Letter Sequence Response to RAI |
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EPID:L-2020-LRO-0084, (VCSNS) Unit 1 - Special Report (Spr) 2020002 - Steam Generator Tube Inspection Report (Approved, Closed) |
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MONTHYEARML20296A6922020-10-20020 October 2020 (VCSNS) Unit 1 - Special Report (Spr) 2020002 - Steam Generator Tube Inspection Report Project stage: Request ML20349A3262020-12-14014 December 2020 (Vcsns), Unit 1 - Response to NRC Request for Additional Information Regarding RF-24 Steam Generator Tube Inspection Report Project stage: Response to RAI ML21131A0402021-05-11011 May 2021 NRR E-mail Capture - V.C. Summer, Unit 1 - Final RAI for the Spring 2020 RFO Sgtir Review Project stage: RAI ML21154A1802021-06-0303 June 2021 Response to NRC Request for Additional Information Regarding RGF-25 Steam Generator Tube Inspection Report Project stage: Response to RAI ML21180A4052021-06-29029 June 2021 (Vcsns), Unit 1 - Supplement to Request for Additional Information Regarding RF-25 Stem Generator Tube Inspection Report Project stage: Supplement ML21201A3262021-08-0202 August 2021 Review of Steam Generator Inservice Inspection Report End of the Twenty Fifth Refueling Outage Project stage: Approval 2021-05-11
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Category:Letter
MONTHYEARML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML22353A5462022-12-19019 December 2022 (Vcsns), Unit 1 - Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request ML22300A2202022-10-27027 October 2022 (VCSNS) Unit 1, Alternative Request Rr-4-26 Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) RAI ML22020A2262022-01-20020 January 2022 Response to Request for Additional Information to License Amendment Request LAR-20-203 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency ML21180A4052021-06-29029 June 2021 (Vcsns), Unit 1 - Supplement to Request for Additional Information Regarding RF-25 Stem Generator Tube Inspection Report ML21168A2612021-06-17017 June 2021 (Vcsns), Unit 1 - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors - Final Supplemental Response ML21154A1802021-06-0303 June 2021 Response to NRC Request for Additional Information Regarding RGF-25 Steam Generator Tube Inspection Report ML21007A3232021-01-0707 January 2021 License Amendment Request LAR-20-142 Request for Technical Specification Change Technical Specification 3.6.4, Containment Isolation Valves Response to Request for Additional Information (RAI) ML21007A3402021-01-0707 January 2021 (Vcsns), Unit 1 - License Amendment Request LAR-20-176 Update of Analytical Method to the Core Operating Limits Report with the Full Spectrum Loss of Coolant Accident Approach - Response to Request for Additional Info ML20349A3262020-12-14014 December 2020 (Vcsns), Unit 1 - Response to NRC Request for Additional Information Regarding RF-24 Steam Generator Tube Inspection Report ML19282E2612019-10-0909 October 2019 Response to Follow-Up Question to PRA RAI 03, License Amendment Request - LAR-16-01490 NFPA 805 Program Revisions ML19224B1152019-08-12012 August 2019 Response to NRC Follow-Up Question PRA RAI 03, License Amendment Request - LAR-16-01490 NFPA 805 Program Revisions ML19119A3652019-04-29029 April 2019 (Vcsns), Unit 1 - License Amendment Request - LAR-16-01490, NFPA 805 Program Revisions: Response to Request for Additional Information ML19071A3572019-03-11011 March 2019 Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2., D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.b.2 and 4.8.2.1.c.3 - Request for Additional Information RC-18-0116, (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information2018-09-11011 September 2018 (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information RC-18-0100, (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information2018-08-22022 August 2018 (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information RC-18-0090, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request...2018-07-12012 July 2018 (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request... RC-18-0084, Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Requ2018-07-0303 July 2018 Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Reques RC-18-0046, License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information2018-04-19019 April 2018 License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information2018-04-0202 April 2018 (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information RC-17-0134, Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 12017-09-27027 September 2017 Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1 RC-17-0093, License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, Response To.2017-07-0606 July 2017 License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, Response To. RC-17-0088, Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times - Response to Request for Additional Information2017-06-22022 June 2017 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times - Response to Request for Additional Information RC-17-0032, Spent Fuel Evaluation Supplemental Report, Response to NRC for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2017-03-30030 March 2017 Spent Fuel Evaluation Supplemental Report, Response to NRC for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident ML17087A1512017-03-28028 March 2017 Response to Request for Additional Information on VC Summer Sfpli RC-17-0019, Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 12017-02-0606 February 2017 Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 1 RC-16-0147, VC Summer Nuclear Station, Unit 1, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Pursuant to Title 10 9f the Code of Federal Regulations 05.54(f)2016-11-0303 November 2016 VC Summer Nuclear Station, Unit 1, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Pursuant to Title 10 9f the Code of Federal Regulations 05.54(f) ML16235A2422016-08-18018 August 2016 Response to Request for Information for Triennial Fire Protection Baseline Inspection RC-16-0091, Response to Request for Additional Information on Relief Request RR-III-12 Proposed Alternative Inspection Requirements for Piping Welds2016-06-0202 June 2016 Response to Request for Additional Information on Relief Request RR-III-12 Proposed Alternative Inspection Requirements for Piping Welds RC-16-0077, Relief Request RR-III-12, Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information2016-05-0606 May 2016 Relief Request RR-III-12, Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information RC-16-0046, Response to Request for Additional Information on Relief Request RR-III-2, Proposed Alternative Inspection Requirements for Piping Welds2016-03-18018 March 2016 Response to Request for Additional Information on Relief Request RR-III-2, Proposed Alternative Inspection Requirements for Piping Welds RC-16-0036, License Amendment Request - LAR-15-01424 - Implementation of WCAP-15376-P-A, Revision 1, Response to Request for Supplemental Information2016-03-0707 March 2016 License Amendment Request - LAR-15-01424 - Implementation of WCAP-15376-P-A, Revision 1, Response to Request for Supplemental Information RC-16-0031, License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response2016-03-0404 March 2016 License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response RC-16-0039, Exigent License Amendment Request - LAR (16-00848), Technical Specification Change Request for Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B - Response to Request for Additional..2016-03-0303 March 2016 Exigent License Amendment Request - LAR (16-00848), Technical Specification Change Request for Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B - Response to Request for Additional.. RC-16-0001, V.C. Summer, Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information2016-01-22022 January 2016 V.C. Summer, Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information RC-16-0006, Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis2016-01-14014 January 2016 Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis RC-15-0186, Response to Request for Information (NRC Inspection Report No. 05000395/2015404)2015-11-11011 November 2015 Response to Request for Information (NRC Inspection Report No. 05000395/2015404) IR 05000395/20154042015-11-11011 November 2015 V.C. Summer, Unit 1 - Response to Request for Information (NRC Inspection Report No. 05000395/2015404) RC-15-0160, Response to Request for Information (NRC Inspection Report No. 05000395/2015404)2015-09-25025 September 2015 Response to Request for Information (NRC Inspection Report No. 05000395/2015404) ML15310A0762015-09-21021 September 2015 Response to Request for Information to Support the Cyber Security Inspection RC-15-0142, License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information2015-09-10010 September 2015 License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information RC-15-0116, Response to NRC Request for Information Baseline Radiation Safety Inspection2015-07-13013 July 2015 Response to NRC Request for Information Baseline Radiation Safety Inspection 2022-12-19
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Text
V.C.
Bradham SummerNuclear BIvd Station
& Hwy 215,Jenkinsville, SC 29065 L',7+ QQ@n jQQ Mailing Address: ry neT P.O. Box 88,Jenkinsville, SC 29065 f DominionEnergy.com June3,2021 Document Control Desk Serial No.21-195 U.S. Nuclear Regulatory Commission VCSLIC/BAB/Rev 0 Washington, DC20555 Docket No.50-395 License No.NPF-12 V
RESPONSE TONRCREQUEST FORADDITIONAL INFORMATION REGARDING RF-25 STEAMGENERATOR TUBEINSPECTION REPORT
References:
1 DESCLetter, "Special Report (SPR) 2020-002 -
Steam Generator Tube Inspection Report,"dated October20, 2020 (ADAMS Accession No.
