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Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
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Text
L.M. Stinson (Mike) Southern Nuclear Vice President Operating Company. Inc.
Fleet Operations Support 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 SE SOUTHERN October 9, 2007 COMPANY Energy to Serve Your World' Docket Nos.: 50-424 NL-07-1948 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Additional Information to Support Acceptance Review of Request to Change Maximum Power Level Ladies and Gentlemen:
By way of letter NL-07-1020, dated August 28, 2007, Southern Nuclear Operating Company (SNC) submitted an application to change the Maximum Power Level of Vogtle Electric Generating Plant (VEGP) Units 1 and 2. On October 2, 2007, in a phone call between SNC and the Staff, SNC was requested to provide additional information to support the acceptance review of the radiological analyses described in the application.
As requested by the Staff, SNC is providing the following information regarding the calculation of relative atmospheric dispersion factor (x/Q) values at the Main Control Room air intakes following a loss-of-coolant accident.
- 1. The annual periods for the meteorological data are 1998, 1999, and 2000.
- 2. Meteorological data used in the ARCON96 analyses are located on the enclosed CD (Enclosure 1) in the folder named "Met Data."
- 3. The ARCON96 input data are located on the enclosed CD in the folder named "Input Files." This folder also contains a file named "ARCONInput Output Fname.xls" that cross-references the names of the input and output files with the individual ARCON96 cases.
- 4. For VEGP, the release mode is "ground level" as described in VEGP UFSAR Section 15A.1.
- 5. The source-receptor configuration details are provided in Enclosure 2.
The information is excerpted from the SNC calculation for determining the x/Q values at the Main Control Room air intakes.
U. S. Nuclear Regulatory Commission NL-07-1948 Page 2
- 6. Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) distances are not being provided because offsite x/Q values were not recalculated.
- 7. The ARCON96 output data are located on the enclosed CD in the folder named "Output Files."
- 8. The current x/Q values are reported in Table 15A-2 of the VEGP UFSAR.
The current and revised x/Q values are also reported in Table 111-2 in Enclosure 5,Section III, of the application to change the Maximum Power Level of VEGP Units 1 and 2 referenced above.
Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Vice President Fleet Operations Support Swqrn to and subscribedbefore me this 7 day of 7,, 2007.
Notary Public My commission expires: 3~2010 LMS/RJF/daj
Enclosures:
- 1. CD Containing ARCON96 Files
- 2. Source-Receptor Configuration Details
U. S. Nuclear Regulatory Commission NL-07-1948 Page 3 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. S. P. Lingam, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle State of Georgia Mr. N. Holcomb, Commissioner - Department of Natural Resources
Vogtle Electric Generating Plant Additional Information to Support Acceptance Review of Request to Change Maximum Power Level Enclosure 1 CD Containing ARCON96 Files
Vogtle Electric Generating Plant Additional Information to Support Acceptance Review of Request to Change Maximum Power Level Enclosure 2 Source-Receptor Configuration Details
Design Calculations - Nuclear Southern Company ServicesA IProject Vogtle Units 1 and 2 ICalcuon X6CHA.01.00Number Subject/Title Main Control Room and Technical Support Center Air Intake X/Q Estimates Shed [6] of [10]
Distance between FHB and CR air intake FHBs are located between two reactor buildings with a roof elevation of 288'2". The FHB releases were assumed to occur at the roof, where the distance to the CR air intake is the shortest. This shortest distance is same to Units 1 and 2 air intakes when the release locations are located at the east and west comer of the FHB.
Total source-to-receptor distance = 8085.25 ft - 7998.5 ft + 19.25 ft = 106 ft = 32.3 m Where 19.25 ft is the distance between Row CD and the CR intake, and 8085.25 ft and 7998.5 ft are the locations of Rows CD and FA, respectively (Drwg. IX4DE312, Ver. 11.0). The vertical distance between the FHB roof and the CR intake is:
FRB roof height - CR air intake height = 288.17' - 283' = 5.17 ft The distance between Unit 1 CR intake and Unit 1 FHB release point is shorter than the distance between Unit 1 CR intake and Unit 2 FHB release point. Similarly, the distance between Unit 2 CR intake and Unit 2 FHB release point is shorter than that between Unit 2 CR intake and Unit I FHB release point. Only the expected worst case distances were presented regarding the FHB releases. It is the case involving Unit 1 CR intake and the east comer FHB release. The case involving Unit 2 CR intake and west comer FHB releases will produce results that are identical to the case with Unit 1. All the above source-to-receptor distances were used in the ARCON96 runs. Distances between the release points and air intakes are presented below.
