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| | number = ML14339A030 | | | number = ML14339A030 |
| | issue date = 01/09/2015 | | | issue date = 01/09/2015 |
| | title = Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis (TAC No. MF4699) | | | title = Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis |
| | author name = Williams S A | | | author name = Williams S |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Gatlin T D | | | addressee name = Gatlin T |
| | addressee affiliation = South Carolina Electric & Gas Co | | | addressee affiliation = South Carolina Electric & Gas Co |
| | docket = 05000395 | | | docket = 05000395 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS (TAG NO. MF4699) Dear Mr. Gatlin: By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident. The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed. Docket No. 50-395 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 . Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), LAR-12-04269, dated August 27, 2014, concerning the license basis changes required due to an update to the Steam Generator Tube Rupture (SGTR) analysis. The NRC staff has determined that the following request for additional information (RAJ) is required to complete its review. RAI No.1 I In application dated August 27, 2014, it stated: New SGTR dose analyses are also performed by Westinghouse using, consistent with the Virgil C. Summer Licensing Basis, the RADTRAD computer program following the guidance of Regulatory Guide 1.183. Dose consequences are provided for the mass transfer input from the current licensing basis and new transient analyses. -During the review process the NRC staff noticed what appear to be some differences between the current license basis SGTR analysis parameters and the proposed SGTR analysis parameters that are not discussed in SCE&G's LAR. Therefore, the NRC staff is requesting that a table be provided for the SGTR analysis that lists: (1) The parameters used in the SGTR dose analysis, (2) the current approved SGTR modeled value for each parameter listed in VCSNS Updated Final Safety Analysis Report, (3) the new modeled value for each parameter in the revised SGTR analysis, and (4) a description of the technical basis that explains why the new modeled value changed. "-(NOTE: Tables 9 through 14 in the LAR already provide items (1) and (3) above and could be revised to include items (2) and (4)). RAI No.2 Provide the RADTRAD input and output files for the new SGTR analysis. RAI No.3 As presented in LAR 12-04269, LOFTTR2 was used, per the methodology of WCAP:10698-P, to perform SGTR transient analyses for VCSNS. Does the version of LOFTTR2 used in the analysis presented in LAR 12-04269 contain any code modifications? Enclosure | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 |
| -2 -RAI No.4 The referenced Steam Generator Tube analysis methodology (WCAP-1 0698) contains a single failure analysis relative to margin to overfill. When a new methodology is referenced by an applicant, exceptions to portions of the methodology typically require a technical basis. What is the technical basis for not considering a single failure?
| | |
| January 9, 2015 Mr. Thomas D. (3atlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer NUclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SG 29065 SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN GENERATOR TUBE RUPTURE ANALYSIS (TAC NO. MF4699) Dear Mr. Gatlin: By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident. The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed. Docket No. 50-395 Enclosure: Sincerely, /RAJ Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrDoriDpr Resource RidsNrrLASFigueroa Resource LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrDRA Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn2MaiiCenter Resource RidsNrrPMSummer Resource ADAMS Accession No.: ML 14339A030 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 12/31/14 01/06/15 01/08/15 01/09/15 OFFICIAL RECORD COPY
| | ==SUBJECT:== |
| }} | | VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS (TAG NO. MF4699) |
| | |
| | ==Dear Mr. Gatlin:== |
| | |
| | By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident. |
| | The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed. |
| | Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 . |
| | Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), LAR-12-04269, dated August 27, 2014, concerning the license basis changes required due to an update to the Steam Generator Tube Rupture (SGTR) analysis. The NRC staff has determined that the following request for additional information (RAJ) is required to complete its review. |
| | RAI No.1 I |
| | In application dated August 27, 2014, it stated: |
| | New SGTR dose analyses are also performed by Westinghouse using, consistent with the Virgil C. Summer Licensing Basis, the RADTRAD computer program following the guidance of Regulatory Guide 1.183. Dose consequences are provided for the mass transfer input from the current licensing basis and new transient analyses. - |
