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MONTHYEARML0215504372002-05-0808 May 2002 Unit 2 - Supplemental Information to Support Emergency Technical Specification (TS) Change 02-05, Steam Generator (SG) Inspecton Scope - TAC MB4994 Project stage: Supplement ML0213405952002-05-10010 May 2002 Amendment 266 Regarding Steam Generator Tube Inspection Scope & Safety Evaluation Project stage: Approval ML0234300252002-11-13013 November 2002 G20020651- Thomas Saporito Ltr 2.206 Sequoyah Unit 2, & San Onofre Units 2 and 3 Project stage: Other 2002-05-10
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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:Technical Specification
MONTHYEARCNL-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) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases 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-23-028, 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) CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML22145A1412022-05-16016 May 2022 Technical Specification Bases, Manual ML22125A1272022-05-0404 May 2022 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML22108A2822022-04-27027 April 2022 Summary of Regulatory Audit Regarding the License Amendment Request to Revise TS to Adopt TSTF 505, Rev. 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)2021-10-22022 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) 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-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2020-09-23023 September 2020 Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-072, Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03)2019-07-14014 July 2019 Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03) ML19151A5842019-05-31031 May 2019 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays ML17333A4012017-11-29029 November 2017 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-16-051, 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)2017-03-13013 March 2017 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-16-011, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)2016-03-11011 March 2016 Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01) CNL-15-128, Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8 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 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 ML15176A7182015-06-19019 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 6 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 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 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 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 5 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 82015-06-19019 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 7 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 CNL-14-176, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03)2014-12-0202 December 2014 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) ML14342B0042014-12-0101 December 2014 Cycle 19 - 180-Day Steam Generator Tube Inspection Report ML13193A0392013-07-0505 July 2013 Revisions to the Technical Requirements Manual and Specification Bases ML11249A0612011-08-31031 August 2011 Application for Temporary Change to TS to Allow Use of Penetrations in Shield Building Dome During Modes 1 Through 4;and Request for Specific Usage of Alternate Source Term Methodology for Calculating Radiation Doses Associated. ML11195A1172011-07-29029 July 2011 Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956) ML11129A1882011-05-0606 May 2011 TS 11-06, Emergency Technical Specification Change for One-Time Extension of Surveillance Requirements Associated with Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation ML1014701582010-05-24024 May 2010 Revisions to Technical Requirements Manual and Technical Specification Bases ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0833701212008-12-0101 December 2008 Revisions to the Technical Requirements Manual (TRM) and Technical Specification (TS) Bases (Unit 1 Revisions 31, 32, and 33; Unit 2 Revisions 30, 31 and 32) ML0710101532007-04-0202 April 2007 Additional Information for Technical Specification Change 05-09 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity and Deletion of License Condition ML0702500312007-01-12012 January 2007 Technical Specification (TS) Change 06-06 - Revised Steam Generator (SG) Voltage-Based Repair Criteria - Probability of Prior Cycle Detection (Popcd) ML0634700292006-12-0707 December 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information ML0635302012006-11-30030 November 2006 Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818 ML0635302082006-11-30030 November 2006 Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819 ML0622300952006-08-0202 August 2006 Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) ML0622301112006-08-0202 August 2006 Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) ML0621401022006-07-12012 July 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes 2023-09-20
[Table view] Category:Bases Change
