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Category:Inspection Report
MONTHYEARIR 05000382/20244022024-10-10010 October 2024 Security Baseline Inspection Report 05000382/2024402 Public IR 05000382/20244032024-10-0909 October 2024 Security Baseline Inspection Report 05000382/2024403 IR 05000382/20240112024-10-0101 October 2024 State Fire Protection Team Inspection Report 05000382/2024011 IR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised IR 05000382/20253012024-09-0303 September 2024 Notification of NRC Initial Operator Licensing Examination 05000382/2025301 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23158A1042023-06-0808 June 2023 – Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion IR 05000382/20230012023-04-24024 April 2023 Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) IR 05000382/20230902023-02-0101 February 2023 Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090 IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 IR 05000382/20220912023-01-12012 January 2023 Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation IR 05000382/20220032023-01-0505 January 2023 Revised Integrated Inspection Report 05000382/2022003 IR 05000382/20220132022-11-28028 November 2022 – Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 ML22300A1032022-11-0101 November 2022 Integrated Inspection Report 05000382/2022003 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 IR 05000382/20224022022-10-24024 October 2022 NRC Security Inspection Report 05000382 2022402 IR 05000382/20220122022-09-16016 September 2022 Digital Instrumentation and Control Modification Inspection Report 05000382/2022012 IR 05000382/20224032022-09-14014 September 2022 NRC Security Inspection Report 05000382 2022403 IR 05000382/20220902022-09-12012 September 2022 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter, NRC Insp Rprt 05000382/2022090 IR 05000382/20220102022-08-24024 August 2022 Biennial Problem Identification and Resolution Inspection Report 05000382/2022010 ML22229A0662022-08-17017 August 2022 Security Baseline Inspection Report 05000382/2022403 ML22217A1112022-08-0909 August 2022 Integrated Inspection Report 05000382/2022002 IR 05000382/20220112022-07-14014 July 2022 License Renewal Phase 1 Inspection Report 05000382/2022011 IR 05000382/20224012022-06-16016 June 2022 Security Baseline Inspection Report 05000382/2022401 IR 05000382/20225012022-06-11011 June 2022 Emergency Preparedness Inspection Report 05000382/2022501 and Preliminary White Finding IR 05000382/20220012022-05-17017 May 2022 Reissue IR 05000382/2022001 ML22124A3062022-05-0808 May 2022 Integrated Inspection Report 05000382/2022001 IR 05000382/20223012022-03-28028 March 2022 NRC Examination Report 05000382/2022301 IR 05000382/20210142022-03-0909 March 2022 Digital Instrumentation and Control Modification Inspection Report 05000382/2021014 IR 05000382/20210062022-03-0202 March 2022 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2021006) IR 05000382/20210042022-02-0808 February 2022 Integrated Inspection Report 05000382/2021004 and Exercise of Enforcement Discretion ML22011A0992022-01-14014 January 2022 IR 2021012 EOI CO3 2024-09-03
[Table view] Category:Letter
MONTHYEARIR 05000382/20244022024-10-10010 October 2024 Security Baseline Inspection Report 05000382/2024402 Public IR 05000382/20244032024-10-0909 October 2024 Security Baseline Inspection Report 05000382/2024403 IR 05000382/20240112024-10-0101 October 2024 State Fire Protection Team Inspection Report 05000382/2024011 IR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24268A1132024-09-24024 September 2024 Acknowledgment of Response to NRC Inspection Report 05000382/2024013, and Notice of Violation ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure 05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 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 ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement2024-02-14014 February 2024 Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 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 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-30030 December 2023 Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000382/20230032023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARW3F1-2024-0038, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0039, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24101A3882024-04-10010 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 ML17037D0552017-02-0707 February 2017 Groundwater Resources (Gw) RAI GW-1 WF3 Groundwater Monitoring Program_Five-Year Review 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 ML17030A1872017-02-0707 February 2017 Aquatic RESOURCES-RAI AR-6 LPDES Permit Modification_2008 ML17038A2772017-02-0707 February 2017 Surface Water Resources (SW) RAI SW-11 Ldwf Letter of No Objection ML17037C9972017-02-0707 February 2017 Aquatic Resources (AR) RAI AR-7 WF3 1998_WF3 LPDES Fact Sheet and Rationale for Draft LPDES Permit ML17024A2392017-02-0707 February 2017 Alternatives RAI-AL-3 Lanning 2014_Correspondence Lanning-Entergy to Buckley-Entergy ML17037D0362017-02-0707 February 2017 Cumultive Impacts (Cu) RAI CU-1 Reasonably Foreseeable Future Projects within WF3 Area 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 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 2024-09-24
