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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
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-A Southern Nuclear Justin T. Wheat Nuclear Licensing Manager 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 5998 tel AUG 0 9 2017 205 992 7601 fax jtwheat@ southernco.com Docket Nos.: 50-348 NL-17-0348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Alternative FNP-ISI-ALT-05-01 in Accordance with 10 CFR 50.55a(z)(1) to Utilize ASME Code Case N-854 Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(z)(1 ), Southern Nuclear Operating Company (SNC) hereby requests Nuclear Regulatory Commission (NRC) approval of Alternative FNP-ISI-ALT-05-01, for the use of American Society of Mechanical Engineers (ASME) Code Case N-854, for Farley Nuclear Plant (FNP) Units 1 and 2. This alternative is applicable to the Fifth lnservice Inspection Interval, which will start on December 1, 2017. This proposed alternative request removes hold times for Class 2 and 3 components directly connected to a Class 1 system that are pressurized as part of the Class 1 system leakage test. SNC believes that use of Code Case N-854 provides an acceptable level of quality and safety.
To support planning and preparation needed for the Spring 2018 outage, SNC requests that the NRC approve the proposed alternative for FNP Units 1 and 2 by March 1, 2018.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Respectfully submitted, Justin Wheat Nuclear Licensing Manager JTW/PDB/Iac
Enclosure:
Proposed Alternative FNP-ISI-ALT-05-01, Version 1.0 Cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RTYPE: CFA04.054
Joseph M. Farley Nuclear Plant- Units 1 and 2 Proposed Alternative FNP-ISI-ALT-05-01 in Accordance with 10 CFR 50.55a{z){1) to Utilize ASME Code Case N-854 Enclosure Proposed Alternative FNP-ISI-ALT-05-01, Version 1.0
Proposed Alternative FNP-ISI-ALT-05-01, Version 1.0 In Accordance with 10 CFR 50.55a(z){1)
Plant Site-Unit:
Joseph M. Farley Nuclear Plant (FNP) - Units 1 & 2 Interval Dates:
Fifth lnservice Inspection (lSI) Interval- December 1, 2017 through November 30, 2027 Requested Date for Approval:
Approval is requested by March 1, 2018.
ASME Code Components Affected:
ASME Code Class 2 and 3 components connected directly to a Class 1 system that are pressurized as part of the Class 1 system leakage test.
Applicable Code Edition and Addenda
ASME Section XI, "Rules for lnservice Inspection of Nuclear Power Plant components,"
2007 Edition with the 2008 Addenda (Code) is the applicable Code edition and addenda for the fifth lSI interval.
Applicable Code Requirement
ASME Section XI, 2007 Edition through 2008 Addenda, IWA-5213(a) specifies the test condition holding time after pressurization to test conditions before the visual examinations commence for system pressure tests.
Reason for Request
The Code test conditions for hold time requirements during system leakage tests are based on the component classifications of ASME Section XI Code Class 1, 2, or 3 components and essentially whether the system is normally inservice. The actual hold time requirements for the system leakage tests for each Class of components are required in accordance with IWA-5213(a).
Specifically, for Class 1 components there is no hold time after attaining test pressure.
IWA-5213(a)(1 ): "For Class 1 components (IWB-2500-1 Examination Category 8-P), no holding time is required after attaining test pressure."
For Class 2 or 3 components, the hold times are 10 minutes or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> depending on specific conditions in IWA-5213(a)(2) and (a)(3):
IWA-5213(a)(2): "For Class 2 (IWC-2500-1, Examination Category C-H) and Class 3 (IWD-2500-1, Examination Category D-B) components not required to operate during normal plant operation, a 10 min holding time is required after attaining test pressure."
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Proposed Alternative FNP-151-ALT-05-01, Version 1.0 In Accordance with 10 CFR 50.55a(z)(1)
IWA-5213(a)(3): "For Class 2 (IWC-2500- 1, Examination Category C-H) and Class 3 (IWD-2500-1, Examination Category D-B) components required to operate during normal plant operation, no holding time is required, provided the system has been in operation for at least 4 hr for insulated components or 10 min for noninsulated components."
