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MONTHYEARRC-14-0112, License Amendment Request - LAR-12-04269 License Basis Changes in Steam Generator Tube Rupture Analysis2014-08-27027 August 2014 License Amendment Request - LAR-12-04269 License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: Request RC-14-0178, License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information2014-10-31031 October 2014 License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information Project stage: Response to RAI RC-15-0025, License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information2015-02-12012 February 2015 License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information Project stage: Response to RAI RC-15-0075, Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis2015-05-12012 May 2015 Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: Response to RAI RC-15-0142, License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information2015-09-10010 September 2015 License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information Project stage: Response to RAI 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 Project stage: Other ML15320A3382015-12-0101 December 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: RAI RC-16-0006, Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis2016-01-14014 January 2016 Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Project stage: Response to RAI RC-16-0031, License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response2016-03-0404 March 2016 License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response Project stage: Supplement ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident Project stage: Approval 2015-02-12
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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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Thomas D. Gatlin Vice President,Nuclear Operations 803.345.4342 A SCANA COMPANY May 12, 2015 RC-1 5-0075 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Attn: S. A. Williams
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSE AMENDMENT REQUEST - LAR-12-04269 LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
References:
- 1. SCE&G Letter from Thomas D. Gatlin to NRC Document Control Desk, License Amendment Request - LAR-12-04269, "License Basis Changes in Steam Generator Tube Rupture Analysis," dated August 27, 2014
[ML14245A408]
- 2. NRC Letter from Shawn A. Williams to Thomas D. Gatlin, "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)," dated April 13, 2015 [ML15076A118]
South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority pursuant to 10 CFR 50.90, submitted License Amendment Request (LAR) per Reference 1 concerning license basis changes in the steam generator tube rupture analysis. NRC review of this request determined that additional information was required and a request for additional information (RAI) was issued per Reference 2. This submittal's attachment contains SCE&G's response to the RAls dated April 13, 2015.
This letter contains a regulatory commitment for VCSNS to provide a new set of three-year meteorological data, along with an update to thermal dispersion factors, to provide responses to RAIs No. 1 and No. 3 by September 11, 2015.
If you have any questions regarding this submittal, please contact Mr. Bruce L. Thompson at (803) 931-5042.
4Ao V.C.Summer Nuclear Station . P.O.Box 88 . Jenkinsville, SC. 29065 . F (803) 941-9776
Document Control Desk CR- 12-04269 RC-15-0075 Page 2 of 2 I certify under penalty of perjury that the foregoing is correct and true.
Executed on (D Gatlie TSITDG/rp Attachment I: VCSNS Response to Request for Additional Information Attachment II: List of Regulatory Commitments c: K. B. Marsh S. A. Byrne J. B. Archie N. S. Carns J. H. Hamilton J. W. Williams W. M. Cherry V. M. McCree S. A. Williams NRC Resident Inspector S. E. Jenkins Paulette Ledbetter K. M. Sutton NSRC RTS (CR-12-04269)
Files (813.20)
PRSF (RC-15-0075)
Document Control Desk Attachment I CR-12-04269 RC-1 5-0075 Page 1 of 3 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT I DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ATTACHMENT I VCSNS RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
Document Control Desk Attachment I CR-12-04269 RC-1 5-0075 Page 2 of 3 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), dated August 27, 2014 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML14245A408) and supplements dated October 31, 2014, and February 12, 2015 (ADAMS Accession Nos.
ML14308A075 and ML15055A143, respectively). The NRC staff has determined that the following requests for additional information (RAI) are required to complete the review.
RAI No. 1 In the NRC staffs Safety Evaluation dated October 4, 2010 (ADAMS Accession No. ML102160020), approving the Alternative Source Term (AST), Section 3.1.1 it states:
"However, because of the apparent uncertainties discussed above, the NRC staff notes that these data may not be considered acceptable for use in other dose assessments of other meteorological applications without further NRC review and approval."
Therefore, please provide the most recent 3 years, with 90% recovery rate (per RG 1.230),
of current meteorological data so that the staff can perform an assessment of the proposed x/Qs.
SCE&G Response The Steam Generator Tube Rupture (SGTR) LAR used the Analysis of Record (AOR) dispersion factors (X/Qs). These were approved for use under the Alternative Source Term (AST) safety evaluation in 2010. The same dose analysis methodology is used for both the AOR and the current SGTR LAR with similar results. SCE&G believes that a re-analysis of dispersion factors is not necessary for the SGTR LAR.
However, a new set of meteorological data will be submitted along with an update to the thermal dispersion calculation. This effort will require vendor support and calendar time beyond the thirty day RAI response. SCE&G will provide meteorological data in Regulatory Guide 1.23 format, meteorological data in ACRON96 format and the updated calculation for thermal dispersion factors. These items will be submitted to the NRC by September 11, 2015.
RAI No. 2 The NRC staffs previous approval for the Steam Generator Tube Rupture (SGTR) AST did not include an atmospheric dispersion factor for the low population zone from 0-2 hours; however, the reanalysis used a value of 5.06E-5. The application stated that this value was derived from a fuel handling accident analysis. Since a fuel handling accident is different from a SGTR, please justify the use of this value for the SGTR accident analysis.
SCE&G Response In calculating post-accident x/Qs with PAVAN for the low population zone (LPZ) at a site, the release point to receptor location (LPZ) is taken to be the same for all of the AST design basis accidents (DBAs) due to the large distance from the release point to the LPZ (approximately 3
Document Control Desk Attachment I CR-12-04269 RC-15-0075 Page 3 of 3 miles). The x/Q is not a function of the activity release characteristics but only the time duration of the release. In all of the AST DBA cases a ground level release is conservatively applied.
RAI No. 3 Page 35 of the August 27, 2014, submittal, states that the atmospheric dispersion factors are presented in Table 11. A review of Table 11 shows that the values used are the same as those contained in the following application:
Letter from SCE&G to NRC, "License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67," February 17, 2009. (ADAMS Accession No. ML090720887)
In the NRC staffs approval of this application it states, "Therefore, the X/Q values should not be considered acceptable for use in other dose assessments or other meteorological applications without further NRC review and approval."
Given that the staff previously stated that these values should not be considered acceptable, please provide justification for using these values and demonstrate that these values are still appropriate with a more recent data set that does not have the uncertainties that were inherent in the previously provided data set.
SCE&G Response Under RAI No. 1 above, a new set of meteorological data will be collected and new thermal dispersion factors will be calculated. This data will be submitted to the NRC for closure of the concerns related to the AOR thermal dispersion factors.
Document Control Desk Attachment II CR- 12-04269 RC-15-0075 Page 1 of 1 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT I DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ATTACHMENT II LIST OF REGULATORY COMMITMENTS The following table identifies the action committed to by the Virgil C. Summer Nuclear Station (VCSNS) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Mr. Bruce L. Thompson at (803) 931-5042.
VCSNS is to provide a new set of three-year meteorological data, along with an update to thermal dispersion factors, to September 11, 2015 provide responses to RAIs No. 1 and No. 3.