Letter Sequence RAI |
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EPID:L-2022-LLR-0034, Brown Ferry Nuclear Station, Sequoyah Nuclear Station and Watts Bar Station - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update (Approved, Closed) |
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MONTHYEARCNL-20-033, Brown Ferry Nuclear Station, Sequoyah Nuclear Station and Watts Bar Station - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2020-04-24024 April 2020 Brown Ferry Nuclear Station, Sequoyah Nuclear Station and Watts Bar Station - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update Project stage: Request CNL-20-088, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2020-10-29029 October 2020 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update Project stage: Request CNL-21-048, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Miilstone Status Update2021-04-29029 April 2021 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Miilstone Status Update Project stage: Request CNL-21-089, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2021-10-29029 October 2021 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update Project stage: Request ML22167A1672022-03-15015 March 2022, 27 May 2022, 28 June 2022, 9 August 2022, 12 August 2022, 28 September 2022, 29 September 2022, 1 December 2022 1 and 2 Request for Alternative RV-02 - PIV Leakage (EPID L 2022-LLR-0034 Project stage: Request ML22095A0182022-04-0404 April 2022 NRR E-mail Capture - Sequoyah Nuclear Plant - Acceptance of Request for Alternative - Pressure Isolation Valve Leakage ISTC-3630 (L-2022-LLR-0034) Project stage: Acceptance Review CNL-22-052, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status2022-04-27027 April 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Project stage: Request ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 Project stage: RAI ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 Project stage: RAI CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 Project stage: Response to RAI ML22220A1072022-08-0909 August 2022 Regulatory Audit in Support of Review of the Request for Alternative to American Society of Mechanical Engineers Operation and Maintenance Code Project stage: Approval ML22263A0082022-09-28028 September 2022 Audit Summary Request for Alternative RV-02 - PIV Leakage Project stage: Other ML22263A3752022-09-29029 September 2022 Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage Project stage: Other CNL-22-104, Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-10-31031 October 2022 Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 Project stage: Response to RAI CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update Project stage: Request ML22304A1862022-12-0101 December 2022 Revised Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage Project stage: Other 2022-04-27
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Category:E-Mail
MONTHYEARML24309A0552024-11-0101 November 2024 NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5 ML24281A0072024-10-0202 October 2024 NRR E-mail Capture - Acceptance Review Results for the Sequoyah License Amendment Request to Modify the FHA Analysis, Tech Spec TS 3.9.4 and Tech Spec 3.3.6 (L-2024-LLA-0117) ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24128A1802024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review for Sequoyah License Amendment Request to Modify TS 3.8.1 and TS 3.8.2 (L-2024-LLA-0047) ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24074A4252024-03-14014 March 2024 NRR E-mail Capture - Sequoyah Hydrologic Analysis License Amendment Request - Notification of Change to Estimated Completion and Hours ML24059A4052024-02-28028 February 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-02 ML24053A0302024-02-21021 February 2024 NRR E-mail Capture - Request for Steam Generator (SG) Tube Inspection Call for Sequoyah, Unit 1 ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23165A2862023-06-14014 June 2023 Tennessee Multi-Sector Permit (Tmsp), 2023 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, SW-17, SW-18, SW-19, and SW-21 ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23058A1312023-02-27027 February 2023 FW: TVA Intentions on EA-22-129 ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23046A3552023-02-15015 February 2023 Annual Water Withdrawal Report 2022 ML23019A3442023-01-19019 January 2023 Tennessee Multi-Sector Permit (Tmsp), 2022 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, and SW-19 ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22348A0432022-11-28028 November 2022 NRR E-mail Capture - State Consultation - Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Modify the Approved 10 CFR 50.69 Categorization Process (L-2022-LLA-0033) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22196A0732022-07-15015 July 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - TSTF-505 RICT (L-2021-LLA-0145) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A0332022-06-17017 June 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - Reactor Trip System Instrumentation (L-2021-LLA-0200) ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22137A2692022-05-17017 May 2022 Notice of Termination, TNR192066, Gravel Lot Restoration Project ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22132A1762022-05-12012 May 2022 Tennessee Multi-Sector Permit (Tmsp), 2021 Annual Discharge Monitoring Report for Outfalls SW-2, SW-3, SW-4, SW-6, SW-8, SW-9, and SW-13 2024-06-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24309A0552024-11-0101 November 2024 NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5 ML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283B0592018-10-10010 October 2018 NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18233A1942018-08-21021 August 2018 NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML17112A0402017-04-20020 April 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING ML17004A0612017-01-0404 January 2017 Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007) ML15194A3882015-07-13013 July 2015 Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec ML15175A2912015-06-24024 June 2015 E-mail Re. Request for Additional Information RR RP-07 ML15159B1642015-06-22022 June 2015 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482) ML15050A0962015-02-19019 February 2015 E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec 2024-05-31
[Table view] |
Text
From: Green, Kimberly Sent: Thursday, May 26, 2022 4:12 PM To: Taylor, Andrew Charles Cc: Wells, Russell Douglas; Buckberg, Perry
Subject:
Request for Additional Information re Sequoyah Nuclear Plant Alternative Request RV-02 (EPID L-2022-LLR-0034)
Attachments: Sequoyah RV-2 PIV RAIs L-2022-LLR-0034 5-26-22 .pdf
Dear Mr. Taylor,
By letter dated March 15, 2022 (ADAMS Accession No. ML22074A315), the Tennessee Valley Authority (TVA) submitted Alternative Request RV-02 for the Sequoyah Nuclear Plant, Units 1 and 2, to allow operation for 1 cycle if certain pressure isolation valves undergo mechanical agitation as a means to achieve acceptable valve seat leakage.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has identified areas where additional information is needed to complete its review. A draft request for additional information (RAI) was previously transmitted to you by email dated May 20, 2022.
At TVAs request, a clarification call was held on May 26, 2022, to clarify the NRC staffs draft RAI. As a result of the clarification call, the following changes were made the RAI:
EMIB-RAI-1(b) was revised to add, general design, including thecurrent EMIB-RAI-2(a) was revised to remove the word operating and replace it with the word any EMIB-RAI-4(a) was revised to add, ifexperienced any subsequent physical damage or degradation after and in an attempt to control leakage was deleted.
EMIB-RAI-4(b) was revised to change the term credible potential to reasonable potential EMIB-RAI-6 was revised to add leakbefore they are disassembled and inspected EMIB-RAI-9 was corrected to refer to Sequoyah Unit 2 in two places As agreed during the call, a response to the attached RAI is requested by June 30, 2022.
The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact Perry Buckberg at (301) 415-1383 or via email at Perry.Buckberg@nrc.gov.
On behalf of Perry Buckberg, Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier: NRR_DRMA Email Number: 1653 Mail Envelope Properties (DM6PR09MB5462F473562C512351533FEE8FD99)
Subject:
Request for Additional Information re Sequoyah Nuclear Plant Alternative Request RV-02 (EPID L-2022-LLR-0034)
Sent Date: 5/26/2022 4:11:32 PM Received Date: 5/26/2022 4:11:00 PM From: Green, Kimberly Created By: Kimberly.Green@nrc.gov Recipients:
"Wells, Russell Douglas" <rdwells0@tva.gov>
Tracking Status: None "Buckberg, Perry" <Perry.Buckberg@nrc.gov>
Tracking Status: None "Taylor, Andrew Charles" <actaylor@tva.gov>
Tracking Status: None Post Office: DM6PR09MB5462.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2088 5/26/2022 4:11:00 PM Sequoyah RV-2 PIV RAIs L-2022-LLR-0034 5-26-22 .pdf 96085 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
REQUEST FOR ADDITIONAL INFORMATION REGARDING ALTERNATIVE REQUEST RV-02 PRESSURE ISOLATION VALVE LEAKAGE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 and 50-328 EPID-L-2022-LLA-0034 References
- 1. Letter from Tennessee Valley Authority [TVA] to U.S. Nuclear Regulatory Commission (NRC), Sequoyah Nuclear Plant (SQN), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02, dated March 15, 2022 (ADAMS Accession No. ML22074A315).
