Letter Sequence Request |
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EPID:L-2019-LLR-0020, Proposed Alternative for the Fifth Interval Inservice Inspection FNP-ISI-AL T-05-04, Version 1.0 (Open) |
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MONTHYEARNL-18-1041, Proposed Alternative for the Fifth Interval Inservice Inspection FNP-ISI-AL T-05-04, Version 1.02019-03-0808 March 2019 Proposed Alternative for the Fifth Interval Inservice Inspection FNP-ISI-AL T-05-04, Version 1.0 Project stage: Request ML19079A2042019-03-20020 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Acceptance of Proposed Relief Request FNP-ISI-ALT-05-04 Project stage: Acceptance Review ML19150A1022019-05-29029 May 2019 Request for Additional Information Regarding Relief Request FNP-ISI-05-04, Version 1.0 (L-2019-LLR-0020) Project stage: RAI NL-19-0676, Proposed Alternative FNP-ISI-ALT-05-04, Response to NRC Request for Additional Information2019-06-11011 June 2019 Proposed Alternative FNP-ISI-ALT-05-04, Response to NRC Request for Additional Information Project stage: Response to RAI ML19129A2322019-07-0101 July 2019 Inservice Inspection Alternative, FNP-ISI-ALT-05-04, Regarding Examination Frequency for Tendon Anchorhead Replacement Project stage: Other 2019-05-29
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-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-24-0227, 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-24-0201, 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-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 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-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-22-0552, 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-22-0147, Updated Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2022-03-0707 March 2022 Updated Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements NL-21-0646, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302021-07-16016 July 2021 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 NL-21-0061, Inservice Inspection Program Owner'S Activity Report for Outage 2R272021-02-12012 February 2021 Inservice Inspection Program Owner'S Activity Report for Outage 2R27 NL-20-0417, Refueling Outage 1R29 Steam Generator Tube Inspection Report2020-04-17017 April 2020 Refueling Outage 1R29 Steam Generator Tube Inspection Report NL-20-0034, Inservice Inspection Program Owner'S Activity Report for Outage 1R292020-01-17017 January 2020 Inservice Inspection Program Owner'S Activity Report for Outage 1R29 NL-19-1296, Refueling Outage 2R26 Steam Generator Tube Inspection Report2019-10-24024 October 2019 Refueling Outage 2R26 Steam Generator Tube Inspection Report NL-19-0872, Inservice Inspection Program Owner'S Activity Report for Outage 2R262019-07-26026 July 2019 Inservice Inspection Program Owner'S Activity Report for Outage 2R26 NL-19-0347, Snubber Program Plan for the Fifth Ten Year Inservice Testing Interval2019-04-10010 April 2019 Snubber Program Plan for the Fifth Ten Year Inservice Testing Interval NL-17-2005, Fifth Ten-Year Interval Inservice Testing Program Update2019-03-11011 March 2019 Fifth Ten-Year Interval Inservice Testing Program Update NL-18-1041, Proposed Alternative for the Fifth Interval Inservice Inspection FNP-ISI-AL T-05-04, Version 1.02019-03-0808 March 2019 Proposed Alternative for the Fifth Interval Inservice Inspection FNP-ISI-AL T-05-04, Version 1.0 NL-18-1384, Fourth 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements2018-11-30030 November 2018 Fourth 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements NL-18-1000, Lnservice Inspection Program Owner'S Activity Report for Outage 1R282018-07-31031 July 2018 Lnservice Inspection Program Owner'S Activity Report for Outage 1R28 NL-18-0192, Submittal of Refueling Outage 2R25 Lnservice Inspection Report2018-02-12012 February 2018 Submittal of Refueling Outage 2R25 Lnservice Inspection Report ML17180A4392017-07-18018 July 2017 Inservice Testing Alternative for Pumps Per Code Case OMN-20 (RR-VR-01) NL-17-0167, Refueling Outage 1R27 Inservice Inspection Report2017-02-0606 February 2017 Refueling Outage 1R27 Inservice Inspection Report NL-17-0082, Submittal of the Lnservice Testing Program Alternatives for the Fifth Ten-Year Interval2017-02-0606 February 2017 Submittal of the Lnservice Testing Program Alternatives for the Fifth Ten-Year Interval NL-16-1277, 