Letter Sequence RAI |
---|
|
Results
Other: ML13317A969, ML15141A468, ML15272A398, W3F1-2012-0092, Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), W3F1-2012-0093, Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049), W3F1-2013-0006, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, Order Number EA-12-051, W3F1-2013-0010, (Waterford 3), Entergy Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3, W3F1-2013-0049, First Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, W3F1-2013-0050, First Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, W3F1-2014-0014, Second Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, W3F1-2014-0015, Second Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, W3F1-2014-0049, Third Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, W3F1-2014-0050, Third Six-Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Waterford Steam Electric Station, Un, W3F1-2015-0003, Fourth Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, W3F1-2015-0004, Fourth Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, W3F1-2015-0068, Fifth Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation
|
MONTHYEARW3F1-2012-0042, Entergy'S 90-Day Response to the March 12, 2012, Information Request, Action Plan for Completing Emergency Communication and Staffing Assessments2012-06-0707 June 2012 Entergy'S 90-Day Response to the March 12, 2012, Information Request, Action Plan for Completing Emergency Communication and Staffing Assessments Project stage: Request W3F1-2012-0092, Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2012-10-26026 October 2012 Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other W3F1-2012-0093, Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2012-10-26026 October 2012 Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) Project stage: Other W3F1-2013-0010, (Waterford 3), Entergy Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.32013-02-21021 February 2013 (Waterford 3), Entergy Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3 Project stage: Other W3F1-2013-0006, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, Order Number EA-12-0512013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation, Order Number EA-12-051 Project stage: Other W3F1-2013-0017, (Waterford 3), Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 (Waterford 3), Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Request ML13246A3182013-08-28028 August 2013 Request for Additional Information E-mail, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: RAI W3F1-2013-0049, First Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation2013-08-28028 August 2013 First Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Other W3F1-2013-0050, First Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-08-28028 August 2013 First Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other W3F1-2013-0055, Response to Request for Additional Information (RAI) for the Overall Integrated Plan (OIP) in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool (SFP) Instrumentation2013-09-26026 September 2013 Response to Request for Additional Information (RAI) for the Overall Integrated Plan (OIP) in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool (SFP) Instrumentation Project stage: Response to RAI ML13317A9692013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Waterford Steam Electric Generating Station, Unit 3, TAC No.: MF0977 Project stage: Other ML13220A4022013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies Project stage: Acceptance Review ML13312A7872013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: RAI W3F1-2014-0015, Second Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation2014-02-28028 February 2014 Second Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Other W3F1-2014-0014, Second Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-02-28028 February 2014 Second Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other W3F1-2014-0050, Third Six-Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Waterford Steam Electric Station, Un2014-08-28028 August 2014 Third Six-Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Waterford Steam Electric Station, Unit 3 Project stage: Other W3F1-2014-0049, Third Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation2014-08-28028 August 2014 Third Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Other W3F1-2015-0003, Fourth Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-02-26026 February 2015 Fourth Six Month Status Report for Implementation of Order EA-12-049, Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other W3F1-2015-0004, Fourth Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation2015-02-26026 February 2015 Fourth Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Other ML15141A4682015-05-27027 May 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other W3F1-2015-0068, Fifth Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation2015-08-27027 August 2015 Fifth Six Month Status Report for Implementation of Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Other W3F1-2015-0073, Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.2015-08-31031 August 2015 Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. Project stage: Request ML15245A3442015-10-0404 October 2015 Relaxation of the Schedule Requirements for Order EA-12-049 Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Approval ML15272A3982015-10-0606 October 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other 2013-09-26
