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Category:Inservice/Preservice Inspection and Test Report
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-24-0340, 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, 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-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-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 2024-09-04
[Table view] 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-24-0349, 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-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-24-0259, 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, 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-24-0201, 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-23-0828, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift2023-11-30030 November 2023 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift 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 2024-09-04
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5)RUP2$52ZQHUV$FWLYLW\5HSRUW FORMOAR-1OWNER'S ACTMTYREPORT Report Number Plant UnitNo.1 (if applicable)
Commercial service date W Refueling outage no. 1.R30 Current inspection interval J (1st,2nd,3rd, other) 4th, Current inspection period d (1st,2nd,3rd)
EditionandAddenda ofSection XIapplicableto the inspection plans:
Dateandrevision ofinspection plans:
EditionandAddenda ofSection XIapplicable torepair/replacement activities, if different than theinspection plans: h CodeCasesusedfor inspection andevaluation:
applicable, (if including cases modified by CaseN-532andlater revisions)
CERTIFICATE OFCONFORMANCE Icertify (a) that thestatements madeinthis reportarecorrect; (b) theexaminations andtests meetthe inspection Plan asrequired bythe ASMECode, conform Section tothe Xt; requirements (c) and therepair/replacement XI.
ofSection activitiesandevaluations supporting the completionofJ (retuenng outage number)
SignedR.M.McAdams Owner orOwner'sDesignee, Title
. n ineerin Director Date /
CERTIFICATE OFINSERVICE INSPECTION theundersigned, I, holding avalidcommission issued bytheNational Board ofBoiler andPressure Vessel Inspectors and employed byT ofHaartfordJL haveinspected theitems describedinthis Owner's Activity Report, andstatethat,tothe bestofmyknowledge andbelief, theOwner hasperformed all activities represented bythisreport inaccordance withtherequirements ofSection XI.
Bysigning thiscertificate neither theInspector norhis employer makes anywarranty, expressed orimplied, concerning the repair/replacementactivities andevaluationdescribed inthis report. Furthermore, neither theInspector norhis employer shallbe liable inanymanner for anypersonal injury orproperty damage ora loss ofanykind arising fromorconnected with this inspection.
RodneSenn ' Commission 12603 C IN R Inspector'sSignature (National Board NumberandEndorsement)
Date O 2- 02
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5)RUP2$52ZQHUV$FWLYLW\5HSRUW Table 1 FarleyNuclear Plant Unit 1,5thinterval, 2ndPeriod, 1stReport Items withFlawsorRelevant Conditions That Required Evaluation forContinued Service Examination Item Description Evaluation Description Category and Item Number D-B A through-wall leak wasnoted inthe8" CR10675320 documents the D2.10 Service Water piping oftheUnit 1B evaluation foroperability. Thelocation train Service Water pumpsmini-flow,wasisolated andisbeing tracked per downstream ofQ1P16V579,BTRNSW clearance order1-DT19-P16-00607.
MINIFLOW.
D-B A through-wall leak wasnoted onthe6" CR10735066 documents the D2.10 ServiceWater piping ofthe1CServiceevaluation foroperability. Theflaw was Water pump mini-flow line onanelbow evaluated inaccordance with Code inthehorizontal section ofpiping that CaseN-513-4, reference Request for ties intothemain Service Water headerEngineering Review (RER) between Q1P16V506 and Q1P16V507 SNC1115980, andthepiping waslater andisupstream ofthe mini-flow replaced byworkorder SNC930301.
isolation valve Q1P16V575.
D-B A through-wall leak wasnoted on the CR10742390 documents the D2.10 Service Water return piping from the 2B evaluation foroperability, reference Diesel Generator near theflange Prompt Determination ofOperability upstream ofvalve Q1P16V593. This (PDO)2-20-01. Theflaw was wasidentified during theUnit 2 ISI evaluated inaccordance with Code pressure test 160.28-3. Note: This was Case N-513-4, reference RER also included in2R27OAR-1Report, SNC1121545-01, andtheimpacted since wasidentified it during Unit 2 piping was later replaced bywork order ressure test oncommon iin SNC1126770 andSNC1121637.