ML20296A692)
- 2. E-mail fromNRCSenior Manager,Vaughn Thomas, "Summer, Project Unit 1-Final RAIsfor theSGTubeInspection Report Review," dated May11,2020 (ADAMS Accession No.ML21131A040)
InReference 1,DESCsubmitted a TechnicalSpecification required report related tosteam generator inspections performed during C.SummerUnit theVirgil 1 Twenty-Fifth Refueling Outage (RF-25). In Reference 2, the NRC Staffprovided a request for a dditional information (RAI) regarding this report. Theenclosure tothisletterprovides theDESCresponses tothe RAl.
Ifyouhaveanyquestions orrequireadditional information,please contact Mr.Michael Moore at (803) 345-4752.
Sincerely, GeorgeLippard SiteVice President V.C. Summer Nuclear Station Commitments contained inthisletter:
None
Enclosure:
Response toNRCRequest for Additional Information cc: G.J.Lindamood -
SanteeCooper L.Dudes NRCRegion II V.Thomas NRCProject Mgr.
NRCResident Inspector
Serial No.21-195 Docket No.:50-395 Response toRAlRegarding SGReport RF-25 Enclosure toNRCRequest Response for Additional information C.SummerNuclear Virgil Station (VCSNS) Unit 1 Energy Dominion South C arolina, (DESC)
Inc.
SerialNo.21-195 Docket No.:50-395 Enclosure -
RAlResponse: Page1of3 DESC RESPONSE TONRCREQUEST FORADDITIONAL INFORMATION REGARDING VCSNSUNIT1RF-25 STEAMGENERATOR TUBEINSPECTION REPORT 1.Please discuss ifthere wasany degradation noted during the primary side visualinspections of the channelhead bowl cladding andinternal surfaces, performed oneach SG.
2.With respect tothesecondary side inspections,please clarifythe scope (i.e.,
whether they were inallthree SGs) andresults ofthe secondary side inspections performed.
3.TheDecember 14,2020, response tothe NRC's request for additional information onthe 2018SGtube inspection report fall (ADAMS Accession No.
ML20349A326), statedthat heavy deposit formations andtube denting were identified during thevisual inspectionof the top (9th) tube support plate (TSP) ineach SG.It isstatedinthespring 2020 SG tube inspection report that Deposit Minimization Treatment (DMT) cleaning was performed during RFO
- 25. Please provideadditional detailregardingthe extent ofthe deposit formations andprovide anyadditional insights, including the extentofdenting, youmayhave withregards tothedenting that could be related to the heavy deposit formation.
4.Section 6.0, "Tubes Plugged during the Inspection Outage," of the spring 2020 SGtube inspection report states thata total of4 tubes wereplugged; 2 tubes were preventively plugged inSGA duetoTSPwear indications (neither exceeded the 40percent plugging criterion) and2 tubes (1 inSGA and 1in SGB)were plugged duetopossible loose parts Please (PLPs). clarify whether the PLPswere newly identified during RFO25andhowmanytotal PLPs there were inthetwotubes.
M Asnoted intheRF-25 Condition Monitoring andFinal Operational Assessment, inresponse toNSAL12-1, Revision 1,thevisual inspection oftheSteam Generator (SG) channel headbowl included inspections oftheentire channel headinternal surfaces.Specifically, theentire tubesheet, cladding, divider plate, andassociated welds/components. This visual inspection confirmed that the channel headbowl ineachSGwasinsatisfactory condition andidentified no signs ofdegradation, rust,deformation, orabnormal conditions.
SerialNo.21-195 Docket No.:50-395 Enclosure -
RAIResponse: Page2of3 M
As noted inSpecial Report 2020-02 -
Steam Generator TubeInspection Report, secondary side inspections (SSl) wereperformed during RF-25 forthetopofthe tubesheet (TTS), flow distribution baffle (FDB), andtop(9th) tube support plate (TSP) in all three SGs. Inspection results from t heR F-25 C onditionMonitoring andFinal Operational Assessment arediscussed below.