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML24159A2672024-06-0707 June 2024 NRR E-mail Capture - NRC Notice of Acceptance: Waterford Steam Electric Station, Unit 3, Licensee Amendment Request (LAR) to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program ML24137A2702024-05-16016 May 2024 NRR E-mail Capture - Entergy Fleet - Acceptance Review of License Amendment Request to Remove Obsolete License Conditions from Operating Licenses for GGNS, RBS, and WF3 (L-2024-LLA-0062) ML24115A0862024-04-23023 April 2024 NRR E-mail Capture - NRC Notice of Acceptance: Waterford Steam Electric Station, Unit 3, Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24115A0882024-04-23023 April 2024 NRR E-mail Capture - NRC Notice of Acceptance: Waterford Steam Electric Station, Unit 3, Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24088A0092024-03-27027 March 2024 NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054) ML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML23097A0412023-04-0606 April 2023 June 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23076A0552023-03-13013 March 2023 EP Program Inspection RFI Hjs 10132022 ML23072A3672023-03-0909 March 2023 NRR E-mail Capture - Entergy Fleet - Acceptance Review of Quality Assurance Program Manual Reduction in Commitment ML23052A0882023-02-17017 February 2023 Inspection Request for Information ML22336A0202022-12-0101 December 2022 NRR E-mail Capture - Acceptance Review for Waterford Unit 3 - License Amendment Request to Revise Technical Specification 3/4.3.2 ML22335A4802022-12-0101 December 2022 NRR E-mail Capture - NRC Update Completion Date for Waterford 3 LAR to Adopt TSTF-505 ML22329A0152022-11-0202 November 2022 NRR E-mail Capture - NRC Update Completion Date for Waterford 3 LAR to Adopt TSTF-505 ML22290A0442022-10-13013 October 2022 December 2022 Emergency Preparedness Program Inspection - Request for Information ML22215A1492022-08-0303 August 2022 NRR E-mail Capture - Waterford 3 - LAR to Permit the Use of Risk-Informed Completion Times in Accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2 ML22215A2062022-08-0303 August 2022 NRR E-mail Capture - Waterford 3 - LAR to Adopt Title 10 of the Code of Federal Regulations, Section 50.69: Loe and Completion Date Update ML22206A0172022-07-22022 July 2022 NRR E-mail Capture - Request for Additional Information: Waterford 3 - License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 ML22206A0152022-07-21021 July 2022 NRR E-mail Capture - Entergy (Grand Gulf, River Bend, and Waterford-3) - Acceptance Review of the RR EN-RR-22-001, Case N-752, Risk-informed Cat & Treatment for Repair/Replacement Activities in Class 2 & 3 Systems ML22209A1082022-07-15015 July 2022 NRR E-mail Capture - Draft RAIs to License Amendment Request for Application to Adopt 10 CFR 50.69 and Revise Technical Specifications to Adopt TSTF-505, Revision 2 ML22144A1662022-05-24024 May 2022 PI&R Request for Information and Transmittal e-mail ML22108A1792022-04-14014 April 2022 WF3 Cpcs Installation Inspection Plan Email ML22209A1062022-01-20020 January 2022 NRR E-mail Capture - (External_Sender) Options Moving Forward Regarding Waterford TSTF-505 and 50.69 ML22209A1052022-01-0606 January 2022 NRR E-mail Capture - Estimate for Completion of 50.69-TSTF-505 Peer Review ML22012A1592022-01-0505 January 2022 WF3 2022 EP Exercise Inspection RFI Sdh 010522 ML21356A5872021-12-22022 December 2021 NRR E-mail Capture - Acceptance for Review: Waterford 3 - Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML21349A2242021-12-14014 December 2021 NRR E-mail Capture - (External_Sender) Waterford 3 - Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial EP Exercise ML21312A4792021-11-0505 November 2021 Email: NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development ML21308A5602021-11-0404 November 2021 NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, Grand Gulf, River Bend, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21292A0112021-10-18018 October 2021 NRR E-mail Capture - ANO, 1 and 2, Grand Gulf, River Bend, Waterford, 3 - Acceptance Review of LAR to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21280A0812021-10-0505 October 2021 Email 10-5-21 - Request for Information_ Waterford EP Inspection (71114.04 & 