D-B A through-wall leak ofless than 1drop CR10777229 documents the D2.10 perminute wasdiscovered between the evaluation for operability. Thepiping 1BComponent Cooling Water (CCW) wasreplaced by work order Heat Exchanger (HX) andService SNC1144530.
Water vent valveQ1P16V004B. The through-wall indication isapproximately 2"above thesocket weldwhere theline attaches totheheat exchan er.
E-A During theContainment Moisture CR10785469 documents the condition, E1.30 Barrier visual exam,a small section of Indication Notification Form(INF) I concrete toconcrete interface was F1-001 documents theevaluation, and found tohave degraded sealant. This WOSNC1091821 repaired moisture approximately 12"section islocated on barrier sealant.
the105' outer circumference ofthebio-wall near Az 15.
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(QFORVXUHWR1/
5)RUP2$52ZQHUV$FWLYLW\5HSRUW F-A During the visual inspectionsupportCR10790278 for documentsthecondition F1.40 D170239-SW 501A, SNC877640-340,andevaluation along withINFI-21-F1-(Unit 1 B-train Service WaterStrainer002.Theanchor bolt maintains still Q1P16F501A), oneanchor bolt thread engagement andstructural (stud/nut) wasfound tohave corrosion which integrity issufficient tomaintain andloss ofcross-sectional areagreaterthe load full bearing ofthebolt capacity than 10%.Thethree remaining anchorandsupport andisacceptableperIWF-bolts areacceptable. 3410(b)(5)
Roughness orgeneral corrosion which doesnotreduce the loadbearing ofthe capacity support.
F-A Replacement 32"Main SteamLoop1 CR10790795 documentsthecondition F1.20C spring can pipingsupport ALA2-4100-andINFI-21-F1-003 andRER MS3-H6 hot load wasfound setting out SNC1152832-01 document the ofadjustment. Themain steamspringevaluation.Thehot loadsettings were canMS3-H6 was replaced in1R30, notwithin theacceptance standardsin Thehot load setting wasfoundtobeout accordance ASMESection with XI, oftolerance during the NOPT This IWF-3410(a)(4). condition was walkdown. bydesign evaluated engineering in accordancewithIWF-3112.3andis accetablewithoutcorrective actions.
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(QFORVXUHWR1/
5)RUP2$52ZQHUV$FWLYLW\5HSRUW Table 2 Farley Nuclear Unit Plant 1,5thInterval, 2ndPeriod, 1stReport Abstract ofRepair /Replacement Activities Requiredfor ContinuedService Code Item Description Description ofWork DateCompletedRepair /
Class Replacement PlanNumber 2 1"Balancing LinepipingReplaced piping and 1/16/2020 SNC1070049 toflangeweld leakfrom weld duetoleak.
the1CCharging Pump casin 3 8"Service Water return Replaced section of 11/6/2020 SNC1126770 piping from the 2B Diesel leakingService Water Generator near the piping.
flange upstream ofvalve Q1P16V593. Note:This wasalso included in 2R27OAR-1Report, since it wasidentified during Unit 2 pressure test oncommon iin 3 3/4" Service Water inlet Replacedsection of 2/26/2021 SNC1144530 vent piping tothe18 leakingService Water CCWHeat Exchan er. iin 3 10CCWHeat The1CCCWHeat 1/25/2021 SNC1121067 Exchanger tube. Exchanger affected leakingtubes were lu ed.
2 32"Main Steam Loop1 Replaced east andwest 4/19/2021 SNC1056981 spring canpiping supportspring cans dueto ALA2-4100-MS3-H6 repetitively outofdesign s ecification tolerance.
3 6"Service Water piping Replaced section of 4/20/2021 SNC930301 ofthe1CService Water leaking Service Water pumpmini-flow lineon piping.
anelbow inthe horizontal section of piping that ties the into main Service Water header between Q1P16V506 and Q1P16V507 andis upstream ofthemini-flow isolation valve Q1P16V575.
CC 12"degraded sealant in Repaired moisture 4/11/2021 SNC1091821 concrete toconcrete barrier sealant.
moisture barrier.
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