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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARW3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections ML21175A3622021-06-24024 June 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML21148A1042021-05-28028 May 2021 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program W3F1-2021-0032, Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-05-21021 May 2021 Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2021-0027, Supplement to Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-04-0808 April 2021 Supplement to Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4b W3F1-2021-0026, Open Item Response, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-03-19019 March 2021 Open Item Response, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2021-0003, Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B2021-02-0808 February 2021 Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B W3F1-2021-0002, Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-22022 January 2021 Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2020-0017, Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2020-03-12012 March 2020 Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification W3F1-2019-0073, (Waterford 3) - License Amendment Request to Revise Technical Specification 3.8.1.1 Surveillance Requirements2019-10-24024 October 2019 (Waterford 3) - License Amendment Request to Revise Technical Specification 3.8.1.1 Surveillance Requirements W3F1-2019-0062, License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2019-09-20020 September 2019 License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2019-0047, Application for Technical Specification Change to Control Room Air Conditioning System2019-08-27027 August 2019 Application for Technical Specification Change to Control Room Air Conditioning System CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 W3F1-2018-0043, Amendment 2 to License Renewal Application2018-07-30030 July 2018 Amendment 2 to License Renewal Application W3F1-2018-0031, Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components2018-06-13013 June 2018 Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components W3F1-2018-0025, (Waterford 3) - Supplemental Information Supporting the License Amendment Request Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update2018-05-17017 May 2018 (Waterford 3) - Supplemental Information Supporting the License Amendment Request Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update W3F1-2018-0014, License Amendment Request for Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components2018-04-12012 April 2018 License Amendment Request for Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components W3F1-2017-0050, License Amendment Request - Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update2018-03-26026 March 2018 License Amendment Request - Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update W3F1-2018-0011, License Amendment Request to Update the Results for the Inadvertent Loading of a Fuel Assembly Into the Improper Position (Fuel Assembly Misload) Event2018-03-0808 March 2018 License Amendment Request to Update the Results for the Inadvertent Loading of a Fuel Assembly Into the Improper Position (Fuel Assembly Misload) Event W3F1-2017-0067, License Amendment Request to Remove Technical Specification 3/4.3.2 Table 4.3-2 Note 3 Exemption for Testing Relays K114, K305, and K3132017-12-0606 December 2017 License Amendment Request to Remove Technical Specification 3/4.3.2 Table 4.3-2 Note 3 Exemption for Testing Relays K114, K305, and K313 W3F1-2017-0065, License Amendment Request for Use of RAPTOR-M3G Code for Neutron Fluence Calculations2017-11-28028 November 2017 License Amendment Request for Use of RAPTOR-M3G Code for Neutron Fluence Calculations W3F1-2017-0081, Amendment 1 to License Renewal Application (Laa)2017-11-15015 November 2017 Amendment 1 to License Renewal Application (Laa) ML17268A2132017-09-21021 September 2017 ISFSI, River Bend Station Unit 1 & ISFSI, Waterford 3 Steam Electric Station & ISFSI, Grand Gulf Nuclear Station & ISFSI, Application for Order Approving Transfers of Licenses and Conforming License Amendments W3F1-2017-0025, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2017-03-28028 March 2017 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. W3F1-2016-0055, License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System (ESFAS) Subgroup Relays to the Surveillance Frequency Control Program2016-09-0101 September 2016 License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System (ESFAS) Subgroup Relays to the Surveillance Frequency Control Program W3F1-2016-0036, Application to Revise Technical Specifications to Adopt TSTF-545, Rev 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code2016-07-25025 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Rev 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code W3F1-2016-0049, Supplement to the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-07-12012 July 2016 Supplement to the Risk-Informed Surveillance Requirements License Amendment Request (LAR) ML16088A3312016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 1 of 9) ML16088A3252016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 3 of 9) W3F1-2016-0012, License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 9 of 9)2016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 9 of 9) ML16088A3292016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 7 of 9) ML16088A3282016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 6 of 9) ML16088A3272016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 5 of 9) ML16088A3262016-03-23023 March 2016 License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 