Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML040300802, ML040631055, ML042520157, ML042670485, ML050870511, ML051090111, W3F1-2004-0085, Schedule Clarification for Amendment Request NPF-38-249, Extended Power Uprate, W3F1-2004-0101, to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 3
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MONTHYEARML0401405152004-01-14014 January 2004 Meeting with Entergy, Waterford Steam Electric Station, Unit 3 Extended Power Uprate Amendment Request Dated 11/13/2003 Project stage: Meeting ML0425201572004-01-14014 January 2004 E-mail to T. Alexion Dated 1/14/04 Waterford - Extended Power Uprate Project stage: Other ML0403008022004-01-28028 January 2004 FRN -Notice of Consideration of Issuance of Amendment for Extended Power Uprate and Opportunity for Hearing Project stage: Other ML0403302602004-01-28028 January 2004 1/28/04 Waterford 3 - RAI Revision to Facility Operating License & TS - Extended Power Uprate Request. TAC MC1355 Project stage: RAI W3F1-2004-0004, Supplemental Information Extended Power Uprate - Power Ascension Testing2004-01-29029 January 2004 Supplemental Information Extended Power Uprate - Power Ascension Testing Project stage: Request ML0425201642004-01-30030 January 2004 E-mail Dated 1/30/04 RAI from Environmental Section on Waterford Unit 3 Project stage: RAI ML0425201672004-02-10010 February 2004 E-mail Dated 2/10/04 Waterford - Draft RAI from Human Performance, Piping Integrity and Electrical Groups Project stage: Draft RAI ML0425201702004-02-18018 February 2004 E-mail Dated 2/18/04 Re RAI from I&C - Waterford Project stage: RAI ML0405506052004-02-20020 February 2004 Westinghouse Request Withholding from Public Disclosure, Waterford 3, Extended Power Uprate, Appendix 1 - Safety Evaluation Report Compliance, MC1355 Project stage: Approval ML0425201712004-02-23023 February 2004 E-mail Dated 2/23/04 Waterford RAI Containment Systems Project stage: RAI ML0406310552004-02-26026 February 2004 Summary of Entergy Operations, Inc. Presentation of Extended Power Uprate Project stage: Other ML0426704892004-03-0202 March 2004 E-mail from B. Miller to N. Kalyanam RAI from SPLB-Angelo Stubbs Project stage: RAI ML0426704852004-03-0202 March 2004 E-mail from D. Miller to K. Kalyanam Re RAI from J. Tsao Project stage: Other W3F1-2004-0017, Supplement to Amendment Request NPF-38-249 Regarding Extended Power Uprate2004-03-0404 March 2004 Supplement to Amendment Request NPF-38-249 Regarding Extended Power Uprate Project stage: Supplement ML0406909622004-03-0909 March 2004 Extended Power Uprate Acceptance Review Project stage: Acceptance Review ML0407809952004-03-16016 March 2004 RAI, Proposed Revision to Facility Operation License and TSs - Extended Power Uprate Request Project stage: RAI ML0408506542004-03-24024 March 2004 RAI Related to Revision to Facility Operating License and TSs - Extended Power Uprate Request Project stage: RAI ML0412102452004-03-26026 March 2004 Request for Additional Information, Revision to Facility Operating License & Technical Specifications - Extended Power Uprate Request Project stage: RAI ML0409102392004-03-31031 March 2004 RAI Related to Revision to Facility Operating License and TSs - Extended Power Uprate Request Project stage: RAI ML0410005142004-04-0808 April 2004 RAI Related to Revision to Facility Operating License and TSs - Extended Power Uprate Request Project stage: RAI W3F1-2004-0029, Extended Power Uprate, Waterford, Unit 3 Supplement to Amendment Request2004-04-15015 April 2004 Extended Power Uprate, Waterford, Unit 3 Supplement to Amendment Request Project stage: Supplement ML0411301942004-04-20020 April 2004 RAI Related to Revision to Facility Operating License and TSs - Extended Power Uprate Request Project stage: RAI ML0412705672004-05-0404 May 2004 RAI, Revision to Facility Operating License and TSs - Extended Power Uprate Request Project stage: RAI W3F1-2004-0035, Supplemental to Amendment Request for Extended Power Uprate2004-05-0707 May 2004 Supplemental to Amendment Request for Extended Power Uprate Project stage: Supplement W3F1-2004-0037, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-05-12012 May 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement ML0413801452004-05-13013 May 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement W3F1-2004-0043, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-05-21021 May 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement W3F1-2004-0047, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-05-26026 May 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement ML0417405772004-06-21021 June 2004 RAI, Revision to Facility Operating License and Technical Specifications - Extended Power Uprate Request, TAC MC1355 Project stage: RAI W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-07-14014 July 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement ML0420202942004-07-15015 July 2004 License Amendment Request NPF-38-256, Alternate Source Term Project stage: Request W3F1-2004-0061, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-07-28028 July 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement ML0421100882004-07-29029 July 2004 Meeting with Entergy to Discuss Issues with Extended Power Uprate and Alternate Source Term Submittals Project stage: Request ML0422303352004-08-10010 August 2004 August 11, 12 and 13, 2004 Meeting with Westinghouse Re Waterford Main Steam Line Break, Feedwater Line Break and EPU Project stage: Meeting W3F1-2004-0068, Supplement to Amendment Request NPF-38-249 Extended Power Uprate2004-08-10010 August 2004 Supplement to