Receptor: Unit 1 CR Air Intake Horizontal, Vertical Direction to Source Release Point Distance (ft) Distance (ft) Straight-Line Distance degree)
Unit 1 Ft m Containment 72 0 72.0 21.9 135 Hatch Door 275 -54.5 280.3 85.5 135 FHB 106 5.17 106.1 32.3 180 Unit 2 Containment 189 0 189.0 57.6 247 Hatch door 363 -54.5 367.1 111.9 243 Receptor: Unit 2 CR Air Intake Horizontal Vertical Direction to Source Release Point Distance (ft) Distance (ft) Straight-Line Distance (degree)
Unit I ft m Containment 189 0 189.0 57.6 73 Hatch Door 363 -54.5 367.1 111.9 118 Unit 2 Containment 72 0 72.0 21.9 226 Hatch door 275 -54.5 280.3 85.5 225 FHB 106 5.17 106.1 32.3 180
Design Calculations - Nuclear Southern Company ServicesA Project Calculation Number Vogtle Units I and 2 X6CHA.01.00 Subject/Title Main Control Room and Technical Support Center Air Intake X/Q Estimates Sheet [7] of [ 10]
Receptor: TSC Air Intake .
Horizontal Vertical Direction to Source Release Point Distance (ft) Distance (ft) Straight-Line Distance (degree)
Unit 1 ft m Containment 81 0 81.0 24.7 173 Hatch Door 240 -5.75 240.1 73.2 161 Unit 2 Containment 283 0 283.0 86.3 246 Hatch door 455 -5.75 455.0 138.7 243 The elevations of air intakes and release points are presented in the following table.
Location Elevation (ft)
CR Intake 283 TSC Intake 234.25 Hatch Door 228.5 FHB Roof 288.17 Note: The grade elevation is 220 ft.
It should be noted that for the postulated FHB releases, besides the cases presented above, four other scenarios were also analyzed. They are 1) east comer release - Unit 2 CR intake; 2) west comer release - Unit 1 CR intake; 3) mid-point release - Unit I CR intake; and 4) mid-point release - Unit 2 CR intake. The mid-point is assumed to be located in the middle of the line connecting east and west comer release points. The above 4 scenarios all have their "intake to source" distances larger than that of the east comer release and Unit 1 CR intake (or west comer release and Unit 2 CR intake). They were considered to ensure that the meteorological conditions associated with the specific wind direction window would not cause the X/Qs to become greater than the cases presented in this calculation.
5.4 Effective Wind Directions The direction to the source from the intake and "wind direction window width" are part of the input requirements for the ARCON96 program. As suggested in NUREG/CR-6331 (1997), the wind direction window sector size was chosen as the direction from the receptor to the source, +/-450. The "direction to source" for each combination of release point and receptor (air intake) is presented in the table shown in Sheets 5 and 6.
5.5 Building Areas Building areas used for wake analysis were calculated based on the assumptions described in Section 4.3.
Design Calculations - Nuclear Southern Company Services A I Proct Vogtle Units 1 and 2 X6CHA.01.00 Calculation Number Subject/Title Main Control Room and Technical Support Center Air Intake X/Q Estimates Sheet [10] of [10]
Figure 1 Air Intake Locations and Release Points Hatch Door TSC Intake 0 North Unit I CR Intake FHB Release Pt. x 0
Fuel Handling Building (Units 1 & 2) 0 Unit 2 CR Intake Hatch Door Note: Release point from the reactor was a point on the containment surface closest to the receptor location.