4 of 9) W3F1-2015-0040, License Amendment Request to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-07-0202 July 2015 License Amendment Request to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 W3F1-2015-0037, License Amendment Request, Cyber Security Plan Implementation Schedule2015-06-29029 June 2015 License Amendment Request, Cyber Security Plan Implementation Schedule ML15170A1262015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 5 of 5 ML15170A1252015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 4 of 5 W3F1-2015-0006, Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part2015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 3 of 5 ML15170A1232015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 2 of 5 ML15170A1222015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 1 of 5 W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years ML14217A4962014-08-0404 August 2014 Attachment 1 - W3F1-2014-0005 - Waterford Steam Electric Station, Unit 3, Analysis of Proposed Operating License Change, Section 4 Thru 6, Including Attachment 2 and 3 2023-07-26
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21148A0522021-06-0808 June 2021 Correction to License Amendment 214 Request to Support Next Generation Fuel; Review and Approval of Revised ECCS Performance Analysis; and Review and Approval of Supplement to the ECCS Performance Analysis ML21116A1432021-04-26026 April 2021 (Waterford 3) - Revision to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML20148M1062020-06-22022 June 2020 Corrections to Technical Specifications Issued in Amendments Nos. 102 and 225 and with the Renewed License ML20113E8362020-04-23023 April 2020 Summary of March 19, 2020, Category 1 Public Meeting with Entergy Operations Inc. a Planned LAR to Install Digital Systems in Accordance with Di&C ISG-06 Revision 2, Licensing Processes at Waterford Steam Electric Station ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule W3F1-2016-0010, Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-03-0303 March 2016 Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR) ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15244B3862015-09-0303 September 2015 Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power ML15217A1432015-08-24024 August 2015 Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015 Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual ML14321A7132014-12-10010 December 2014 Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications W3F1-2012-0084, Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink2012-10-0808 October 2012 Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink W3F1-2012-0028, Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. ML1125103192011-09-20020 September 2011 Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report ML1109501232011-04-0404 April 2011 Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page ML1021001582010-09-13013 September 2010 Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions ML1021504662010-09-13013 September 2010 Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition2010-08-12012 August 2010 Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System.2010-07-20020 July 2010 License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System. 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References ML1011100352010-04-22022 April 2010 Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program2010-02-22022 February 2010 License Amendment Request, Technical Specification Change Regarding Steam Generator Program ML1005504632010-02-22022 February 2010 Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009 License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-06-0303 June 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 ML0819904722008-07-30030 July 2008 License and Technical Specification Pages, Issuance of Amendment No. 216, Modify Diesel Generator Fuel Oil Testing Surveillance Requirements ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis ML0803800062008-04-16016 April 2008 License Page 4 and Technical Specification Page 5-5, Issuance of Amendment No. 215 Use of Optimized ZIRLO-TM Fuel Rod Cladding ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis ML0804401272008-02-12012 February 2008 2/12/2008 E-mail from Licensee Enclosing Markup of Technical Specification Page 5-5, Supplement to 4/24/2007 License Amendment Request Use of Optimized ZIRLO-TM Fuel Rod Cladding W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability ML0711603482007-04-24024 April 2007 License Amendment Request to Allow the Use of Optimized Zirlo Fuel Rod Cladding ML0706803372007-03-19019 March 2007 Tech Spec Pages for Amendment 212 Reactor Coolant System Leakage Detection Instrumentation ML0703704312007-02-0606 February 2007 Technical Specifications, Issuance of Amendment No. 211 to Facility Operating License Removal of Vendor Recommended Diesel Generator Surveillance Requirement 2023-07-26
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Text
Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6715 Fax 504-739-6698 jkowale@entergy.com Joseph A. Kowalewski Vice President, Operations Waterford 3 W3F1-2010-0011 February 22, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Amendment Request Technical Specification Change Regarding Steam Generator Program Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Pursuant to 1 OCFR50.90, Entergy Operations, Inc. (Entergy) hereby requests a license amendment to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications (TS). The proposed amendment will modify TS 6.5.9, "Steam Generator (SG)
Program," and TS 6.9.1.5, "Steam Generator Tube Inspection Report" to eliminate currently allowed SG tube alternate repair criteria and to modify the SG tube inservice inspection frequency.