2R24 Lnservice Inspection Report Summary2016-08-0909 August 2016 2R24 Lnservice Inspection Report Summary NL-16-1329, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.02016-08-0404 August 2016 Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.0 NL-16-0723, Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 1.02016-06-30030 June 2016 Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 1.0 NL-15-2130, Responds to Request for Additional Information for Proposed Inservice Inspection Alternative FNP-ISI-ALT-18, Version 1.02015-11-25025 November 2015 Responds to Request for Additional Information for Proposed Inservice Inspection Alternative FNP-ISI-ALT-18, Version 1.0 NL-15-1483, Refueling Outage 1R26 Inservice Inspection Report2015-08-0404 August 2015 Refueling Outage 1R26 Inservice Inspection Report NL-15-0850, Refueling Outage 2R23 Steam Generator Tube Inspection Report2015-05-11011 May 2015 Refueling Outage 2R23 Steam Generator Tube Inspection Report NL-15-0718, Proposed Inservice Inspection Alternative FNP-ISI-ALT-17, Version 2.02015-04-21021 April 2015 Proposed Inservice Inspection Alternative FNP-ISI-ALT-17, Version 2.0 NL-15-0317, Refueling Outage 2R23 Inservice Inspection Report2015-02-16016 February 2015 Refueling Outage 2R23 Inservice Inspection Report NL-14-1276, Snubber Inspection Plan Submittal in Accordance with ASME OM Code2014-10-31031 October 2014 Snubber Inspection Plan Submittal in Accordance with ASME OM Code ML14148A4922014-05-28028 May 2014 ISI Program Alternative FNP-ISI-ALT-16. Version 1 NL-14-0295, Proposed Lnservice Inspection Alternative FNP-ISI-ALT-15, Version 1.02014-03-24024 March 2014 Proposed Lnservice Inspection Alternative FNP-ISI-ALT-15, Version 1.0 NL-14-0143, Refueling Outage 1R25 Lnservice Inspection Report2014-01-24024 January 2014 Refueling Outage 1R25 Lnservice Inspection Report NL-13-1729, Refueling Outage 2R22 Inservice Inspection Report2013-08-0707 August 2013 Refueling Outage 2R22 Inservice Inspection Report NL-12-2014, Proposed Inservice Inspection Alternative FNP-ISI-AL T-13 Version 1.02012-10-0101 October 2012 Proposed Inservice Inspection Alternative FNP-ISI-AL T-13 Version 1.0 NL-12-1499, Refueling Outage 1R24 Inservice Inspection Report2012-07-20020 July 2012 Refueling Outage 1R24 Inservice Inspection Report NL-12-0242, Joseph M. Farley Nuclear Plant - Unit 2 Refueling Outage 2R21 Inservice Inspection Report2012-02-0909 February 2012 Joseph M. Farley Nuclear Plant - Unit 2 Refueling Outage 2R21 Inservice Inspection Report ML12045A0672012-02-0909 February 2012 Unit 2 Refueling Outage 2R21 Inservice Inspection Report NL-12-0242, NL-12-0242 Part 2, Form NIS-2 Owner'S Report for Repair/Replacement Activity2012-02-0909 February 2012 NL-12-0242 Part 2, Form NIS-2 Owner'S Report for Repair/Replacement Activity NL-11-0255, Outage Inservice Inspection Summary Report2011-02-15015 February 2011 Outage Inservice Inspection Summary Report NL-10-2355, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping FNP-ISI-AL T-12, Version 2.02011-01-0505 January 2011 Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping FNP-ISI-AL T-12, Version 2.0 NL-10-1514, 2R20 Inservice Inspection Report2010-08-11011 August 2010 2R20 Inservice Inspection Report NL-08-1007, Withdrawal of Proposed Alternative FNP-ISI-ALT-07-02 Continued Operation with Pinhole Leaks in Class 2 Valve Q2N11V003B2008-06-27027 June 2008 Withdrawal of Proposed Alternative FNP-ISI-ALT-07-02 Continued Operation with Pinhole Leaks in Class 2 Valve Q2N11V003B NL-08-0136, Inservice Inspection Summary Report2008-02-0606 February 2008 Inservice Inspection Summary Report NL-07-1560, Inservice Inspection Summary Report2007-08-14014 August 2007 Inservice Inspection Summary Report NL-07-1418, Fourth Ten-Year Interval Inservice Testing Program Update2007-08-14014 August 2007 Fourth Ten-Year Interval Inservice Testing Program Update NL-06-1766, Unit 1, Inservice Inspection Summary Report2006-08-17017 August 2006 Unit 1, Inservice Inspection Summary Report 2024-09-04
[Table view] Category:Letter type:NL