[Table view] |
See also: IR 05000382/2018007
Text
April 10, 2018
Mr. John Dinelli, Site Vice President
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-0751
SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION
OF AN NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT 05000382/2018007) AND REQUEST FOR
INFORMATION
Dear Mr. Dinelli:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
Region IV staff will conduct a triennial fire protection baseline inspection at the Waterford Steam
Electric Station, Unit 3 in July and August 2018. The inspection team will be comprised of
five reactor inspectors from the NRC Region IV office. The inspection will be conducted in
accordance with Inspection Procedure 71111.05XT, Fire Protection - NFPA 805 (Triennial),
the NRCs baseline fire protection inspection procedure. In addition, the inspection will review
the actions taken in response to Confirmatory Order NRC Inspection Report 05000382/2016007
and NRC Investigation Report 4-2014-017 in accordance with Inspection Procedure 92702,
Followup on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory
Action Letters, Confirmatory Orders, and Alternative Dispute Resolution Confirmatory Orders.
The schedule for the inspection is as follows:
- Information gathering visit: July 10 - 11, 2018
- On-site inspection: July 30, 2018 - August 3, 2018
August 13 - 17, 2018
The purpose of the information gathering visit is to obtain information and documentation
needed to support the inspection, and to become familiar with the fire protection program, fire
protection features, safe shutdown success paths, plant layout, and mitigating strategies to
address Section B.5.b of NRC Order EA-02-026, Order for Interim Safeguards and Security
Compensatory Measures, dated February 25, 2002, and 10 CFR 50.54(hh)(2).
The team leader and one team member will participate in the information gathering visit to
select the fire areas for evaluation, identify additional documents needed to support the
inspection, obtain unescorted access, and meet with the key personnel who will support the
inspection. The fire area selection will require a walkdown of candidate fire areas with key
personnel from your staff. The enclosure to this letter provides an initial list of the documents
the team will need for their review.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: (1) office space size and location; (2) specific documents
J. Dinelli 2
requested to be made available to the team in their office spaces; (3) arrangements for reactor
site access (including radiation protection training, security, safety, and fitness for duty
requirements); and (4) the availability of knowledgeable plant staff and licensing organization
personnel to serve as points of contact during the inspection.
We request that during the on-site inspection weeks you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the station fire
protection program, including the success path necessary to achieve and maintain the nuclear
safety performance criteria, be readily accessible to the team for their review. Of specific
interest for the fire protection portion of the inspection are those documents which establish that
your fire protection program satisfies NRC regulatory requirements, and conforms to applicable
NRC and industry fire protection guidance (i.e., fire protection compliance assessment
documents). For the 10 CFR 50.54(hh)(2) portion of the inspection, those documents
implementing your mitigating strategies and demonstrating the management of your
commitments for the strategies are of specific interest. Also, personnel should be available at
the site during the inspection who are knowledgeable regarding those plant systems required to
achieve and maintain safe and stable plant conditions, including the electrical aspects of the
nuclear safety capability assessment, reactor plant fire protection systems and features, and the
station fire protection program and its implementation.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget under control
number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget control
number.
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html, and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection or the inspection teams information or logistical needs, please
contact John Mateychick, the team lead inspector, in the Region IV office at (817) 200 1560 or
john.mateychick@nrc.gov.
Sincerely,
/RA James Drake Acting for/
Gregory E. Werner, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-382
License No. NPF-38
Attachments: 1. Triennial Fire Protection Inspection Document Request
2. Mitigating Strategies Document Request
3. Confirmatory Letter Document Request
Triennial Fire Protection Inspection Document Request
The documents and information requested below should generally be made available to the
inspection team during the inspection. Electronic format is the preferred format, except where
specifically noted. If electronic files are made available via the internet-based inspection
management system (IMS), then the remote document access must allow inspectors to
download, save, and print the documents in the NRCs regional office.