Entergy will be replacing the two Waterford 3 steam generators (SGs) during the 1 7 th refueling outage which will commence in the spring of 2011. The existing Waterford 3 SG Program under TS 6.5.9 contains an alternate repair criterion for SG tube inspections that is no longer applicable to the replacement SGs. The replacement SGs will contain new thermally treated Alloy 690 tubing material which will have no tube inspection limitations that will require additional revision to the Waterford 3 Steam Generator Program. Additionally, with the new Alloy 690 thermally treated SG tubing, inservice inspection frequencies may be extended beyond that currently allowed. Therefore, this request is only to eliminate the alternate SG tubing repair criterion that is not applicable to the replacement SGs and to incorporate SG tube inspection frequencies consistent with TSTF-449-A.
A description of the proposed change is provided in Attachment 1. A markup of the affected TS pages is contained in Attachment 2. Associated changes to the TS Bases being controlled under the Waterford 3 TS Bases Control Program are provided for information in Attachment 3.
The proposed change has been evaluated in accordance with 10CFR50.91(a)(1) using criteria in 10CFR50.92(c) and it has been determined that the changes involve no significant hazards consideration.
The proposed change involves no new commitments.
W3F1-2010-001 1 Page 2 Entergy requests approval of the proposed amendment by February 19, 2011. Once approved, the amendment shall be implemented prior to the first SG tube inservice inspection for the replacement SGs.
Please contact Robert Murillo, Manager, Licensing at 504-739-6715 if there are any comments regarding this submittal.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 22, 2010.
Sincerel JA sab Attachments:
- 1. Analysis of Proposed Technical Specification Change
- 2. Proposed Technical Specification Changes (mark-up)
- 3. Proposed Technical Specification Bases Changes (mark-up for information only)
W3F1-2010-0011 Page 3 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station, Unit 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam MS 0-07 D1 Washington, DC 20555-0001 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library 95 Glastonbury Blvd.
Suite 300 Glastonbury, CT 06033-4443 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817
'Morgan, Lewis & Bockius LLP Attn: T. C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004
Attachment I to W3FI-2010-0011 Analysis of Proposed Technical Specification Change to W3F1-2010-0011 Page 1 of 6
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-38 for the Waterford Steam Electric Station, Unit 3 (Waterford 3). Entergy will be replacing the two Waterford 3 steam generators (SGs) during the 1 7 th refueling outage which will contain SG tubes having Alloy 690 Thermally Treated (TT) material. The Waterford 3 Technical Specifications (TS) 6.5.9, "Steam Generator (SG) Program," and TS 6.9.1.5, "Steam Generator Tube Inspection Report" contain a SG tube alternate repair criterion that is only applicable to original SGs. Therefore, this amendment request will propose the removal of the alternate repair criterion which will not be applicable to the replacement SGs. Additionally with the replacement of the SGs with new Alloy 690 TT material, the SG tube inspection frequency is being extended after the initial inspection post-SG replacement. No other changes to the Waterford Steam Generator Program TSs are being requested as a result of the replacement SGs.
2.0 PROPOSED CHANGE
The proposed modification to TS 6.5.9 and 6.9.1.5 will remove currently approved alternate repair criteria applicable to the original SGs and modify the SG tube inspection frequencies in the Waterford 3 Steam Generator Program for the new SG tube material. These changes will be consistent with Technical Specification Task Force (TSTF)-449-A, Revision 4 (Reference 1). The Waterford 3 SG Program contains one alternate repair criterion. This criterion excludes inspection and repair of the bottom portion of the SG tube within the hot leg tubesheet region to only require inspections of the upper portion of the tube within the hot-leg tubesheet region. The following proposed TS changes will remove inspection, flaw acceptance, and reporting requirements associated with this alternate repair criterion. These changes are contained in Attachment 2 of this submittal.
