Letter Sequence Response to RAI |
---|
|
|
|
|
---|
Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter 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 IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 2024-01-04
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation ML23117A1162023-04-27027 April 2023 Response to Follow-up Questions to TVAs Response to NRCs Request for Supplemental Information (Rsi) Related to August 4, 2022, Sequoyah ISFSI Exemption Request CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 ML22353A0662022-12-19019 December 2022 Response to Request for Supplemental Information (D-RSI) Request for Exemption from Non-Destruction-Examination Compliance CNL-22-084, Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-09-16016 September 2022 Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ2022-08-22022 August 2022 Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Reques CNL-22-069, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-07-0101 July 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. 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 CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-21-024, Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02)2021-06-15015 June 2021 Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02) CNL-21-039, Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2021-05-0505 May 2021 Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-20-082, Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)2020-11-10010 November 2020 Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02) CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020 Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-20-057, Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02)2020-08-12012 August 2020 Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02) ML20196L6892020-07-16016 July 2020 TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request CNL-20-032, Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis2020-05-14014 May 2020 Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis CNL-20-026, Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-02-18018 February 2020 Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-19-119, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-19019 November 2019 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-061, Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task2019-10-18018 October 2019 Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Fo ML19231A2082019-08-19019 August 2019 Response to Request for Information Regarding Unit 2 Cycle 22 - 180-Day Steam Generator Tube Inspection Report CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. CNL-19-057, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-12019-06-19019 June 2019 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-1 CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,.2019-03-21021 March 2019 Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,. CNL-19-016, Response to Request for Additional Information on License Amendment Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report2019-01-30030 January 2019 Response to Request for Additional Information on License Amendment Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. CNL-17-063, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2017-10-26026 October 2017 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-17-104, Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-08-0707 August 2017 Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-16-194, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2016-12-23023 December 2016 Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-16-178, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2016-12-23023 December 2016 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-123, Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-52016-07-28028 July 2016 Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 CNL-16-086, Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System2016-05-31031 May 2016 Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System CNL-15-218, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information2015-10-23023 October 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information CNL-15-171, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) - Response to Request for Additional Information2015-09-11011 September 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) - Response to Request for Additional Information CNL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. CNL-15-146, Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 (TAC Nos. MF0481 and MF0482)2015-08-0303 August 2015 Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 (TAC Nos. MF0481 and MF0482) NL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. CNL-15-136, Response to NRC Request for Additional Information Regarding ASME Request for Relief RP-072015-07-22022 July 2015 Response to NRC Request for Additional Information Regarding ASME Request for Relief RP-07 ML15176A6822015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8 ML15176A6812015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8 ML15176A7482015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 8 of 8 ML15176A7402015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 ML15176A6792015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 ML15176A6642015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8 2024-01-03
[Table view] Category:Technical Specifications