- 2. Summary of February 16, 2022, public pre-application meeting with Tennessee Valley Authority regarding a future submittal of a request for an alternative to requirements for addressing Pressure Isolation Valve Leakage (ADAMS Accession No. ML22048B785).
Regulatory Basis The SQN Units 1 and 2 Inservice Testing Program implements the American Society of Mechanical Engineers (ASME) Operation and Maintenance Code as required by SQN Units 1 and 2 Technical Specification 5.5.6, Inservice Testing Program, and Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(f). Subsection ISTC-3630 of the SQN Units 1 and 2 Operation and Maintenance Code of record requires PIV testing to verify their seat leakages within acceptable limits and states, Valve closure before seat leakage testing shall be by using the valve operator with no additional closing force applied. In accordance with 10 CFR 50.55a(z)(2), the NRC staff may authorize an alternative to an ASME Code requirement if the licensee demonstrates that the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Requests for Additional Information EMIB-RAI-1 Alternative Request RV-02,Section V, in the subsection Summary, first paragraph, states:
The proposed alternative would permit continued startup if the PIV [pressure isolation valve]could be demonstrated to have acceptable seat leakage following mechanical agitation. Thevalve would only be acceptable for normal operation for one cycle and only if the final PIV seat leakage met the TS [Technical Specification] leakage criteria. This alternative will apply to ISTC-3630 requirements as they relate to use of additional closing force to achieve PIV closure before seat leakage testing, ISTC-3630(f) requirements as they relate to corrective action following a failed seat leakage test, ISTC-5221(a)(1) requirements as they relate to demonstrating that a PIV check valve disc travel to its seat following cessation of flow, and ISTC-5224 requirements as they relate to retesting following any required corrective action before the valve is returned to service.
The licensee is requested to provide the following information:
(a) Clarify how the mechanical agitation activity described in Alternative Request RV-02 relates to preconditioning.
(b) Specify the general design, including manufacturer/vendor, for the current check valves within the scope of therequest, and describe how mechanical agitation will provide sealing for the various check valve designs.
EMIB-RAI-2 Alternative Request RV-02,Section VI, Basis for Proposed Alternative, Item 2, Description of the mechanical agitation to be used, if needed, states:
Mechanical agitation is performed using a tool appropriately sized for the valve in question and for the location of the valve. The primary consideration is that the tool should not deform the valve body. The impact surface of the tool should be relativelylarge (greater than 1/2 diameter is preferred), and approximately flat or slightly rounded. The tool will contact the valve body surface so that it does not impact the body with an edge or sharp point. If available, a rubber coated tool may be used. In cases where there is limited access, a power-operated tool may be used provided thesame precautions discussed above can be used. Agitation should be applied incrementally, starting with minimal force, and may be applied to different locations onthe body, until either the disc is freed, or the plant determines agitation will not be successful. Because this activity does not lend itself to quantifiable parameters, the task is performed using the skill of the craft within the limitations discussed above. Because mechanical agitation is not a repair or replacement activity, this alternative is needed to avoid potential unnecessary emergent demands on plantequipment, resources, and personnel.
The licensee is requested to provide the following information:
(a) Describe any experience with mechanical agitators at Sequoyah orother plants if known.
(b) Specify the size of the actual mechanical agitators used on the 2-inch through 10-inch valves at Sequoyah if applied in the past.
(c) Specify and describe the procedures that have been established to control the mechanical agitation activity such that the hand-operated and power-operated tools will not damage the valve seat, valve stem or pressure boundary function, etc.
(d) Describe the weak link analysis that has been performed to verify that the mechanical agitation activity will not damage the check valves.
(e) Explain the statement: Because mechanical agitation is not a repair or replacement activity, this alternative is needed to avoid potential unnecessary emergent demands on plant equipment, resources, and personnel.
(f) Specify any available standard, or industry or vendor guidelines, that will beused in applying the mechanical agitators.