| | During the review process the NRC staff noticed what appear to be some differences between the current license basis SGTR analysis parameters and the proposed SGTR analysis parameters that are not discussed in SCE&G's LAR. Therefore, the NRC staff is requesting that a table be provided for the SGTR analysis that lists: (1) The parameters used in the SGTR dose analysis, (2) the current approved SGTR modeled value for each parameter listed in VCSNS Updated Final Safety Analysis Report, (3) the new modeled value for each parameter in the revised SGTR analysis, and (4) a description of the technical basis that explains why the new modeled value changed. |
| | (NOTE: Tables 9 through 14 in the LAR already provide items (1) and (3) above and could be revised to include items (2) and (4)). |
| | RAI No.2 Provide the RADTRAD input and output files for the new SGTR analysis. |
| | RAI No.3 As presented in LAR 12-04269, LOFTTR2 was used, per the methodology of WCAP:10698-P, to perform SGTR transient analyses for VCSNS. Does the version of LOFTTR2 used in the analysis presented in LAR 12-04269 contain any code modifications? |
| | Enclosure |
| | |
| | RAI No.4 The referenced Steam Generator Tube analysis methodology (WCAP-1 0698) contains a single failure analysis relative to margin to overfill. When a new methodology is referenced by an applicant, exceptions to portions of the methodology typically require a technical basis. What is the technical basis for not considering a single failure? |
| | |
| | ML14339A030 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 12/31/14 01/06/15 01/08/15 01/09/15}} |
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MONTHYEARML14248A4322014-09-18018 September 2014 Acceptance Review Project stage: Acceptance Review ML14339A0302015-01-0909 January 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: RAI ML15050A2092015-02-25025 February 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15076A1182015-04-13013 April 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: RAI ML15261A0512015-09-22022 September 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: RAI 2015-02-25
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Category:Letter
MONTHYEARML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23270B8712023-09-27027 September 2023 NRR E-mail Capture - Draft RAIs for License Amendment Request (LAR) to Revise the Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Emergency Plan (L-2023-LLA-0083) ML22263A0502022-09-19019 September 2022 NRR E-mail Capture - Draft Request for Additional Information for Proposed Alternative Request RR-4-26 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval V.C. Summer Unit 1 ML22194A9422022-07-13013 July 2022 NRC 50.59 Inspection (IP 71111.17T) Information Request ML22075A0482022-03-16016 March 2022 V.C. Summer Nuclear Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000395/2022401 ML21333A1892021-11-29029 November 2021 NRR E-mail Capture - Draft RAI for Summer LAR Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, (TSTF-425) ML21253A1352021-09-0808 September 2021 Document Request for VC Summer Nuclear Station - Radiation Protection Inspection - Inspection Report 2021-04 ML21154A2792021-06-0303 June 2021 Requalification Program Inspection 05000395/2021003 - Virgil C. Summer Nuclear Station, Unit 1, ML21145A0222021-05-24024 May 2021 003 Radiation Safety Baseline Inspection Information Request ML21131A0402021-05-11011 May 2021 NRR E-mail Capture - V.C. Summer, Unit 1 - Final RAI for the Spring 2020 RFO Sgtir Review ML21020A0562021-01-20020 January 2021 Email Capture Upcoming V.C. Summer POV Inspection (IP71111.21N.02) Information Request ML20342A1822020-12-0707 December 2020 NRR E-mail Capture - Final RAI for Summer LAR - TS 3.6.4 ML20342A3822020-12-0707 December 2020 NRR E-mail Capture - Final RAIs for Summer Fs LOCA LAR ML20321A2112020-11-16016 November 2020 NRR E-mail Capture - Summer, Unit 1 - Final RAIs for the SG Tube Inspection Report Review ML20196L7782020-07-13013 July 2020 Notification of Virgil C. Summer Nuclear Station Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000395/2020010 ML20106E8902020-04-15015 April 2020 Program Inspection RFI ML20056E3042020-02-25025 February 2020 VC Summer 2020-002 Radiation Safety Baseline Inspection Information Request ML19211D5102019-07-30030 July 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-16-01490 NFPA-805 (Supplement to PRA RAI 03) ML19179A1262019-06-27027 June 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-16-01490 NFPA-805 Program Revisions ML19095A6532019-04-0404 April 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information NFPA-805 Program Revisions LAR ML19072A1442019-03-13013 March 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-16-01490 NFPA-805 Program Revisions ML19009A1052019-01-0909 January 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-10-02395, TS 3.8.2, D.C. Sources - Operating ML18249A1932018-09-0505 September 2018 TS 4.3.3.6 SR LAR - Request for Additional Information ML18225A0932018-08-13013 August 2018 Notification of Inspection and Request for Information ML18218A2622018-08-0101 August 2018 Emergency Preparedness Program Inspection Request for Information ML18066A0002018-03-0808 March 2018 Request for Additional Information Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML18023B0692018-02-15015 