- Revise TS 6.5.9.c to remove the sentence which states: "The following alternate tube repair criteria may be applied as an alternative to the 40% depth based criteria".
- Delete TS 6.5.9.c.1 in its entirety which allows flaws located greater than 10.6 inches below the bottom of the hot leg expansion transition to remain in service.
Revise TS 6.5.9.d to remove discussion regarding the alternate repair criterion. The wording in this section is being revised to be consistent with TSTF-449-A.
- Revise TS 6.5.9.d.2 to replace the current sequential SG tube inspection period frequency for Alloy 600 mill annealed tubing to that for new Alloy 690 TT material.
" Revise TS 6.9.1.5.g to remove "...assessment of accident induced leakage from all tubesheet indications..." since this was added to address the alternate repair criterion.
The following changes are being proposed to the TS Bases as reflected in Attachment 3.
Since TS Bases changes are controlled by the Waterford 3 TS Bases Control Program, they are provided for information only.
- Revise TS Bases 3/4.4.4 under Limiting Conditions for Operation, to remove the discussion regarding tubesheet inspection depth as part of the definition of a SG tube.
The wording in this section is being revised to be consistent with TSTF-449-A. i
Attachment 1 to W3F1-2010-001 1 Page 2 of 6
- Delete Reference 7 of TS Bases 3/4.4.4 which is associated with WCAP-16208-P that was the basis for the tubesheet inspection depth alternate repair criterion.
3.0 BACKGROUND
In response to Generic Letter 2004-01 (Reference 2), Entergy determined that the Waterford 3 SG tube inspection scope was not consistent with the NRC position for performing tube inspections within the tubesheet region of the SG. As a result, Entergy.
committed to modify the Waterford-3 TSs to include a specific limitation for tubesheet depth inspection associated with the existing SGs. In letter dated March 15, 2005 (Reference 3),
Entergy sought a license amendment for Waterford 3 that proposed an alternate repair criterion that would allow the tube inspection depth to be based on a joint industry testing program which was reported in WCAP-1 6208-P (Reference 4). This report concluded that flaws below a defined inspection distance below the tubesheet expansion transition region do not pose a safety concern. Based on the results of WCAP-16208-P, Entergy determined that Waterford 3 could exclude inspections of the tube portion from 10.6 inches below the top of the tubesheet and would not affect SG operational safety. Any tube with degradation within the tubesheet above this inspection distance would be plugged upon detection. The NRC approved this license amendment request including supplements in Waterford 3 License
,Amendment 207 dated August 26, 2006 (Reference 5).
Under a separate license amendment request by Entergy, the NRC approved Waterford 3 License Amendment 204 (Reference 6) which changed.the SG tube surveillance program to be consistent with the approach and format approved. by the NRC in TSTF-449-A. At the time of implementation of this change, the subsequent inspection frequency for SG tube inspections was based on having mill annealed Alloy 600, tubing (Alloy 600 MA). This amendment provided the current Waterford 3 SG Tube Integrity requirements in TS 3/4.4.4 and SG Program requirements in TS 6.5.9.
4.0 TECHNICAL ANALYSIS
The Alloy 600 MA tubing material in the original SGs has shown to be susceptible to primary water stress corrosion cracking (PWSCC). The Waterford 3 replacement SGs have been designed using Alloy 690 TT tubing. Based on extensive industry-wide testing, Alloy 690 TT materials have been determined to be the material of choice for reactor coolant system applications including SG tubing. Alloy 690 TT has been proven through both laboratory testing and operational experience to provide increased corrosion resistance compared to Alloy 600 MA. No steam generator tube degradation due to PWSCC has occurred in Westinghouse steam generators using Alloy 690 TT tube material. Each of the original Waterford 3 SGs contain 9350 vertical U-tubes having an outside diameter (OD) of 0.750 inches and a tube wall thickness of 0.048 inches. Each replacement SG will contain 8968 tubes having a tube OD of 0.750 inches and a tube wall thickness of 0.044 inches (rows 1 and 2) or 0.043 inches (rows 3 through 138).
