|
---|
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:Response to Request for Additional Information (RAI)
MONTHYEARML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities 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 W3F1-2022-0049, 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 W3F1-2022-0015, 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. W3F1-2022-0009, 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 W3F1-2021-0050, 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 W3F1-2021-0041, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System2021-06-0202 June 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L W3F1-2020-0062, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62020-12-15015 December 2020 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 W3F1-2020-0043, Response to NRC Request for Additional Information Regarding License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2020-07-0606 July 2020 Response to NRC Request for Additional Information Regarding License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2020-0033, (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.8.1, A.C. Sources Operating2020-05-29029 May 2020 (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.8.1, A.C. Sources Operating CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary W3F1-2019-0056, Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-12019-07-31031 July 2019 Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1 W3F1-2019-0054, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-12019-07-22022 July 2019 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1 W3F1-2019-0040, Response to U. S. Nuclear Regulatory Commission Second Round Request for Additional Information Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side2019-07-11011 July 2019 Response to U. S. Nuclear Regulatory Commission Second Round Request for Additional Information Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Intern W3F1-2019-0039, (Waterford 3) - Response to Request for Additional Information Regarding Relief Request W3-ISI-0322019-07-0808 July 2019 (Waterford 3) - Response to Request for Additional Information Regarding Relief Request W3-ISI-032 W3F1-2019-0005, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update2019-02-15015 February 2019 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update W3F1-2019-0011, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Request WF3-RR-19-1 for Application of Dissimilar Metal Weld Full Structural Weld Overlay2019-02-0404 February 2019 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Request WF3-RR-19-1 for Application of Dissimilar Metal Weld Full Structural Weld Overlay W3F1-2019-0002, (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across2019-01-19019 January 2019 (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across W3F1-2018-0067, Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-0312018-11-19019 November 2018 Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-031 W3F1-2018-0059, (Waterford 3) - Response to NRC Request for Additional Information Regarding License Amendment Request to Update the Results for the Inadvertent Loading of a Fuel Assembly Into the Improper Position ...2018-10-18018 October 2018 (Waterford 3) - Response to NRC Request for Additional Information Regarding License Amendment Request to Update the Results for the Inadvertent Loading of a Fuel Assembly Into the Improper Position ... CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station W3F1-2018-0020, Responses to Request for Additional Information Set 18 Regarding the License Renewal Application2018-04-23023 April 2018 Responses to Request for Additional Information Set 18 Regarding the License Renewal Application ML18101A0962018-04-10010 April 2018 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2018007) and Request for Information W3F1-2017-0039, Responses to Request for Additional Information Set 17 Regarding the License Renewal Application2017-05-12012 May 2017 Responses to Request for Additional Information Set 17 Regarding the License Renewal Application W3F1-2017-0027, Responses to Request for Additional Information Set 16 Regarding the License Renewal Application2017-05-0202 May 2017 Responses to Request for Additional Information Set 16 Regarding the License Renewal Application ML17114A4322017-04-21021 April 2017 Responses to Request for Additional Information for the Environmental Review (SAMA Round 2) Regarding the License Renewal Application W3F1-2017-0026, Responses to Request for Additional Information Set 15 Regarding the License Renewal Application2017-04-11011 April 2017 Responses to Request for Additional Information Set 15 Regarding the License Renewal Application W3F1-2017-0023, Responses to Request for Additional Information Set 14 Regarding the License Renewal Application2017-03-30030 March 2017 Responses to Request for Additional Information Set 14 Regarding the License Renewal Application W3F1-2017-0015, Responses to Request for Additional Information Set 13 Regarding the License Renewal Application2017-03-16016 March 2017 Responses to Request for