 May 2018 (VCSNS) - Request to Revise Technical Specifications to Correct Administrative Error RC-18-0064, (Vcsns), Unit 1 - Annual Commitment Change Summary Report2018-05-18018 May 2018 (Vcsns), Unit 1 - Annual Commitment Change Summary Report RC-18-0063, Submittal of 10 CFR 72.48 Biennial Report for the Independent Spent Fuel Storage Installation2018-05-0202 May 2018 Submittal of 10 CFR 72.48 Biennial Report for the Independent Spent Fuel Storage Installation RC-18-0056, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors2018-04-25025 April 2018 (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors RC-18-0059, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report RC-18-0046, License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information2018-04-19019 April 2018 License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information2018-04-0202 April 2018 (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information RC-18-0041, Report of Status of Decommissioning Funding2018-03-28028 March 2018 Report of Status of Decommissioning Funding RC-17-0175, Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error2018-01-31031 January 2018 Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error RC-18-0006, Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses2018-01-25025 January 2018 Independent Spent Fuel Storage Installation Re Application for Order Approving Indirect Transfer of Control of Operating License and Combined Licenses RC-17-0169, Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-00192017-12-11011 December 2017 Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-0019 RC-17-0182, (VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status2017-12-11011 December 2017 (VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status RC-17-0172, Notification of Personnel Changes2017-11-30030 November 2017 Notification of Personnel Changes RC-17-0161, Submittal of Change of the Commitment Date of DRIB/105A&B Door2017-11-28028 November 2017 Submittal of Change of the Commitment Date of DRIB/105A&B Door RC-17-0135, Annual Commitment Change Summary Report2017-11-0303 November 2017 Annual Commitment Change Summary Report RC-17-0123, Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds2017-10-30030 October 2017 Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds RC-17-0140, Transmittal of 10 CFR 50.59 Biennial Report2017-10-23023 October 2017 Transmittal of 10 CFR 50.59 Biennial Report RC-17-0107, (Vcsns), Unit 1 - Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change2017-10-0606 October 2017 (Vcsns), Unit 1 - Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change RC-17-0134, Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 12017-09-27027 September 2017 Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1 RC-17-0126, Reply to a Notice of Violation, Per Inspection Report 05000395/20170022017-09-0606 September 2017 Reply to a Notice of Violation, Per Inspection Report 05000395/2017002 RC-17-0112, Special Report (Spr) 2017-007 Regarding Waste Gas Holdup System Explosive Gas Monitoring System Being Inoperable for Greater than Thirty Days2017-09-0101 September 2017 Special Report (Spr) 2017-007 Regarding Waste Gas Holdup System Explosive Gas Monitoring System Being Inoperable for Greater than Thirty Days RC-17-0069, (Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description2017-08-30030 August 2017 (Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description 2022-01-14
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Text
Jeffrey B. Archie Vice President,Nuclear Operations 803.345.4214 January 31, 2007 RC-07-0021 A SCANA COMPANY U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 INSPECTION AND MITIGATION OF ALLOY 82/182 PRESSURIZER BUTT WELDS (C-04-1719)
Reference:
Marvin S. Fertel (NEI) Letter to Luis A. Reyes (NRC), Industry Actions Associated with Potential Generic Implications of Wolf Creek Inspection Findings, January 26, 2007 In October of 2006, while performing inspections of its pressurizer Alloy 82/182 butt welds in accordance with MRP-1 39, a PWR licensee discovered several circumferential indications in its pressunzer surge, safety and relief nozzles. Because of the potential importance of this issue, SCE&G is submitting this letter as notification of VCSNS actions taken or planned for inspecting or mitigating Alloy 82/182 butt welds on pressurizer spray, surge and relief lines.
Inspection of pressurizer Alloy 82/182 butt welds at VCSNS has not yet been completed, but SCE&G will complete the inspection and mitigation activities on these locations during the next refueling outage (RF17) currently scheduled for April 2008. Justification for delaying these activities beyond December 31, 2007 is provided in Attachment I. Details concerning the VCSNS inspection and mitigation activities are provided by Attachment II. Future inspections of pressurizer dissimilar metal (DM) butt welds at VCSNS will be performed in accordance with industry guidance (MRP-139).
In addition to the inspection and mitigation activities described above, low threshold procedures for monitoring primary system leakage are in place for VCSNS. If VCSNS should shut down due to excessive pdmary system unidentified leakage and, if the leakage can not be confirmed to originate from a source other than the pressurizer, a bare metal visual (BMV) examination of Alloy 82/182 butt weld locations on the pressurizer will be performed to determine whether the leakage originated at those locations.
Consistent with the actions discussed in the referenced letter, SCE&G is evaluating enhancements to leakage monitoring procedures for VCSNS and will provide the details of these actions to the NRC by March 31, 2007.