If IMS is utilized, it is recommended that a separate folder be used corresponding to each item
listed below and that multiple documents within each folder be combined into a ZIP file before
uploading. Electronic media on compact disc or paper records (hard copy) are also acceptable.
To allow review before the on-site information gathering visit, the following documents should be
made available to the team in the regional office no later than June 22, 2018:
- Post-fire Nuclear Safety Capability, Systems, and Separation Analysis (request A.1)
- Fire Hazards Analysis and/or NFPA 805 Design Basis Document (request A.2)
(request A.3)
- Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3) (request A.5)
- Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4) (request A.6)
- Analysis that demonstrates nuclear safety performance criteria can be achieved and
maintained for those areas that require recovery actions (request A.7)
- Thermal hydraulic calculation or analysis that determines the time requirements for time-
critical manual operator actions (request E.6)
- Operating procedures to achieve and maintain nuclear safety performance criteria from
outside the control room with a postulated fire in the control room, cable spreading room,
or any area requiring recovery actions (other than recovery actions performed in the
control room or primary control stations), and any associated procedure basis
documents. (request E.8)
- Information concerning radio communications (request E.12)
- Information concerning telephone, plant pager or sound powered phone systems, if
relied upon to achieve and maintain safe and stable conditions (request E.13)
Based on a review of the above items, team leader should identify a preliminary list of fire areas
being considered for inspection prior to the on-site information gathering visit. During the
Attachment 1
information gathering visit, or shortly thereafter, the fire areas selected for inspection will be
determined.
This document request is based on typical documents that a generic plant might have. As such,
this generic document request is not meant to imply that any specific plant is required to have all
of the listed documents. It is recognized that some documents listed below may not be
available for your plant. In addition, the document titles listed below are based on typical
industry document names; your plant-specific document titles may vary.
To allow review before the on-site inspection weeks, the following documents should be made
available to the team in the regional office no later than July 13, 2018.
A1-2
A. DESIGN AND LICENSING BASIS DOCUMENTS
A.1 Post-fire Nuclear Safety Capability, Systems, and Separation Analysis
A.2 Fire Hazards Analysis and/or NFPA 805 Design Basis Document
A.3 Fire PRA Summary Document or full PRA Document (if summary document not
available)
A.4 NFPA 805 Transition Report, developed in accordance with NEI 04-02
A.5 Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3)
A.6 Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4)
A.7 Analysis that demonstrates nuclear safety performance criteria can be achieved
and maintained for those areas that require recovery actions.
A.8 Fire Protection Program and/or Fire Protection Plan
A.9 List of post-fire safe shutdown components (i.e., safe shutdown equipment list)
A.10 Fire Protection System Design Basis Document
A.11 List of applicable NFPA codes and standards and issuance dates (i.e., codes of
record)
A.12 List of deviations from (a) NFPA codes of record or (b) NFPA 805 fundamental
fire protection program and design elements (i.e., NFPA 805, Chapter 3)
A.13 NFPA compliance review report
A.14 Copy of licensee submittals and NRC safety evaluation reports that are
specifically listed in the facility operating license for the approved fire protection
program
A.15 Copy of NRC Safety Evaluation Reports that form the licensing basis for:
- Post-fire Nuclear Safety Capability
A.16 List of nuclear safety capability design changes completed in the last 3 years
(including their associated 10 CFR 50.59 and NFPA 805 plant change
evaluations)
A.17 Facility Operating License
A.18 Technical Specifications (electronic format only)
A.19 Technical Requirements Manual (electronic format only)
A1-3
A.20 Updated Final Safety Analysis Report (electronic format only)
B. GENERAL PLANT DESIGN DOCUMENTS
B.1 Piping and instrumentation diagrams (P&IDs) and legend list for components
used to achieve and maintain nuclear safety performance criteria for: (electronic
format and C-size paper drawings)
- Fires outside the main control room
- Fires in areas requiring recovery actions at other than primary control stations
B.2 Piping and instrumentation diagrams and legend list for fire protection systems,
including the fire water supply; water suppression sprinklers; and deluge, CO2,
and Halon systems (electronic format and C-size paper drawings)
B.3 Yard layout drawings for underground fire protection buried piping (electronic