Additional Information Set 13 Regarding the License Renewal Application W3F1-2017-0018, Supplement to Response to RAI on License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System Subgroup Relays to Surveillance.2017-02-27027 February 2017 Supplement to Response to RAI on License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System Subgroup Relays to Surveillance. ML17054D2392017-02-23023 February 2017 Responses to Request for Additional Information Set 12 Regarding the License Renewal Application ML17024A2392017-02-0707 February 2017 Alternatives RAI-AL-3 Lanning 2014_Correspondence Lanning-Entergy to Buckley-Entergy ML17037D0172017-02-0707 February 2017 Aquatic Resources (AR) RAI-7 Lpl 1979_WF3 Demonstration Under Section 316(b) ML17038A2642017-02-0707 February 2017 Surface Water Resources (Sw)Rai SW-11 Usace NNOD-SP (Mississippi River) 796 Permit ML17034A3232017-02-0707 February 2017 Aquatic Resources (AR)- RAI AR-7 Ensr 2005_W1&2 PIC ML17038A2772017-02-0707 February 2017 Surface Water Resources (SW) RAI SW-11 Ldwf Letter of No Objection ML17030A1872017-02-0707 February 2017 Aquatic RESOURCES-RAI AR-6 LPDES Permit Modification_2008 ML17023A2682017-02-0707 February 2017 Air Quality RAI AQ-5 WF3 2004a_WF3 Air Permit 2520-00091-00 ML17037D0362017-02-0707 February 2017 Cumultive Impacts (Cu) RAI CU-1 Reasonably Foreseeable Future Projects within WF3 Area ML17037D0552017-02-0707 February 2017 Groundwater Resources (Gw) RAI GW-1 WF3 Groundwater Monitoring Program_Five-Year Review ML17038A4362017-02-0707 February 2017 Responses to Request for Additional Information for the Environmental Review ML17024A1702017-02-0707 February 2017 Alternatives RAI AL-1 Power Replacement Suitable Sites ML17018A1862017-02-0707 February 2017 Air Quality- RAI AQ-2 Temperature Analysis Mississippi River ML17037D2822017-02-0707 February 2017 Surface Water Resources (Sw)Rai SW-1 WF3 Surface Water Withdrawals_Discharges_2011-2015 ML17024A1932017-02-0707 February 2017 Alternatives RAI AL-3 - Enercon 2015b_Calc Supporting Section 07_01 Alternatives ML17024A2472017-02-0707 February 2017 Aquatic Resources RAI AR-4 -Entergy 2005_WF3 316(b) Proposal for Information Collection ML17038A2802017-02-0707 February 2017 Surface Water Resources (SW) RAI SW-11 U.S. Coast Guard Permit CG-2554.pdf 2024-01-12
[Table view] |
Text
Phil Couture Senior Manager Fleet Regulatory Assurance - Licensing 601-368-5102 W3F1-2022-0059 10 CFR 50.90 October 13, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 Waterford Steam Electric Station, Unit 3 NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38 By letter dated February 8, 2021 (Reference 1), as supplemented by letters dated April 8, 2021 (Reference 2), May 16, 2022 (Reference 3), and August 19, 2022 (Reference 4), Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) to permit the use of risk-informed completion times (RICTs) consistent with the methodologies presented in Technical Specification Task Force (TSTF) Traveler TSTF-505, Revision 2, "Provide Risk-Informed Extended Completion Times - Initiative 4b," and Nuclear Energy Institute (NEI) 06-09, Revision 0-A, "Risk-Informed Technical Specifications Initiative 4b: Risk-Managed Technical Specifications (RMTS) Guidelines."
On August 30, 2022, Entergy received a set of five questions via electronic mail (email) from the Nuclear Regulatory Commission (NRC) Electrical Engineering Branch (EEEB) and a request for a clarification call to discuss the questions. The questions were prepared by the EEEB to clarify concerns regarding the May 16, 2022 supplement to the TSTF-505 LAR. A conference call was subsequently held with the NRC EEEB on September 19 to provide the requested clarification.
Following the clarification call, the NRC and Entergy agreed to docket the responses to questions 2, 3, and 5. This submittal provides those responses.
The Enclosure of this letter provides a restatement of the three NRC EEEB questions followed by Entergy's responses. The Attachment to the Enclosure provides the changes to Table E.1-1; the complete table was previously provided in Reference 3. There were no changes to the table other than those indicated in the Attachment.
Entergy has reviewed the information supporting the No Significant Hazards Considerations and the Environmental Evaluations that were previously provided to the NRC in the Enclosure of the Reference 1 LAR. The information in this submittal does not alter the previous conclusions that Entergy Operations, Inc., 1340 Echelon Parkway, Jackson, MS 39213
W3F1-2022-0059 Page 2 of 3 the proposed changes present no significant hazards consideration and no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendments.
This letter contains no new regulatory commitments.
In accordance with 10 CFR 50.91(b)(1), "Notice for public comment; State consultation," a copy of this letter is being provided to the designated State Official.
Should you have any questions or require additional information, please contact Leia Milster, Regulatory Assurance Manager, Waterford 3, at 504-739-6250.
I declare under penalty of perjury, that the foregoing is true and correct. Executed on October 13, 2022.
