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MONTHYEARML11350A0532012-01-0404 January 2012 Plan for the Scoping and Screening Regulatory Audit Regarding the Grand Gulf Nuclear Station, Unit 1 License Renewal Application Review Project stage: Other ML12009A1052012-01-18018 January 2012 Plan for the Aging Management Program Regulatory Audit Regarding the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Review Project stage: Other ML12067A2352012-04-0303 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12068A2332012-04-0404 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12080A1912012-04-11011 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Grand Gulf LRA RAI Set 3 Project stage: RAI ML12074A0082012-04-12012 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12076A0142012-04-16016 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA Draft RAI Set 5 Project stage: Draft RAI ML12076A0092012-04-17017 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal (TAC ME7493) Grand Gulf LRA Draft RAI Set 6 Project stage: Draft RAI ML12087A0012012-04-18018 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC ME7493)Grand Gulf LRA RAI Set 07 Project stage: RAI ML12094A0092012-04-25025 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nulcear Station Licesne Renewal Application Project stage: RAI ML12101A3602012-04-26026 April 2012 Request for Additional Information for the Review of Th Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 09 Project stage: RAI ML12104A2192012-04-30030 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)LRA RAI Set 10 Project stage: RAI GNRO-2012/00029, Response to Request for Additional Information (RAI) Regarding the License Renewal Application2012-05-0101 May 2012 Response to Request for Additional Information (RAI) Regarding the License Renewal Application Project stage: Response to RAI ML12109A2132012-05-0303 May 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 11 Project stage: RAI GNRO-2012/00036, Response to Request for Additional Information (RAI) Dated April 12, 20122012-05-0909 May 2012 Response to Request for Additional Information (RAI) Dated April 12, 2012 Project stage: Response to RAI ML12118A5392012-05-15015 May 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12125A3732012-05-24024 May 2012 Requests for Additional Information for the Review of the Grant Gulf Nuclear Station License Renewal Application (TAC No. ME7493)Grand Gulf LRA RAI Set 17 Project stage: RAI ML12139A0552012-05-29029 May 2012 LRA RAI Set 19 Project stage: RAI ML12151A2652012-06-15015 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 20 Project stage: RAI ML12165A3872012-06-20020 June 2012 Scoping and Screening Methodology Audit Report Regarding the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Project stage: Other ML12151A3682012-06-20020 June 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12152A3932012-06-22022 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12152A3452012-06-22022 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (Tac No. ME7493) Project stage: RAI ML12157A0562012-06-27027 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)Grand Gulf LRA RAI Set 24 Project stage: RAI ML12164A7262012-06-27027 June 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12180A5412012-07-17017 July 2012 Summary of Telephone Conference Call Held on March 14, 2012, Between NRC and Entergy Operations, Inc., Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12188A7062012-07-17017 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12188A5162012-07-23023 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12200A1382012-07-27027 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B4762012-07-27027 July 2012 LRA RAI Set 30 Project stage: RAI ML12191A1872012-07-31031 July 2012 LRA RAI Telecon 2012-04-13 Project stage: RAI ML12208A2672012-08-0707 August 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12193A0712012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12220A3372012-08-15015 August 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B5042012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/23/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning the RAIs Pertaining to the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12202A2142012-08-15015 August 2012 5/30/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12230A3102012-08-21021 August 2012 Correction to Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B5452012-08-28028 August 2012 Summary of Telephone Conference Call Held on 6/5/12, Between NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12209A1482012-08-28028 August 2012 6/8/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12234A6712012-09-0505 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12242A5452012-09-0707 September 2012 Revision of Schedule for the Conduct of Review of the Grand Gulf Nuclear Station, LRA Project stage: Approval ML12230A2472012-09-0707 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12214A5482012-09-14014 September 2012 7/18/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12248A1582012-09-14014 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12270A2492012-10-0303 October 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12278A0362012-10-17017 October 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12286A0242012-10-19019 October 2012 RAI for the Review of the Grand Gulf Nuclear Station LRA Project stage: RAI GNRO-2012/00128, Response to Requests for Additional Information (RAI) Set 38 Dated 10/03/20122012-10-22022 October 2012 Response to Requests for Additional Information (RAI) Set 38 Dated 10/03/2012 Project stage: Response to RAI ML12264A3872012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/21/12, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12250A1052012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI 2012-05-15