Amendment Request NPF-38-249 Extended Power Uprate Project stage: Supplement W3F1-2004-0071, Supplement to Alternate Source Term Submittal2004-08-19019 August 2004 Supplement to Alternate Source Term Submittal Project stage: Request ML0423904892004-08-26026 August 2004 Meeting with Entergy to Discuss Issues with Extended Power Uprate and Alternate Source Term Submittals Project stage: Meeting W3F1-2004-0076, Supplement 2 to Amendment Request NPF-38-256, Alternate Source Term2004-09-0101 September 2004 Supplement 2 to Amendment Request NPF-38-256, Alternate Source Term Project stage: Supplement W3F1-2004-0078, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-09-14014 September 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement ML0427505192004-09-29029 September 2004 RAI Extended Power Uprate Request and Alternate Source Term Request Project stage: RAI ML0427402482004-09-30030 September 2004 (3) Steam Elecric Station, #3, Draft EA and Finding of No Significant Impact Related to a Proposed License Amendment to Increase the Licensed Power Level (Tac. MC1355) Project stage: Draft Other W3F1-2004-0092, Supplement to Amendment Request NPF-38-249 Extended Power Uprate2004-10-0808 October 2004 Supplement to Amendment Request NPF-38-249 Extended Power Uprate Project stage: Supplement W3F1-2004-0086, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-10-0808 October 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement W3F1-2004-0085, Schedule Clarification for Amendment Request NPF-38-249, Extended Power Uprate2004-10-13013 October 2004 Schedule Clarification for Amendment Request NPF-38-249, Extended Power Uprate Project stage: Other W3F1-2004-0095, Supplement 3 to Amendment Request NPF-38-256 Alternate Source Term2004-10-13013 October 2004 Supplement 3 to Amendment Request NPF-38-256 Alternate Source Term Project stage: Supplement W3F1-2004-0096, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2004-10-18018 October 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement W3F1-2004-0101, to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 32004-10-19019 October 2004 to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 3 Project stage: Other ML0430102382004-10-21021 October 2004 Supplement to Amendment Request NPF-38-249, Extended Power Uprate Project stage: Supplement ML0431006112004-10-26026 October 2004 RAI - Revision to Facility Operating License and Technical Specifications - Extended Power Uprate Request Project stage: RAI W3F1-2004-0089, Supplement to Amendment Request NPF-38-2492004-10-29029 October 2004 Supplement to Amendment Request NPF-38-249 Project stage: Supplement 2004-03-04
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Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 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 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 ML23312A1832023-11-14014 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 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 ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information 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 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 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 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 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23108A2542023-04-18018 April 2023 WCGS Information Request, Security IR 2023401 IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 ML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc ML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23060A1092023-03-0101 March 2023 Proof of Financial Protection (10 CFR 140.15) IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 ML23024A0822023-01-20020 January 2023 Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment 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 ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22332A5292022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000382/2023301 IR 05000382/20220132022-11-28028 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23348A1222023-12-14014 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 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 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.) ML16354A1052016-12-27027 December 2016 RAI License Amendment Request to Revise TS 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Feature Actuation System (ESFAS) Subgroup Relays to the Surveillance Frequency Control Program ML16356A5942016-12-19019 December 2016 NRR E-mail Capture - MF8325 Draft RAIs Regarding the License Amendment Request to Revise the Table Notation for Table 4.3-2, ESFAS Surveillance Requirements 2023-07-10
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION o
3WASHINGTON, D.C. 20555-0001 March 26, 2004 n**
Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 (WATERFORD 3) -
REQUEST FOR ADDITIONAL INFORMATION RELATED TO REVISION TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS -
EXTENDED POWER UPRATE REQUEST (TAC NO. MC1355)
Dear Mr. Venable:
By letter dated November 13, 2003, and supplemented by letters dated January 29 and March 4, 2004, Entergy Operations, Inc. proposed revisions to the Waterford 3 operating license and Technical Specifications which would allow an increase in the rated thermal power from 3,441 megawatts thermal (MWt) to 3,716 MWt.
After reviewing your request, the Nuclear Regulatory Commission staff has determined that additional information is required to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested in the enclosure within 30 days of receipt of this letter.