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22259A2042022-09-29029 September 2022 Correction to Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) ML21084A1902021-05-0404 May 2021 Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation ML21021A3492021-03-0303 March 2021 Issuance of Amendment Nos. 354 and 347 Regarding Revision to Technical Specification 4.2.2, Control Rod Assemblies ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML19319C8312019-11-21021 November 2019 Issuance of Exigent Amendment No. 348 to Operate One Cycle with One Control Rod Removed ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection CNL-16-178, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2016-12-23023 December 2016 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-16-086, Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System2016-05-31031 May 2016 Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System ML15320A2182015-11-30030 November 2015 Issuance of Amendments to Revise Technical Specification for Containment Leakage Rate Program ML15310A0422015-11-0404 November 2015 License Amendment Nos. 334 and 327, Improved Technical Specifications, Implementation CNL-15-218, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information2015-10-23023 October 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information ML15238B4602015-09-30030 September 2015 Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues CNL-15-163, Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Proposed License Conditions2015-08-0505 August 2015 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Proposed License Conditions NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 3 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 3 of 9 ML15205A4142015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 9 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 4 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 4 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 5 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 5 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 6 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 6 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 7 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 7 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 8 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 8 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9 NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 92015-07-24024 July 2015 Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9 CNL-15-156, Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 92015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9 ML15205A4062015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9 ML15205A4072015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 3 of 9 ML15205A4082015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 4 of 9 ML15205A4092015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 5 of 9 ML15205A4112015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 6 of 9 ML15205A4122015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 7 of 9 ML15205A4132015-07-24024 July 2015 Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 8 of 9 ML13330A9242013-11-22022 November 2013 Enclosure 2 - Volume 12 - Improved Technical Specifications Conversion, ITS Section 3.7, Plant Systems ML13330A9272013-11-22022 November 2013 Enclosure 2 - Volume 13 - Improved Technical Specifications Conversion, ITS Section 3.8, Electrical Power Systems ML13329A7182013-11-22022 November 2013 Enclosure 1 - Improved Technical Specifications (ITS) Submittal, Enclosure 3 - Licensee Identified Changes That May Require a Formal Technical Branch Review Through Enclosure 10 ML13330A9282013-11-22022 November 2013 Enclosure 2 - Volume 9 - Improved Technical Specifications Conversion, ITS Section 3.4, Reactor Coolant System (Rcs), Revision 0 ML13329A7902013-11-22022 November 2013 Enclosure 2 - Volume 3 - Improved Technical Specifications Conversion, ITS Chapter 1.0, Use and Application, Revision 0 ML13330A9312013-11-22022 November 2013 Enclosure 2 - Volume 11 - Improved Technical Specifications Conversion, ITS Section 3.6, Containment Systems ML13330A9532013-11-22022 November 2013 Enclosure 4, Attachments 3, 4 and 5, Reactor Trip System (RTS) and Engineered Safety Fatures Actuation System (ESFAS) Instrumentation Completion Times, Bypass Times, and Surveillance Test Interval Extensions Based On.. ML13330A9302013-11-22022 November 2013 Enclosure 2 - Volume 14 - Improved Technical Specifications Conversion, ITS Section 3.9 Refueling Operations ML13330A9292013-11-22022 November 2013 Enclosure 2 - Volume 10 - Improved Technical Specifications Conversion, ITS Section 3.5, Emergency Core Cooling Systems (Eccs), Revision 0 ML13330A9252013-11-22022 November 2013 Enclosure 2 - Volume 15 - Improved Technical Specifications Conversion, ITS Chapter 4.0, Design Features, Revision 0 ML13330A9222013-11-22022 November 2013 Enclosure 2 - Volume 16 - Improved Technical Specifications Conversion, ITS Chapter 5.0 Administrative Controls, Revision 0 ML13329A9162013-11-22022 November 2013 Sequoyah, Units 1 and 2, Enclosure 2 - Volume 6 - Improved Technical Specifications Conversion, ITS Section 3.3 Instrumentation, Revision 0 ML13329A8592013-11-22022 November 2013 Enclosure 2 - Volume 7 - Improved Technical Specifications Conversion, ITS Section 3.2 Power Distribution Limits, Revision 0 ML13329A8582013-11-22022 November 2013 Enclosure 2 - Volume 6 - Improved Technical Specifications Conversion, ITS Section 3.1 Reactivity Control Systems, Revision 0 2024-01-29
[Table view] |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402
CNL-16-086 May 31, 2016 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 328
Subject: Response to Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW)
System (TAC Nos. MF7450 And MF7451) References: 1. Letter from TVA to NRC, CNL-16-011, "Sequoyah Nuclear Plant, Units 1 and 2, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to OPERABLE Status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days (TS-SQN-16-01)," dated March 11, 2016 2. Email from NRC to TVA, "Request For Additional Information Sequoyah Nuclear Plant, Units 1 and 2, TS) 3.7.8 ERCW Change to Support Shutdown Board Maintenance, (TAC No. MF7450 and MF7451)," dated April 28, 2016 By the Reference 1 letter, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to revise Technical Specification (TS) 3.7.8 to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to OPERABLE Status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days for Sequoyah Nuclear Plant (SQN) Units 1 and 2. In Reference 2, the NRC provided a Request for Additional Information (RAI) related to the proposed change to TS 3.7.8. The due date for the response to the NRC RAI provided by the Reference 2 letter is May 31, 2016. The enclosure to this letter provides the response to the RAI included in the Reference 2 letter.
