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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
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Text
- ~ Entergy Entergy Operations Inc .
17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6678 jdinell@entergy.com John C. Dinelli Site Vice President Waterford 3 W3F1-2017-0081 10 CFR 54.21 November 15, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Amendment 1 to License Renewal Application (LAA)
Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
REFERENCES:
- 1. Entergy Letter W3F1-2016-0012, "License Renewal Application, Waterford Steam Electric Station, Unit 3" dated March 23, 2016.
- 2. Entergy Letter W3F1-2016-0016, "License Renewal Application Drawings, Waterford Steam Electric Station, Unit 3" dated March 23, 2016
Dear Sir or Madam:
In accordance with 10CFR54.21 (b), each year following submittal of the license renewal application (LAA) and at least 3 months before scheduled completion of the NRC review an amendment to the renewal application must be submitted that identifies any changes to the current licensing basis that materially affects the content of the LAA including the Updated Final Safety Analysis Report (UFSAR) supplement. In the referenced letters, Entergy Operations, Inc (Entergy) applied for renewal of the Waterford 3 operating license. This letter provides Amendment 1 of the Waterford 3 license renewal application.
No new commitments have been identified in this letter.
I declare under penalty of perjury that the foregoing is true and correct. Executed on November 15,2017.
If you have any questions or require additional information, please contact John Jarrell, Regulatory Assurance Manager, at 504-739-6685.
W3Fl-2017-0081 Page 2 of2 Attachments:
- 1. Annual Update Amendment cc: Mr. Kriss M. Kennedy Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn : Dr. April Pulvirenti Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Attn : Phyllis Clark Washington, DC 20555-0001 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P.O. Box 4312 Baton Rouge, LA 70821-4312
Attachment 1 to W3F1-2017-0081 Annual Update Amendment Waterford 3 License Renewal Application to W3Fl-2017-0081 Page 1 of 12 Annual Update Amendment Waterford 3 License Renewal Application 1 INTRODUCTION In accordance with 10CFR54.21(b), each year following submittal of the license renewal application (LRA) and at least 3 months before scheduled completion of the NRC review an amendment to the renewal application must be submitted that identifies any changes to the current licensing basis (CLB) that materially affects the content of the license renewal application, including the Updated Final Safety Analysis Report (UFSAR) supplement.
Amendment 1 is based on review of documents potentially affecting the CLB during the period of April 1, 2015 through June 30, 2017.
2
SUMMARY
OF CHANGES The review concluded that certain sections of the LRA are affected by changes to the CLB documents and other related LRA reviews. The table below summarizes the changes listing the affected systems (if applicable), a description of the change (including effect on the LRA),
and the affected LRA section.
Affected LRA Sections Change LRA Section Affected EC 49686 EC replaces carbon steel pipe with stainless steel pipe in various locations. The LRA is affected by one change.
Sections of pipe leading to the flame arrestors on the A and Table 3.3.2-7 B diesel oil feed tanks (EGFMTNK0002A & B, ISOs V8.19-1001-15 & 16) was changed from CS to SS. The LRA requires revision to include stainless steel piping with an internal environment of air in system EGF. No other changes documented in this EC resulted in an LRA or report change.
to W3Fl-2017-0081 Page 2 of 12 Change LRA Section Affected EC 58410 EC permanently removed carbon steel drain piping and drain valves FW MVAAA174A, 175A in the main feedwater system. Drain piping was replaced with a stainless steel Table 3.4.2-3 pipe nipple and stainless steel socket welded cap with no valves in the line. Stainless steel piping is a new material/type combination for the main feedwater system and the LRA changed accordingly. In addition, a new line item for stainless steel "insulated piping components" with an air - outdoor (ext) environment is added.
Editorial change By letter W3F1 -2016-0074 dated December 7, 2016, Entergy revised LRA Section B.1.15, lnservice Inspection, by adding an enhancement. However, the NUREG-1801 consistency B.1 .15 statement included in LRA Section B.1.15 was not revised to indicate a program enhancement was added. The NUREG-1801 consistency statement in LRA Section B.1.15 is revised to reflect the addition of an enhancement to the program.
Editorial change The NUREG-1801 consistency statement in LRA Section B.1.10 B.1 .10, External Surfaces Monitoring Program , is revised to reflect that the program "will be" consistent with GALL after enhancements are incorporated.
to W3Fl-2017-0081 Page 3 of 12 Change LRA Section Affected EC 59101 EC authorizes installation of internal tube sleeves in dry cooling tower heat exchanger tubes (CC MTWR0001A, 1B).