71151) - Nov-Dec 2021 ML21285A0242021-10-0505 October 2021 Digital Instrumentation and Control Modification Inspection Request for Information ML22112A1512021-08-0606 August 2021 NRR E-mail Capture - for Review: Draft RAIs to LAR to Relocate Chemical Detection Systems Technical Specifications (TS) to Technical Requirements Manual (TRM) ML21216A4562021-08-0404 August 2021 WF3 2021 EP Exercise Inspection Request for Information (RFI) ML21218A0402021-07-26026 July 2021 NRR E-mail Capture - Final RAIs to Entergy Operations, Waterford Steam Electric Station, Unit 3 LAR to Adopt 10 CFR 50.69 ML21201A0062021-07-19019 July 2021 NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21173A1082021-06-22022 June 2021 NRR E-mail Capture - Acceptance Review for Waterford Unit 3 - License Amendment Request to Adopt TSTF-563 ML21174A0342021-06-22022 June 2021 NRR E-mail Capture - Entergy Fleet (ANO, Ggulf, Rbend, & Waterford) - Acceptance Review for Relief Request to Use a Provision of a Later Edition of the ASME Code, Section XI for Periodic System Pressure Tests Exemptions ML21160A0852021-06-0404 June 2021 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Louisiana Regarding a Waterford Steam Electric Station, Unit 3 Amendment - Digital Upgrade I&C ML21145A0062021-05-24024 May 2021 NRR E-mail Capture - Supplement Received - Waterford Unit 3 - License Amendment Request for Boration Systems Tech Specs ML21120A1192021-04-30030 April 2021 NRR E-mail Capture - Acceptance Review for Waterford Unit 3 - LAR to Relocate Chemical Detection TSs to TRM ML21105A0512021-04-14014 April 2021 4-14-21 Email - RFI for In-Office Inspection of Recent WF3 Submission of EAL Procedure Revision ML21104A0382021-04-13013 April 2021 NRR E-mail Capture - Acceptance Review for Waterford Unit 3 - License Amendment Request for TSTF-505 ML21084A2552021-03-22022 March 2021 NRR E-mail Capture - Supplement to Audit Plan Dated October 1, 2020 (Waterford 3, L-2020-LLA-0164) ML21088A1512021-03-15015 March 2021 NRR E-mail Capture - Draft Waterford Acceptance Review Letter for TSTF-505 LAR ML21069A1842021-03-0202 March 2021 NRR E-mail Capture - Announcement of QA Inspection ML21040A3892021-02-0808 February 2021 NRR E-mail Capture - Announcement of QA Inspection ML21039A6412021-01-28028 January 2021 NRR E-mail Capture - NRC LIC-109 Acceptance Review Results for Waterford 3 50.69 LAR ML21022A1692021-01-22022 January 2021 NRR E-mail Capture - Entergy Fleet (ANO, Grand Gulf, River Bend, and Waterford) - Acceptance Review for RR EN-20-RR-003, Proposed Alternative to Use ASME Code Case N-711-2 ML20329A1442020-11-20020 November 2020 Terrapower QAPD Preliminary Questions Email ML20288A2082020-10-0808 October 2020 8Oct2020 Email - Request for Information (RFI) to Support and Prepare for the Emergency Preparedness (EP) Program Inspection at the Waterford 3 Station Scheduled to Occur the Week of December 7, 2020 2024-06-07
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24088A0092024-03-27027 March 2024 NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054) ML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23097A0412023-04-0606 April 2023 June 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23076A0552023-03-13013 March 2023 EP Program Inspection RFI Hjs 10132022 ML23052A0882023-02-17017 February 2023 Inspection Request for Information ML22290A0442022-10-13013 October 2022 December 2022 Emergency Preparedness Program Inspection - Request for Information ML22206A0172022-07-22022 July 2022 NRR E-mail Capture - Request for Additional Information: Waterford 3 - License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 ML22209A1082022-07-15015 July 2022 NRR E-mail Capture - Draft RAIs to License Amendment Request for Application to Adopt 10 CFR 50.69 and Revise Technical Specifications to Adopt TSTF-505, Revision 2 ML22103A1712022-04-13013 April 2022 LAR to Revise TS to Adopt TSTF-505_NRC Request for Additional Information ML22012A1592022-01-0505 January 2022 WF3 2022 EP Exercise Inspection RFI Sdh 010522 ML21285A0242021-10-0505 October 2021 Digital Instrumentation and Control Modification Inspection Request for Information ML21280A0812021-10-0505 October 2021 Email 10-5-21 - Request for Information_ Waterford EP Inspection (71114.04 & 71151) - Nov-Dec 2021 ML22112A1512021-08-0606 August 2021 NRR E-mail Capture - for Review: Draft RAIs to LAR to Relocate Chemical Detection Systems Technical Specifications (TS) to Technical Requirements Manual (TRM) ML21216A4562021-08-0404 August 2021 WF3 2021 EP Exercise Inspection Request for Information (RFI) ML21218A0402021-07-26026 July 2021 NRR E-mail Capture - Final RAIs to Entergy Operations, Waterford Steam Electric Station, Unit 3 LAR to Adopt 10 CFR 50.69 ML21196A5302021-07-19019 July 2021 Wat 2021010 RFI Letter 21N_05 Gap ML21195A0692021-07-13013 July 2021 Staton, Unit 3 - Notification of Digital Instrumentation and Control Modification