Respectfully, Philip Digitally signed by Philip Couture Couture Date: 2022.10.13 16:10:00 -05'00' Phil Couture PC/cdm
Enclosure:
Response to NRC EEEB Questions 2, 3, and 5 Attachment to Enclosure - Proposed Changes to Table E.1-1
References:
- 1) Entergy letter to NRC, "Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B," (ADAMS Accession No. ML21039A648), dated February 8, 2021
- 2) Entergy letter to NRC, "Supplement to Application for Technical Specifications Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4b," (ADAMS Accession No. ML21098A262),
dated April 8, 2021
W3F1-2022-0059 Page 3 of 3
- 3) Entergy letter to NRC, "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 Initiative 4b,'" (ADAMS Accession No. ML22136A310),
dated May 16, 2022
- 4) Entergy letter to NRC, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505, (ADAMS Accession No. ML22231B160), dated August 19, 2022 cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford Steam Electric Station, Unit 3 NRC Project Manager Waterford Steam Electric Station, Unit 3 Louisiana Department of Environmental Quality
Enclosure W3F1-2022-0059 Response to NRC EEEB Questions 2, 3, and 5
W3F1-2022-0059 Enclosure Page 1 of 3 RESPONSE TO NRC EEEB QUESTIONS 2, 3, AND 5 By letter dated February 8, 2021 (Reference 1), as supplemented by letters dated April 8, 2021 (Reference 2), May 16, 2022 (Reference 3), and August 19, 2022 (Reference 4), Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) to permit the use of risk-informed completion times (RICTs) consistent with the methodologies presented in Technical Specification Task Force (TSTF) Traveler TSTF-505, Revision 2, "Provide Risk-Informed Extended Completion Times - Initiative 4b," and Nuclear Energy Institute (NEI) 06-09, Revision 0-A, "Risk-Informed Technical Specifications Initiative 4b: Risk-Managed Technical Specifications (RMTS) Guidelines."
On August 30, 2022, Entergy received a set of five questions via electronic mail (email) from the Nuclear Regulatory Commission (NRC) Electrical Engineering Branch (EEEB) and a request for a clarification call to discuss the questions. A conference call was subsequently held with the NRC EEEB on September 19 to provide the requested clarification. Following the clarification call, the NRC and Entergy agreed to docket the responses to questions 2, 3, and 5. These questions and Entergys responses are provided below.
EEEB Question 2 UFSAR Section 8.1.3 (see UFSAR page 8.3-1) describes the transfer scheme to energize ESF buses 3AB3-S and 3AB31-S. These swing buses have dual feeder breakers from the ESF buses that supply each of them implying that only buses 3AB3-S and 3AB31-S are de-energized initially during this transfer process. The UFSAR Section 8.3.1.1.2.3 (see page 8.3-7) indicates that transfer process is a dead-bus transfer and not usually done at power. (a)
Please indicate if those swing buses are ever de-energized during Modes 1 and 2? (b) If they are always energized, is that true for their loads also (discriminate between motor and non-motor loads)? (c) Can one swing bus (3AB3-S or 3AB31-S) enter the RICT program independently of the other swing bus?
Entergy Response to EEEB Question 2(a)
The 3AB3-S 4.16 kV and 3AB31-S 480 V AB swing busses are normally energized during Modes 1, 2, 3, and 4 except during bus transfers from the Train A power supply (3A3-S 4.16 kV and 3A31-S 480 V busses) to the Train B power supply (3B3-S 4.16 kV and 3B31-S 480 V busses), or vice versa. The bus transfers are dead bus transfers performed manually and are typically short in duration. The transfer times are the time it takes to perform the bus transfers.
In direct response to the question, the AB swing busses (3AB3-S 4.16 kV and 3AB31-S 480 V) are, on occasion, deenergized during Modes 1 and 2 to support planned and emergent maintenance.
Entergy Response to EEEB Question 2(b)
The purpose of the AB swing busses is to provide extra redundant loads (a third high pressure safety injection pump, a third component cooling water pump, a third essential chiller, and associated valves) to ensure the availability of one component in each division/train during extensive maintenance. The third-of-a-kind equipment consisting of the installed spares may be utilized by connecting the 3AB3-S 4.16 kV swing bus to either the 3A3-S 4.16 kV bus or the
W3F1-2022-0059 Enclosure Page 2 of 3 3B3-S 4.16 kV bus (i.e., to the bus that has a component requiring extensive maintenance). At the same time, the 3AB31-S 480 V swing bus will be connected to the 480 V bus (3A31-S or 3B31-S) corresponding to the 4.16 kV connection. This will ensure that all related AB bus loads are always connected to the same train (division). The connection of the extra redundant loads on the 3AB3-S swing bus requires a dead bus transfer. It is, therefore, not a frequent practice to transfer the 3AB3-S and 3AB31-S swing busses when the plant is at power because the loads on the 3AB3-S bus are required to maintain Technical Specification (TS) compliance and support continued plant operation. During the infrequently performed bus transfers, the loads on the 3AB3-S and 3AB31-S swing busses are not energized.
