|
---|
Category:Letter type:NL
MONTHYEARNL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit 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-23-0542, 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-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use 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-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application 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-23-0372, 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-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 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-23-0019, 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-23-0263, 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-23-0208, 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-23-0014, 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-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 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-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
[Table view] |
Text
Charles A. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 ._ Southern Nuclear Tel 205.992.7872 Fax 205.992.7601 October 14, 2016 Docket Nos.: 50-348 NL-16-2204 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Unit 1 Proposed Alternative FNP-ISI-ALT-21. Version 1.0 Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(z)(2), Southern Nuclear Operating Company (SNC) hereby requests Nuclear Regulatory Commission (NRC) staff approval of proposed Code Alternative FNP-ISI-ALT-21 Version 1.0. This Alternative will allow Farley Nuclear Plant (FNP) Unit 1 to delay the permanent Code repair or replacement of a 1" drain line leaking weld until prior to the start of the spring 2018 refueling outage 1R28. FNP Unit 1 is currently in refueling outage 1R27. Appendix IX, Article IX-1000(a) of ASME Section XI, 2001 Edition through the 2003 Addenda specifies that mechanical clamping devices used as a piping pressure boundary may remain in services only until the next refueling outage. As an alternate to the permanent code repair during this refueling outage 1R27, it is requested that approval be granted to allow a temporary code repair designed and implemented in accordance with ASME Code Section XI Appendix IX to remain in place for plant startup from refueling outage 1R27 and until no later than the beginning of 1R28, which is scheduled to begin in March 2018. By then, the fuel pool heat load will have diminished sufficiently to allow adequate margin for temperature rise in the pool while the repair is being implemented. Thus, the duration of this relief request is until the start of 1R28. Note that the 41h ten year lSI interval ends in November 2017 so this request would extend into the next ten year interval.
The details of the 10 CFR 50.55a alternative is contained in the enclosure. Approval is requested by October 21, 2016, to support startup of the Fall 2016 Outage at FNP Unit 1 to proceed according to the current schedule.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Rz~~~";;;d*
C. R. Pierce Regulatory Affairs Director
U.S. Nuclear Regulatory Commission NL-16-2204 Page2 CRP/RMJ
Enclosure:
FNP-ISI-ALT-21, Version 1.0 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley
Joseph M. Farley Nuclear Plant Unit 1 Proposed Alternative FNP-181-ALT-21, Version 1.0 Enclosure FNP-181-ALT-21, Version 1.0
Enclosure to NL-16-2204 FNP-ISI-ALT-21 Version 1.0 Plant Site - UNIT: Farley Nuclear Plant (FNP) Unit 1 Interval- 41h lSI Interval extending from December 1, 2007, through Interval Dates: November 30, 2017.
Reguested Date Approval is requested by October 21, 2016, to support startup of for Aooroval: the Fall 2016 Outage (1R27) at FNP Unit 1 ASME Code FNP Units: Unit 1 Com~onents ASME Code Class: Code Class 3 Affected: Component: Stainless Steel Socket Weld on Line 1"-HCC-110, upstream side of drain valve Q1G31V017 Ae~licable ASME Section XI, 2001 Edition through 2003 Addenda Code Edition and Addenda:
A~~licable Code Appendix IX, Article IX-1000(a) specifies that "Mechanical clamping Reguirements devices used as a piping pressure boundary may remain in service only until the next refueling outage, at which time the defect shall be removed or reduced to an acceptable size."
Background and On October 11, 2016, during the 1R27 refueling outage, a through Reason for wall leak was discovered at a socket weld on valve Q1G31V017, a Reguest: 1-inch drain line off of the 8-inch Spent Fuel Pool (SFP) cooling common return header. The leak location cannot be isolated using normal means because there is no isolation valve between the leak location and the SFP. Also, the FNP spent fuel pools are not cross-connected to allow cooling from the opposite unit.
The leak was visually characterized as a circumferentially oriented linear indication at the toe of the socket weld at the valve. To perform a permanent Code repair or replacement (i.e., pipe replacement, or flaw removal and re-welding) at the location of the leak, both trains of the SFP cooling system will have to be removed from service and a non-conventional tagging boundary (e.g., freeze seal) will be required for personnel safety, to perform hot work, and to maintain the required inventory in the SFP. The total estimated time for establishing the boundary, implementing the code repair, and returning the SFP system to service is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. FNP has similar experience establishing a tagging boundary that would be required to conduct this repair.