Tubes have been sleeved in the area of degradation between the header and the end of the fins. The 12" long tube sleeves are mechanically expanded inside the existing tubes. Because they are expanded into the existing tubes, the 12" tube sleeves are only exposed to an internal environment (treated water). Loss of material and reduction of heat transfer line items exist in LRA Table 3.3.2-3 for Table 3.3.2-3 stainless steel tubes exposed to treated water (int) due to Table 2.3.3-3 another heat exchanger in the same system; therefore a revision to LRA Table 3.3.2-3 due to the sleeve internal environment is not required.
Tube plugs are intended to be temporary until the tube can be reclaimed ; however it is possible for plugs to remain permanent. Plugs in sleeved tubes are made of stainless steel (CPI/ Perma Plug Part# V-735-S) and plugs in un-sleeved tubes are made from carbon steel (Torq N' Seal) according to the EC (page 33 of 33). Therefore, line entries are included in the LRA for both carbon and stainless steel tube plugs. This change does not create a new material/environment combination.
to W3Fl-2017-0081 Page 4 of 12 Change LRA Section Affected EC 60103 EC documents NRC approval letter dated August 24, 2015 (Accession No. ML15217A143) amending Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program," by replacing the reference to Regulatory Guide 1.163, "Performance-Based Containment Leak Test Program," with a reference to Nuclear Energy Institute (NEI) 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J,"
as the implementation document used by Entergy Operations, Inc. (Entergy) to develop the WF3 performance-based leakage testing program in accordance with Option B, "Performance Based Requirements," of Title Section A.1 .7 10 of the Code of Federal Regulations Part 50, Appendix J, Section B.1.7 "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." The approval was in response to the Entergy LAR dated August 28, 2014 (ADAMS Accession No. ML14241A305), as supplemented by letters dated April 15, May 4, and June 18, 2015 (ADAMS Accession Nos. ML15105A615, ML15124A946, and ML15169A180, respectively).
This change permits the performance-based primary containment Integrated Leak Rate Testing (ILRT), also known as Type A test, intervals to be extended from no longer than 10 years to no longer than 15 years on a permanent basis, provided acceptable performance history and the other requirements of NEI 94-01, Rev. 2-A are satisfied .
to W3Fl-2017-0081 Page 5 of 12 Change LRA Section Affected EC 69791 EC replaces 2" carbon steel root instrument valves ACCMVAAA136A and ACCMVAAA137A with 1" stainless steel valves. The EC also replaces carbon steel piping leading to the root valves from penetrations with stainless steel (SS) piping. The valves, piping, and tubing are exposed to air-outdoor (ext) and raw water (int). The material change to stainless steel requires a change to LRA Table 3.3.2-3 Table 3.3.2-3 including a new line item for stainless steel "insulated piping components" with an air - outdoor (ext) environment. However, the raw water internal environment is already included for SS valves and tubing . Therefore line items will not be added for these. The changes by this EC do not require removal of any line items in LRA Table 3.3.2-
- 3. The same LRA changes are required as a result of EC 69792. EC 69792 made similar changes to the "B" train as this EC did to the "A" train.
EC 69792 EC replaces 2" carbon steel root instrument valves ACCMVAAA136B and ACCMVAAA137B with 1" stainless steel valves. The EC also replaces carbon steel piping leading to the root valves from penetrations with stainless steel (SS) piping. The valves, piping, and tubing are exposed to air-outdoor (ext) and raw water (int). The material change to stainless steel requires a change to LRA Table 3.3.2-3 Table 3.3.2-3 including a new line item for stainless steel "insulated piping components" with an air - outdoor (ext) environment. However, the raw water internal environment is already included for SS valves and tubing . Therefore line items will not be added for these. The changes by this EC do not require removal of any line items in LRA Table 3.3.2-
- 3. The same LRA changes are required as a result of EC 69791. EC 69791 made similar changes to the "A" train as this EC did to the "B" train.
Attachment 1 to W3Fl-2017-0081 Page 6 of 12 3 LRA CHANGES WF3 LRA changes are shown below. Additions are shown with underline and deletions with strikethrough.