Steam generator tube wear is considered to be the only degradation mechanism that has the potential to reduce tube life and tube integrity. The tube wear is typically caused by fretting between a tube and a neighboring object. Based on the replacement SG design, unacceptable tube wear is not expected. The replacement SGs include a number of features that minimize the potential for tube wear at the tube supports and the anti-vibration bars
Attachment 1 to W3F1-2010-0011 Page 3 of 6 (AVBs). Provisions to minimize the potential for wear include the spacing between the tube supports, the configuration of the broached hole through the support plate, the surface finish of the broached hole in the tube support plate, the clearance between the tube and the hole in
.the tube support plate, tube support plate material selection, and the configuration of the AVB assemblies. Based on the above design changes for the replacement SGs, Entergy believes that significant wear will be limited over the remaining life of the plant.
Therefore, Entergy is eliminating the current alternate repair criterion that is only applicable to the original SGs and is not proposing any additions for new or different alternate repair criteria. Even though not final, Entergy believes that the Regulatory Guide 1.121 (Reference 7) analyses will validate the current 40% tube repairlimit. The SG Program requirements for the structural integrity, accident induced leakage, and operational leakage performance criteria will be confirmed by design analyses which will be performed under the requirements of 10CFR50.59. Entergy also does not anticipate any other changes to the Waterford 3 Steam Generator Program technical specifications associated with the replacement SGs.
The current SG tube inspection frequency contained under TS 6.5.9.d.2 for subsequent tube inspections is based on having Alloy 600 MA tubing material. Since this material is more susceptible to stress corrosion cracking, the inspection frequency is based on a 60 effective full power month period. However, with the improved material design of the replacement SG tubing, the frequency of subsequent SG tube is justified. TSTF-449-A provides various SG tube inspection frequency options based on tubing material. Since the replacement SGs use the latest improved Alloy 690 TT materials, the inspection frequency can be extended. As a result, Entergy will be revising TS 6.5.9.d.2 to extend the inspection of 100% of the tubes to sequential periods of 144, 108, 72, and, thereafter, 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs.
In addition, inspect 50% of the tubes by the refueling outage nearest the, midpoint of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall operate for more than 72 effective full power months or three refueling outages (whichever is less) without being inspected.
Therefore, the scope of the proposed changes to the Waterford 3 Steam Generator-Tube Integrity and Steam Generator Program contained in the technical specifications will eliminate the existing alternate repair criterion that is not applicable to the replacement SGs and will extend the subsequent SG tube inspection period to conform with the SG Program.
requirements for the new tube materials under TSTF-449-A.
5.0 REGULATORY ANALYSIS
5.1 Applicable Regulatory Requirements/Criteria Entergy Operations, Inc. (Entergy) proposes to remove the steam generator (SG) tube alternate repair criteria that are contained in Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specification (TS) 6.5.9, "Steam Generator (SG) Program," and TS 6.5.1.5, "Steam Generator Tube Inspection Report." The Waterford 3 TSs contain one alternate repair criterion which is only applicable to the originalISGs. The original SGs are scheduled to be replaced in the spring 2011 refueling outage. Additionally, the allowed subsequent sequential SG tube inspection period after initial inspection is being extended based on replacement SGs that contain Alloy 690 Thermally Treated (TT) material. No other to W3F1-2010-0011 Page 4 of 6 changes to the Waterford 3 SG Program contained in the TSs are being proposed as a result of the replacement SGs. The proposed changes will revise the Waterford 3 TSs to the discussion contained in NRC approved Technical Specification Task Force (TSTF)-449-A, Revision 4 having no alternate repair criteria.
In conclusion, Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and does not affect systems, structures, and components described in the Waterford 3 Final Safety Analysis Report (FSAR).
