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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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Tom Tynan Southern Nuclear Vice President Vogtle Operating Company, Inc. 7821 River Road Waynesboro, Georgia 30830 Tel 706 8263151 Fax 706 826 3321 April 3, 2008 SOUTHERN'\
COMPANY Energy to Serve Your World " Docket Nos.: 50-424 NL-08-0522 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Supplemental Information Related to License Amendment Request for Interim Alternate Repair Criterion to Technical Specification "Steam Generator (SG)
Ladies and Gentlemen:
On February 13, 2008, Southern Nuclear Operating Company (SNC) submitted an application to revise Vogtle Electric Generating Plant (VEGP) Technical Specification (TS) 5.5.9, "Steam Generator (SG) Program" and TS 5.6.10, "Steam Generator Tube Inspection Report," to propose a one cycle revision to incorporate an interim alternate repair criterion (ARC) in the provisions for SG tube repair criteria during Refueling Outages 1 R14 (Unit 1) and 2R13 (Unit 2) and the subsequent operating cycles for each unit. On February 8, 2008, Wolf Creek Nuclear Operating Company (WCNOC) submitted a similar application to revise TS 5.5.9 and TS 5.6.10 to incorporate an interim ARC, and on February 20, 2008, the Nuclear Regulatory Commission (NRC) provided, by electronic mail, issues and comments related to the WCNOC amendment application.
A teleconference was held with representatives from SNC, WCNOC, Exelon Generation Company, NRC and other industry representatives on February 21, 2008, to discuss the issues and comments related to the WCNDC submittal.
Subsequent to this teleconference, the NRC provided WCNDC a request for additional information (RAI) letter by electronic mail on February 28, 2008 that contained thirteen (13) questions.
On March 10 and 18,2008, subsequent to the WCNOC RAlletter, the NRC provided SNC RAI letters containing seventeen (17) questions by electronic mail regarding the SNC February 13, 2008 amendment application for VEGP. On March 21, 2008, SNC provided a response to the seventeen (17) questions contained in the NRC RAI letters. Regarding question 13, the SNC response, as well as the WCNDC response, indicated that an administrative limit would be established to not exceed the calculated steam line break leakage value. On March 26,2008, SNC was informed by a telephone call from the VEGP NRC Project Manager that, during a teleconference with WCNDC and the WCNOC NRC Project Manager, it was identified that a regulatory commitment was U. S. Nuclear Regulatory Commission NL-08-0522 Page 2 required for this administrative limit since the NRC safety evaluation for the requested amendment was relying on the use of a constant multiplier of 2.5 to calculate a steam line break administrative limit. Enclosure 1 provides additional details. In addition, as a result of the subsequent discussions with the NRC and Wolf Creek personnel, SNC will not require the interim ARC for 2R13 (Unit 2) and the subsequent operating cycle as previously submitted in the February 13, 2008 application.
Mr. T. E. Tynan 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. The additional information provided in the Enclosures does not impact the conclusions of the No Significant Hazards Consideration provided in Reference 1 of Enclosure
- 1. The NRC commitment contained in this letter is provided as a table in Enclosure
- 2. If you have any questions, please advise. Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY T.
.: ,.'..* , t}'"TA : "..:.... -.' . '. Vice President
-Vogtle ':,.'(" ***...7..:. ***** .:
Sworn to and subscribed before me this day of ,2008.
c/Jjvr; JJ.