ENCLOSURE Response to NRC Request for Additional Information
Enclosure
Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW) System, (TAC No. MF7450 And MF7451) Page E-1 of 6 Regulatory Bases: 10CFR50 Appendix A - General Design Criteria. Criterion 44 Cooling Water RAI SBPB - 1
Background:
The amendment proposes to change TS 3.7.8, "Essential Raw Cooling Water (ERCW) System," to extend the allowed completion time to restore one ERCW System train to OPERABLE status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days for planned maintenance for SQN. These changes are needed to facilitate cleaning and inspection of the 6.9 kilovolt (kV)shutdown boards and associated 480 Volt (V) shutdown boards without requiring a dual unit shutdown.
However, the amendment does not clearly state whether physical plant modifications are needed as part of this TS 3.7.8 change.
RAI: Please confirm if plant modification(s) are needed as part of the proposed TS 3.7.8 change and describe the details of those plant modification(s). TVA Response: There are no physical plant modifications required to implement this change.
RAI SBPB- 2
Background:
The amendment proposes to change TS 3.7.8, "Essential Raw Cooling Water (ERCW)
System," to extend the allowed completion time to restore one ERCW System train to OPERABLE status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days for planned maintenance for SQN. These changes are needed to facilitate cleaning and inspection of the 6.9 kilovolt (kV) shutdown boards and associated 480 Volt (V) shutdown boards without requiring a dual unit shutdown.
However, during the proposed 7 day TS 3.7.8 LCO with one ERCW train inoperable for planned maintenance, the LAR did not describe defense-in-depth strategies employed by plant operations to minimize challenges to the only remaining operable train during the extended completion time of the inoperable train.
RAI: Please describe the defense-in-depth strategies on how operable equipment (such as electrical buses, emergency diesel generators, switch yard, emergency pumps, etc.) will be protected from maintenance or inadvertent operations that would challenge plant safety.
Enclosure
Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW) System, (TAC No. MF7450 And MF7451) Page E-2 of 6 TVA Response: TVA employs a graded approach to Defense-in-Depth (DID) and Protected Equipment strategies based on the operating status of the affected unit. Because ERCW is a shared system, TVA's response addresses both the outage unit and the operating unit.
For the Outage Unit:
At least once per shift, Control Room Operations completes a Defense-In-Depth (DID) Assessment in accordance with Procedure 1-PI-OPS-000-020.2 (2-PI-OPS-000-022.2),
"Operator At The Controls Duty Station Checklists-Modes 5, 6 And De-Fueled." This DID Assessment provides instructions for verifying the status and availability of components required to maintain key safety functions (Reactivity Control, Decay Heat Removal, Containment, RCS Inventory, Power Availability, and Spent Fuel Cooling/Inventory). This assessment includes guidance to ensure Protected Equipment/Systems are identified and protected. Work is screened to ensure that protected components or systems are not jeopardized. Protected components or systems are identified on shift turnover checklist and reviewed during shift turnover meetings and pre-job briefings, as well as through the use of physical or administrative barriers to prevent entry into a given area. Physical barriers may consist or roped off areas, posting signs, and/or placing cover devices with DID tag attached to door knob or breaker compartment handle. When Operations determines that additional barriers are needed, placement of DID placards and tags is documented and maintained. For the Operating Unit:
Fleet procedure NPG-SPP-07.3.4, "Protected Equipment" provides similar guidance for protecting operating plant equipment in order to minimize the potential for adverse operational events. Due to the duration of the planned board outage (greater than one shift), components will be posted and barricaded as "protected equipment." RAI SBPB- 3
Background:
The amendment proposes to change TS 3.7.8, "Essential Raw Cooling Water (ERCW)
System," to extend the allowed completion time to restore one ERCW System train to OPERABLE status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days for planned maintenance for SQN. These changes are needed to facilitate cleaning and inspection of the 6.9 kilovolt (kV)shutdown boards and associated 480 Volt (V) shutdown boards without requiring a dual unit shutdown.