5.2 No Significant Hazards Consideration Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10CFR50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change continues to implement the Waterford 3 Steam Generator Program performance criteria for tube structural integrity, accident induced leakage, and operational leakage for the replacement SGs. Meeting the performance criteria provides reasonable assurance that the replacement SG tubing will remain capable of fulfilling its specific safety function of maintaining reactor coolant system (RCS) pressure boundary integrity throughout each operating cycle and in the unlikely event of a design basis, accident.
The Steam Generator Tube Rupture (SGTR) is the primary accident analysis associated with SG tube integrity. The replacement SG tubing contains improved materials that will reduce the likelihood of tubing flaws. The proposed change to remove alternate repair criteria from the SG inspection program does not affect the design of the replacement SGs, their method of operation, operational leakage limits, or primary coolant chemistry controls. Therefore, the proposed change does not affect the probability of a SGTR accident. The SGs will be designed with substantial margin to burst. The SG tube inspection repair limit will also identify potential flaws before they become a safety concern. The extension of the SG tube inspection frequency after initial inspection is based on the low likelihood of having potential tube flaws and is considered to be an acceptable inspection period to preserve pressure boundary integrity. As a result, there will be no affect on the previous dose analysis reported in the FSAR and the consequences of any accident are unchanged.
Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
to W3F1-2010-0011 Page 5 of 6
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
Steam generator tube rupture events have already been postulated and analyzed in the Waterford 3 FSAR. The proposed change does not affect the design of the SGs, their method of operation, or primary or secondary coolant chemistry controls.
Additionally, the proposed amendment does not impact any other plant systems or components. The TSs have established SG tube inspection requirements which assure that potential tubing flaws will be detected prior to affecting tube integrity and the RCS pressure boundary. Therefore, the proposed change does not create the possibility of a new or different type of accident from any accident previously evaluated.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in.a margin of safety?
Response: No.
The structural integrity, accident induced leakage, and operational leakage performance criteria required by the Waterford 3 TSs provide substantial design margin for assuring SG tube integrity against the possibility of a SG tube pressure boundary failure. The proposed change removes an existing alternate repair criterion that is not applicable to the replacement SGs and establishes appropriate SG tube subsequent inspection periods consistent with the new SG tubing design. The replacement SGs will continue to meet their required performance criteria. The Waterford 3 SG tube inspection program will assure that this margin is maintained through the operational life of the plant.
Therefbre, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10CFR50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in'the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9). Therefore, pursuant to 10CFR51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
to W3F1-2010-0011 Page 6 of 6 6.0 PRECEDENCE Similar changes to remove alternate repair criteria as part of SG replacements have been previously sought and approved by other licensees. A recent example was that performed for Progress Energy's Crystal River Nuclear Plant which the NRC approved on May 29, 2009 (Reference 8).
7.0 REFERENCES
- 1. Technical Specification Task Force (TSTF)-449-A, "Steam Generator Tube Integrity",
Revision 4, May 5, 2006.
- 2. NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections",
August 30, 2004.
- 3. Proposed Technical Specification Change Regarding Tubesheet Inspection Depth for Steam Generator Tube Inspections, March 15, 2005 (W3FI-2005-0009). [ML050770200]
- 4. WCAP-16208-P, "NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions", Revision 0, October 2004.
- 5. NRC Amendment 207 issued to Entergy Operations on August 29, 2006, "Waterford Steam Electric Station, Unit 3 - Issuance of Amendment Re: Steam Generator Tube Inspections and Repair Criteria within the Hot-Leg Tubesheet Region" (TAC No.
MC6421). [ML062220137]
- 6. NRC Amendment 204 issued to Entergy Operations on July 31, 2006, "Waterford Steam Electric Station, Unit 3 - Issuance of Amendment Re: Steam Generator Tube Integrity" (TAC NO. MC7973). [ML062000169]
- 7. U. S. Nuclear Regulatory Commission Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes", August 1976.