MONTHYEARNL-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-24-0321, 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-24-0261, 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-24-0227, 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, Plants Units 1&2, 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 Plants Units 1&2, 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-24-0201, 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-24-0238, 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-24-0202, 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-24-0064, 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-24-0137, 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-24-0134, 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-24-0116, 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-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 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-24-0033, 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-24-0011, 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-23-0713, 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-23-0716, 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-23-0704, 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 2024-09-04
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~ Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5316 tel M.~R 0 8 2019 205 992 7601 fax Docket Nos.: 50-348 NL-18-1041 50-364 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Units 1 and 2 Proposed Alternative for the Fifth lntervallnservice Inspection FNP-ISI-ALT 04, Version 1.0 Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(z)(1 ), Southern Nuclear Operating Company (SNC) hereby submits Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0. This alternative proposes use of an alternate IWL examination schedule for performing the 45th Unit 1 IWL surveillance activities and 40th Unit 2 IWL surveillance activities at Joseph M. Farley Nuclear Plant (FNP) during the Fifth lnservice Inspection (lSI) Interval, which began December 1, 2017. This alternative also proposes a one-time exemption for Unit 1 from the examination frequency requirement in Table IWL-2521-2.
The basis for the proposed alternative for FNP Unit 1 and Unit 2 is provided in the Enclosure to this letter.
This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.
Respectfully submitted, Clieryl Regulatory Affairs Director CAG/tle/scm
Enclosure:
Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55a(z)(1) 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 Enclosure Proposed Alternative FNP-181-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55a(z)(1)
Enclosure to NL-18-1 041 Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55 a(z)(1)
Plant Site- Unit: Joseph M. Farley Nuclear Plant (FNP)- Unit 1 and Unit 2 Interval Dates: 5th lnservice Inspection (lSI) Interval- December 1, 2017 through November 30, 2027 Requested Date Approval is requested by September 8, 2019.
for Approval:
Unit 1 containment is scheduled to undergo the tendon anchorhead replacement project starting in June 2019. This tendon anchorhead replacement project is expected to take four to six months to complete. The IWL surveillance is scheduled to immediately begin once the replacement project is completed. The requested approval date will allow the vendor to complete the anchorhead replacement and immediately enter the IWL surveillance.
This approval will also allow a one-time exemption for Unit 1 from the examination frequency requirement in Table IWL-2521-2. It is proposed that the initial examination of the repair/replacement population be performed at the next regularly scheduled IWL examination (Unit 1 soth year (i.e., July 2026)).
ASME Code The American Society of Mechanical Engineers (ASME) Code components Components associated with this alternative are the unbonded post-tensioning system Affected: tendons and concrete that are part of the Reactor Containment Building.
Category and System Details:
ASME Code Class: Concrete Containment (CC)
- 1. Subsection: Table IWL-2500-1
Description:
Examination Category L-A, Concrete and Examination Category L-8, Unbonded Post-Tensioning System The affected components associated with Table IWL-2500-1 for the proposed early surveillance following post-tensioning system anchorhead replacement activities scheduled to commence in Spring 2019 are:
- 18 randomly selected tendons (3 vertical tendons, 3 dome tendons, and 3 hoop tendons per unit),
- 1 hoop tendon for Unit 1 randomly selected from the augmented repair/replacement scope related to the 2012 failure, i.e., from the first augmented examination group.
- the containment concrete for the 45th Unit 1 and 40th Unit 2 IWL surveillances.