Notary Public, Burke county,
... C mmission expires January 13, My commission expires: IV_,Y_O _ TET/DRG/daj
Enclosures:
Supplemental Information Related to License Amendment Request for an Interim Alternate Repair Criterion
- 2. List of Regulatory Commitments U. S. Nuclear Regulatory Commission NL-08-0522
Page 3 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. H. Jones, Vice President - Engineering RType: CVC7000
U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Acting 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 Supplemental Information Related to License Amendment Request for an Interim Alternate Repair Criterion to Technical Specification 5.5.9, "Steam Generator (SG) Program" Enclosure 1 Supplemental Information Related to License Amendment Request for an Interim Alternate Repair Criterion
Supplemental Information Related to License Amendment Request for an Interim Alternate Repair Criterion E1-1 On February 13, 2008 Southern Nuclear Operating Company (SNC) submitted an application to revise Vogtle Electric Generating Plant (VEGP) Technical Specification (TS) 5.5.9, "Steam Generator (SG) Program" and TS 5.6.10, "Steam Generator Tube Inspection Report," to propose a one cycle revision to incorporate an interim alternate repair criterion (ARC) in the provisions for SG tube repair criteria during Refueling Outages 1R14 (Unit 1) and 2R13 (Unit 2) and the subsequent operating cycles for each unit (Reference 1).
On March 10 and 18, 2008 the Nuclear Regulatory Commission (NRC) provided SNC request for additional information (RAI) letters containing seventeen (17) questions by electronic mail regarding the SNC February 13, 2008 amendment application for VEGP. On March 21, 2008 SNC provided a response to seventeen (17) questions contained in the NRC RAI letters (Reference 2).
In the response to question 13 in Reference 2, SNC indicated that an administrative limit would be established to not exceed the calculated steam line break leakage value. On March 26, 2008 SNC was informed by a telephone call from the VEGP NRC Project Manager that during a teleconference with Wolf Creek Nuclear Operating Corporation's (WCNOC) and the WCNOC NRC Project Manager, it was identified that a regulatory commitment was required for this administrative limit since the NRC safety evaluation for the requested amendment was relying on the use of a constant multiplier of 2.5 to calculate a steam line break administrative limit.
Specifically, the response to question 13 stated, in part:
For integrity assessments, the ratio of 2.5 will be used in the completion of both the condition monitoring (CM) and operational assessment (OA) upon implementation of the IARC. For example, for the CM assessment, the component of leakage from the lower 4 inches for the most limiting steam generator during the prior cycle of operation will be multiplied by a factor of 2.5 and added to the total leakage from any other source and compared to the allowable accident analysis leakage assumption. For the OA, the difference in leakage from the allowable limit during the limiting design basis accident minus the leakage from the other sources will be divided by 2.5 and compared to the observed leakage. An administrative limit will be established to not exceed the calculated value.
As such, SNC considers the above to be a regulatory commitment.
In addition, as a result of the subsequent discussions with the NRC and Wolf Creek personnel, SNC will not require the interim ARC for 2R13 (Unit 2) and the subsequent operating cycle as previously submitted in the February 13, 2008 application.
References:
- 1. SNC letter NL-08-0148, "License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9, "Steam Generator (SG) Program" and TS 5.6.10, "Steam Generator Tube Inspection Report" for Interim Alternate Repair Criterion," February 13, 2008.
- 2. SNC letter NL-08-0343, "Response to Request for Additional Information Related to License Amendment Request for an Interim Alternate Repair Criterion to Technical Specification 5.5.9, "Steam Generator (SG) Program"," March 21, 2008.
Vogtle Electric Generating Plant Supplemental Information Related to License Amendment Request for an Interim Alternate Repair Criterion to Technical Specification 5.5.9, "Steam Generator (SG) Program" Enclosure 2 List of Regulatory Commitments List of Regulatory Commitments E2-1 The following table identifies those actions committed by Southern Nuclear Operating Company in this document for Vogtle Electric Generating Plant. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
Commitment Due Date/Event For VEGP Unit 1 Only: For integrity assessments, the ratio of 2.5 will be used in the completion of both the condition monitoring (CM) and operational assessment (OA) upon implementation of the IARC. For example, for the CM assessment, the component of leakage from the lower 4 inches for the most limiting steam generator during the prior cycle of operation will be multiplied by a factor of 2.5 and added to the total leakage from any other source and compared to the allowable accident analysis leakage assumption. For the OA, the difference in leakage from the allowable limit during the limiting design basis accident minus the leakage from the other sources will be divided by 2.5 and compared to the observed leakage. An administrative limit will be established to not exceed the calculated value.
Completion of CM and OA