February 2018 Request for Additional Information Relief Request (RR-4-13), Use of Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds ML17095A2842017-05-11011 May 2017 Request for Additional Information License Amendment Request for Implementation of TSTF-411 (WCAP-15376-P-A), Revision 1 ML17067A5322017-03-0808 March 2017 Notification of Radiation Protection Baseline Inspection and Request for Information ML17059C5382017-02-23023 February 2017 Notification of Inspection and Request for Information ML16302A1252016-11-0808 November 2016 Request for Additional Information License Amendment Request for Implementation of TSTF-411 and WCAP-15376-P-A, Revision 1 RC-16-0112, NRC Request Information Baseline Radiation Safety Inspection2016-07-0707 July 2016 NRC Request Information Baseline Radiation Safety Inspection ML16111A0912016-05-0303 May 2016 Request for Additional Information Regarding the Station Physical Security Plan, Revision 14 ML16097A0812016-04-0808 April 2016 Request for Additional Information ML16064A0332016-03-0303 March 2016 NRR E-mail Capture - Request for Additional Information Related to the March 1, 2016, Exigent Amendment Request ML16042A4712016-02-18018 February 2016 Request for Additional Information ML15320A3382015-12-0101 December 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis RC-15-0177, Submits LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Response to Response for Additional Information2015-11-0505 November 2015 Submits LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Response to Response for Additional Information ML15261A0512015-09-22022 September 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis ML15118A4592015-05-19019 May 2015 Request for Additional Information Regarding Alternative Request ML15118A3802015-05-0505 May 2015 Request for Additional Information Regarding Snubber Program Alternative Request ML15076A1182015-04-13013 April 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis ML15079A0992015-03-26026 March 2015 Request for Additional Information ML14339A0302015-01-0909 January 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis ML14268A5162014-10-23023 October 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-evaluation Related to Southeastern Catalog Changes ML14226A2552014-08-29029 August 2014 Request for Additional Information ML14182A4732014-07-11011 July 2014 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML14071A1692014-03-24024 March 2014 Request for Additional Information ML14023A7402014-01-30030 January 2014 (VCSNS) - Request for Additional Information ML13347B0492013-12-19019 December 2013 (VCSNS) - Request for Additional Information ML13340A3772013-12-11011 December 2013 (VCSNS) - Request for Additional Information 2023-09-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS (TAG NO. MF4699)
Dear Mr. Gatlin:
By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident.
The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 .
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), LAR-12-04269, dated August 27, 2014, concerning the license basis changes required due to an update to the Steam Generator Tube Rupture (SGTR) analysis. The NRC staff has determined that the following request for additional information (RAJ) is required to complete its review.
RAI No.1 I
In application dated August 27, 2014, it stated:
New SGTR dose analyses are also performed by Westinghouse using, consistent with the Virgil C. Summer Licensing Basis, the RADTRAD computer program following the guidance of Regulatory Guide 1.183. Dose consequences are provided for the mass transfer input from the current licensing basis and new transient analyses. -
During the review process the NRC staff noticed what appear to be some differences between the current license basis SGTR analysis parameters and the proposed SGTR analysis parameters that are not discussed in SCE&G's LAR. Therefore, the NRC staff is requesting that a table be provided for the SGTR analysis that lists: (1) The parameters used in the SGTR dose analysis, (2) the current approved SGTR modeled value for each parameter listed in VCSNS Updated Final Safety Analysis Report, (3) the new modeled value for each parameter in the revised SGTR analysis, and (4) a description of the technical basis that explains why the new modeled value changed.
(NOTE: Tables 9 through 14 in the LAR already provide items (1) and (3) above and could be revised to include items (2) and (4)).
RAI No.2 Provide the RADTRAD input and output files for the new SGTR analysis.
RAI No.3 As presented in LAR 12-04269, LOFTTR2 was used, per the methodology of WCAP:10698-P, to perform SGTR transient analyses for VCSNS. Does the version of LOFTTR2 used in the analysis presented in LAR 12-04269 contain any code modifications?
Enclosure
RAI No.4 The referenced Steam Generator Tube analysis methodology (WCAP-1 0698) contains a single failure analysis relative to margin to overfill. When a new methodology is referenced by an applicant, exceptions to portions of the methodology typically require a technical basis. What is the technical basis for not considering a single failure?
ML14339A030 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 12/31/14 01/06/15 01/08/15 01/09/15