Inspection and Request for Information ML21125A6522021-05-0606 May 2021 Wat 2021003 Brq RFI- Md, Waterford Steam Electric Station, Unit 3, Notification of Inspection (NRC Inspection Report 05000382/2021003) and Request for Information ML21112A2542021-04-29029 April 2021 Request for Additional Information Digital Upgrade to the Core Protection and Control Element Assembly Calculator System (EPID L 2020 Lla 0164) - Redacted Version ML20288A2082020-10-0808 October 2020 8Oct2020 Email - Request for Information (RFI) to Support and Prepare for the Emergency Preparedness (EP) Program Inspection at the Waterford 3 Station Scheduled to Occur the Week of December 7, 2020 ML20289A3502020-10-0505 October 2020 NRR E-mail Capture - NRC Request for Additional Information - WF3 EAL Scheme Change - L-2020-LLA-0122 ML20125A3212020-05-0404 May 2020 WAT2020410 Inspection Document Request ML20086M3852020-04-0101 April 2020 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4 8.1, A.C. Sources Operating W3F1-2020-0014, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System2020-03-20020 March 2020 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System ML20049A4102020-02-20020 February 2020 Request for Additional Information Regarding License Amendment Request to Revise Surveillance Requirement 4.7.6.1.d, Control Room Air Filtration System ML19262H0362019-09-0404 September 2019 Ti 2515/194 Request for Information and Email ML19274D4932019-07-24024 July 2019 Request for Information IR 05000382 2019-003 Occupational Radiation Safety Inspection ML19203A0062019-07-19019 July 2019 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information (Rais) Re Relief Request WF3-RR-19-2: Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19151A6102019-06-0404 June 2019 Non-Proprietary Second Round RAI Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19172A0852019-05-24024 May 2019 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information (Rais) Re Relief Request W3-ISI-032: Volumetric Examination Requirements ML19035A0412019-02-0101 February 2019 NRR E-mail Capture - Waterford 3 - Final Request for Information Regarding Relief Request WF3-RR-19-001 for Application of Dissimilar Metal Weld Full Structural Weld Overlay ML19018A0102019-01-28028 January 2019 Request for Additional Information Regarding License Amendment Request for Revision of Technical Specification 3/4.7.4,Ultimate Heat Sink ML18320A0902018-11-26026 November 2018 Request for Additional Information Regarding License Amendment Request for Use of the Transflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML18318A4352018-11-14014 November 2018 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information Regarding Request for Alternative to ASME Code Case N-770-2 ML18299A0862018-11-0707 November 2018 Draft Request for Additional Information License Amendment Request Regarding the Revision of UFSAR Section 3.9 ML18262A0412018-09-25025 September 2018 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 ML18145A2652018-06-0101 June 2018 Supplemental Information Needed for Acceptance of Request for Licensing Action Use of Tranflow Code for Determining Pressure Drops Across Steam Generator Secondary Side Components ML18085A6942018-03-26026 March 2018 Ref: Waterford Steam Electric Station, Unit 3, License Renewal Application - RAI Set 18 ML18058A0572018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update) ML18039A9722018-02-0808 February 2018 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000382/2018002) and Request for Information ML17233A2402017-08-14014 August 2017 NRR E-mail Capture - Draft RAI for Waterford Unit 3 Regarding License Amendment Request to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML17170A3012017-06-16016 June 2017 Notification of Inspection (NRC Integrated Inspection Report 05000382/2017003) and Request for Information ML17101A4432017-04-17017 April 2017 Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 17 ML17086A5852017-03-28028 March 2017 Request for Additional Information for the Environmental Review of Waterford 3 ML17072A0102017-03-14014 March 2017 Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application Set - 15 ML17272A3352017-03-0101 March 2017 Request for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 14 ML17040A5382017-02-14014 February 2017 Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 13 ML17018A3592017-01-26026 January 2017 Requests For Additional Information For The Review Of The Waterford Steam Electric Station, Unit 3, License Renewal Application Set 12 (CAC MF7492.) 2024-06-04
[Table view] |
Text
1Burkhardt, JanetFrom:Kalyanam, KalySent:Wednesday, August 28, 2013 9:02 AMTo:PELLEGRIN, BRYAN J (BPELLEG@entergy.com)Cc:Burkhardt, JanetSubject:RAI on Licensee's letter dated February 28, 2013, re. Requirements for Reliable SFP InstrumentationSUNSI Information:
Licensee: Entergy Operations Inc.