MONTHYEARML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML22145A1412022-05-16016 May 2022 Technical Specification Bases, Manual CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)2021-10-22022 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) CNL-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2020-09-23023 September 2020 Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-19-072, Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03)2019-07-14014 July 2019 Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03) ML19151A5842019-05-31031 May 2019 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays ML17333A4012017-11-29029 November 2017 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-16-011, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)2016-03-11011 March 2016 Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01) 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, 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 82015-06-19019 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 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 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 5 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 82015-06-19019 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 7 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 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 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 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 CNL-15-128, Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8 ML15176A7182015-06-19019 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 6 of 8 CNL-14-176, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03)2014-12-0202 December 2014 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) ML14342B0042014-12-0101 December 2014 Cycle 19 - 180-Day Steam Generator Tube Inspection Report ML13193A0392013-07-0505 July 2013 Revisions to the Technical Requirements Manual and Specification Bases ML11249A0612011-08-31031 August 2011 Application for Temporary Change to TS to Allow Use of Penetrations in Shield Building Dome During Modes 1 Through 4;and Request for Specific Usage of Alternate Source Term Methodology for Calculating Radiation Doses Associated. ML1014701582010-05-24024 May 2010 Revisions to Technical Requirements Manual and Technical Specification Bases ML0833701212008-12-0101 December 2008 Revisions to the Technical Requirements Manual (TRM) and Technical Specification (TS) Bases (Unit 1 Revisions 31, 32, and 33; Unit 2 Revisions 30, 31 and 32) ML0710101532007-04-0202 April 2007 Additional Information for Technical Specification Change 05-09 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity and Deletion of License Condition ML0702500312007-01-12012 January 2007 Technical Specification (TS) Change 06-06 - Revised Steam Generator (SG) Voltage-Based Repair Criteria - Probability of Prior Cycle Detection (Popcd) ML0634700292006-12-0707 December 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information ML0621401022006-07-12012 July 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes ML0513102802005-04-27027 April 2005 Technical Specifications Change 04-06 - Relocation of Specifications in Accordance with Part 50.36 in Title 10 of the Code of Federal Regulations. ML0428600542004-09-30030 September 2004 Units 1 and 2 - Technical Specification Change No. 04-01 - New Specification for Loss of Power Instrumentation for Emergency Diesel Generator and Auxiliary Feedwater Actuation. ML0423804982004-08-12012 August 2004 Technical Specifications Change 03-11 Deletion of Vacuum Relief Flow Requirements from Auxiliary Building Gas Treatment System Surveillance Requirements L-87-009, Revisions to the Technical Requirements Manual (TRM) (Revisions 21, 22, 23, 24, 25, 26, and 27) and Technical Specification (TS) Bases (Unit 1 Revisions 22, 23, and 24; Unit 2 Revisions 22 and 23)2004-05-0505 May 2004 Revisions to the Technical Requirements Manual (TRM) (Revisions 21, 22, 23, 24, 25, 26, and 27) and Technical Specification (TS) Bases (Unit 1 Revisions 22, 23, and 24; Unit 2 Revisions 22 and 23) ML0407608862004-03-0505 March 2004 Technical Specifications (TS) Change 03-05, Physics Tests Exceptions and Refueling Operations. ML0330404062003-10-22022 October 2003 Technical Specification (TS) Change 03-12, Application for TS Improvement to Extend the Completion Time for Action a of TS 3/4.5.1, 'Accumulator,' Using the Consolidated Line Item Improvement Process (Cliip). ML0316108592003-06-0505 June 2003 TS Change No.03-08, Reactor Coolant System Heatup & Cooldown Curves ML0314903552003-05-19019 May 2003 Revised Information Regarding TS Change 02-07, One Time Frequency Extension for Type a Test Containment Integrated Leak Rate Test ML0313507612003-05-0909 May 2003 Tech Spec Change 01-09, Operations Involving Positive Reactivity Additions. ML0307902812003-03-13013 March 2003 TS Change 03-01, Revision of Boron Requirements for Cold Leg Accumulators & Refueling Water Storage Tanks ML0303401192003-01-29029 January 2003 Application for Technical Specification (TS) Change - Missed Surveillances Using the Consolidated Line Item Improvement Process (Revision 2) ML0229404772002-10-0404 October 2002 Seqouyah Units 1 & 2 Technical Specification (TS) Change No. 02-07, One-Time Frequency Extension for Type a Test (Containment Integrated Leak Rate Test (Cilrt). ML0215504372002-05-0808 May 2002 Unit 2 - Supplemental Information to Support Emergency Technical Specification (TS) Change 02-05, Steam Generator (SG) Inspecton Scope - TAC MB4994 2023-10-04
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Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 May 8, 2002 TVA-SQN-TS-02-05 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket No. 50-328 Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 2 - SUPPLEMENTAL INFORMATION TO SUPPORT EMERGENCY TECHNICAL SPECIFICATION (TS)
CHANGE NO. 02-05, STEAM GENERATOR (SG) INSPECTION SCOPE - TAC NO. MB4994 Enclosed is supplemental information that is provided to support NRC review and approval of the subject TS change.
