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EPID:L-2019-LLA-0230, (Waterford 3) - License Amendment Request to Revise Technical Specification 3.8.1.1 Surveillance Requirements (Approved, Closed) |
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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: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
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Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.90 W3F1-2020-0033 May 29, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
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" Waterford Steam Electric Station, Unit 3 (Waterford 3)
NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38
References:
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "License Amendment Request to Revise Technical Specification 3.8.1.1," W3F1-2019-0073, (ADAMS Accession Number ML19297H543), dated October 24, 2019
- 2. NRC letter to Entergy, " Waterford Steam Electric Station, Unit 3 -
Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.8.1, "A.C. Sources Operating" (EPID L-2020-LLA-0230)," (ADAMS Accession No. ML20086M385), dated April 1, 2020 By letter dated October 24, 2019 (Reference 1), Entergy requested an amendment to revise Technical Specification 3/4.8.1 (A.C. Sources - Operating) for Waterford Steam Electric Station, Unit 3 (Waterford 3).
By letter dated April 1, 2020 (Reference 2), the NRC staff informed Entergy that they have reviewed the license amendment request and have determined that additional information is required to complete the review. A clarification call between the NRC and Entergy was previously held on March 26, 2020.
The additional information requested by the NRC in Reference 2 is provided in the Enclosure to this letter.
W3F1-2020-0033 Page 2 of 2 This letter contains no new regulatory commitments.
Should you have any questions or require additional information, please contact Paul Wood, Regulatory Assurance Manager, at 504-464-3786.
I declare under penalty of perjury, that the foregoing is true and correct. Executed on May 29, 2020.
Respectfully, Ron Gaston RWG/mmz
Enclosure:
Response to NRC Request for Additional Information cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford Steam Electric Station, Unit 3 NRR Project Manager Louisiana Department of Environmental Quality, Office of Environmental Compliance
Enclosure W3F1-2020-0033 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION
W3F1-2020-0033 Enclosure Page 1 of 5 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(b) states, in part, that Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or § 50.22 will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34.
The NRC also considered the following General Design Criteria of 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants.
General Design Criterion (GDC) 17, Electric power systems, states in part, that:
An onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety.
GDC 34, Residual heat removal, states that:
A system to remove residual heat shall be provided. The system safety function shall be to transfer fission product decay heat and other residual heat from the reactor core at a rate such that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary are not exceeded.
GDC 35, Emergency core cooling, states that:
A system to provide abundant emergency core cooling shall be provided.
The system safety function shall be to transfer heat from the reactor core following any loss of reactor coolant at a rate such that (1) fuel and clad damage that could interfere with continued effective core cooling is prevented and (2) clad metal-water reaction is limited to negligible amounts.
Suitable redundancy in components and features, and suitable interconnections, leak detection, isolation, and containment capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure.
GDC 38, Containment heat removal, states that:
A system to remove heat from the reactor containment shall be provided.
The GDC also requires, in part, that containment capabilities shall be provided to assure that for onsite electric power system operation, (assuming offsite power is not available) the system safety function can be accomplished, assuming a single failure.
W3F1-2020-0033 Enclosure Page 2 of 5 NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve [MOV] Testing and Surveillance (ADAMS Accession No. ML031150300), dated June 28, 1989, requested that licensees consider the performance of MOVs during degraded voltage conditions.
Request for Additional Information Request 1 For the emergency diesel generator lube oil pump and jacket water pump on the emergency diesel generator skid, and the fuel oil transfer pump, discuss whether or not the proposed diesel generator under-frequency limit of 59.7 hertz (Hz) has any effect on the flow rates for these pumps.
Entergy Response The EDG lube oil pump is driven by the diesel engine. The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change.
Since generator frequency is directly related to engine speed this requires engine speed to be controlled in a tighter band. Therefore, engine driven pump performance is improved.
The change in EDG lube oil pump speed due to a change in generator frequency (i.e., engine speed) from the nominal 60 Hz case, will cause a minimal decrease in pump flow. A standby lube oil pump is available which will start automatically if lube oil pressure drops below a set pressure. Therefore, the proposed diesel generator under-frequency limit of 59.7 Hz will not affect operation of the EDG Lube Oil System.
The Main Jacket Water Pump is a centrifugal pump driven off the diesel crankshaft via a chain and sprocket. The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change. Since generator frequency is directly related to engine speed this change requires engine speed to be controlled in a tighter band.
Therefore, engine driven pump performance is improved.
The change in Main Jacket Water Pump speed due to a change in generator frequency (i.e.,
engine speed) from the nominal 60 Hz case, is accommodated by the pump rating as well as operation of the jacket water temperature control valve which will open to maintain jacket water temperature.
The diesel oil transfer pumps pump fuel from the fuel oil storage tank to replenish the diesel feed tank. The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change which will result in improved pump performance by increasing the minimum allowed pump speed.
Operation of the diesel oil transfer pumps pump at the proposed under-frequency limit of 59.7 Hz would cause delivered flow to be lower compared to the nominal 60 Hz case based on the pump affinity laws; however, this is well within the margin available. Calculation ECM91-001 (EDG Fuel Oil Transfer Pump Recirculation & Discharge Flow, Revision 4) determines that the minimum flow to the diesel oil feed tanks is 47 gpm. The maximum required flow from the diesel oil feed tanks is less than 15 gpm, so the required flow to the feed tanks is less than
W3F1-2020-0033 Enclosure Page 3 of 5 15 gpm. Potential EDG underfrequency is not accounted for in this calculation because of the large margin between required flow and delivered flow.
Request 2 Section 3.2, Current Licensing Basis and Evaluation, of the LAR states, in part, that the diesel generator under-frequency limit of 59.7 Hz is needed to ensure that the minimum low-pressure safety injection and high-pressure safety injection safety analysis delivery assumptions are met.