In addition, SCE&G is assessing the feasibility of on-line monitoring equipment for the VCSNS pressurizer to provide diverse leakage detection capabilities. The details of these actions will be provided to the NRC by May 31, 2007.
SCE&G I Virgil C.Summer Nuclear Station - P.0. Box 88 - Jenkinsville, South Carolina 29065
Document Control Desk Letter C-04-1719 RC-07-0021 Page 2 of 2 SCE&G is also participating in, and sharing the cost of, a newly developed EPRI project to perform additional refined crack growth calculations of the limiting pressurizer nozzle Alloy 82/182 weld configuration using 3-dimensional finite element analysis.
Commitments made through this letter are identified in Attachment IV.
The NRC will be informed if SCE&G deviates from any of the actions described in this letter.
SCE&G staff is available to meet with the NRC to discuss any of the information contained in this letter.
Should you have questions, please call Mr. Bruce Thompson at (803) 931-5042.
Very tru y rs,
/
Jeffrey B. Archie JWT/JBA/dr Attachment I Inspection and Mitigation Plan/Schedule for Alloy 82/182 Pressurizer Butt Welds at V.C. Summer Nuclear Station (VCSNS)
Attachment II Inspection and Mitigation Summary for Alloy 82/182 Pressurizer Butt Welds Attachment III Previous ISI Program Examinations for Alloy 82/182 Pressurizer Butt Welds Attachment IV List of Commitments c: K. B. Marsh S. A. Byrne N. S. Cams J. H. Hamilton R. J. White W. D. Travers R. E. Martin NRC Resident Inspector K. M. Sutton J. Riley (NEI)
NSRC RTS (C-04-1719)
File (815.02)
DMS (RC-07-0021)
Document Control Desk Letter Attachment I C-04-1719 RC-07-0021 Page 1 of 3 INSPECTION AND MITIGATION PLAN / SCHEDULE OF ALLOY 82/182 PRESSURIZER BUTT WELDS AT V. C. SUMMER NUCLEAR STATION (VCSNS)
Inspection and mitigation activities at VCSNS will be completed during the next refueling outage (RF1 7) currently scheduled for April 2008. The activities necessary to effectively address this issue warrant additional time beyond the MRP-1 39 prescribed end date of December 31, 2007.
VCSNS utilized the last scheduled outage (RF-16 in October 2006) after MRP-139 was issued (September 2005) to plan the mitigation weld overlays. It was determined that the pressurizer welds could not be inspected in accordance with MRP-139 inspection requirements at all six pressurizer locations. In order to adequately plan implementation, address interference with the "as built" configuration, and minimize radiation dose during implementation, a pre-implementation walk-down was necessary. VCSNS has completed the necessary walk-downs, performed laser profiling to support design and implementation activities, and awarded a contract to perform full structural weld overlay application. The application of the structural weld overlay will allow the welds to be inspected in accordance with MRP-1 39. The weld overlay design process requires approximately seven months of engineering evaluation and design analysis to develop the appropriate weld overlay configuration. Upon issuance of the design package, three months is required for tooling design, welder qualification and the weld and NDE process mock-up and demonstration. Pre-outage planning and preparations require approximately three months following the completion of the mock-up demonstration. This allows for an appropriate amount of time to ensure ALARA planning as well as any specific plant support such as shielding, scaffolding and other logistical needs. Finally, a one month period is expected for contractor mobilization. The schedule outlined above provides assurance that the activity can be effectively completed, while assuring the radiological and industrial safety of the plant staff and our contractors.
This schedule is acceptable based on the following:
PREVIOUS INSPECTION RESULTS Bare Metal Visual (BMV) inspections of the dissimilar metal (DM) Pressurizer welds were made in the Spring 2005 outage (RF-15) and also in the Fall of 2006 outage (RF16) as required by NRC Bulletin 2004-01, INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS. Neither of these inspections identified any leakage. Volumetric and surface inspections (ultrasonic and dye penetrant) were performed on the subject welds in the period from September 1994 through April 1999 using non-PDI (Performance Demonstration Initiative) techniques with coverage and results shown in Attachment II1. There were no recordable or reportable flaws from these pressurizer weld examinations.
WELD FABRICATION REVIEWS An assessment of original fabrication weld documentation to identify welds that may have been reworked is currently in process. VCSNS has contracted with Westinghouse to perform a comprehensive review of the factory fabrication DM weld history.
The assessment is scheduled to be completed in mid-February 2007. SCE&G will make every effort to provide the NRC an update on the assessment results by February 28, 2007 but accounting for possible delays due to vendor delivery and/or SCE&G review and acceptance, no later than March 31, 2007.