Entergy Response to EEEB Question 2(c)
Yes. With either the 3AB3-S 4.16 kV swing bus or the 3AB31-S 480 V swing bus deenergized, entry into Waterford 3 TS Limiting Condition for Operation (LCO) 3.8.3.1 Action a would be required due to the bus not being fully energized from the train (A or B) to which it is connected.
Accordingly, the RICT program would apply to the 3AB3-S swing bus or the 3AB31-S swing bus independently when the TS LCO 3.8.3.1 Action a entry condition (bus not fully energized) is met.
EEEB Question 3 LCO 3.8.3.1 (see page 3/4 8-13) indicates that both the ESF 4.16 kV bus and the ESF 480 V bus per train must be energized. However, the design success criteria (DSC) for RA 3.8.3.1.a (see Table E1-1 of May 16th supplement) indicates that train A AC bus or train B AC bus is required with swing AB AC bus when that swing bus is powered by train A AC bus or train B AC bus when train AB AC bus loads are operational. Please verify that the DSC meets minimum required operating equipment about the number of buses (both 4kV and 480 Vac buses) required per train if LCO RA 3.8.3.1.a is entered into RICT program taking into account that each available, required remaining train must be fully energized, not partially, to perform its assigned safety functions.
Entergy Response to EEEB Question 3 The A.C. Engineered Safety Features (ESF) busses consist of the Train A 3A3-S 4.16 kV and 3A31-S 480 V busses, the Train B 3B3-S 4.16 kV and 3B31-S 480 V busses, and the Train AB 3AB3-S 4.16 kV and 3AB31-S 480 V swing busses. There are no ties between the Train A and Train B busses. The Train A and Train B busses are redundant and each train's busses can supply sufficient power to its safety related loads to enable safe shutdown, or to mitigate the consequences of a design basis accident. The Train AB swing bus loads are third-of-a-kind equipment to support unavailability of the Train A or Train B equipment. The Train AB 3AB3-S 4.16 kV swing bus is connected to either the Train A 3A3-S 4.16 kV bus or the Train B 3B3-S 4.16 kV bus, but never to both. Similarly, the Train AB 3AB31-S 480 V swing bus is tied to the same train as the 3AB3-S 4.16 kV bus at all times. The Train AB swing busses are not considered separate ESF power sources since they are powered from the Train A or the Train B busses.
TS LCO 3.8.3.1 requires the Train A, Train B, and Train AB A.C. ESF busses to be energized in Modes 1, 2, 3, and 4. Entry into TS LCO 3.8.3.1 Action a would be required if one of these
W3F1-2022-0059 Enclosure Page 3 of 3 required trains (divisions) is not fully energized due to its associated 4.16 kV and/or 480 V bus(es) being not fully energized. If the Train AB bus(es) (4.16 kV and/or 480 V) and the Train A or Train B bus(es) it is connected to are both not fully energized, then entry into TS LCO 3.8.3.1 Action a would be required. Likewise, if only the Train AB bus(es) (4.16 kV and/or 480 V) is not fully energized, entry into TS LCO 3.8.3.1 Action a would be required. Accordingly, the RICT program would apply to a Train A, Train B, and Train AB A.C. ESF 4.16 kV or 480 V bus if it is not fully energized.
It is proposed to clarify the Table E1-1 DSC for TS LCO 3.8.3.1 Action a to clarify that the Train A, Train B, and Train AB A.C. ESF busses consist of both the 4.16 kV and 480 V busses.
An excerpt from Table E1-1 that provides the revised DSC is contained in the Attachment to this Enclosure.
EEEB Question 5 Table E1-1 of Enclosure 1 of the LAR supplement dated May 16, 2022, includes descriptions of the DSC for TS to be included in the RICT program. The DSC provides the minimum remaining equipment that can achieve the TS safety function while in the specified TS Condition.
According to TS 3.8.3.1 Action cs DSC, Train DC-AB-S is required at all times. If DC-AB was declared inoperable, there would be a loss of safety function (LOF). However, a LOF condition is not allowed in the RICT program according to TSTF-505 Revision 2, please provide justification for this variation.