The supplemental information is based on ongoing discussions with NRC staff and the staffs request regarding application of W* technology to the Unit 2 SGs.
Enclosure 1 provides supplemental information that contains a TVA commitment. As requested by NRC, the TVA commitment states that TVA will submit a SQN Unit 2 license amendment that applies W* methodology to the SQN Unit 2 SGs on a schedule to support SG inspections performed during the Unit 2 Cycle 12 refueling outage (the refueling outage is scheduled to begin October 26, 2003). Enclosure 2 provides supplemental information that provides a comparison of the SQN specific W* analysis (as contained in WCAP-13532, Revision 1) to the generic W* analysis (as contained in WCAP-14797, Revision 1). Enclosure 3 provides a revised TS page for the subject TS change.
Printed on recycTed paper
U.S. Nuclear Regulatory Commission Page 2 May 8, 2002 TVA has determined that the supplemental information does not affect the no significant hazards considerations associated with the subject TS change.
This emerging regulatory issue, as TVA understands it, concerns the NRC's opinion that additional rotating pancake probe inspections (below the top of tubesheet) are now a prerequisite for compliance with existing TS provisions, unless this TS change is granted. Nevertheless, since there is a common understanding that any tube degradation in this region, regardless of morphology, does not have a nexus to safety, TVA requests prompt approval of this amendment to avoid unnecessary restart delays. The current Mode 4 projection date remains as May 13.
There is a TVA commitment associated with this letter. This letter is being sent in accordance with NRC RIS 2001-05. If you have any questions about this change, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672.
Sincerely, James D. Smith Siue Licensing Supervisor Subscribed and sworn to before me on his 8th day of May Notary olnEic r c My Commission Expires October 9, 2A02 Enclosures
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNIT 2 DOCKET NO. 328 TVA COMMITMENT TVA will submit a license amendment for SQN Unit 2 that will apply W* technology to the Unit 2 steam generators on a schedule that supports steam generator inspections performed during the Unit 2 Cycle 12 refueling outage (the refueling outage is scheduled to begin October 26, 2003).
E1-I
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)
UNIT 2 WESTINGHOUSE COMPARISON OF SQN SPECIFIC W* ANALYSIS TO GENERIC W* ANALYSIS E2-1
Application of W* to Unit 2 Cycle 11 Sequoyah SG Tube Inspection The Tennessee Valley Authority (TVA) is utilizing the W* analysis (Reference 1) forSequoyah Nuclear Plant (SQN) Cycle 12 operation to eliminate consideration of indications below a specified distance within the tubesheet, referred to as the W* distance. SQN is not implementing the W* alternate repair criteria, (i.e., indications will be repaired on detection instead of being allowed to remain in service). W* criteria were also developed for generic application to Westinghouse Series 51 steam generators (SGs) (Reference 2). These criteria were reviewed and approved by the NRC staff for application at another plant. The generic criteria that were developed are not numerically the same as in the document developed specifically for SQN.
Moreover, the generic criteria differ in their scope of application.
The sections below discuss some of the features of the W* criteria and the effect of the differences between the generic development and the SQN-specific development. Detection of circumferential indications is the primary concern. A list of circumferential indications identified during the end of Cycle 11 inspection of the SQN SGs in and below the W* distance is provided in Table 1.
W* Background W* is the length of sound engagement of the tube within the tubesheet such that the force resisting expulsion from the tubesheet balances the force applied to the end of a presumed severed tube.
