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Category:Letter type:NL
MONTHYEARNL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-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-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption 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-24-0126, – 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-24-0286, 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-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 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-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 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-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use 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-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis 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-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. 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-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits 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-24-0170, 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-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 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-24-0098, Report on Status of Decommissioning Funding2024-03-28028 March 2024 Report on Status of Decommissioning Funding 2024-09-09
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Jeffrey T. Gasser Southern Nuclear Executive Vice President Operating Company, Inc.
and Chief Nuclear Officer 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7721 Fax 205.992.6165 A October 13, 2004 COMPANY Energy to Serve Your World SM Docket Nos.: 50-321 50-348 50-424 NL-04-1475 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Edwin I. Hatch Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.55a Request for an Alternative Alignment of IWE / IWL Inspection Program Interval with Corresponding Plant ISI Program Intervals Ladies and Gentlemen:
It is a requirement of 10 CFR 50.55a(b)(2)(vi) that successive IWE and IWL 120-month interval updates be implemented in accordance with 10 CFR 50.55a(g)(4)(ii). Pursuant to 10 CFR 50.55a(a)(3), Southern Nuclear Operating Company (SNC) is requesting an alternative to the requirements of 10 CFR 50.55a(g)(4)(ii) subject to Commission approval as provided in 10 CFR 50.55a(g)(4)(iv).
On August 8, 1996, the NRC issued a rulemaking (61 FR 41303) requiring licensees to implement the first period of IWE and IWL inservice examinations by September 9, 2001. Therefore, using Table IWE-2412-1 of the 1992 Edition with the 1992 Addenda of the ASME Section XI Code, the current Class MC and Class CC interval start and end dates for all SNC nuclear plants were determined to be September 10, 1998, and September 9, 2008, respectively. These start and end dates do not coincide with any of SNC's Class 1, 2, and 3 inservice inspection (ISI) program intervals which are January 1, 1996, through December 31, 2005, for the Edwin I. Hatch Nuclear Plant (HNP) Units 1 and 2; May 31, 1997, through May 30, 2007, for the Vogtle Electric Generating Plant (VEGP) Units 1 and 2; December 1, 1997, through November 30, 2007, for the Joseph M.
Farley Nuclear Plant (FNP) Unit 1; and July 30, 2001, through July 20, 201 1, for FNP Unit 2.
SNC proposes to change each of the current HNP Class MC and VEGP Class MC and Class CC inspection intervals to be consistent with the corresponding plant's Class 1, 2, and 3 ISI program interval. These Class MC and Class CC inspection program interval updates will be performed concurrently with the next Class 1, 2, and 3 ISI program interval update of each corresponding plant. In addition, SNC proposes to change the FNP Units I and 2 Class MC and Class CC inspection intervals to be consistent with the FNP Unit I Class 1, 2, and 3 ISI program interval. These Class MC and Class CC inspection program interval updates will be performed concurrently with the next
U. S. Nuclear Regulatory Commission NL 1475 Page 2 Class 1, 2, and 3 ISI program interval update of FNP Unit 1. These changes will result in a reduction in length of each plant's first and current Class MC and Class CC inspection program interval. This submittal requests NRC approval as an alternative to the regulations pursuant to 10 CFR 50.55a(a)(3)(ii) in that compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
In Federal Register Notice, Volume 67, Number 187, dated September 26, 2002, the NRC stated that they agreed with licensee comments that the final rule, dated August 8, 1996, creates a hardship when implementing 120-month interval updates required by 10 CFR 50.55a(g)(4)(ii). The final rule required licensees to implement an ISI program for Class MC and Class CC components using the 1992 Edition with the 1992 Addenda of IWE and IWL. Consequently, the schedule for 120-month interval updates for the ISI of Class MC and Class CC components and the ISI of Class 1, 2, and 3 components does not coincide. This creates a hardship because ISI programs are required to maintain two separate editions and addenda of Section XI, i.e., one edition applicable to the ISI of Class MC and Class CC components and another edition and addenda applicable to the ISI of Class 1, 2, and 3 components. The NRC also stated in the Federal Register Notice that licensees may wish to synchronize 120-month interval updates such that the same edition and addenda of Section XI apply to the ISI of Class MC and Class CC components and the ISI of Class 1, 2, and 3 components. It was further indicated that licensees wishing to synchronize their 120-month intervals may submit a request in accordance with 10 CFR 50.55a(a)(3) to obtain authorization to extend or reduce 120-month intervals. Southern Nuclear Operating Company agrees with the NRC assessment.
In addition, it is SNC's position that concurrently updating the IWE and IWL inspection programs with the ISI program for each plant will result in a more comprehensive examination being achieved, enhancing the possibility of detecting a generic problem, and will reduce the costs involved with maintaining two separate code versions should the use of different code versions be required. In addition, use of the same edition and addenda of the code for each program would help prevent possible errors associated with maintaining separate programs with different requirements.
The remaining examinations for each of the current IWE and IWL inspection program intervals will correspond with the method required by the edition and addenda of the ASME Section XI Code adopted by the applicable SNC plant's updated ISI program and will be performed using the requirements of this edition and addenda in the sequence previously established by the current IWE and IWL inspection program interval. Where the requirements of the latest edition and addenda of the ASME Section XI Code adopted by the ISI program cannot be met, relief will be requested from the NRC through the formal relief request process addressed in 10 CFR 50.55a. Any such relief requests will be submitted to the NRC in the updated ISI programs for each plant.
Southern Nuclear Operating Company hereby requests the NRC to grant an alternative to the requirements of 10 CFR 50.55a(g)(4)(ii). This alternative will allow SNC to align each of the IWE / IWL inspection program intervals with the corresponding plant's IST 120-month program interval. The proposed early updated IWE / IWL inspection program intervals are January 1, 2006, through December 31, 2015, for HNP Units I and 2;
U. S. Nuclear Regulatory Commission NL 1475 Page 3 May 31, 2007, through May 30, 2017, for VEGP Units 1 and 2; and December 1, 2007, through November 30, 2017, for FNP Units 1 and 2. SNC will carry these revised interval dates forward through the end of licensed operation for each plant and unit, and the early updates will be documented in each plant's IWE and IWL programs.
In order to apply to the first ISI program update required for an SNC plant (i.e., HNP),
NRC approval is requested by October 15, 2005.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, JfryT. Gasser JTG/DRG/daj cc: Southern Nuclear Operating Company Mr. L. M. Stinson, Vice President - Plant Farley Mr. H. L. Sumner, Jr., Vice President - Plant Hatch Mr. D. E. Grissette, General Manager - Plant Farley Mr. G. R. Frederick, General Manager - Plant Hatch Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CFA04.054; CHAO2.004; CVC7000; LC# 14135 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. C. Gratton, NRR Project Manager - Hatch Mr. C. Gratton, NRR Project Manager - Vogtle Mr. C. A. Patterson, Senior Resident Inspector - Farley Mr. D. S. Simpkins, Senior Resident Inspector - Hatch Mr. G. J. McCoy, Senior Resident Inspector - Vogtle