format and C-size paper drawings)
B.4 AC and DC electrical system single line diagrams, from off-site power down to
the highest safety-related bus level (typically 4kV, EDG bus) (electronic format
and C-size paper drawings)
B.5 Single line diagrams for motor control centers (MCCs) that supply post-fire
nuclear safety component loads (only for selected fire areas) (electronic format
and C-size paper drawings)
B.6 Equipment location drawings which identify the physical plant locations of post-
fire nuclear safety capability equipment (electronic format and C-size paper
drawings)
B.7 Plant layout drawings which identify: (electronic format and C-size paper
drawings)
- Plant fire area boundaries
- Combustible control zone drawings
- Areas protected by automatic fire suppression and detection
- Locations of fire protection equipment
C. CLASSIC FIRE PROTECTION
C.1 Copy of fire protection program implementing procedures (e.g., administrative
controls, surveillance testing, and fire brigade)
C.2 List of calculations and engineering analyses, studies, or evaluations for the fire
protection system, including the fire water system
C.3 Hydraulic calculation or analysis for fire protection water system
A1-4
C.4 Last two completed surveillances of fire protection features in the selected fire
areas (detection, suppression, damper inspections, damper tests, penetration
inspections, barrier inspections, etc.)
C.5 List of routine tests, surveillances, and preventive maintenance on fire pumps,
including pump controllers and batteries
C.6 Last two completed annual fire pump pressure and flow tests
C.7 Last two completed monthly and/or quarterly fire pump tests
C.8 Last two completed fire loop flow tests and loop flushes
C.9 CO2 and Halon initial discharge testing or calculation that determined appropriate
concentrations and soak or hold times can be achieved (only for selected fire
areas)
C.10 Last five hot work permits (at power)
C.11 Last five transient combustible permits (at power)
C.12 For Fire Brigade Drills, provide the following:
- Last five fire brigade drill critiques
- Last drill critique for a drill with off-site fire department support
- Last unannounced drill critique
- Last back-shift drill critique
- Dates, shifts, and locations of unannounced drills for last 3 years
- Summary of any unsatisfactory drill performance items for last 3 years
- Last unannounced drill critique by a qualified individual independent of the
licensees staff
C.13 For fire brigade equipment provide the following:
- Procedure for inventory and inspection
- Most recent inspection and inventory results
C.14 Fire Brigade Qualifications, including self-contained breathing apparatus, (SCBA)
and training lesson plans
C.15 Copy of the mutual aid agreement for the first-due local fire department that is
currently in effect
A1-5
C.16 Copy of the evaluation or analysis of the effects of fire suppression activities on
the ability to achieve the nuclear safety performance criteria (only for selected fire
areas) demonstrating:
- The automatic or manually actuation of a suppression system, due to a fire in
a single location, will not indirectly cause damage to the success path
- The inadvertent actuation or rupture of a suppression system will not
indirectly cause damage to the success path
- Adequate drainage for areas protected by water suppression systems
areas that are credited with keeping water from leaking into fire areas below
C.17 Pre-fire plans for all fire areas
C.18 For emergency lighting units, provide the following:
- Copy of performance-based emergency light assessments
- List of Preventive Maintenance tasks, frequencies, and bases
- Most recently performed monthly or quarterly functional test
- Most recently performed battery discharge performance test or conductance
measurement test
- Vendor manual(s) for onsite inspector use
- Results of black-out testing (if performed)
system
service
- Drawings showing emergency light locations and lamp orientation
C.19 Impairment Log (at start of inspection) for fire protection features that are out of
service
C.20 Fire protection screening reviews for recent design changes, modifications, or
temporary modifications (i.e., an NFPA 805 plant change evaluation that
screened out) in the last 3 years
C.21 List of penetration seal work, re-work, or installation activities, in the last 3 years
A1-6
C.22 List of fire wrap work, re-work, or installation activities, in the last 3 years
C.23 Fire protection system health reports for the two most recent quarters
C.24 Fire protection program health reports for the two most recent quarters
C.25 Emergency lighting system health reports for the two most recent quarters
C.26 LIST of fire protection system design changes completed in the last 3 years
(including their associated 10 CFR 50.59 and NFPA 805 plant change
evaluations)
C.27 List of fire protection system NFPA 805 engineering equivalency evaluations
completed in the last 3 years.