The proposed changes to the surveillance requirements identify considerations in the performance of pumps within the high-pressure safety injection and the low-pressure safety injection systems, as documented in Waterford 3 Condition Report CR-WF3-2008-5183 (Reference 12 of the LAR).
The effects of diesel generator frequency variations and the performance of all pumps associated with emergency core cooling systems were described in the LAR and reviewed for conformance with associated regulatory requirements (e.g., GDC 17, 34, 35, 38). However, the NRC staff notes that performance capabilities of other equipment, such as MOVs, heaters, and fans associated with emergency core cooling systems or related heating and ventilation systems are also susceptible to voltage and frequency variations. This equipment in these systems is not discussed in the LAR. Typically, licensees evaluated the performance of MOVs during degraded voltage conditions in their responses to NRC Generic Letter 89-10.
Therefore, provide a discussion of how all of the safety-related equipment that could be impacted by the voltage limits and frequency variations proposed in the LAR, such as MOVs, heaters, fans, or pumps, was evaluated for conformance using the assumptions in the accident analyses for Waterford 3. Provide confirmation that the voltage limits and frequency variations proposed in the LAR will not adversely impact the assumptions in the safety analysis.
Entergy Response The LAR proposes an increase of the EDG steady state under-voltage limit of 3740 volts to 3920 volts which is a conservative change.
The minimum voltage of 3920 volts envelopes and protects the degraded voltage relay trip setpoint of 3875 volts and its reset value of 3915 volts. The degraded voltage relay trip setpoint is shown in Waterford 3 Technical Specification Table 3.3-4. The 3920V ensures safe operations of all safety related electrical loads. Additionally, it assures the minimum voltage output of the EDG is adequate before the safety related loads are connected and the degraded voltage relays reset.
Specifically, an analysis of the Waterford 3 electrical distribution system has determined the proper degraded voltage relay setpoint by considering voltage drop during a 100% Load Rejection or Loss of Coolant Accident (LOCA) scenario. These two scenarios provide the most conservative avenue for a voltage analysis during a sustained degraded voltage condition. The analysis shows with the degraded voltage relay trip setpoint at 3875 volts, all safety related buses at the 4.16KV, 480V, and 120V would have sufficient voltage to operate all safety related equipment. The conclusion from this voltage analysis supports the TS Change in the Amendment 74 to the Waterford 3 Operating License dated August 24, 1992 which is consistent with the change proposed in this LAR.
W3F1-2020-0033 Enclosure Page 4 of 5 The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change.
A review of the under-frequency on the electrical performance of motors, static uninterruptible power supplies (SUPS), battery chargers, transformers, and heaters that are fed by the EDG during a LOCA coincident with a LOOP was performed. For motors, specification 1564.283 (Class 1E 4KV Motors) requires that motors are capable of starting at 90-110% of rated voltage at rated frequency. When motors are started from the EDG, the motor terminal voltage may dip to 75% of rated voltage with a simultaneous drop in frequency to 95% of normal. Restoration of EDG voltage and frequency are at 90% and 98%, respectively. Similarly, Class 1E 460V (ref.
Specification 1564.264) motors comply with the requirements of NEMA standards. NEMA MG-1 Section 12.44 states that alternating current motors shall operate successfully under running conditions at rated load with a variation in the frequency +/-5%. For safety related Static Uninterruptible Power Supplies (SUPS), specification DES-E-029 states +/-5% of rated frequency. For battery chargers, specification 1564.280B states +/-5% of rated frequency. For transformers, the proposed under-frequency is within the acceptable and normal range for electrical equipment, including power transformers. Specification 1564.261B (Station Service Transformers) specifies an operating frequency for the transformers at a minimum of 58.8 Hz.
Heaters are a resistive load and hence, the proposed change in frequency has negligible impact if any, to the heaters. Therefore, the proposed under-frequency value is within the span of frequency where the motors, SUPS, battery chargers, transformers, and heaters can operate.
A review of the under-frequency on the mechanical performance of motor-operated equipment (pumps, fans, and valves) fed by the EDG during a LOCA coincident with a LOOP was performed. The applicable affinity equations were reviewed to determine the effect of the proposed change.
Pump flow is directly proportional to pump speed (i.e., motor frequency) while head is proportional to the square of speed. The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change and will result in improved pump performance by increasing the minimum allowed pump speed which results in improved flow and head while only minimally reducing net positive suction head (due to increased flow).
The allowance of a lower EDG frequency limit of 59.7 Hz will result in a reduction of 0.5% pump flow and 1.0% pump head as compared to the nominal 60 Hz case. Available net positive suction head will have a minor increase due to the reduction in pump flow as compared to the nominal 60 Hz case. These changes are minimal and well within existing margins.
MOV stroke time is directly proportional to frequency. The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change and will improve MOV performance. Compared to the based 60 Hz case operation at 59.7 Hz will lower MOV stroke time by 0.5%. This is a minimal change which is well within existing margins.
Fan flow is also directly proportional to frequency. The LAR proposes an increase of the EDG steady state under-frequency limit of 58.8 Hz to 59.7 Hz which is a conservative change and will result in improved fan performance by increasing the minimum allowed fan speed which results in improved flow. Compared to the based 60 Hz case operation at 59.7 Hz will lower flow by 0.5% which is a minimal change and is well within existing margins.
W3F1-2020-0033 Enclosure Page 5 of 5 Existing pump flow, pump head, fan flow and motor operated valve stroke time margins were reviewed. The proposed minimum allowed EDG steady state under-frequency limit of 59.7 Hz will present a minimal change in pump, MOV and fan performance from the nominal 60 Hz case which is well within existing margins.