Letter Sequence Response to RAI |
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EPID:L-2018-LLA-0058, Relief Requests Associated with the Fifth Inservice Inspection Interval (Approved, Closed) |
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Category:Letter type:W
MONTHYEARW3F1-2024-0040, Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days2024-09-0303 September 2024 Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0019, (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 252024-07-22022 July 2024 (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0032, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-07-17017 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation W3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program2024-05-0808 May 2024 Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0014, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20242024-04-29029 April 2024 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2024 W3F1-2024-0015, Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure2024-04-24024 April 2024 Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure W3F1-2024-0016, Annual Radiological Environmental Operating Report (AREOR) - 20232024-04-24024 April 2024 Annual Radiological Environmental Operating Report (AREOR) - 2023 W3F1-2024-0017, Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.22062024-04-23023 April 2024 Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.2206 W3F1-2024-0020, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20232024-04-11011 April 2024 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 W3F1-2024-0008, Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0009, Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0012, Response to NRC Integrated Inspection Report 05000382/20230042024-03-11011 March 2024 Response to NRC Integrated Inspection Report 05000382/2023004 W3F1-2024-0006, Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days2024-02-28028 February 2024 Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0056, 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 W3F1-2022-0031, 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 W3F1-2022-0009, 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 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 “Risk-Informed Categorization and Treatment for Repair ML24012A1962024-01-12012 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 2024-04-10
[Table view] |
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Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6698 jdinell@entergy.com John Dinelli Site Vice President Waterford 3 10 CFR 50.90 W3F1-2018-0059 October 18, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
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 (Fuel Assembly Misload) Event Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
REFERENCES:
- 1. 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) Event, March 8, 2018 [NRC ADAMS Accession Number ML18099A096].
- 2. NRC Letter, Waterford Steam Electric Station, Unit 3 - Request for Additional Information Regarding License Amendment Request to Revise Section 15.4.3.1 of the Waterford 3 Updated Final Safety Analysis Report to Account for Fuel Misload (EPID L-2018-LLA-0058), September 25, 2018 [NRC ADAMS Accession Number ML18262A041].
Dear Sir or Madam:
By letter dated March 8, 2018 (Reference 1), Entergy Operations, Inc. (Entergy) requested an amendment to revise the Waterford Steam Electric Station, Unit 3 (Waterford 3) Updated Final Safety Analysis Report (UFSAR), Section 15.4.3.1, to update the results for an inadvertent loading of a fuel assembly into the improper position.
By letter dated September 25, 2018 (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 September 18, 2018.
The enclosure to this letter provides the responses to the NRC request for additional information.
This letter contains no new regulatory commitments.
W3F1-2018-0059 Page 2 of 2 If you have any questions or require additional information, please contact John V. Signorelli, Acting Regulatory Assurance Manager, at (504) 739-6032.
I declare under penalty of perjury that the foregoing is true and correct. Executed on tober 18, 2018.
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 (Fuel Assembly Misload) Event cc: Mr. Kriss Kennedy, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 April.Pulvirenti@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division Ji.Wiley@LA.gov
Enclosure to W3F1-2018-0059 Waterford Steam Electric Station, Unit 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 (Fuel Assembly Misload) Event (2 pages)
Enclosure to W3F1-2018-0059 Page 1 of 2 Request for Additional Information 1 Section 3.1, "Selecting the Worst Undetectable Misload," of the LAR indicates that an initial survey of a large number of potential misloads from several representative and potential future loading patterns is performed by comparing assembly reactivity, peaking factors, and proximity to incore detectors to determine several potential candidates for the worst undetectable misload.
All candidates from this initial survey are then explicitly analyzed.
Please explain (or reference an approved methodology that explains) how candidates for the worst undetectable misload event may be reliably identified from the vast number of possibilities. If the specific methodology used has not been previously approved by the NRC staff, then expand upon and further justify the method used to identify the candidates for the worst undetectable fuel misload.