C.28 Licensee evaluations of industry operating experience concerning fire protection
issues completed in the last 3 years.
D. ELECTRICAL
D.1 Identify whether the cables in the selected fire areas are predominantly
thermoset or thermoplastic. Specifically identify any thermoplastic cable in the
selected fire areas.
D.2 Nuclear safety circuit coordination analysis for fuse and breaker coordination of
nuclear safety capability components (only for selected fire areas)
D.3 Administrative or configuration control procedures that govern fuse replacement
(e.g., fuse control procedures)
D.4 Maintenance procedures that verify breaker over-current trip settings to ensure
coordination remains functional for post-fire nuclear safety capability
components.
D.5 Electrical system health reports for the two most recent quarters
D.6 Last surveillance demonstrating operability of those components operated from
the primary control stations
D.7 Schematic or elementary diagrams for circuits to be reviewed (samples to be
identified by the inspector) (C-size paper drawings)
D.8 Cable routing for components and equipment credited for post-fire nuclear safety
capability systems and components (only for selected fire areas)
D.9 List of post-fire nuclear safety capability system and component design changes
completed in the last 3 years.
D.10 List of identified fire induced circuit failure configurations (only for selected fire
areas)
A1-7
E. OPERATIONS
E.1 List of calculations and engineering analyses, studies, or evaluations for the
nuclear safety capability methodology
E.2 List of licensed operator Job Performance Measures (JPMs) for operator actions
required to achieve and maintain post-fire nuclear safety performance criteria.
E.3 List of non-licensed operator training associated with non-licensed operator
actions to achieve and maintain post-fire nuclear safety performance criteria
(including JPMs, in-field training walkdowns, simulations, or initial qualification)
E.4 Lesson plans for post-fire nuclear safety capability training for licensed and non-
licensed operators
E.5 For recovery actions, provide the following:
- Manual Action Feasibility Study
- Operator Time Critical Action Program
- Time lines for time-critical recovery actions
E.6 Thermal hydraulic calculation or analysis that determines the time requirements
for time-critical manual operator actions
E.7 Operating procedures to achieve and maintain nuclear safety performance
criteria from the control room with a postulated fire in the selected fire areas.
E.8 Operating procedures to achieve and maintain nuclear safety performance
criteria from outside the control room with a postulated fire in the control room,
cable spreading room, or any area requiring recovery actions (other than
recovery actions performed in the control room or primary control stations), and
any associated procedure basis documents.
E.9 For safe shutdown equipment and tools, provide the following:
- Procedure for inventory and inspection
- Most recent inspection and inventory results
E.10 List of procedures that implement cold shutdown repairs.
E.11 For cold shutdown repairs, provide the following:
- Procedure for inventory and inspection (i.e., needed tools, material, etc.)
- Most recent inspection and inventory results
A1-8
E.12 For radio communications, provide the following:
- Communications Plan for firefighting and post-fire safe shutdown manual
actions
- Cable routing for repeater power supply cables
- Radio coverage test results
- Radio Dead Spot locations in the plant
E.13 For telephone, plant pager, or sound powered phone systems, if relied upon to
achieve and maintain safe and stable conditions, provide the following:
- Communications Plan for firefighting and post-fire safe shutdown manual
actions
- Locations of phone, pager units, sound powered phone jacks and sound
powered phone headsets
- Cable routing including power supply cables
E.14 Environmental and habitability evaluations for post-fire operator actions
(temperature, smoke, humidity, SCBAs, etc.)
F. ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION
PROGRAMS
F.1 Corrective actions for fire-induced circuit failures (including but not limited to
NRC IN 92-18), both single and multiple spurious actuations (only for selected
fire areas).