E-1
Enclosure to NL-18-1041 Proposed Alternative FNP-ISI-ALT 04, Version 1.0, in accordance with 10 CFR 50.55 a(z)( 1)
- 2. Subsection: Table IWL-2521-2
Description:
Augmented Examination Requirements Following Post-Tensioning System Repair/Replacement Activities The affected components for the augmented examination requirements per Table IWL-2521-2 following post-tensioning system anchorhead replacement activities scheduled to commence in Spring 2019, i.e., the second augmented examination group, are up to 15 hoop tendons on Unit 1. These hoop tendons will undergo field end anchorhead replacement related to the corrective action based on the failure of H11AB as part of the extent of condition inspection associated with this effort. Namely:
Tendon To be Comment Identifier Replaced?
H1AC Yes In same lot as previously replaced H11A8.
H18C Yes In same lot as previously replaced H11 A8.
H38C Yes In same lot as previously replaced H11 A8.
H58C Yes In same lot as previously replaced H11A8.
H78C Yes In same lot as previously replaced H11A8.
H9AB Yes In same lot as previously replaced H11A8.
H138C Yes In same lot as previously replaced H11 A8.
H15A8 Yes In same lot as previously replaced H11 A8.
H158C Yes In same lot as previously replaced H11 A8.
H29AC Yes In same lot as previously replaced H11A8.
H31AC Yes In same lot as previously replaced H11A8.
In different lot than that of H11 A8. Replacing and testing H37A8 Yes to confirm extent of condition .
In different lot than H11 A8. SNC will apply its Corrective Action Program per 10 CFR Appendix 8 , Criterion XVI to H7AC Contingent initiate replacement based on test results of H37A8, if necessary.
In different lot than H11 AB. SNC will apply its Corrective Action Program per 10 CFR Appendix 8, Criterion XVI to H9AC Contingent initiate replacement based on test results of H37A8, if necessary.
In different lot than H11 A8. SNC will apply its Corrective Action Program per 10 CFR Appendix 8 , Criterion XVI to H15AC Contingent initiate replacement based on test results of H37A8 , if necessary.
E-2
Enclosure to NL-18-1041 Proposed Alternative FNP-ISI-ALT 04, Version 1.0, in accordance with 10 CFR 50.55 a(z)( 1)
Applicable Code The applicable Code edition and addenda is ASME Section XI, "Rules for Edition and lnservice Inspection of Nuclear Power Plant Components," 2007 Edition through Addenda: the 2008 Addenda.
Applicable Code Subsection IWL-2500 of the ASME Section XI Code states that examination shall Requirements: be performed in accordance with the requirements of Table IWL 2500-1.
Subsection IWL-2521.2 of the ASME Section XI Code states that tendons affected by repair/replacement activities shall require augmented examination in accordance with Table IWL-2521-2. Table IWL-2521-2 requires an initial inspection one year (+1- three months) following completion of an IWL repair/replacement activity that affects the containment post-tensioning system.
Table IWL-2521-2 also indicates that subsequent lnservice Inspections will coincide with IWL-2420, Unbonded Post-Tensioning Systems, following completion of repair/replacement activities.
IWL sections referenced in this proposed alternative are:
IWL-2400, lnservice Inspection Schedule, IWL-241 0, Concrete, IWL-2420, Unbounded Post-Tensioning Systems, IWL-2500, Examination Requirements, IWL-2521, Tendon Selection, IWL-2523, Tendon Wire and Strand Sample Examination and Testing.
Background:
The containment post-tensioning system consists of horizontal, dome, and vertical tendons based on the spatial orientation around the Containment Building. A total of 135 horizontal tendons are anchored at three vertical buttresses. Three groups of dome tendons, for a total of 93 tendons, are anchored at the vertical face of the dome ring girder. A total of 130 vertical tendons are anchored at the top surface of the ring girder and at the bottom of the base slab. The number of tendons is the same for both units, except one horizontal tendon was not installed on Unit 2 during construction; therefore, there are only 134 horizontal tendons on Unit 2.
On May 3, 2012, the Unit 1 field end anchorhead on horizontal tendon H7AB failed. On April14, 2017, the Unit 1 field end anchorhead on horizontal tendon H 11 AB failed. The failed horizontal tendon field anchorheads are part of the post-tensioning system for the Unit 1 FNP Reactor Containment Building.