The value of W* is determined using applicable performance criteria relative to tube burst, expulsion from the tubesheet in this case, and relative to allowable leakage, relative to that established for alternate repair criteria (ARC). The structural performance criteria are that tube burst will not occur with a margin of 3 during normal operation and 1.4 during the most severe faulted event, a postulated steamline break (SLB) for SQN. The development of the W* criteria is based on balancing the forces resisting pull-out from the tubesheet, the cumulative reaction load, against the applied load from the internal pressure. These are explained further in the following paragraphs.
Applied Load The applied force comes from the internal pressure in the tube. At the U-bend there is a component of the primary-to-secondary differential pressure acting in the axial direction. For the development of the criteria it is also assumed that the tube is severed in the tubesheet so that the differential pressure acts on the entire cross section area of the tube as calculated using the outside diameter (OD) of the tube. The applied force, FA, is determined from the applied pressure, AP, and the outside diameter, D,, area, A, as:
FA = P A where, A= 4 D2 (1)
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Here, AP is the difference between the primary, Pp, and secondary pressure, Ps, at the top of the tubesheet, (i.e., Pp - Ps).
Reaction Load The reaction load in developing the W* length arises from friction between the tube and the tubesheet within the tubesheet hole. The friction force is the product of the normal force between the tube and the tubesheet and coefficient of friction between the tube and the tubesheet. The normal force arises or is affected by four sources:
- 1. The residual preload from the expansion process,
- 2. Differential thermal expansion between the tube and the tubesheet,
- 3. Internal pressure in the tube within the tubesheet, and
- 4. Dilation of the tubesheet holes from bowing of the tubesheet.
The first three items result in a compressive normal force between the OD of the tube and the ID of the tubesheet hole. The last item results in a reduction of the normal force near the top of the tubesheet and an increase in the normal force near the bottom of the tubesheet.
Determination of W* Length The calculation performed is to find the length, W*, that makes the following equality true between the resisting force on the left and the applied force on the right,
[t(Nx + NT + Np + No)= AP A (2) where Nx = The residual normal force from the expansion process, NT = The normal force from the differential thermal expansion, Np = The normal force due to the internal pressure in the tube, ND = The normal force resulting from dilation of the tubesheet hole, S= The coefficient of friction between the tube and the tubesheet.
The resisting forces are due to the interface pressure between the tube and the tubesheet. The actual force is the product of the interface pressure times the effective area of contact, the circumference of the tube times the length of contact. Conservative uncertainty adjustments are then made to the length of contact to determine W*. The diameter of the tube is constant, so an expression for the force per unit length is used and solved for the length,L. This means that each force term must be replaced by force per unit length term.
The solution for W* is then, W APA (3) j (FX + FT + Fp + FD)
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where W stands for the W* length and the letterF stands for the force per unit length of engagement. Each force per unit length term is then replaced by a corresponding pressure times circumference term, i.e.,
APA W= 11(Px + PT +P + PP + PD) nD.,
(4) where D, is the outside diameter of the expanded tube. Substituting for the cross section area
- yields, W = APD° (5) 4 (Px +PT +Pp +PD) for the determination of W, sans adjustments for uncertainties in measurement and end effects where the assumption of a severed tube has been made. The following points are to be noted:
"* The applied load term, the numerator is affected by changes in the operation of the plant. The value used for the generic document is larger than that for the plant specific application at SQN because of the use of a lower-bound secondary side pressure, hence the W* length would be expected to be less for SQN than that for the generic application.
"* The residual expansion pressure, Px, is not affected by changes in the operation of the plant.
However, different values have been determined and used in the two different documents. A bounding lower value was selected for use in the generic document. This contributed to the calculation of a larger value of the W* distance than for application at SQN.
" The thermal expansion term, PT, is affected by changes in the hot leg temperature, Thot. The hot leg temperature at SQN is greater than the value used for the generic determination, hence the value of W* for use at SQN should be less than the generic value.