Plant: Waterford Steam Electric Station, Unit 3 Docket No.: 50/382 From: N. Kalyanam To: Bryan Pellegrin
Subject:
RAI on Licensee's letter dated February 28, 2013, re. Requirements for Reliable SFP Instrumentation TAC No.: MF0946 SUNSI Review Done: Yes.
Publicly Available, Normal Release, Non-sensitive,
To: Bryan Pellegrin
By letter dated February 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13063A263), Entergy Operations, Inc. submitted an Overall Integrated Plan (OIP) in response to the March 12, 2012, Commission Order to modify licenses with regard to requirements for Reliable Spent Fuel Pool (SFP) Instrumentation (Order Number EA-12-051) for Waterford Steam Electric Station, Unit 3. The NRC staff has identified additional information that is needed to complete the Technical Review (TR). The staff's Request for Additional Information (RAI) is as below.
Thanks (Kaly) N. Kalyanam
REQUEST FOR ADDITIONAL INFORMATION 2OVERALL INTEGRATED PLAN IN RESPONSE TO ORDER EA-12-051 "RELIABLE SPENT FUEL POOL INSTRUMENTATION" ENTERGY OPERATIONS, INC WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 1.0 INTRODUCTION By letter dated February 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13063A263), Entergy Operations, Inc. submitted an Overall Integrated Plan (OIP) in response to the March 12, 2012, Commission Order modifying licenses with regard to requirements for Reliable Spent Fuel Pool (SFP) Instrumentation (Order Number EA-12-051; ADAMS Accession No.
ML12054A679) for Waterford Steam Electric Station, Unit 3. The NRC staff endorsed Nuclear Energy Institute (NEI) 12-02 "Industry Guidance for Compliance with NRC Order EA-12-051, to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," Revision 1, dated August 2012 (ADAMS Accession No.
ML12240A307), with exceptions, as documented in Interim Staff Guidance (ISG) 2012-03 "Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation," Revision 0, dated August 29, 2012 (ADAMS Accession No. ML12221A339).
The NRC staff has reviewed the February 28, 2013, response by the licensee and determined that the following Request for Additional Information (RAI) is needed to complete its Technical Review. If any part of this information is not available within the 30-day response period for this RAI, please provide the date this information will be submitted.
2.0 LEVELS OF REQUIRED MONITORING The OIP states, in part, that LEVEL 1: Level 1 is the level adequate to support operation of the normal fuel pool cooling system. It is the higher of the following two points: (1) the level at which reliable suction loss occurs due to uncovering the coolant inlet pipe or any weirs or vacuum breakers associated with suction loss. For Waterford, this level, (1), is established based on the level at which the SFP cooling pumps automatically trip which is at elevation 41 feet 6 inches (Reference 6). This elevation is above the point where the pumps lose suction (Reference 7). (2) the level at which the normal fuel pool cooling pumps lose required NPSH assuming saturated conditions in the pool. An evaluation will be completed to demonstrate that this elevation is below the elevation that defines Level 1. The higher of the above points is (1). Therefore, LEVEL 1 is elevation 41 feet 6 inches.
3LEVEL 2: Level 2 is the level adequate to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck. Level 2 may be based on either of the following: (1) 10 feet + 1 foot above the highest point of any fuel rack seated in the spent fuel pool. The elevation associated with this level is 30 feet 0 inches + 1 foot (i.e., Level 3+10 feet).