- 8. NRC Amendment 234 issued to Progress Energy on May 29, 2009, "Crystal River Unit 3
-issuance of Amendment Regarding the Revision of the Steam Generator Portion of the Technical Specifications to Reflect the Replacement of the Steam Generators" (TAC No.
MD9547). [ML091100056]
Attachment 2 to W3F1-2010-0011 Proposed .Technical Specification Changes (mark-up) to W3F1-2010-0011 Page 1 of 3 ADMINISTRATIVE CONTROLS STEAM GENERATOR (SG) PROGRAM (Continued)
- b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational leakage.
- 1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary to secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.
- 2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG.
Primary to secondary leakage is not to exceed 540 gpd through any one SG.
- 3. The operational leakage performance criterion is specified in LCO 3.4.5.2, "Reactor Coolant System Operational Leakage."
- c. Provisions for SG tube repair criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged.
The~follcf~ , ~m tu e e rcpcir efitefie Fmy be applied as k9c alttorntive te the 0 1.Flaws leated gfeater them :19.6 irnckc5 blacw the bettaft of ihe het ice c if f h het log tubes~eet, wiLiehe~eF is le-Nr, ffiay-ftiiam ii logoxpn4in tznsition 9r !op ef the heilgtubeg ee4ieo, vvihe 4J'e, -ýti of-ihe hot fegth~~e*
Gf WATERFORD -UNIT 3 6-7b AMENDMENT NO. p84, 207 to W3F1-2010-0011 Page 2 of 3 ADMINISTRATIVE CONTROLS STEAM GENERATOR (SG) PROGRAM (Continued}) ,- ¢ . 44-
- d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed.
The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be pres go.h4ngth of the tube, fromI-j o the tube-to-tu esheet w ae tube outlet and that may satis the applica le tube repair criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d. 1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity Is maintained until the next SG inspection. An assessment of degradation shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 1. Inspect 100% of the tubes in each SG during the first refueling outage following SG replacement.
- 2. -Irtspectien*0% f-he-ube -t-sequent~afkper ode Gf60-o felntWA4uII-wer .
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- 3. If crack Indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichiever is less). If definitive information, such as from examination of a pulled ttabe, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indicatiion need not be treated as a crack.
- e. Provisions for monitoring operational primary to secondary leakage.
Inspect 100% of the tubes at sequential periods of 144, 108, 72, and, thereafter, 60 effective full power months. The first sequential period shall*
be considered to begin after the first inservice inspection of the SGs. In 9,
, addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by the refueling outage nearest the end'of the period. No SG shall operate for more than 72 effective full power months or three refueling outages (whichever is less) ,'*
r witnout being inspected.
WATERFORD - UNIT 3 6-7c AMENDMENT NO. 2204, 207 to W3F1-2010-0011 Page 3 of 3 ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued)
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131. concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiolodine limit.
6.9.1.5 STEAM GENERATOR TUBE INSPECTION REPORT A report shall be submitted within 180 days after the initial entry into HOT SHUTDOWN following completion of an inspection performed in accordance with the Specification 6.5.9, Steam Generator (SG) Program. The report shall include:
- a. The scope of inspections performed on each SG,
- b. Active degradation mechanisms found,
- c. Nondestructive examination techniques utilized' for each degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
- e. Number of tubes plugged during the inspection outage for each active degradation mechanism,
- f. Total number and percentage of tubes plugged to date,
- g. Thersults of condition rrjopitoriog,jincluoing the results of tube pulIsjo-s t.ý testing, and
- h. The effective plugging percentage for all plugging in each SG.
WATERFORD - UNIT 3 6-17a AMENDMENT NO., - .. i 6,,18, 2e2, 204, 207
Attachment 3 to W3FI-2010-0011 Proposed Technical Specification Bases Changes (Mark-up provided for information only) to W3F1-2010-0011 Page 1. of 2 For accidents that do not involve fuel damage, the primary coolant activity level is assumed to be equal to the LCO 3.4.7 RCS Specific Activity limits. For accidents that assume fuel damage, the primary coolant activity is a function of the amount of activity released from the damaged fuel.