The amendment also proposed that for TS 3.7.8 Action A.1, that certain conditions exists and one ERCW system flow is isolated for planned maintenance at the other unit that is shutdown. For example, while Unit 2 is in operation and Unit 1 is defueled or in Mode 6 with refueling cavity > 23 feet (above top of reactor flange) after defueled, the ERCW system design function for Train A can be met with only one running ERCW pump per train, during a Unit 1 cold shutdown, subject to a maximum ERCW supply
Enclosure
Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW) System, (TAC No. MF7450 And MF7451) Page E-3 of 6 temperature of 79° F. The analysis assumptions include that the 1A EDG, 1A CS HX, U1 TDAFW pump, 1A and 1C LCC groups, and 1A IIRC all have no ERCW flow. The analysis also assumed that the yard header, the 16¬inch Auxiliary Building header, and the 6¬inch ESF header crossties are in service supported by Train A ERCW.
The amendment stated a margin of up to 100 gallons per minute (gpm) would not affect the results of the Multiflow analysis.
However, the LAR did not state that operational controls are in place to ensure that the valve line-up and other conditions are maintained in the correct state for the 7 day LCO duration. RAI: 1. Describe if the extensive valve line-ups that support TS 3.7.8 Action A.1, that are described in the proposed Final Safety Analysis Report, insert Page 9.2-10, will be controlled via an Operations Lock-out Program.
2. Describe how valve leakage (> 100 gpm) will be tracked for acceptability for the 7 day duration.
3. Describe the controls in place to maintain the refueling cavity > 23 feet 4. Describe the TS actions required by the station if: a. Unacceptable ERCW flow is determined from any closed boundary valves.
b. UHS temperature exceed 79 °F. c. Refueling cavity water level goes lower than 23 feet TVA Response:
- 1. As discussed with the NRC during the RAI clarification teleconference on April 25, 2016, valve/equipment line-ups are procedurally controlled in accordance with equipment-specific operating procedures.
2. Various groupings of ERCW boundary valves were evaluated, as described in section 3.2.3 of the enclosure to TVA's letter dated March 11, 2016, . Based on a number of criteria including valve classification (I.e., ASME Code Class, Appendix J), valve design, valve size, and operating experience, it is unlikely that any realistic boundary valve leakage would challenge the analytical accuracy of the ERCW system hydraulic model. The 100 gpm value referenced in section 3.2.3 is an unrealistically high value for valve leakage. In accordance with TVA's Corrective Action Program (CAP) and the "Operability Determination Process and Limiting Conditions for Operation Tracking" procedure, an Immediate Determination of Operability (IDO) is required for any identified leakage from a process system, such as ERCW. As described in the
Enclosure
Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW) System, (TAC No. MF7450 And MF7451) Page E-4 of 6 referenced procedure, if system operability cannot be ensured via the IDO, additional evaluations may be necessary. If at any time during the Operability Determination Process, a reasonable assumption of operability is not supported, appropriate system-specific TS actions would be taken as necessary.