A causal evaluation was performed due to the anchorhead failure and determined that H7AB and H11AB were both part of the same heat treatment certification lot. Of the certification lot, twelve anchorheads remain that are E-3
Enclosure to NL-1 B-1 041 Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55 a(z)(1) currently installed on Unit 1 Containment. Based on the ALTRAN analysis, hydrogen embrittlement along with improper heat treatment is the most likely cause of the anchorhead failures. Of these remaining twelve tendons, one (H 11 BC) will not be replaced during the Spring 2019 anchorhead project due to its location in the Penetration Room Filter (PRF) barrier. Based on the failure trend and the ALTRAN analyses performed, the replacement of the remaining eleven field end anchorheads within this lot will reduce the likelihood of future failures. Tendon H11 BC may be de-tensioned to lessen likelihood of its failure.
SNC analysis demonstrates that containment operability will not be affected if H11 BC is de-tensioned.
In addition, anchorhead (H37AB), not in the affected certification lot, is being replaced and tested to further knowledge in confirming the extent of condition.
Based on the results of testing on H37AB, three additional anchorheads with similar properties to H37AB may be replaced.
Since the number of Unit 1 horizontal tendons affected by the anchorhead replacement project (at least twelve, up to fifteen) is greater than 5% of the total number of horizontal tendons (i.e., 135), the required sample size for augmented examination, per Table IWL-2521-2, is one horizontal tendon (i.e., the lesser of 4% of the affected tendons or ten tendons).
Reason for The lSI Program commitments to the ASME Section XI, 2007 Edition through the Request: 2008 Addenda, Section IWL-2400, Section IWL-2500, and Table IWL-2500-1 establish the specified dates following the completion of the containment Structural Integrity Test and every five years thereafter(+/- 1 year). The current prescribed schedule for the lSI examination of the concrete and containment tendons is July 2021 +1- 1 year. The containment tendon field end anchorhead replacement project is scheduled to begin in June 2019 and is scheduled to end approximately four to six months later (i.e., possibly as soon as September 2019), which is prior to the allowed time to perform the IWL examinations.
This alternative is being submitted to propose a one-time exemption from the examination frequency requirement in Table IWL-2500-1. It is proposed that the next regularly scheduled IWL examinations, including the first Unit 1 augmented examination group, (45 1h year for Unit 1 and 401h year for Unit 2) commence immediately after the anchorhead replacement projects ends (as soon as September 2019), which would be up to ten months sooner than prescribed by the applicable Code requirements (i.e., July 2020 using the year grace period). FNP still wishes to use the +1- 12-month grace period allowed by IWL-2420(c) for the next regularly scheduled tendon examination if needed for scheduling optimization. Please note that the examination window for E-4
Enclosure to NL-18-1041 Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55 a(z)(1) subsequent examinations is not changing (i.e., the subsequent examination will be performed July 2026 +1- 1 year).
The one-time exemption will also allow the deferral of performing the initial inspection of the augmented scope of up to fifteen tendons affected by the H 11 AB failure extent of condition. The 1-year (+1- 3 months) inspection prescribed in Table IWL-2521-2 will instead be performed during the next regularly scheduled IWL examination (July 2026, +1- 1 year).
Proposed Discussion I Analysis:
Alternative and The purpose for conducting the inspections is to monitor the post-tensioning Basis for Use:
system for degradation and to verify that actual loss of pre-stress is consistent with predicted values used in design and that the required minimum pre-stress for the containment system is being met. Moving the regularly scheduled IWL examinations up by ten months or less would not have a detrimental effect in evaluating that the minimum pre-stress for the containment system is meeting the required values. Because the tendon prestress loss has shown minimum change over the last two inspections, performing the next regularly scheduled IWL examination as scheduled (July 2026, +1- 1 year) would also not be detrimental.
The replacement anchorhead replacement project requires the new anchorheads to be manufactured with a lower Rockwell "C" hardness number (i.e., 38 +1- 1) to improve resistance to hydrogen embrittlement failure. The horizontal tendons that are affected by the anchorhead replacement project utilize the same pre-stressing system, and will be exposed to, or protected from, the same outside environment as the existing tendons, which have been in service for the last forty-plus years. Ten lSI examinations have been completed to date for Unit 1.
The existing horizontal tendons have met all the post-tensioning test and examination acceptance criteria. The replacement activities that impact the horizontal tendons will not result in any unique condition that may subject the horizontal tendons to a different potential for structural or tendon deterioration.