Document Control Desk Letter Attachment I C-04-1719 RC-07-0021 Page 2 of 3 ENHANCED LEAKAGE MONITORING FOR UNIDENTIFIED PRIMARY SYSTEM LEAKAGE The VCS Reactor Coolant System (RCS) Leakage Management Program monitors RCS leakage at a very low threshold. While the VCSNS Technical Specifications 3.4.6.2 specifies that NO pressure boundary leakage is acceptable and that up to 1 gpm is allowed as unidentified leakage, the VCSNS monitoring thresholds are established to ensure that the Technical Specification requirements are not challenged. VCSNS monitors more frequently than required by Technical Specifications.
The current program identifies action levels which begin with a validated change in leakage rate of 0.05 gpm above the existing normal leak rate for a period of 3 days. Additional action levels have been established at a total unidentified leakage rate of 0.2 gpm and 0.6 gpm with prescribed actions to determine the source, evaluate and eliminate the source of the leakage.
Various other procedures are utilized to perform measurements and determine the source of leakage.
RCS leakage is given a high priority by management which is reflected by taking actions above and beyond the procedure requirements on a routine basis:
" RCS unidentified leakage trend is part of the daily Plant Information Meetings and included in the Management Duty Supervisors daily report.
" The RCS Leakage Program Manager provides weekly updates to Operations.
" RCS leakage is a point of discussion at senior plant management meetings.
If VCSNS should shut down due to excessive primary system unidentified leakage and if the leakage cannot be confirmed to originate from a source other than the pressurizer, a bare metal visual examination of the DM butt weld locations on the pressurizer will be performed to determine whether the leakage originated from those locations.
PWR OWNERS GROUP ENHANCED LEAK DETECTION In addition to the current RCS leakage monitoring program, VCSNS is currently evaluating the documents issued by the PWR Owners Group with respect to enhanced processes and methods of calculating RCS leakage.
SCE&G will update our response concerning this subject by March 31, 2007 in a follow-up letter.
INDUSTRY SAFETY ASSESSMENT The conclusions from the butt weld safety assessment, MRP-1 09, indicate that there is no immediate safety concern associated with PWSCC of Alloy 82/182 butt welds based on the following:
" The case of the longitudinal flaw is a safe situation, because the length of the flaw is limited to the width of the weld material (-2.5"), which is less than the critical flaw size for burst.
(MRP-109, Sect. 7)
" The circumferential crack growth analysis results for the Westinghouse designed spray nozzle showed it would take at least 2.5 years to propagate a flaw to a critical crack length from a 1 GPM leak. (MRP-109, Table 5-3 and Section 7)
- A very small number of leaks/cracks have been identified given the large number of locations worldwide. (MRP-139, Sect. 4.3)
Document Control Desk Letter Attachment I C-04-1719 RC-07-0021 Page 3 of 3
" Axial cracking is much more likely than circumferential. (MRP-109 and MRP-1 39, Sect.1)
- Probabilistic analysis shows the impact of butt weld PWSCC on CDF is insignificant, but probability of leaks is not. (MRP-139, Sect. 1.3)
" The potential for boric acid corrosion (BAC) is considered low for all Alloy 82/182 pressurizer joint upper head locations since any leak at operating conditions would be essentially pure water/steam with little boric acid carryover to cause corrosion.
" The potential for BAC of the surge line as well as the top head pressurizer joint locations is addressed by the bare metal visual inspections.
" The Susceptibility Analysis performed by Westinghouse and documented in WCAP-1 6388, "PWSCC Susceptibility Assessment of the Alloy 600 and Alloy 82/182 Components in V. C.
Summer Nuclear Station", indicates a very low probability of PWSCC failure of these components prior to the Spring 2008 outage timeframe.
As a result of the circumferential indications found in October 2006, the industry, through EPRI MRP, reviewed the Alloy 82/182 Pipe Butt Weld Safety Assessment (MRP-1 13) and the Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139). This review can be found in the white paper titled "Implications of Wolf Creek Pressurizer Butt Weld Indications to Safety Assessment and Inspection Requirements." The conclusions from the industry review included:
- Critical flaw sizes are several times larger than the indications observed in October 2006.
- Bare metal visual inspections during the last refueling outage (October 2006 for VCSNS) ensure a low risk of leaks and an extremely low risk of rupture through the spring of 2008.