3. Refueling cavity water level is controlled by TS 3.9.7 and the 0-GO-9, "Refueling Procedure." 0-GO-9 requires the Fuel Handling Supervisor to ensure the Refueling cavity water level is greater than 23 feet above the reactor vessel flange within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to fuel movement per SR 3.9.7.1. If Refueling cavity water level less than 23 feet above the reactor vessel flange, level must be raised prior to moving irradiated fuel. Additionally, SR 3.9.7.1 is performed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per the Surveillance Frequency Control Program while fuel movement is in progress. 4.a. In accordance with TVA's CAP and the "Operability Determination Process and Limiting Conditions for Operation Tracking" procedure, an IDO is required for any identified leakage from a process system, such as ERCW. As described in the referenced procedure, if system operability cannot be ensured via the IDO, additional evaluations may be necessary. 4.b. If the Ultimate Heat Sink (UHS) temperature exceeds 79°F, TS 3.7.8, Required Action A2 could not be completed. Therefore, the station would enter TS 3.7.8, Condition C which would require the operating unit to be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. 4.c. LCO 3.9.6 requires "Two RHR loops to be OPERABLE, and one RHR loop shall be in operation," if the Outage Unit is in MODE 6 with the water level less than 23 feet above the top of reactor vessel flange. In this scenario, the RHR train associated with the affected shutdown board would not be operable. Condition A of TS 3.9.6 would be entered for less than the required number of RHR loops OPERABLE. Required Action A.2 requires Operations to "Immediately" initiate action to establish minimum 23 feet of water above the top of reactor vessel flange.
LCO 3.9.7 requires Refueling cavity water level to be maintained 23 ft above the top of reactor vessel flange, during movement of irradiated fuel assemblies within containment. Condition A of TS 3.9.7 would be entered for Refueling cavity water level not within limit. Required Action A.1 requires Operations to "Immediately" suspend movement of irradiated fuel assemblies within containment.
Enclosure
Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW) System, (TAC No. MF7450 And MF7451) Page E-5 of 6 RAI SBPB- 4 Background: The amendment proposes to change TS 3.7.8, "Essential Raw Cooling Water (ERCW)
System," to extend the allowed completion time to restore one ERCW System train to OPERABLE status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days for planned maintenance for SQN. These changes are needed to facilitate cleaning and inspection of the 6.9 kilovolt (kV) shutdown boards and associated 480 Volt (V) shutdown boards without requiring a dual unit shutdown. The LAR states that current 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is not adequate to safely clean and inspect a shutdown board and perform corrective maintenance, and a 7 day allowance is proposed.
However, justification is not clearly provided as to why a 7-day time limit is appropriate.
RAI: Describe in detail the timeline of planned cleaning and maintenance activities. Address any potential repairs that may require extra time. TVA Response: Based on the timeline provided below, it will take approximately 69 hours7.986111e-4 days <br />0.0192 hours <br />1.140873e-4 weeks <br />2.62545e-5 months <br /> to complete required maintenance activities and restore the 6.9 kV shutdown board. The potential repair activity with the longest duration has been identified as a bus replacement that would require an additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Shutdown Board Cleaning Timeline Activity Duration 1 Install Clearance 5 Hours 2 Prerequisite Maintenance Activities 12 Hours 3 As Found Inspections 2 Hours 4 As Found Megger Test 3 Hours 5 Cleaning and Maintenance 26 Hours 6 As Left Megger Test 4 Hours 7 Restoration Maintenance Activities 12 Hours 8 Release Clearance 5 Hours Total 69 Hours RAI: Justify why 7 days is needed, as opposed to a shorter timeline, such as 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. TVA Response: As discussed above, TVA estimates that the activities associated with the 6.9 kV shutdown boards can be completed in approximately 69 hours7.986111e-4 days <br />0.0192 hours <br />1.140873e-4 weeks <br />2.62545e-5 months <br /> with an
Enclosure
Request For Additional Information (RAI) Technical Specifications (TS) 3.7.8 Change - Essential Raw Cooling Water (ERCW) System, (TAC No. MF7450 And MF7451) Page E-6 of 6 additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for contingencies for a total of approximately 4.5 days. Seven days provides additional margin for unanticipated repair activities.
RAI: Clarify in the proposed TS 3.7.8 Condition "A" with a 7 day completion time is for planned electrical bus maintenance only, as stated in the request. TVA Response: TS 3.7.8 Condition A has been revised to clarify that this condition is for planned Shutdown Board maintenance. Revised mark-ups of TS 3.7.8 are provided as an attachment to this enclosure.