" The differential pressure term, Pp, is affected by changes in the primary or secondary pressure.
The differential pressure term used for the SQN analysis is slightly smaller than the term used for the generic application for this term, assumed pressure in the crevice.
" The dilation term, PD, is also affected by changes in the primary or secondary pressure. The differential pressure acting across the tube sheet was assumed to be greater in the generic report than for the SQN specific application because of the selection of lower-bound secondary side pressure value. The dilation loss is proportional to the differential pressure, hence the W*
value determined for SQN would be expected to be less than the generic value.
" Finally, the coefficient of friction justified for the generic application is larger than that used for the SQN specific determination. Thus, the SQN determination is more conservative than the generic determination.
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Conservatism in SQN Inspection Distance
"* All indications identified are taken out of service by plugging.
" The 5.5" inspection length represents the most limiting length in the bundle. WCAP 13532, Rev. 1, allows for a shorter distance for the outer region of the SG bundle. SQN inspects all tubes in the bundle using the 5.5" length.
" The area of concern is the central region of the bundle where tubes would not be able to pull out without being restrained by contact with neighboring tubes, thus, the 5.1" pull out distance is very conservative.
" SQN Unit 2 has known denting at support plates which would further restrain tube pull out, and likely prevent the axial pressure load.
" A 0.7" tapered gap is assumed extending down from the bottom of the WEXTEX transition, which adds conservatism to the evaluation.
"* Bobbin coil examinations were performed over the full length of each tube in the bundle.
"* The circumferential cracks identified within the W* distance and below the W* distance during the inspection would satisfy the structural performance criteria even if evaluated as freespan indications.
"* Thot for Cycle 11 and planned for Cycle 12 is actually higher than the SQN-specific WCAP, which adds additional conservatism to the SQN determination ofW*.
"* Actual secondary side pressure is within 1 pound of the SQN-specific WCAP.
Discussion The effect of the differences in the application documents can be evaluated by considering each of the terms separately and by considering a combination of the terms. A listing of each of the terms and their expected effect is provided in Table 2. To consider the combination of the terms the ratio of a W* value developed for Sequoyah, Ws, to a W* value developed for generic application, WG, can be evaluated by treating per the following expression, WS =.G (PXG + PTG + PPG + PDG) APS (6)
WG ýtS (Pxs + PTs + PPs + PDs) AIP(
where the subscript S stands for Sequoyah and G stands for generic. The combination of the terms makes this a difficult process. Therefore, alternate calculations were performed.
References 1 and 2 document the following evaluation steps. Section 3 determines the Axial loading a tube must withstand, the most conservative scenario is for normal operating conditions times a factor of 3. Section 4 of the WCAP documents report on the determination of the W*
length based on the consideration that the radial contact pressure over the W* length times a static CAWINDOWS\Temporary Internet PIes\OLKB1 CSIVA vs Generic W-Star TVArl.doc 4 of 6
friction coefficient must equal the axial loading force determined above. The summation of four forces is used to determine the net radial contact pressure.
- 1. Residual radial contact force from the WEXTEX process.
- 2. Radial force from the difference in the coefficient for thermal expansion between the Alloy 600 tube and the low alloy tubesheet.
- 3. Radial contact force from the operating pressure difference the tube experiences during normal operation, (i.e., primary minus secondary side pressure).
- 4. The loss in interface pressure as a result of tubesheet hole dilation due to tubesheet flexure.
Both References add a 0.7-inch transition zone that goes from the bottom of WEXTEX transition. This derives from the analysis of the sample test specimens. A series of independent checking calculations of the required length of engagement were performed using a model originally developed for calculating the interface pressure when the radial interference was known. The results demonstrate reasonable consistency between the SQN specific and the generic calculation results. The qualitative effect of the changes are listed in Table 2. It is expected that the SQN specific W* should be less than the generic value because of the net effect of the changes. The independent considerations lead to the results similar to those presented in the WCAP. The conclusion is that the generic report should have reported results greater than those for SQN because ofconservatisms associated with a generic analysis.