Table 3.3.2-7 Emergency Diesel Generator System Summary of Aging Management Evaluation Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless steel Air - outdoor Cracking Internal Surfaces --- --- § boundary ilo.tl in Miscellaneous Piping and Ducting Components Piping Pressure Stainless steel Air - outdoor Loss of material Internal Surfaces --- --- § boundary (int) in Miscellaneous Piping and Ducting Components Piping Pressure Stainless steel Air - outdoor Cracking External Surfaces VII.H1 .AP-209 3.3.1-4 8 boundary (ext) Monitoring
.E.iQing Pressure Stainless steel Air - outdoor Loss of material External Surfaces VII.H2.AP-221 3.3.1-6 8 boundary (ext) Monitoring
Attachment 1 to W3Fl-2017-0081 Page 7 of 12 Table 3.4.2-3 Main Feedwater System Summary of Aging Management Evaluation Table 3.4.2-3: Main Feedwater System Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless steel Air - outdoor Cracking External Surfaces Vlll.01 .SP-1 18 3.4.1-2 8 boundary (ext) Monitoring Piping Pressure Stainless steel Air - outdoor Loss of material External Surfaces Vlll.01 .SP-127 3.4.1-3 8 boundary (ext) Monitoring Insulated piping Pressure Stainless steel Air - outdoor Cracking External Surfaces Vlll.01 .S-402 3.4.1-63 8 components boundary (ext) Monitoring Insulated piping Pressure Stainless steel Air - outdoor Loss of material External Surfaces Vlll.01 .S-402 3.4.1-63 8 components boundary (ext) Monitoring Piping Pressure Stainless steel Treated water Cracking Water Chemistry Vlll.01 .SP-88 3.4.1-11 A, 401 boundary > 140°F (int) Control - Primary and Secondary Piping Pressure Stainless steel Treated water Cracking - fatigue TLAA-metal VII.E1.A-57 3.3.1 -2 g boundary > 140°F (int) fatigue
.E.iQing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.01 .SP-87 3.4.1-16 A, 401 boundary > 140°F (int) Control - Primary and Secondary
Attachment 1 to W3Fl-2017-0081 Page 8 of 12 Table 3.3.2-3 Component Cooling and Auxiliary Component Cooling Water System Summary of Aging Management Evaluation Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Programs Item Item Notes OCT Tube Plug Pressure Stainless steel Treated water Loss of material Water Chemist!}'. VII.C2.A-52 3.3.1-49 6 boundary (int) Control - Closed Treated Water Systems OCT Tube Plug Pressure Stainless steel Air - outdoor Cracking External Surfaces VII.C1 .AP-209 3.3.1-4 6 boundary (ext) Monitoring OCT Tube Plug Pressure Stainless steel Air - outdoor Loss of material External Surfaces VII.C1 .AP-221 3.3.1-6 6 boundary (ext) Monitorin_g OCT Tube Plug Pressure Carbon steel Treated water Loss of material Water Chemist!}'. VII.C2.AP-202 3.3.1-45 6 boundary (int) Control - Closed Treated Water Systems OCT Tube Plug Pressure Carbon steel Air - outdoor Loss of material External Surfaces VII.H1 .A-24 3.3.1-80 .Q boundary (ext) Monitoring Insulated 12i12ing Pressure Stainless steel Air - outdoor Cracking External Surfaces VII.C1 .A-405 3.3.1-132 6 com12onents boundary (ext) Monitoring Insulated 12i12ing Pressure Stainless steel Air - outdoor Loss of material External Surfaces VII.C1 .A-405 3.3.1-132 6 com12onents boundary (ext) Monitoring Pi12ing Pressure Stainless steel Air - outdoor Cracking External Surfaces VII.C1 .AP-209 3.3.1-4 6 boundary (ext) Monitoring Pi12ing Pressure Stainless steel Air - outdoor Loss of material External Surfaces VII.C1 .AP-221 3.3.1-6 6 boundary (ext) Monitoring
Attachment 1 to W3Fl-2017-0081 Page 9 of 12 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Programs Item Item Notes P.iQing Pressure Stainless steel Raw water {int} Loss of material Service Water VII.C1 .A-54 3.3.1-40 8 bounda[Y lntegrit~
Valve bod~ Pressure Stainless steel Air - outdoor Cracking External Surfaces VII.C1 .AP-209 3.3.1-4 8 bounda[Y (ext} Monitoring Valve bod~ Pressure Stainless steel Air - outdoor Loss of material External Surfaces VII.C1 .AP-221 3.3.1-6 8 bounda[Y {ext} Monitoring Tubing Pressure Stainless steel Air - outdoor Cracking External Surfaces VII.C1 .AP-209 3.3.1-4 8 boundar~ (ext} Monitoring Tubing Pressure Stainless steel Air - outdoor Loss of material External Surfaces VII.C1 .AP-221 3.3.1-6 8 boundar~ (ext} Monitoring to W3Fl-2017-0081 Page 10 of 12 Table 2.3.3-3 Component Cooling and Auxiliary Component Cooling Water Systems Components Subject to Aging Management Review Component Type Intended Function OCT Tube Plug Pressure boundary B.1.15 lnservice Inspection NUREG-1801 Consistency The lnservice Inspection Program, with enhancement. will be consistent with the program described in NUREG-1801,Section XI.M1, ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD.