Entergy Response to EEEB Question 5 The Table E1-1 DSC for TS LCO 3.8.3.1 Action c included with the May 16, 2022 LAR supplement was overly restrictive, in that it unnecessarily included consideration of concurrent failures. Currently, in accordance with TS LCO 3.8.3.1 Action c, with the 3AB-DC-S 125-volt D.C. bus inoperable due to not being energized, which includes a condition involving its associated battery bank (3AB-S) not being connected, the D.C. bus is required to be reconnected from its associated Operable battery bank within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. During this period (i.e., while in Action c), the other two 125-volt DC safety busses (3A-DC-S and 3B-DC-S) along with the AC safety busses would remain available. Therefore, entry into TS LCO 3.8.3.1 Action c would have no effect on the capability of the A and B D.C. busses or their associated A.C. power sources to perform their specified TS functions. Accordingly, TS LCO 3.8.3.1 Action c is within the scope of the RICT program in accordance with TSTF-505, Revision 2.
It is proposed to revise the Table E1-1 DSC for TS LCO 3.8.3.1 Action c to clarify the status of the 125-volt D.C. ESF busses and associated battery banks (batteries) needed to ensure power is provided to the 125-volt D.C. busses for operability, consistent with the TS LCO 3.8.3.1 specified function. The changes to the DSC also include the correction of an editorial error in the written designation of the 3AB-S Battery. An excerpt from Table E1-1 that provides the revised DSC is contained in the Attachment to this Enclosure.
Enclosure, Attachment W3F1-2022-0059 Changes to Table E1-1
W3F1-2022-0059 Enclosure, Attachment Page 1 of 2 Changes to Table E1-1 (Note: Changes are in BOLD and Underlined)
Table E1-1 Proposed TS LCO and SSCs Covered SSC in Functions Covered Design Success PRA Success Criteria Disposition Proposed Actions by TS LCO PRA by TS LCO Action Criteria Action Model 3.8.3.1 Onsite Power Distribution Systems.
The following Engineered Safety Features (ESF) and Static Uninterruptible Power Supply (SUPS) busses shall be energized in the specified manner. The tie breakers from the Train AB Busses shall be connected to either Train A or Train B.
See TS 3.8.3.1 list of onsite A.C. and D.C.
busses required to be energized.
Action 3.8.3.1 a A.C. Busses. Yes Engineered Safety Train A A.C. 4.16 kV and Same as Design SSCs are modeled With one of the required Features (ESF) and 480 V busses energized Success Criteria. consistent with the TS divisions of A.C. ESF Static Uninterruptible or Train B A.C. 4.16 kV scope and so can be busses not fully Power Supply and 480 V busses evaluated using the energized, reenergize (SUPS) busses shall energized and supplying CRMP tool. The success the division within 8 be energized in the safety related criteria in the PRA are hours specified manner: equipment. consistent with the design basis success criteria.
- a. Train A A.C. AND Busses.
Train AB A.C. 4.16 kV
- b. Train B A.C. and 480 V busses Busses. powered from Train A A.C. 4.16 kV and 480 V
- c. Train AB A.C. busses or Train B A.C.
Busses. 4.16 kV and 480 V busses when one or
W3F1-2022-0059 Enclosure, Attachment Page 2 of 2 Table E1-1 Proposed TS LCO and SSCs Covered SSC in Functions Covered Design Success PRA Success Criteria Disposition Proposed Actions by TS LCO PRA by TS LCO Action Criteria Action Model more AB swing components are being utilized to replace Train A or B safety related components.
Action 3.8.3.1 c Three 125-volt Yes Power to 125-volt 3A-DC-S bus energized Same as Design SSCs are modeled With one D.C. bus not D.C. Busses D.C. Busses. and connected to 3A-S Success Criteria. consistent with the TS connected to its and associated Battery, and 3AB-DC-S scope and so can be associated battery bank, Battery Banks: bus energized and evaluated using the reconnect the D.C. bus connected to 3AB-S CRMP tool. The success from its associated 1. Bus 3A-DC- Battery. criteria in the PRA are OPERABLE battery S and 3A-S consistent with the design bank within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Battery. OR basis success criteria.
- 2. Bus 3B-DC- 3B-DC-S bus energized S and 3B-S and connected to 3B-S Battery. Battery, and 3AB-DC-S bus energized and
- 3. Bus 3AB- connected to 3AB-S DC-S and Battery.
3AB-S Battery. OR 3A-DC-S bus energized and connected to 3A-S Battery, and 3B-DC-S bus energized and connected to 3B-S Battery.