Entergy Response The method of screening the possible adverse fuel assembly misloads is the same as that used in the Waterford 3 Analysis of Record (AOR) as well as that approved by the NRC for Palo Verde Nuclear Generating Station (LAR Reference 7). The initial screening involved comparing the k-infinity differences between two possible misloaded assemblies. Beginning of Cycle (BOC) and Middle of Cycle (MOC) k-infinity differences were calculated for the proposed misloads using the ANC code.
The k-infinity at BOC is used to identify worst case undetectable fuel assembly misloads. The k-infinity at MOC is used to identify fuel assembly misloads with the highest Required Overpower Margin (ROPM). MOC is chosen since the ROPM limit is generally set at MOC, just after burnable absorber burnout. If a misload is undetectable at BOC, but has a low ROPM at MOC it is not considered limiting. Likewise, if a misload has a high ROPM at MOC, but is highly detectable at BOC it is also not considered limiting.
Additional consideration was given for the assemblies immediately adjacent to the nominal ANC depletion peak radial peaking factor (Fr) locations throughout the cycle. For these locations, the k-infinity and interchange difference between the peak Fr adjacent assembly and every sub-region in the core were calculated using BOC k-infinity values. The maximum ANC Fr calculated from the base misload case is also a good indicator of the maximum ROPM, and as such was used as a screening parameter in order to ensure the worst undetectable misload would be captured.
Based on the above considerations and assuming up to 25% incore instrument (ICI) failure at startup, per the Technical Requirements Manual (TRM), the worst undetectable fuel assembly misloads were identified and examined for this analysis.
Enclosure to W3F1-2018-0059 Page 2 of 2 Request for Additional Information 2 Section 3.2, "Determining Fuel Pin Failure," of the LAR states, in part:
The amount of fuel failure that occurs as a direct result of DNB [departure from nucleate boiling] is determined by counting the number of fuel rods that have a power greater than the radial peaking factor that is greater than the CECOR measured value by an amount corresponding to a decrease in OPM (overpower margin] equivalent to the ROPM (required overpower margin] (as determined by CETOP).
Please clearly restate or explain the above quotation. In particular, the phrase "that have a power greater than the radial peaking factor that is greater than the CECOR measured value" compares a rod power to a radial peaking factor, makes consecutive "greater than" comparisons, and discusses "CECOR measured values" in the context of candidate misloads that could derive from several representative and "potential future loading patterns." As such, the meaning of the above statement cannot reasonably be inferred from the information available to the NRC staff.
Entergy Response The Core Operating Limit Supervisor System (COLSS) assures that the core always maintains sufficient DNB overpower margin (OPM) during normal operation to prevent fuel failure from Condition II transients to a 95/95 confidence level. The amount of margin that must be reserved for Condition II transients (ROPM) is pre-determined and is one of the COLSS setpoints. The COLSS uses the CECOR measured planar radial peaking factor (Fxy) in its online calculation of the DNB OPM. If a core misload were to occur, some of the effects of the misload would be seen in the CECOR measured Fxy. The CECOR measured Fxy is input into COLSS which would cause a decrease in DNB OPM. This means that only the decrease in DNB OPM associated with the unseen increase in Fxy would need to be accommodated by available margin to prevent fuel failure.
The CETOP code is used to correlate ROPM with an increase in Fxy to calculate the OPM associated with different values of Fxy. These CETOP calculations are used to determine the Fxy that would be equivalent to the current reserved Waterford ROPM value. Any fuel rod having a Fxy greater than the reserved COLSS ROPM calculated Fxy could have a DNBR below the 95/95 DNBR limit. The Waterford misload analysis has assumed that the value of Fxy installed into COLSS for a core operating with a postulated misload would be the value that CECOR would measure for that core assuming that 25% of the incore detectors were inoperable. Thus, the analysis assumed that all fuel rods having an Fxy greater than reserved COLSS ROPM calculated Fxy would be below the 95/95 DNBR limit. To conservatively account for postulated DNB propagation, it was assumed all the rods in any assembly having at least one rod with an Fxy greater than the reserved COLSS ROPM calculated Fxy would be counted as failed.