The dose consequences of these events are within the limits of GDC 19 (Reference 2) and 10 CFR 50.67 (Reference 3). Steam generator tube,, integrity 50.36(c)(2)(ii). --
- satisfies Criterion 2 of 10 CFR
,-* . ,_ -,* - "" "' - - ' e-Limitinq Condition for Operation *j V ,"- . \v.,\t-A oLA>A.-. ,
- tRN 06-907. ch 1.9 The LCO requires that SG tube integrity be maintained. The LCO also requires that all SG tubes that satisfy the repair criteria be plugged in accordance with the Steam GeneratorProgram.
During a SG inspection, any inspected tube that satisfies the Steam GeneratorProgramrepair criteria is removed from service by plugging. Ifa tube was determined to satisfy the repair criterias but was not plugged, the tube may still have tube integrity. In the context of this Specification, a SG tube is defined as the entire length of the tube, including the tube walLXikdiOnh let ..QWhtthe tube-to-tubesheet weld at the tube outlet. The tube-to-tubesheet weld is not considered'part of the tube, PDDRNOG-G97. Ch, 49)
A SG tube has tube integrity when it satisfies the SG performance criteria. The SG performance criteria are defined in Specification 6.5.9, Steam GeneratorProgram,and describe acceptable SG tube performance. The Steam Generator Program also provides the evaluation process for determining conformance with the SG performance criteria.
There are three SG performance criteria: structural integrity, accident induced leakage, and operational leakage. Failure to meet anyone of these criteria is considered failure to meet the LCO.
The structural integrity performance criterion provides a margin of safety against tube burst or collapse under normal and accident conditions, and ensures structural integrity of the SG tubes under all anticipated transients included in the design specification. Tube burst is defined as, "The gross structural failure of the tube wall. The condition typically corresponds to an unstable opening displacement (e.g., opening area increased in response to constant pressure) accompanied by ductile (plastic) tearing of the tube material at the ends of the degradation." Tube collapse is defined as, "For the load displacement curve for a given structure, collapse occurs at the top of the load versus displacement curve where the slope of the curve becomes zero." The structural integrity performance criterion provides guidance on assessing loads that significantly affect burst or collapse. In that context, the term "significantly" is defined as "An accident loading condition other than differential pressure is considered significant when the addition of such loads in the assessment of the structural integrity performance criterion could cause a lower structural limit or limiting burst/collapse condition to be established." For tube integrity evaluations, except for circumferential degradation, axial thermal loads are classified as secondary loads. For circumferential degradation, the classification of axial thermal loads as primary or secondary loads will be evaluated on a case-by-case basis. The division between primary and secondary classifications will be based on detailed analysis and/or testing.
Structural integrity requires that the primary membrane stress intensity in a tube not exceed the yield strength for all ASME Code,Section III, Service Level A (normal operating conditions) and Service Level B (upset or abnormal conditions) transients included in the WATERFORD - UNIT 3 B 3/4 4-3a CHANGE NO. 46, 49 to W3F1-2010-0011 Page 2 of 2 The frequency of prior to entering HOT SHUTDOWN following a SG inspection ensures that the Surveillance has been completed and all tubes meeting the repair criteria are plugged prior to subjecting the SG tubes to significant primary to secondary pressure differential.
REFERENCES
- 1. NEI 97-06, Steam GeneratorProgramGuidelines.
- 2. 10 CFR 50 Appendix A, GDC 19.
- 3. 10 CFR 50.67.
- 4. ASME Boiler and Pressure Vessel Code,Section III, Subsection NB.
- 5. Draft Regulatory Guide 1.121, Basis for Plugging DegradedSteam GeneratorTubes, August 1976.
- 6. EPRI, PressurizedWater Reactor Steam GeneratorExamination Guidelines.
I WATERFORD - UNiT 3 B 3/4 4-3d CHANGE NO. 4-6,49 I.
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