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
MONTHYEARML24278A2832024-11-0707 November 2024 Letter to E. Carr Environmental Impact Statement Scoping Summary Report for Virgil C. Summer Nuclear Station Unit 1 ML24305A1302024-10-31031 October 2024 Submittal of 30 Day Report Per 10 CFR 26.719(c) Blind Performance Testing ML24308A0052024-10-28028 October 2024 10-28-24 NRC V.C. Summer Nuclear Station SLR Cherokee Nation Letter to USNRC ML24308A0062024-10-25025 October 2024 Subsequent License Renewal Application Area of Potential Effect (Ape) Clarification Fairfield County, South Carolina SHPO Project No. 22-EJ0147 ML24302A1442024-10-24024 October 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 4 and Requested Information Formation in Response to Limited Aging Management Audit ML24250A0782024-10-22022 October 2024 Relief Request RR-5-V1 Regarding Service Water Return Header Check Valves ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System ML24290A1052024-10-0707 October 2024 Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment ML24221A2112024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0552024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0642024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0542024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0592024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24185A1902024-06-25025 June 2024 Submittal of Updated Final Safety Analysis Report, Revision 24 ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator2024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. 2024-09-26
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24087A2262024-03-26026 March 2024 License Amendment Request - Inverter Allowed Outage Time Extension Response to Request for Additional Information ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. ML22353A5462022-12-19019 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 2024-08-01
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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.