Ifyou have any questions, please call me at (301) 415-1480.
Sincerely, N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Request for Additional Information cc w/encl: See next page
Waterford Steam Electric Station, Unit 3 cc:
Mr. Michael E. Henry, State Liaison Officer Regional Administrator, Region IV Department of Environmental Quality U.S. Nuclear Regulatory Commission Permits Division 611 Ryan Plaza Drive, Suite 1000 P.O. Box 4313 Arlington, TX 76011 Baton Rouge, Louisiana 70821-4313 Parish President Council Vice President, Operations Support St. Charles Parish Entergy Operations, Inc. P. 0. Box 302 P. O. Box 31995 Hahnville, LA 70057 Jackson, MS 39286-1995 Executive Vice President Director & Chief Operating Officer Nuclear Safety Assurance Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 17265 River Road Jackson, MS 39286-1995 Killona, LA 70066-0751 Chairman Wise, Carter, Child & Caraway Louisiana Public Services Commission P. 0. Box 651 P. O. Box 91154 Jackson, MS 39205 Baton Rouge, LA 70825-1697 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Resident Inspector/Waterford NPS P. 0. Box 822 Killona, LA 70066-0751 July 2003
REQUEST FOR ADDITIONAL INFORMATION ENTERGY OPERATIONS. INC.
WATERFORD STEAM ELECTRIC STATION. UNIT 3 (WATERFORD 3)
DOCKET NO. 50-382 Instrumentation and Controls
- 1. Discuss the instrument setpoint methodology used to calculate trip setpoints and allowable values of the plant parameters affected by the extended power uprate (EPU).
If your methodology has not been previously reviewed by the U. S. Nuclear Regulatory Commission (NRC) staff, then submit a copy of the plant instrument setpoint methodology for the staff's review and approval. If you use 'method 3" specified in Independent Safety Analysis S67.04.02, then confirm that a check calculation is performed to account for all loop uncertainties not measured during the channel operational test/channel functional test. Please assure that adequate margin exists between the analytical limit and the allowable value that equals or exceeds the value of uncertainties not measured during the channel operational test. Please provide the documentation of the calculation which demonstrates the existence of an adequate margin. Discuss how the channel operability is determined for each of the plant parameters affected by the power uprate.
- 2. The Waterford 3 License Amendment Request NPF-38-249, EPU, dated November 13, 2003 (the application) states on page 2.13-10 that, as part of the power uprate, the response times for core protection calculator system low departure from nucleate boiling ratio and high low-power density trips were reviewed and enhancements to clarify the time requirements were identified, which included reductions in some of the times required to be assumed in safety analyses. Please identify these response time reduction items and the related safety analysis sections.
- 3. The application states on page 2.4-1 that the EPU also affects the atmospheric dump valve (ADV) controllers. The existing ADV analog controllers are being replaced with more accurate digital controllers. The ADV controllers perform safety-related functions, and therefore, covered by Part 50 of Title 10 of the Code of Federal Regulations (10 CFR), Appendix A, General Design Criterion 1, "Quality Standards and Records,"
which requires, in part, that structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Additionally, 10 CFR 50.55a(h) requires, in part, that protection systems satisfy the criteria of the Institute of Electrical and Electronics Engineers (IEEE) Standard 603, "Criteria for Safety Systems for Nuclear Power Generating Stations." Discuss the modification package of the ADV controllers to be installed at the Waterford 3 and address the following design requirements:
- a. Compliance with IEEE-603 (or IEEE-279) requirements
- b. Software life cycle process planning
- c. Design verification and validation process
- d. Configuration management process
- e. Maintenance, testing, and calibration process
- f. Environmental considerations, such as electro-magnetic interference, radio-frequency interference, effects of temperature and humidity, etc.
- 4. If ADV controllers use the commercial software-based devices, the digital components to be used in safety systems must be qualified for their intended application. Address the Waterford 3 plant-specific dedication of commercial grade digital equipment for nuclear safety application with respect to the guidance provided in NRC Standard Review Plan (SRP), Appendix 7.0-A, Section C.3.8, "Review of the Acceptance of Commercial-Grade Digital Equipment," and SRP Section 7.1, "Acceptance Criteria on Supplemental Guidance for Digital Computer-Based Safety Systems."
- 5. The ADVs are credited for small-break loss-of-coolant accident (SBLOCA) mitigation at greater than 70 percent rated power. A new Technical Specification (TS) was proposed.
Because the ADV controllers are digital devices, the common mode failure due to software error should be considered. Additional surveillance may be required after detecting one ADV inoperable. Discuss the adequacy of the proposed TS with respect to the common mode failure concern.