Proposed Alternative:
Pursuant to 10 CFR 50.55a(z)(1 ), Acceptable Level of quality and safety, the use of ASME Code Case N-854, "Alternative Pressure Testing Requirements for Class 2 and 3 Components Connected to the Class 1 Boundary Section XI, Division 1 ," (Reference 1) is being requested for use by Southern Nuclear Operating Company (SNC) since this Case has not yet been included in Regulatory Guide 1.147 Rev. 17 (Reference 2}. Use of Code Case N-854 does not change any pressure testing requirements except for eliminating the hold time for Class 2 and 3 components connected directly to Class 1 components that are under Class 1 pressure during the Class 1 system leakage tests that are performed during plant startup following each refueling outage at FNP Units 1 and 2.
Basis for Use Class 1 Hold Time for Class 2 and 3 Components Under Class 1 Pressure The basis for the Class 1 no hold time requirement in IWA-5213(a)(1) is centered on the fact that it takes (several hours) increasing the temperature and pressure to reach the required pressure corresponding to 100% rated reactor power in IWB-5221 to perform the system leakage test. This time period either exceeds or is more restrictive than the required 10 minute or 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time for Class 2 or 3 components in IWA-5213(a).
When Class 1 components are connected directly to Class 2 or 3 components (for example, by having a restricting orifice) the Class 1 boundary interface to Class 2 or 3 components are pressurized and examined to Class 1 pressure during the system leakage test. The Class 2 or 3 hold time requirement is not currently addressed for this design configuration in IWA-5213(a) of the ASME Code Section XI, 2007 Edition through the 2008 Addenda. The hold time requirements for these components are now included as an alternative in Code Case N-854 that may be used upon NRC authorization.
At FNP, the components affected by this request are Class 2 pipes and valves used for vents and drains with a design configuration where a flow restrictor serves as the boundary interface between the Class 1 and Class 2 components and where the Class 2 components are under Class 1 pressure during normal operation and examined during the Class 1 system leakage test under Class 1 pressure. This test is performed following each refueling outage during plant startup. An example of this design configuration are sample line connections to the reactor coolant system (RCS) piping that contain a 3/8" orifice opening restricting flow from the RCS to a loss that can be made up by normal makeup.
Due to this configuration, the sample lines downstream of the orifice are not E1-2
Proposed Alternative FNP-151-ALT-05-01, Version 1.0 In Accordance with 10 CFR 50.55a(z)(1) required to be Class 1. However, this section of sample lines may be examined as part of the Class 1 system leakage test under Class 1 pressure.
Conclusion SNC has determined that this proposed alternative request per 10 CFR 50.55a(z)(1) to use Code Case N-854 for the fifth inspection interval at FNP, Units 1 and 2, addresses the needed criteria for meeting the specific no hold time requirement that is associated with the examinations to be conducted during the Class 1 system leakage test on specifically designed Class 2 components that are directly connected to Class 1 components. Since the requirement for no hold time on Class 2 and 3 components as permitted in Code Case N-854 results in the Class 2 components being tested with the same hold time requirement as the associated Class 1 component, SNC believes that use of Code Case N-854 provides an acceptable level of quality and safety. Therefore, SNC is seeking approval to use Code Case N-854 with authorization of this request for the fifth inspection interval at FNP, Units 1 and 2.
Duration of Proposed Alternative:
The Fifth lSI Interval.
Precedents:
None.
References:
- 1. ASME Code Case N-854, "Alternative Pressure Testing Requirements for Class 2 and 3 Components Connected to the Class 1 Boundary Section XI, Division 1," dated: April 15, 2015
- 2. USNRC Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 17, dated: August 2014 Status:
Under NRC Review.
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