The issue was discovered after the reactor core was offloaded to the SFP. Performing a permanent repair during 1R27 with the reactor core offloaded or even shortly after the core reload is not a viable option based upon reaching 200 degrees F within approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> if no SFP cooling were available. The E-1
Enclosure to NL-16-2204 FNP-ISI-ALT-21 Version 1.0 estimated time to reach 200 degrees Fin the SFP, if cooling were removed from service, will increase throughout the operating cycle as the decay heat from the fuel decreases. The earliest FNP would consider performing the permanent repair, assuming no significant degradation, which is not expected, would be after decay heat is reduced sufficiently to allow time to perform the repair with margin.
The desire would be to conduct the repair at least 40 to 50 weeks after the core reload. After 40 to 50 weeks, the decay heat would be low enough such that it would take at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to reach 200 degrees F after SFP cooling is removed from service. The time to 200 degrees F is dependent on the initial SFP temperature when cooling is removed from service, which is related to environmental factors (i.e., service water temperatures).
The issue has been entered into the corrective action program and the work management process will ensure the evolution is planned at the appropriate time and executed in a manner to manage the risk of the maintenance activity.
Proposed Southern Nuclear Operating Company (SNC) proposes to install a Alternative and mechanical clamping device in accordance with ASME Section XI, Basis for Use: Appendix IX during and prior to the startup from the 1R27 refueling outage to address the through-wall leak on the line 1"-HCC-110, in lieu of implementing a permanent Code repair/ replacement. As a compensatory measure, operations will monitor the temporary repair at least once a day.
Basis for Use Appendix IX, Article IX-1000(a) specifies that "Mechanical clamping devices used as a piping pressure boundary may remain in services only until the next refueling outage." However, since FNP is currently in the 1R27 refueling outage, this is interpreted to need implementation of a permanent Code repair/ replacement prior to startup from 1R27. The optimum time for repair of the leak from a decay heat load perspective is just prior to the next refueling outage. This will allow for the maximum time with adequate margin to repair or replace the weld while still protecting the fuel in the SFP. SNC proposes to install a Code compliant mechanical clamping device on the leak and repair or replace the leaking weld prior to the next refueling outage 1R28. It is estimated that the time to 200 degrees F for the SFP, after cooling is removed from service, will be at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> within 40 to 50 weeks after the 1R27 refueling outage. Installing the temporary repair now and scheduling the permanent repair later in the cycle will allow ample time with margin to isolate the leak, repair and inspect the weld, and return the system to service while ensuring the fuel in the SFP remains adequately cool. Temporary repairs utilizing ASME Code Section XI, Appendix IX are typically implemented on-line and left in E-2
Enclosure to NL-16-2204 FNP-ISI-ALT-21 Version 1.0 place until plant shutdown. For the circumstances of this request, a refueling outage presents the greatest risk to the decay heat removal functionality of the SFP.
In summary, the repair will meet all ASME Code Section XI, Appendix IX provisions with the exception of the IX-1000(a). The repair will be designed as a pressure retaining clamping device in accordance with Section IX 3200. Completing a permanent Code repair/replacement prior to startup from 1R27 would not result in a compensating increase in quality and safety given that the heat load on the SFP system is at a maximum during the current refueling outage and a permanent repair would necessitate isolating the common SFP cooling return header.
Pursuant to 10CFR50.55a(z)(2), an alternative is being requested by SNC for FNP Unit 1 on the basis of a hardship without a compensating increase in quality and safety in the repair of a leak on the SFP Cooling System to allow the temporary repair to be in place until no later than the start of 1R28.
Duration of This alternative will remain in effect until prior to the Proposed commencement of the 1R28 outage, currently scheduled in the Alternative: Spring of 2018.
Precedents: None
References:
American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, 2001 Edition, through 2003 Addenda, the American Society_ of Mechanical Engineers, New York.
Status: Relief awaiting NRC approval.
E-3