TopoftheTubesheet (TTS)/FlowDistribution Baffle (FDB)
TheDeposit Minimization Treatment (DMT) process results inremoval oftube deposition. Therefore, post-DMT lancing wasperformed ontopoftheFDB first followed bylancing onthe TTS. Prior totheremoval ofthelancing equipment at each location, quick look visual inspections were performed ontheFDBandTTS toassess the thoroughness of the lancing process. After removal ofthelancing equipment, post-lance SSIwereperformed.
TheFDBpost-lance inspections included innerbundle passes approximately every 20columns (H/L C/L).
and The TTS post-lance inspections included the no-tube lane, annulus regions, andinnerbundle passes. Foreign object search andretrieval (FOSAR) inspections at the FDB and TTS were also performed as needed.
Other than foreign objects that wereidentified butdid not causetube wear, no abnormal conditions wereidentified during the TTSinspections. All foreign object-related findings resulted ineither removal offoreign material orplugging of tubes for possible loose parts (PLP) located onthe 1st TSP that couldnot be visually inspected.
Top(9th) TubeSupport Plate (TSP)
Visual inspections ofthe topTSP(9th TSP) along thenotube laneregion were performed ineachSG.Theinspections focused ongeneral conditionof the TSP looking for general condition ofsludge/fouling oftheno-tube lane, TSP ligaments, andlowrowU-bends. Theinspection also looked for webbing or bridging between thetubes/broaches, tube-to-tube bridging andblocked/partially blocked flow/broached holes. inner bundle passes (H/L andC/L) atright angles tothe 9th support notube lane wasalso performed totheextent possible.The results ofthese inspections identified noconditions quality.
adverse to M
TheV.C. SummerSteam Generator Secondary Side Management Evaluation (Framatome Maestro Evaluation), dated 11/13/2019 (priortocleaning), describes that small, discrete deposit accumulation begins atthe3rd TSPandbecome moreextensive ateachhigher support level. "More extensive" inthis context meansincreased eddy current amplitudes aswell asa greater number of affected broaches. Thedeposition predominantly affects thehotleg; however, at higher elevations thecold legs become moreinvolved. The9th TSPisthemost
Serial No.21-195 Docket No.:
50-395 Enclosure -
RAIResponse: Page3of3 impacted support inall three SGs,atwhich a substantial portion ofthehotleg broaches have large amplitude deposit indications, andmorethan half ofthecold leg broaches have detectibledeposit indications. TheSGA deposition atall support levels is very similarinmagnitude anddistribution tothat ofSGB.SGC hasexperienced moreadvanced accumulation than SGA andSGB atall levels.
InSGC,the hot leg broaches in both TSP8andTSP9 arebroadly affected by large amplitude deposit indications.
During RF-24 (Fall 2018), eight newly formed dents were identified atupper TSP intersections SGC at9th inthehot legs ofSGB andSGC During RF-25, six newdents (one inSGB at8th wereidentified TSP,seven inthehot leg in of TSP).
SGC formed (one at8th byverifying TSPand five at9th that TSP) T nodent signals werepresent hedents were confirmed intheprevious as eddy newly current inspection data. Nowear has beenidentified atanyofthedent locations.
TheMaestro Report concluded that, although nowear hasbeenidentified atthe tubes, themost probable cause ofthe new dentsiselevated crossflow resulting from flow restriction inthe hotleg, primarily atthe toptwoTSPs. This tube denting first identified inRF-24 wasa driving factor for chemical cleaning performed inRF-25 (Spring 2020) that resulted inremoval of 4,048 lbs ofsludge through a combination ofthe DMTprocess and subsequent sludge lancing.
M FromtheRF-25 Condition Monitoring andFinal Operational Assessment, there weretwo(2) tubes plugged duetoPLPs. o f Both these tubes had new PLP single indications whose locations werenot accessible bySSl/FOSAR. These indications wereatlocations onthe 01HTSPthat donothaveinspection ports.