(2) A designated level that provides adequate radiation shielding to maintain personnel dose within acceptable limits while performing local operations in the vicinity of the pool. This level is based on plant-specific or appropriate generic shielding calculations. The elevation associated with this level is not calculated since item (1) is used to establish Level 2 as permitted by NEI 12-02 Revision 1. Therefore, LEVEL 2 is elevation 30 feet 0 inches + 1 foot (i.e., 10 feet above Level 3). LEVEL 3: Level 3 is the level where fuel remains covered. It is defined as the highest point of any fuel rack seated in the spent fuel pool (within + 1 foot). The highest point of any fuel rack seated in the spent fuel pool is elevation 20 feet 0 inches (Reference 8 and 9). Therefore, Level 3 is elevation 20 feet 0 inches + 1 foot. The SFP level instrument span will extend down to at least 3 inches below the upper limit of the range of LEVEL 3 to account for accuracy or instrument loop uncertainty. Therefore, the SFP level probe will extend down to at least elevation 20 feet 9 inches. RAI-1 Please provide the following: a) Specifically, for level 1, demonstrate that the results of the evaluation described shows that the identified elevation represents the HIGHER of the two points described in the NEI 12-02 guidance for this level. b) A clearly labeled sketch depicting the elevation view of the proposed typical mounting arrangement for the portions of instrument channel consisting of permanent measurement channel equipment (e.g., fixed level sensors and/or stilling wells, and mounting brackets). Indicate on this sketch the datum values representing Level 1, Level 2, and Level 3 as well as the top of the fuel racks. Indicate on this sketch the portion of the level sensor measurement range that is sensitive to measurement of the fuel pool level, with respect to the Level 1, Level 2, and Level 3 datum points. c) The OIP states, in section 3.3, Mounting, "Other hardware stored in the SFP will be evaluated to ensure that it does not adversely interact with the SFP instrument probes during a seismic event."
Please provide a discussion regarding dose rates for stored spent fuel versus that of other material that may be stored in the pool.
43.0 INSTRUMENTATION DESIGN FEATURES 3.2 Arrangement The OIP states, in part, that Level instruments will be installed in the approximate locations shown on Attachment 1. Separation of the channels/probes reduces the potential for falling debris or missiles affecting both channels of instrumentation. This placement coupled with separate routing paths for cables and use of rigid conduit provides reasonable protection against falling debris and structural damage.
The location of the display/processors is in the Reactor Auxiliary Building as shown on
Attachment
s 1 and 2. This building is expected to be a mild environment after a Beyond Design Basis External (BDBE) event and can be easily accessed from the Main Control Room; therefore, personnel can promptly obtain readings from the display. This building provides adequate protection against the effects of temperature, flood, humidity, radiation, seismic events, and missile hazards.
RAI-2 Please modify the marked-up plant drawing of the plan view (in Attachment 1, Page 1 of 2) of the SFP area, to depict the approximate SFP inside dimensions.
3.3 Mounting The OIP states, in part, that Both the primary and backup system will be installed as seismic category I to meet the NRC JLD-ISG-2012-03 and NEI 12-02 guidance requirements. Other hardware stored in the SFP will be evaluated to ensure that it does not adversely interact with the SFP instrument probes during a seismic event. RAI-3 Please provide the following: a) The design criteria that will be used to estimate the total loading on the mounting device(s), including static weight loads and dynamic loads. Describe the methodology that will be used to estimate the total loading, inclusive of design basis maximum seismic loads and the hydrodynamic loads that could result from pool sloshing or other effects that could accompany such seismic forces.
b) A description of the manner in which the level sensor (and stilling well, if appropriate) will be attached to the refueling floor and/or other support structures for each planned point of attachment of the probe assembly. Indicate in a schematic the 5c) portions of the level sensor that will serve as points of attachment for mechanical/mounting or electrical connections. d) A description of the manner by which the mechanical connections will attach the level instrument to permanent SFP structures so as to support the level sensor assembly.
e) A description of how other material stored in the SFP will not create adverse interaction with the fixed instrument location(s).
