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Category:Letter type:NL
MONTHYEARNL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0128, License Amendment Request: Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) Testing Frequency2024-04-0404 April 2024 License Amendment Request: Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) Testing Frequency NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0112, Request for Revision to NRC Staff Assessment of Vogtle Site Updated Seismic Hazards2024-03-28028 March 2024 Request for Revision to NRC Staff Assessment of Vogtle Site Updated Seismic Hazards NL-24-0098, Report on Status of Decommissioning Funding2024-03-28028 March 2024 Report on Status of Decommissioning Funding NL-24-0097, Exemption Request: Final Safety Analysis Report Update Schedule2024-03-22022 March 2024 Exemption Request: Final Safety Analysis Report Update Schedule NL-22-0267, License Amendment Request to Revise Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, AC Sources – Operating, Surveillance Requirements2024-03-20020 March 2024 License Amendment Request to Revise Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, AC Sources – Operating, Surveillance Requirements NL-24-0060, Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03)2024-02-15015 February 2024 Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03) NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0045, Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-022024-02-0808 February 2024 Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-02 NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0038, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2024-02-0202 February 2024 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-24-0031, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R23 NL-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-23-0742, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fo Surveillance Technical Specifications2023-09-20020 September 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fo Surveillance Technical Specifications 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-23-0658, 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-23-0670, 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-23-0672, 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 2024-09-09
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& Southern Nuclear Charles R. Pierce Regulatory Affairs Director 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 7872 tel 205 992 7601 fax crpierce@ southernco.com JAN 1 0 2017 Docket Nos.: 50-424 NL-16-2710 50-425 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant- Units 1 and 2 Request for One-Time Exception to LIC-1 09, LIC-1 01. and LIC-500 Acceptance Review Criteria Ladies and Gentlemen:
The Office of Nuclear Reactor Regulation (NRR) Office Instructions No. LIC-1 09, Revision 1, Acceptance Review Procedures, provides guidance to the NRR staff for determining the acceptability of an application for an amendment to a license. One of the criteria listed in LIC-109, Revision 1 is that a requested licensing action (ALA) cannot cite any unapproved guidance. To address Generic Safety Issue (GSI-191) in a timely manner, Southern Nuclear Operating Company (SNC) requests a one-time exception to this LIC-109 acceptance criteria. This exception would allow the reliance of WCAP-17788, "Comprehensive Analysis and Test Program for GSI-191 Closure," for the Vogtle Electric Generating Plant (VEGP) Units 1 and 2 prior to this report being approved by the Nuclear Regulatory Commission (NRC). WCAP-17788 is used to establish the acceptance limits for fiber in the reactor vessel, and thus comprises only a small part of the SNC response. NRR Office Instructions No. LIC-101, Revision 4, License Amendment Review Procedures, and LIC-500, Revision 5, Topical Report Process, also discuss that topical reports (such as WCAP-17788) are to be approved by the NRC prior to being implemented by reference as the technical basis for a licensee action. SNC therefore requests a one-time exception for this specific requirement in these two other NRR Office Instructions.
SNC intends to submit their ALA to resolve GSI-191 (including an updated response to Generic Letter 2004-02, a license amendment request to use a risk-informed methodology for the emergency core cooling systems (ECCS) acceptance criteria, and specific exemption requests) during March or April of 2017. Due to delays during the review process for WCAP-17788, NRC approval is not expected until the third or fourth quarter of 2017. As discussed in a public meeting held November 29, 2016, this delay creates issues for SNC's submittal.
Due to the voluminous nature of WCAP-17788, incorporating the relied-upon information from the 6 volume WCAP-17788 into SNC's submittal is not practical. This would create unnecessary work for the NRC staff and potentially introduce further delay in the approval of this report due to the unnecessary expenditure of resources. The NRC would basically be writing two Safety Evaluation Reports for this methodology: one for the actual WCAP-17788, and another for SNC's application. For these reasons, this was not the preferred approach of the NRC staff in attendance of the November 29, 2016 public meeting.
U.S. Nuclear Regulatory Commission NL-16-2710 Page 2 Waiting until WCAP-17788 is formally approved prior to SNC submitting their RLA is undesirable and/or unpractical for the following reasons:
- 1. SNC delaying their submittal will ultimately delay resolution to this outstanding generic safety issue. Beneficial plant modifications (e.g. modified sump strainer heights) dependent upon NRC approval of this RLA will be unnecessarily delayed.
- 2. Delaying the SNC submittal for six or more months creates a personnel resource issue, as personnel resources are reassigned to other tasks and may not be able to reinvest themselves back into the GSI-191 project once the topical report is approved.
Lastly, allowing a one-time exception to the aforementioned NRR Office Instructions is beneficial for the following reasons:
- 1. Accepting the SNC submittal for review prior to the WCAP-17788 being approved would allow the NRC to see the implementation of the methodology with plant data, possibly increasing the efficiency of the review and acceptance.
- 2. Most of the technical review of the SNC submittal, including the entire risk-informed portion, does not directly involve this topical report methodology. Therefore, the NRC staff will be able to perform much of their review of SNC's submittal in parallel with the review of the methodology.
For these reasons, this one-time waiver to the NRC acceptance criteria was discussed favorably at the November 29, 2016 public meeting.
So that SNC can proceed with their submittal (including review by the appropriate SNC management committees) it is respectfully requested that the NRC grant this waiver in writing by February 10, 2017.
RespecttuWsubmitted, t.fl- f~
C. R. Pierce Regulatory Affairs Director CRP/RMJ cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Mr. D. R. Madison, Vice President- Fleet Operations Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. B. J. Adams, Vice President- Engineering Mr. D. D. Sutton, Regulatory Affairs Manager- Vogtle 1 & 2 RType: CVC7000 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager- Vogtle 1 & 2 Mr. E. T. Coffman, Senior Resident Inspector- Vogtle 1 & 2