Document Control Desk Letter Attachment II C-04-1719 RC-07-0021 Page 1 of 1 Inspection and Mitigation Summary for Alloy 82/182 Pressurizer Butt Welds Nozzle MRP-139 Volumetric Mitigation Inspection Requirement Met Completed or to or to be Met be Completed Comments Function Susceptible Material Outage Start Date Outage Designation Description Designation (MMIYYYY) Designation Spray! Nozzle-to safe end weld RF17 04/2008 RF17 Structural Weld Overlay followed by PDI Qualified CGE-1-4503-46DM Inspection Surge / Nozzle-to safe end weld RF17 04/2008 RF17 Structural Weld Overlay followed by PDI Qualified CGE-1-4500A-1 DM Inspection Safety 801 OA / Nozzle-to safe end weld RF17 04/2008 RF17 Structural Weld Overlay followed by PDI Qualified CGE-1-4501-12DM Inspection Safety 8010B / Nozzle-to safe end weld RF17 04/2008 RF17 Structural Weld Overlay followed by PDI Qualified CGE-1-4501-1 DM Inspection Safety 8010C / Nozzle-to safe end weld RF17 04/2008 RF17 Structural Weld Overlay followed by PDI Qualified CGE-1-4501-23DM Inspection Relief -PORV's/ Nozzle-to safe end weld RF17 04/2008 RF1 7 Structural Weld Overlay followed by PDI Qualified CGE-1-4502-1D M Inspection
Document Control Desk Letter Attachment III C-04-1719 RC-07-0021 Page 1 of 1 Previous ISI Program Examinations for Alloy 82/182 Pressurizer Butt Welds Nozzle Previous ISI/ UT examinations Bare Metal Visual Examinations Function / Susceptible RF-15 RF-16 Designation Material Outage Date NDE Designation PT/UT Spring 2005 Fall-2006 Designation_ Description 4/8/99 PT-No Recordable Surface Indications BMV-No Evidence of BMV-No Evidence of Boric Acid Spray Nozzle-to safe end CGE-1-4503-46DM weld 4/19/99 UT-No Recordable Indications Boric Acid Leakage Leakage
-90.38% Estimated Coverage Surface PT- No Recordable Surge Nozzle-to safe end 4 Indications BMV-No Evidence of BMV-No Evidence of Boric Acid CGE-1-4500A-1DM weld UT-No Recordable Indications Boric Acid Leakage Leakage 100% Coverage Safety 9/23/94 Surface PT- No Recordable Nozzle-to safe end Indications BMV-No Evidence of BMV-No Evidence of Boric Acid 8010A Leakage CGE-1-4501-12DM weld 9/28/94 & UT-No Recordable Indications Boric Acid Leakage 10/1/94 100% Coverage 9/23/94 Surface PT- No Recordable Safety Nozzle-to safe end Indications BMV-No Evidence of BMV-No Evidence of Boric Acid 801GB 8010B weld 9/28/94 & UT-No 100%
Recordable Indications Coverage Boric Acid Leakage Leakage CGE-1-4501-IDM 10/1/94 Surface PT- No Recordable Safety Nozzle-to safe end Indications BMV-No Evidence of BMV-No Evidence of Boric Acid 80100 801 weld 9/28/94 & UT-No Recordable Indications Boric Acid Leakage Leakage CGE-1-4501-23DM 10/1/94 100% Coverage Relief Nozzle-to safe end 9/23/94 Surface PT- No Recordable Indications BMV-No Evidence of BMV-No Evidence of Boric Acid CGE-1-4502-1DV 9/28/94 & UT-No Recordable Indications Boric Acid Leakage Leakage 10/1/94 100% Coverage
Document Control Desk Letter Attachment IV C-04-1719 RC-07-0021 Page 1 of 1 List of Commitments Alloy 82/182 Program Enhancements COMMITTED COMMITMENT TYPE No. COMMITMENT DATE OR ONE-TIME ACTION PROGRAMMATIC ATO "OUTAGE" (YeslNo) ACTION
_____ ____________________________ _______________ __ ___ ___ ___ (Yes/No)
Inspection and Mitigation activities at April 30, 2008 Yes No VCSNS will be completed during the next refueling outage (RF17) currently scheduled for April 2008.
Future inspections of pressurizer As required by No Yes dissimilar metal (DM) butt welds at MRP-139 VCSNS will be performed in accordance with industry guidance (MRP-1 39).
Perform an assessment of original March 31,2007 Yes No fabrication welds documentation to identify welds that may have been reworked and provide results to NRC.
If VCSNS should shutdown due to Upon Occurrence Yes No excessive primary system unidentified leakage and if the leakage cannot be confirmed to originate from a source other than the pressurizer, a bare metal visual examination of the dissimilar metal butt weld locations on the pressurizer will be performed to determine if the leakage originated from those locations.
SCE&G is evaluating PWR Owners March 31, 2007 Yes No Group documents with respect to enhanced leak detection processes and methods of calculating RCS leakage. Results will be provided to the NRC.
SCE&G is assessing the feasibility of May 31, 2007 Yes No on-line monitoring equipment for the VCSNS pressurizer to provide diverse leakage detection capabilities. The details of these actions will be provided to the NRC.