8.1.10 External Surfaces Monitoring NU RE G-1801 Consistency The External Surfaces Monitoring Program, with enhancements, j.s will be consistent with the program described in NUREG-1801,Section XI.M36, External Surfaces Monitoring of Mechanical Components, as modified by LR-ISG-2011-03, Changes to the Generic Lessons Learned (GALL) Report Revision 2 Aging Management Program XI.M41, "Buried and Underground Piping and Tanks," and LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion under Insulation.
to W3F1-2017-0081 Page 11 of 12 Appendix A A.1 AGING MANAGEMENT PROGRAMS A.1. 7 Containment Leak Rate Program The Containment Leak Rate Program consists of tests performed in accordance with the regulations and guidance provided in 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," Option B; R.G 1.163, "Performanoe Based Containment Leak Testing Program"; NEI 94-01 Revision 2-A, "Industry Guideline for Implementing Performance-Based Options of 10 CFR Part 50, Appendix J"; and ANSI/ANS 56.8, "Containment System Leakage Testing Requirements."
Three types of tests are performed under Option B. Type A tests are performed to determine the overall primary containment integrated leakage rate at the loss of coolant accident peak containment pressure. Performance of the integrated leakage rate test (ILRT) per 10 CFR Part 50, Appendix J, Option B, demonstrates the leak-tightness and structural integrity of the containment. Type B and Type C containment local leakage rate tests (LLRTs), as defined in 10 CFR Part 50, Appendix J, are intended to detect local leaks and to measure leakage across each pressure-containing or leakage-limiting boundary of containment penetrations. Type B and Type C leakage rate tests Containment leakage rate tests are performed at frequencies in accordance with the provisions of 10 CFR Part 50, Appendix J, Option B. Type A tests are performed at frequencies no longer than 15 years in accordance with 10 CFR Part 50, Appendix J, Option B, based upon the criteria in NEI 94-01, Revision 2-A.
to W3Fl-2017-0081 Page 12 of 12 Appendix B B.1 Aging Management Programs and Activities B.1. 7 Containment Leak Rate Program Description The Containment Leak Rate Program consists of tests performed in accordance with the regulations and guidance provided in 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," Option B; RG 1.163, "Periormance Based Containment Leak Testing Program"; NEI 94-01, Revision 2-A.
"Industry Guideline for Implementing Performance-Based Options of 10 CFR Part 50, Appendix J"; and ANSI/ANS 56.8, "Containment System Leakage Testing Requirements."
The Containment Leak Rate Program provides for detection of pressure boundary degradation due to aging effects such as loss of leakage tightness, loss of material, cracking, loss of sealing, or loss of preload in various systems penetrating containment. The program also provides for detection of age-related degradation in material properties of gaskets, 0-rings, and packing materials for the containment pressure boundary access points .
Three types of tests are performed under Option B. Type A tests are performed to determine the overall primary containment integrated leakage rate at the loss of coolant accident peak containment pressure. Performance of the integrated leakage rate test (ILRT) per 10 CFR Part 50, Appendix J, Option B demonstrates the leak-tightness and structural integrity of the containment. A general visual examination of the accessible interior and exterior areas of the steel containment vessel is performed prior to any ILRT during a period of reactor shutdown (refueling outages) and during two subsequent refueling outages before the next Type A test. The ILRT is performed at the frequency specified in 10 CFR Part 50, Appendix J, Option 8 1 based upon the criteria in NEI 94-01, Revision 2-A. Type Band Type C containment LLRTs, as defined in 10 CFR Part 50, Appendix J, are intended to detect local leaks and to measure leakage across each pressure-containing or leakage-limiting boundary of containment penetrations. LLRTs are performed at frequencies in accordance with the provisions of 10 CFR Part 50, Appendix J, Option B.