3.4 Qualification The OIP states, in part, that Design criteria will ensure instrument channel reliability during normal, event, and post-event conditions for no fewer than seven days or until off-site resources can be deployed. Analyses, operating experience, and/or manufacturer testing of channel components will be used to validate design criteria and will consider the following:
- Post event conditions in the area of instrument channel components
- Effects of shock and vibration on all instrument channel components
- Seismic effects on instrument channel components during and following a potential seismic event. RAI-4 Please provide the following:
a) A description of the specific method or combination of methods you intend to apply to demonstrate the reliability of the permanently installed equipment under Beyond-Design-Basis (BDB) ambient temperature, humidity, shock, vibration, and radiation conditions.
b) A description of the testing and/or analyses that will be conducted to provide assurance that the equipment will perform reliably under the worst-case credible design basis loading at the location where the equipment will be mounted. Include a discussion of this seismic reliability demonstration as it applies to a) the level sensor mounted in the SFP area, and b) any control boxes, electronics, or read-out and re-transmitting devices that will be employed to convey the level information from the level sensor to the plant operators or emergency responders. c) A description of the specific method or combination of methods that will be used to confirm the reliability of the permanently installed equipment such that following a seismic event the instrument will maintain its required accuracy.
63.5 Independence The OIP states, in part, that The primary instrument channel will be independent of the backup instrument channel. Independence is obtained by physical separation of components between channels and the use of normal power supplied from separate 480V buses. Independence of power sources is described in Section 11. The two (2) permanently mounted instruments in the pool are physically separated as described in Sections 6 and 7. RAI-5 Please provide the following:
a) A description of how the two channels of the proposed level measurement system in each pool meet this requirement so that the potential for a common cause event to adversely affect both channels is minimized to the extent practicable.
b) Further information describing the design and installation of each level measurement system, consisting of level sensor electronics, cabling, and readout devices. Please address how independence of signals sent to the location(s) of the readout devices, and the independence of the displays. 3.6 Power Supplies The OIP states, in part, that The power supplies for the instrument channels are shown on Attachment 2 and arranged as follows:
- Each instrument channel is normally powered from 120VAC 60 Hz plant power to support continuous monitoring of SFP level. The primary channel receives power from a different 480V bus than the backup channel. Therefore, loss of any one 480V bus does not result in loss of normal 120VAC power for both instrument channels.
- On loss of normal 120VAC power, each channel's UPS automatically transfers to a dedicated backup battery. If normal power is restored, the channel will automatically transfers back to the normal AC power.
- The backup batteries are maintained in a charged state by commercial-grade uninterruptible power supplies. The batteries are sized to be capable of supporting intermittent monitoring for a minimum of 3 days of operation. This provides adequate time to allow the batteries to be replaced or until off-site resources can be deployed by the mitigating strategies resulting from Order EA-12-049 Revision 0.
7* An external connection permits powering the system from any portable DC source.
- Instrument accuracy and performance are not affected by restoration of power or restarting the processor. RAI-6 Please provide the following: a) A description of the specific electrical AC power sources and capacities for the primary and backup channels. b) A description of the design criteria that will be applied to size the battery in a manner that ensures, with margin, that the channel will be available to run reliably and continuously following the onset of the BDB event for the minimum duration needed, consistent with the plant mitigation strategies for BDB external events (Order EA-12-049). 3.7 Accuracy The OIP states, in part, that Accuracy will be consistent with the guidelines of NRC JLD-ISG-2012-03 Revision 0 and NEI 12-02 Revision 1. Accuracy and indication features are as follows:
- Accuracy: The absolute system accuracy is better than + 3 inches. This accuracy is applicable for normal conditions and the temperature, humidity, chemistry, and radiation levels expected for BDBE event conditions.
- Trending: The display trends and retains data when powered from either normal or backup power.
- Restoration after Loss of Power: The system automatically swaps to available power (backup battery power or external DC source) when normal power is lost. Neither the source of power nor system restoration impact accuracy. Previously collected data is retained.
- Diagnostics: The system performs and displays the results of real-time information related to the integrity of the cable, probe, and instrument channel.