Conclusions The Reference 1 determination of the W* length of 5.1" for application to the SQNSGs is considered to be valid. The differences between the SQN specific and the generic calculation values is the result of the conservative assumptions associated with performing a generic calculation, (e.g., extremely low secondary side pressure, which increases the applied load and the dilation of the tubesheet holes), additional pressure considered in the crevice, and the use of a lower bound residual expansion pressure. This later effect is almost negated by the use of the higher coefficient of friction. Nevertheless, the application of W* to the SQN SG tubes per the Reference 1 guidance is considered to be justified.
References
- 1. WCAP-13532 (Proprietary) & WCAP-13533 (Non-Proprietary), Revision 1. Sequoyah Units I and 2 W* Tube Plugging Criteriafor SG Tubesheet Region of WEXTEX Expansions.
Westinghouse Electric Company, Madison, PA. November, 1992.
- 2. WCAP-14797 (Proprietary) & WCAP-14797 (Non-Proprietary), Revision 1. Generic W*
Tube Plugging Criteriafor 51 Series Steam GeneratorTubesheet Region WEXTEX Expansions. Westinghouse Electric Company, Madison, PA. February, 1997.
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Table 1: Circumferential Indications in or below W* distance Note: The BWT is assumed to be TTS-0.3", so the W* distance extends from the TTS-0.3" to TTS-5.5", including NDE uncertainties.
SG Number of Type Location Comment Indications 2 1 ID Circ TTS-6.41" R37 C64 320 64% MD 4 5 ID Circ TTS-0.36" R12 C60 970 82% MD TTS-3.59" R15 C60 690 60% MD TTS-3.55" R18 C60 920 85% MD TTS-3.64" R20 C45 480 96% MD TTS-2.67" R24 C9 740 89% MD Table 2: Comparison of W* for Sequoyah SG Tubes Relative to Generic Information Item Analysis Term Sequoyah Generic Application of the Result
& Description WCAP-13532 WCAP-14797 Rev. 1 Rev. 1 1 AP, Applied Ps = 882 psia Ps = 760 psia Sequoyah W* < Generic W*
Pressure 2 Px, Residual PR = 935 psi PR = 693 psi Sequoyah W* < Generic W*
Pressure 3 PT, Thermal Thot = 608.5 0 F Thot = 590OF Sequoyah W* < Generic W*
Tightening 4 Pp, Pressure Ps = 882 psia Ps = 900 psia Sequoyah W* < Generic W*
Tightening 5 PD, Dilation SM-89-53 SM-96-39 Sequoyah W* < Generic W*
Loosening (Higher AP for generic) 6 1t, Friction 0.152 0.210 Sequoyah W* > Generic W*
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ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT UNIT 2 TECHNICAL SPECIFICATION (TS) CHANGE 02-05 REVISED PAGE E3-1
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria
- a. As used in this Specification:
- 1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 2. De-gradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
- 3. Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.
- 4. % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
- 5. Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
- 6. Plugginq Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness. Plugging limit does not apply to that portion of the tube that is not within the pressure boundary of the reactor coolant system (tube end up to the start of the tube-to-tubesheet weld). This definition does not apply to tube support plate intersections if the voltage-based repair criteria are being applied. Refer to 4.4.5.4.a.10 for the repair limit applicable to these intersections. For Cycle 11 and 12 operation, this definition does not apply for axial PWSCC indications, or portions thereof, which are located within the thickness of dented tube support plates which exhibit a maximum depth greater than or equal to 40 percent of the initial tube wall thickness. Refer to 4.4.5.4.a. 11 for the repair limits applicable to these intersections.
- 7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
- 8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg excluding the portion of the tube within the tubesheet below 5.5 inches (as measured from the top of the tubesheet).*
- 9. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
- This exclusion is for Unit 2, Cycle 12 operation only.
SEQUOYAH - UNIT 2 3/4 4-13 Amendment No. 181, 211, 213, 243, E3-2