F.2 Corrective actions associated with operator actions to achieve and maintain post-
fire nuclear safety performance criteria.
F.3 Self assessments, peer assessments, and audits of fire protection activities for
the last 3 years
F.4 Self assessments, peer assessments, and audits of post-fire nuclear safety
capability methodology for the last 3 years
F.5 List of open and closed condition reports for the fire protection system for the last
3 years
F.6 List of fire event analysis reports for the last 3 years
F.7 List of open and closed condition reports for emergency lighting units for the last
3 years
A1-9
F.8 List of open and closed condition reports for post-fire nuclear safety capability
issues for the last 3 years. This includes issues affecting the nuclear safety
capability analysis, fire hazards analysis, NFPA 805 design basis, fire risk
evaluations, plant change evaluations, post-fire operating procedures and/or
training, timeline evaluations for operator actions, and supporting engineering
evaluations, analysis, or calculations.
F.9 List of procedures that control the configuration of the fire protection program,
features, and post-fire nuclear safety capability methodology and system design.
A1-10
Mitigating Strategies Document Request
G. 10 CFR 50.54(hh)(2) MITIGATING STRATEGIES DOCUMENTS
G.1 List of all changes to regulatory commitments made to meet the requirements of,
Section B.5.b of NRC Order EA-02-026, Order for Interim Safeguards and
Security Compensatory Measures, dated February 25, 2002, and Title 10 of the
Code of Federal Regulations (10 CFR) 50.54(hh)(2).
G.2 List of procedures and guidelines that were revised or generated to implement
the mitigating strategies. These could be extensive damage mitigation guidelines
(EDMGs), severe accident management guidelines (SAMGs), emergency
operating procedures (EOPs), abnormal operating procedures (AOPs), etc.
G.3 A matrix that shows the correlation between the mitigation strategies identified in
Nuclear Energy Institute, 06-12, Revision 2, B.5.b Phase 2 and 3 Submittal
Guideline, issued December 2006, and the site-specific procedures or
guidelines that are used to implement each strategy.
G.4 List of engineering evaluations or calculations that were used to verify the
engineering bases for the mitigating strategies.
G.5 Piping and instrumentation diagrams (P&ID) and legend list or simplified flow
diagrams for systems relied upon in the mitigating strategies. These could be the
type used for training (electronic format and C-size paper drawings).
G.6 List of modification packages or summary descriptions of modifications with
simplified drawings, for necessary facility changes to implement the mitigating
strategies.
G.7 List of routine tests, surveillances, and preventive maintenance for equipment
and tools needed to implement 10 CFR 50.54(hh)(2) strategies.
G.8 For equipment and tools needed to implement 10 CFR 50.54(hh)(2) strategies,
provide the following:
- Procedures for inventory and inspection
- Most recent inspection and inventory results
G.9 List of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details
that differ from that documented in the submittals or the safety evaluation report.
G.10 Site general arrangement drawings that show the majority of buildings and areas
referenced in 10 CFR 50.54(hh)(2) documents (electronic format and C-size
paper drawings).
G.11 Training records, training matrix, and lesson plans related to
10 CFR 50.54(hh)(2).
G.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments)
required to implement any mitigating strategies.
Attachment 2
Confirmatory Letter Document Request
H. Waterford Steam Electric Station - Confirmatory Order NRC Inspection
Report 05000382/2016007 and NRC Investigation Report 4-2014-017
H1. Updated Fire Watch Procedures from the Order
H2. Additional Procedures, including new requirement for Fire Watch oversight
monitoring since the Order
H3. Training Programs and Procedure Implementing lessons learned from the Orders
H4. Maintenance activities and Supervisory Monitoring program being implemented
to address the Fire Watch program from the Order
H5. Documented Lessons Learned from the Order
H6. Corrective Actions for the implementation of the Order actions
H7. Assessment activities associated with the Order
H8. Root Cause Analysis associated with Order
Attachment 3
ML18101A096
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002
By: JMM Yes No Publicly Available Sensitive
OFFICE SRI:EB2 C:EB2
NAME JMateychick GWerner
SIGNATURE /RA/ /RA/JFD for
DATE 04/10/18 04/10/18