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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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i f'Thomas D. Gatlin Vice President, Nuclear Operations 803.345.4342 A SCANA COMPANY May 21, 2015 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS), UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 SPECIAL REPORT (SPR) 2014-006 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
- 1. Letter from T. D. Gatlin (VCSNS) to Document Control Desk (NRC),"SPECIAL REPORT (SPR 2014-006)," dated November 5, 2014[ML14314A033]
Reference:
- 2. Letter from S. A. Williams (NRC) to T. D. Gatlin (VCSNS), "Virgil C.Summer Nuclear Station, Unit No. 1 -Request for Additional Information (TAC No. MF5164)", date March 26, 2015[ML15079A099]
South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority pursuant to the requirements of Technical Specifications 6.9.1.12, submitted the Steam Generator Tube Inspection Report (Reference
- 1) following the 2014 Spring Refueling (RF-21) Outage. NRC's review of Reference 1 determined that additional information is required and a Request for Additional Information (RAI) was issued per Reference
- 2. The Attachment of this letter contains SCE&G's response to the RAIs in Reference 2.Should you have any questions, please call Mr. Bruce Thompson at (803) 931-5042.Very truly yours, Thomas D. Gatlin WLT/TDG/wm Attachment c: K. B. Marsh S. A. Byrne J. B. Archie N. S. Cams J. H. Hamilton J. W. Williams W. M. Cherry V. M. McCree S. A. Williams NRC Resident Inspector K. M. Sutton INPO Records Center NSRC RTS (CR-15-01442)
File (818.08)PRSF (RC-15-0081)
AL)D(V. C. Summer Nuclear Station
- Jenkinsville, SC .29065 -F (803) 941-9776 Document Control Desk Attachment CR-15-01442 RC-1 5-0081 Page 1 of 5 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ATTACHMENT I Request for Additional Information (RAI) Response Document Control Desk Attachment CR-1 5-01442 RC-15-0081 Page 2 of 5 VC Summer Spring 2014 Steam Generator Inspection Report RAIs By letter dated March 26, 2015 [ML15079A099], NRC requested the following information to continue review of the Spring 2014 steam generator tube inspections performed at Virgil C. Summer Nuclear Station, Unit 1.RAI No. 1: Please provide the cumulative number of effective full power months (EFPMs)that the steam generators had operated for the last 4 refueling outages. Please also provide the number of EFPMs that the steam generators (SGs) had operated at the time of the first inservice inspection.
VC Summer Response: The approximate cumulative effective full power months (EFPM) that the VC Summer Steam Generators have operated are identified below.1st ISI -RF-09 (Spring 1996) -15.3 EFPM RF-17 (Spring 2008) -141.9 EFPM RF-18 (Fall 2009)- 157.6 EFPM RF-19 (Spring 2011)- 173.3 EFPM RF-20 (Fall 2012) -189.7 EFPM RF-21 (Spring 2014) -205.2 EFPM RAI No. 2: Please discuss the results of the channel head bowl inspections, upper bundle video inspection in SG A, steam drum inspections, and tube plug inspections.
For the tube plug inspections, were all plugs present and in their proper locations?
Was any degradation observed?VC Summer Response: Channel Head Bowl Inspections Westinghouse Nuclear Safety Advisory Letter NSAL-1 2-1 recommends visual inspection of the channel head near the bowl drain line to determine if degradation of the cladding and potential degradation of the channel head base material have occurred.
All three SG channel heads were visually inspected during RF-21. The observed conditions were consistent with the manufacturing process and did not exhibit any signs of degradation.
Visual inspection concluded that a condition similar to that documented in NSAL-12-1 does not currently exist at VC Summer.
Document Control Desk Attachment CR-15-01442 RC-15-0081 Page 3 of 5 Tube Plug Inspections Five tubes were plugged in the VC Summer Steam Generators during RF-12 (Fall 2000). This was the last outage when tubes were plugged at VC Summer. Three tubes were plugged prior to installation at the factory. The cumulative total number of tube plugs is eight.All installed plugs were inspected for degradation and evidence of leakage. All plugs were determined to be in their proper location.
No degradation was noted. No dripping plugs were identified and all plugs were found to be dry.Upper Bundle Video Inspection in SG A A tube lane and in-bundle inspection was performed on the top tube support plate of SG A. The inspection was performed in the tube lane as well as in approximately every tenth column of the tube bundle on both the hot leg and cold leg sides.The inspection of the tube lane region of the top tube support plate resulted in no tube wear, anomalies, or foreign objects being observed.
Very little loose sludge was found in the tube lane while no hard sludge was observed.
The support plate's circular flow holes in the tube lane region were clear of sludge and other deposits while the center stayrod nuts observed were intact and appeared to be in good condition.
Finally, the visible anti-vibration bars were all intact and properly aligned.During the in-bundle inspections, no tube wear, tube anomalies, or foreign objects were observed.
In addition, no support plate anomalies, such as ligament cracking or loss of material, were observed.
The tube column gaps were relatively clean but some loose sludge was observed in-bundle on the top surface of the support plate. The support plate did possess some partial blockage of some of its quatrefoils due to the loose sludge.
Document Control Desk Attachment CR-1 5-01442 RC-1 5-0081 Page 4 of 5 Steam Drum Inspections Visual inspections of the steam drum region were performed in all three steam generators.
The visual inspections included examinations of all visibly accessible components within the steam drum region of each steam generator.
The goal of the steam drum visual inspections was to provide an overall inspection of each steam generator's steam drum components and to identify any evidence of degradation, damage, deformation, anomalies, abnormalities, loose parts, potential loose parts, and foreign objects. The following components were inspected: " Primary Moisture Separators" Secondary Moisture Separators" Steam Outlet Nozzle" Internal Deck Plates* Feedwater Ring and Nozzles* Auxiliary Feed Pipe and Nozzle* Sludge Collector Assembly* Shell Inner Diameter Surface The inspections revealed no visible signs of degradation or structural issues that would prohibit continued steam generator operation and threaten tube integrity until the next scheduled steam drum inspections.
4'.Document Control Desk Attachment CR-15-01442 RC-1 5-0081 Page 5 of 5 RAI No. 3: In Table 2, there is an inspection category for "cold leg new bobbin wear." Were all of the new wear indications located on the cold leg? If not, were new wear indications in the hot leg inspected?
VC Summer Response: The category identified in Table 2 of the RF-21 VC Summer Steam Generator Tube Inspection Report as "cold leg new bobbin wear" was a special interest inspection that is a bobbin retest using an AVB wear standard.
The same special interest inspection was performed on the hot leg as well. Hot Leg Inspection Scope is in Table 1.Table 1 -Hot Leg Bobbin Retest with AVB Standard SGA SGB SGC 2 6 4 RAI No. 4: Please discuss which tubes would not pass a bobbin probe. Were these all low row (i.e., rows 1 and 2) tubes? If not, please discuss the nature of the restrictions in these tubes.VC Summer Response: Inspection scope discussed in Section 2 of RF-21 VC Summer Steam Generator Tube Inspection Report Inspection report described:
- 1) U-bend +Point inspection of tubes that a bobbin probe would not pass through This statement referred to a planned inspection scope of low row u-tubes. There were no restricted/blocked tubes that a bobbin probe would not pass through. As such, as-tested inspection scope did not change from the planned inspection scope. Sample size for this inspection scope is identified in Table 2.Table 2 -U-Bend +Point Inspection of Low Row U-Tubes SG A SG B SG C 23 44 40