8RAI-7 Please provide the following: a) An estimate of the expected instrument channel accuracy performance (e.g., in % of span) under both a) normal SFP level conditions (approximately Level 1 or higher) and b) at the BDB conditions (i.e., radiation, temperature, humidity, post-seismic and post-shock conditions) that would be present if the SFP level were at the Level 2 and Level 3 datum points. b) A description of the methodology that will be used for determining the maximum allowed deviation from the instrument channel design accuracy that will be employed under normal operating conditions as an acceptance criterion for a calibration procedure to flag to operators and to technicians that the channel requires adjustment to within the normal condition design accuracy.
3.8 Testing The OIP states, in part, that Testing and calibration will be consistent with the guidelines of NRC JLD-ISG-2012-03 Revision 0 and NEI 12-02 Revision 1 and vendor recommendations.
The display/processor performs automatic in-situ calibration and automatically monitors for cable, connector, and probe faults using time domain reflectometry (TDR) technology. Channel degradation due to age or corrosion is not expected but can be identified by monitoring trends.
Station procedures and preventive maintenance tasks will be developed to perform required surveillance testing, calibration, backup battery maintenance, functional checks, and visual inspections of the probes.
RAI- 8 Please provide the following:
a) A description of the capability and provisions the proposed level sensing equipment will have to enable periodic testing and calibration, including how this capability enables the equipment to be tested in-situ. b) A description of how such testing and calibration will enable the conduct of regular channel checks of each independent channel against the other, and against any other permanently-installed SFP level instrumentation. c) A description of how calibration tests and functional checks will be performed and the frequency at which they will be conducted. Discuss how these surveillances will be incorporated into the plant surveillance program.
9d) A description of what preventative maintenance tasks are required to be performed during normal operation, and the planned maximum surveillance interval that is necessary to ensure that the channels are fully conditioned to accurately and reliably perform their functions when needed. 3.9 Display The OIP states, in part, that The primary and backup instrument displays will be located in the Reactor Auxiliary Building as shown on Attachments 1 and 2. The display will be consistent with the guidelines of NRC JLD-ISG-2012-03 Revision 0 and NEI 12-02 Revision 1.
RAI-9 Please provide the following: a) For display locations that are not within the main control room, provide a description of the display location that addresses primary and alternate access route evaluation, continuous habitability at display location(s), continual resource availability for personnel responsible to promptly read displays, and provisions for verbal communications with decision makers for the various SFP drain down scenarios and external events.
b) The reasons justifying why the locations selected will enable the information from these instruments to be considered "promptly accessible". Include consideration of various drain-down scenarios. 4.0 PROGRAM FEATURES 4.2 Procedures The OIP states, in part, that Procedures for maintenance and testing will be developed using regulatory guidelines and vendor instructions.
BDBE event operation guidance will also address the following:
- A strategy to ensure SFP water addition is initiated at an appropriate time consistent with implementation of NEI 12-06.
- Restoration of non-functioning SFP level channels after an event 10* Restoration timing will be consistent with the emergency condition. After an event, commercially available components that may not meet all qualifications may be used to replace components to restore functionality. RAI-10 Please provide the following:
a) A list of the operating (both normal and abnormal response) procedures, calibration/test procedures, maintenance procedures, and inspection procedures that will be developed for use of the SFP instrumentation in a manner that addresses the order requirements. b) A brief description of the specific technical objectives to be achieved within each procedure. If your plan incorporates the use of portable spent fuel level monitoring components, please include a description of the objectives to be achieved with regard to the storage location and provisions for installation of the portable components when needed. 4.3 Testing and Calibration The OIP states, in part, that Testing and calibration will be consistent with the guidelines of NRC JLD-ISG-2012- 03 Revision 0 and NEI 12-02 Revision 1 and vendor recommendations.
Station procedures and preventive maintenance tasks will be developed to perform required surveillance testing, calibration, backup battery maintenance, functional checks, and visual inspections of the probes.
RAI-11 Please provide the following:
a) Further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of your plans for ensuring that necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment. b) A description of how the guidance in NEI 12-02 Section 4.3 regarding compensatory actions for one or both non-functioning channels will be addressed.
c) A description of the compensatory actions to be taken in the event that one of the instrument channels cannot be restored to functional status within 90 days. a.