Attachment ERCW System 3.7.8 SEQUOYAH - UNIT 1 3.7.8-1 Amendment 334 XXX 3.7 PLANT SYSTEMS 3.7.8 Essential Raw Cooling Water (ERCW) System
LCO 3.7.8 Two ERCW System trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME -----------NOTES----------- 1. Only applicable when Unit 2 is defueled or in MODE 6 following defueled with Unit 2 refueling water cavity level 23 ft. above top of reactor vessel flange. 2. Only applicable when Ultimate Heat Sink temperature is 79ºF -------------------------------- A. One ERCW System train inoperable for planned Shutdown Board maintenance. A.1 ------------NOTES--------------- 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating," for emergency diesel generator made inoperable by ERCW System. 2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops
- MODE 4," for residual heat removal loops made inoperable by ERCW System. --------------------------------------
Restore ERCW System train to OPERABLE status.
AND A.2 Verify Ultimate Heat Sink temperature is 79ºF.
7 days
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter ERCW System 3.7.8 SEQUOYAH - UNIT 1 3.7.8-2 Amendment 334 XXX AB. One ERCW System train inoperable for reasons other than Condition A.
AB.1 --------------NOTES------------- 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"
for emergency diesel generator made inoperable by ERCW System.
2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4," for residual heat removal loops made inoperable by ERCW System. -------------------------------------
Restore ERCW System train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> BC. Required Action and associated Completion Time of Condition A or B not met.
BC.1 Be in MODE 3.
AND BC.2 Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
ERCW System 3.7.8 SEQUOYAH - UNIT 1 3.7.8-3 Amendment 334 XXX SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -------------------------------NOTE------------------------------ Isolation of ERCW System flow to individual components does not render the ERCW System inoperable. ---------------------------------------------------------------------
Verify each ERCW System manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program
SR 3.7.8.2 Verify each ERCW System automatic valve in the flow path servicing safety related equipment that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program
SR 3.7.8.3 Verify each ERCW System pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program
ERCW System 3.7.8 SEQUOYAH - UNIT 2 3.7.8-1 Amendment 327 XXX 3.7 PLANT SYSTEMS 3.7.8 Essential Raw Cooling Water (ERCW) System
LCO 3.7.8 Two ERCW System trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME --------------NOTES------------- 1. Only applicable when Unit 1 is defueled or in MODE 6 following defueled with Unit 1 refueling water cavity level 23 ft. above top of reactor vessel flange. 2. Only applicable when Ultimate Heat Sink temperature is 79ºF ------------------------------------- A. One ERCW System train inoperable for planned Shutdown Board maintenance. . A.1 --------------NOTES------------- 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating," for emergency diesel generator made inoperable by ERCW System. 2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops
- MODE 4," for residual heat removal loops made inoperable by ERCW System. -------------------------------------
Restore ERCW System train to OPERABLE status.
AND A.2 Verify Ultimate Heat Sink temperature is 79ºF
7 days
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter ERCW System 3.7.8 SEQUOYAH - UNIT 2 3.7.8-2 Amendment 327 XXX AB. One ERCW System train inoperable for reasons other than Condition A.
AB.1 --------------NOTES------------- 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"
for emergency diesel generator made inoperable by ERCW System.
2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4," for residual heat removal loops made inoperable by ERCW System. -------------------------------------
Restore ERCW System train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> BC. Required Action and associated Completion Time of Condition A or B not met.
BC.1 Be in MODE 3.
AND BC.2 Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
ERCW System 3.7.8 SEQUOYAH - UNIT 2 3.7.8-3 Amendment 327 XXX SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -------------------------------NOTE------------------------------ Isolation of ERCW System flow to individual components does not render the ERCW System inoperable. ---------------------------------------------------------------------
Verify each ERCW System manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program
SR 3.7.8.2 Verify each ERCW System automatic valve in the flow path servicing safety related equipment that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program
SR 3.7.8.3 Verify each ERCW System pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program