EMIB-RAI-3 Alternative Request RV-02,Section VI, Item 1, Review of Maintenance History of the PIVs, states, in part:
6 inclined seat swing check valves PIV leak test history has been generally satisfactorily (leakage present on 27.8%
oftests on SQN Unit 1 and 30.3% on SQN Unit 2 - no as-left failures).
10 vertical seat swing check valves PIV leak test history has improved in the last few outages and acceptable leak rateshave been obtained in all cases (leakage present on 52.8% of tests on SQN Unit 1 and 75% on SQN Unit 2 - no as-left failures).
The licensee is requested to provide the following information:
(a) Provide the evaluation of the cause of this high occurrence of leakage for the 6-inch and 10-inch check valves.
(b) Provide the leakage rate history for 8-inch PIVs and describe the evaluation of the leakage rates.
EMIB-RAI-4 Alternative Request RV-02,Section VI, Item 3, Design of the PIV check valves, discusses the failures of PIVs at Sequoyah.
The licensee is requested to provide the following information:
(a) Discuss if any PIVs experienced any subsequent physical damage or degradation after a mechanical agitator was applied.
(b) Describe the evaluation of the design of each check valve to demonstrate that if a valve initially fails its leak rate test and the alternative is applied, there is no reasonable potential for disk separation or failure that might impede flow if the valve must open toperform its safety function.
EMIB-RAI-5 Alternative Request RV-02,Section IV, Reason for Request, states, in part:
Most PIVs tested at the lower pressures met the leakage rate acceptance criteria when correlated to RCS pressure. However, some PIVs have required a higher test pressure (up to nominal RCS pressure) in order to achieve acceptable leakage results. Test proceduresare written to allow testing at low or higher pressures.
The licensee is requested to provide the following information:
Describe how the method to be used when implementing Alternative Request RV-02 will continue to meet ASME OM Code, paragraph ISTC-3630, Leakage Rate for Other Than Containment Isolation Valves, subparagraph ISTC-3630(b), Differential Test Pressure, and subparagraph ISTC-3630(e), Analysis of Leakage Rates, while performing PIV leakage testing at a lower pressure.
EMIB-RAI-6 Alternative Request RV-02,Section V, Proposed Alternative, in the subsection Description of the Proposed Alternative, states, in part, that PIVs that have been mechanically agitated and subsequently passed seat leakage testing, will be repaired, or replaced during the next refueling outage.
In order to support to the long-term effectiveness of Alternative Request RV-02, please discuss any plans to leak test these PIVs before they are disassembled and inspected at the next refueling outage prior to commencing with their repair orreplacement to determine if agitation caused any adverse effects on valve performance.
EMIB-RAI-7 Alternative Request RV-02,Section VI, Basis for Proposed Alternative, Item 4, Description of Preventive Maintenance of the PIVs, first paragraph, states, Each unit has a scoping preventive maintenance (PM) to evaluate and identify PIVs to recommend for inspection and repair (or replace) for an upcoming refueling outage.
Please explain this statement in light of the requirement under Alternative Request RV-02 that all PIVs that have been mechanically agitated must undergo repair or replacement, and retesting, at the next refueling outage.
EMIB-RAI-8 Alternative Request RV-02,Section VI, Item 5, Description of PIV Open Exercise Testing, states in part:
While total pump design flow is instrumented and measured during every comprehensive pump test, flow through each individual injection line is instrumented and measured on analternating basis in accordance with the check valve condition monitoring plan.
The licensee is requested to describe the ASME OM Code Appendix II check valve condition monitoring plan referenced in this item.
EMIB-RAI-9 During the pre-submittal meeting on February 16, 2022, the licensee indicated that recent operating experience has heightened TVAs awareness that mechanical agitation can lead to adequate valve sealing in addition to recent similar experience during the last Sequoyah Unit 2 outage. Please describe this experience during the last Sequoyah Unit 2 outage referenced in this meeting, and its impact on the provisions in Alternative Request RV-02.