- 6. The EPU application, in Section 2.13.1.1.4.1, "General Description of the Event," states that one ADV may be inadvertently opened due to operator error or due to a failure in the ADV control system. Analyze the consequence for inadvertently open all ADVs due to a common mode failure at ADV digital controllers.
- 7. In Attachment 1, "Analysis of Proposed Technical Specification Changes," Section 4.0, states that in an effort to improve clarity for the operators, the word "indicated" or phrase Uan indicated" is being added to identify those values in TS that can be compared directly to plant instrument readings to ensure TS compliance. The staff considers that the plant instrument readings from indicators can only be used for channel check to detect a gross failure of an instrument channel. It is not acceptable to be used for TS compliance. There is no assurance that the "indicated" reading is reliable and conservative. The number in the TS should be based on safety analysis, and should meet the requirements of 10 CFR 50.36.(c)(2) to establish the lowest functional capability or performance level of equipment required for safe operation of the facility.
Therefore, the word "indicated" or "an indicated" cannot be used in the TS.
- 8. Sectibn 7.8.3.2 of the final safety analyses report (FSAR), "Diverse Emergency Feedwater Actuation System (DEFAS)," states that the DEFAS actuation signals are interlocked with steam generator pressure. The power uprate requires a setpoint change on "steam generator pressure-low." Verify that the proposed setpoint change does not affect the DEFAS operation or cause inadvertent actuation of the DEFAS.
- 9. Verify the inconsistency between TS and BASES. For example, TS 3/4.2.6, "Reactor Coolant Cold Leg Temperature," Limiting Condition for Operation 3.2.6 states "The reactor coolant cold leg temperature shall be maintained between 5360F and 5490 F."
while Bases 3/4.2.6 insert states "The safety analysis assumes that cold leg temperature is maintained between 553 0 F and 552°F or indicated temperatures of 556 0F and 5490F."
Quality and Maintenance
- 10. Attachment 3 of your letter dated January 29, 2004 (Supplement 1), states that test, "Load Changes," will be performed only at 95 percent power. This test occurred various times between 50 percent and 100 percent power during initial power ascension tests.
Given the planned modifications on the secondary plant (ADV controller replacement, high pressure main turbine rotor blade replacement, moisture separator reheater relief valve capacity change), please describe how one test will be sufficient to adequately ascertain plant response as specified in FSAR Section 14.2.12.3.31, "Control Systems Checkout."
- 11. Attachment 4 of Supplement 1 states that test SIT-TP-707, "Steam Bypass Control System (SBCS) Capacity Checks," will not be performed. Given the planned modifications on the ADV controllers and SBCS, provide details on the testing method(s) planned to verify and validate that the ADVs will not actuate prior to the SBCS in the event of a load reject.
- 12. Attachment 4 of Supplement 1 states that test SIT-TP-724, "Temperature Decalibration Verification," will not be performed. The evaluation/justification for not performing the test states in the first sentence, "Algorithms contained within the core protection calculator systems (CPCS) are unchanged." The next sentence begins, "The update algorithm within CPCS accommodates for a change in cold leg temperature ..." Based on the lack of clarity in the justification, please explain whether the algorithms within the CPCS are changed or unchanged, and if changed, what test(s) will be performed for validation and verification.
- 13. Attachment 1 of Supplement 1 describes that a modification of the reactor coolant system TaVEr8ge versus pressurizer level program will occur to accommodate a lower reactor coolant system operating temperature. Please provide additional details regarding testing to verify proper operation of affected control systems (i.e. pressurizer level and pressure control).
- 19. Attachment 1 of Supplement 1 briefly describes the impact of individual modifications on dynamic plant response. The information currently provided in the application is not sufficient for the staff to evaluate how the scope of EPU related modifications, known system interactions, transient behavior of systems important to safety, functional system requirements in response to anticipated operational occurrences (AOOs), and other factors were considered in the aggregate. Please describe the process/methodology used in considering how, in the aggregate, the planned EPU modifications could affect expected system interactions, transient behavior of systems important to safety, functional system requirements in response to A0Os, and other factors which could affect the dynamic response of the plant.
Mr. Joseph E. Venable March 26, 2004 Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 (WATERFORD 3) -
REQUEST FOR ADDITIONAL INFORMATION RELATED TO REVISION TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS -
EXTENDED POWER UPRATE REQUEST (TAC NO. MC1355)
Dear Mr. Venable:
By letter dated November 13, 2003, and supplemented by letters dated January 29 and March 4, 2004, Entergy Operations, Inc. proposed revisions to the Waterford 3 operating license and Technical Specifications which would allow an increase in the rated thermal power from 3,441 megawatts thermal (MWt) to 3,716 MWt.
After reviewing your request, the Nuclear Regulatory Commission staff has determined that additional information is required to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested in the enclosure within 30 days of receipt of this letter.
If you have any questions, please call me at (301) 415-1480.
Sincerely, MA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
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