For new containments, the main reason for performing the one-year tendon inspection, as required by sub-article IWL-2420, is to benchmark the tendon losses shortly after the Structural Integrity Test (SIT) when pre-stress losses (which are due to elastic shortening, creep, shrinkage and relaxation) occur at the highest rate. For the re-tensioned tendons in the FNP containment structure, pre-stress losses will be much smaller than those for the original tendons.
Elastic shortening:
The elastic shortening loss is a function of the pre-stress load, the elastic modulus for the steel tendon and the elastic modulus of the concrete. The pre-stress load and tendon material are identical to the original design. The E-5
Enclosure to NL-18-1041 Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55 a(z)(1) elastic shortening loss for the re-tensioned tendons will therefore be unaffected.
Creep:
Creep is a time dependent function of the concrete. Creep is represented by a creep coefficient which is the ratio of creep strain to elastic strain. The creep loss will be the same for the re-tensioned tendons.
Relaxation :
Steel relaxation losses will be lower for the re-tensioned tendons because of the shorter remaining life of the plant.
Shrinkage:
Shrinkage losses will similarly be the same.
The tendons will be re-tensioned to a value above the predicted losses but less than 70% of the specified ultimate tensile strength of the tendon per IWL- 2523.3(a).
Since the losses in the re-tensioned horizontal tendons is less than the original design losses (tendons re-tensioned to values above these predicted forces),
there is additional margin in the post-tensioning system.
There is a high degree of confidence that the postponement of the first scheduled inspection of the re-tensioned horizontal tendons affected by the anchorhead replacement project until the next regularly scheduled IWL examination (July 2026, +1- 1 year) will not involve an increase in radiological risk and would not adversely affect public health and safety.
Additional Considerations:
To perform tendon examinations, a large mobile crane must be located near the Containment Building to lift tendon work platforms and the hydraulic rams used to perform tendon tension tests. There are some inherent risks associated with these rigging and lifting activities. Approving this alternative to move the IWL surveillance up by ten months or less would avoid these risk sources by performing only one examination staging; that is, combining the anchorhead replacement project with the IWL examination. Similarly, delaying the augmented examination of the tendons affected by the anchorhead replacement project also avoids the risk sources of an additional rigging and lifting activity.
Conclusion:
Therefore, it is proposed that the IWL examination in accordance with ASME Section XI, 2007 Edition through the 2008 Addenda, Section IWL-2400, IWL-2500, and Table IWL-2500-1 be performed up to ten months prior to the allowed inspection timeframe. In addition, it is proposed that the first scheduled E-6
Enclosure to NL-18-1041 Proposed Alternative FNP-ISI-ALT-05-04, Version 1.0, in accordance with 10 CFR 50.55 a(z)(1) augmented examination of the horizontal tendon affected by the anchorhead replacement project be delayed until the next regularly scheduled IWL examination (July 2026, +1- 1 year). There would be no deviation from Section XI requirements for subsequent lnservice Inspections since they would be scheduled every five years(+/- one year) as required by Table IWL-2500-1 and paragraph IWL-241 0 and IWL-2420. SNC considers that this proposed alternative schedule will provide an acceptable level of quality and safety, consistent with the provisions of 10 CFR 50.55a(z)(1 ).
Duration of This alternative is requested for the remainder of the current Fifth lnservice Proposed Relief Inspection Interval, which began December 1, 2017 and is scheduled to end on Request: November 30, 2027.
Precedent: Joseph M. Farley Nuclear Plant- Unit 1, received approval of a relief request to delay an lSI Program commitment to the ASME Section XI, 2001 Edition through the 2003 Addenda, Section IWL-2521.2 and Table IWL-2521-2 establishing the specific requirement for the initial inspection at one year (+1- three months) following the completion of repair/replacement activities. The approval allowed the initial inspection to occur concurrent with the next regularly scheduled IWL examination at that time, or up to nearly three years (i.e., July 2017 with the one-year grace period) after the prescribed date (i.e., nominally September 2014).
(ML14169A195)
Reference:
ASME Section XI 2007 Edition through the 2008 Addenda.
Status: Pending NRC Approval.
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