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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 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 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 ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment 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 ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter 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 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 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 IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 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 ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 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)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 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 ML23116A1462023-04-26026 April 2023 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23059A0742023-02-27027 February 2023 Information Request, Security IR 2023402 ML22353A6122022-12-19019 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22271A8572022-10-0303 October 2022 Notification of Commercial Grade Dedication Inspection (05000416/2023011) and Request for Information ML22110A1172022-04-19019 April 2022 (GG) 2022 Emergency Preparedness (EP) Program Inspection RFI Sdh 041922 ML21179A1202021-06-28028 June 2021 Notification of NRC Supplemental Inspection of Action Matrix Column 3 (Degraded Performance) Inputs and Request for Information ML21074A0822021-03-15015 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000416/2021002) and Request for Information ML20363A1462020-12-22022 December 2020 Request for Information: Grand Gulf EP Exercise Inspection - March 2021 ML20258A0202020-09-0909 September 2020 EP Program Inspection RFI, Request for Information to Support and Prepare for Emergency Preparedness (EP) Program Inspection Scheduled to Occur the Week of November 16, 2020 ML20260H4422020-09-0808 September 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Official RAIs for RR Associated with Updating ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20155K7172020-06-0303 June 2020 Notification of NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000416/2020013) and Request for Information ML20150A6012020-05-29029 May 2020 NRR E-mail Capture - Grand Gulf - Official RAI for LAR Associated with Containment ILRT Interval Change from 10 Years to 15 Years ML19302E1082019-10-29029 October 2019 Document Request - GG 95001 - August 2 2019 ML19078A3772019-03-19019 March 2019 NRR E-mail Capture - Grand Gulf - Official Rais for Relief Request GG-ISI-023, Inservice Inspection Impracticality, Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval ML19063B4882019-03-0404 March 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000416/2019002) and Request for Information ML18304A4602018-10-31031 October 2018 NRR E-mail Capture - Final Request for Additional Information - TSTF-425 (L-2018-LLA-0106) ML18250A3042018-08-30030 August 2018 NRR E-mail Capture - Final Request for Additional Information - Emergency Action Level Scheme Change (L-2018-LLA-0116) ML18250A3032018-08-0101 August 2018 NRR E-mail Capture - Correction: Draft RAI - EAL Scheme Change (L-2018-LLA-0116) ML18187A3292018-07-20020 July 2018 Request for Additional Information, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18138A4682018-05-23023 May 2018 Supplemental Information Needed for Acceptance of Request for Licensing Action Adoption of TSTF-425, Relocate Surveillance Frequencies to License Control 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) ML17257A1422017-09-14014 September 2017 NRR E-mail Capture - Grand Gulf - Official Requests for Additional Information (Rais) for RR GG-ISI-020 to Use BWRVIP Guidelines ML17235B1752017-08-23023 August 2017 NRR E-mail Capture - Grand Gulf - Official RAI for Relief Request GG-ISI-021 Associated with Fourth Interval Inservice Inspection Using Code Case N-702 ML17214A0992017-08-0202 August 2017 NRR E-mail Capture - Grand Gulf - Official RAIs for LAR Associated with One Cycle Extension of Appendix J Type a ILRT and Drywell Bypass Test Interval ML17142A2582017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000416/2017007) and Initial Request for Information ML16181A1122016-07-12012 July 2016 Request for Additional Information on Severe Accident Mitigation Alternatives for the Review of the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Environmental Review ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15286A1082015-10-28028 October 2015 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application ML15261A5652015-09-24024 September 2015 Request for Additional Information Regarding Proposed Revision of Technical Specifications for Containment Leak Rate Testing ML15085A4932015-04-0606 April 2015 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application, Set 52 GNRO-2015/00002, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/20142015-03-27027 March 2015 Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/2014 ML15036A5642015-02-18018 February 2015 Updated Fluence Methodology License Amendment Request Unacceptable with Opportunity to Supplement GNRO-2014/00079, Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186)2014-11-13013 November 2014 Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186) GNRO-2014/00076, Response to Request for Additional (RAI) Set 51 Dated September 11, 20142014-11-0606 November 2014 Response to Request for Additional (RAI) Set 51 Dated September 11, 2014 GNRO-2014/00031, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-04-11011 April 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 ML13318A8052014-01-0202 January 2014 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 50 ML13353A6572013-12-19019 December 2013 Licensed Operator Positive Fitness-For-Duty Test ML13345A1822013-12-19019 December 2013 Supplemental Information Needed for Acceptance of Licensing Action, Request to Revise Technical Specification to Allow Operation in Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Domain ML13316B9862013-11-25025 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) ML13263A2252013-11-21021 November 2013 LRA Draft RAI Set 48 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13260A0062013-09-16016 September 2013 Email, Request for Additional Information, Round 3, Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 ML13238A2342013-09-12012 September 2013 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 49 ML13227A3942013-08-28028 August 2013 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 47 ML13226A1902013-08-14014 August 2013 Request for Additional Information Email, Round 2, Request to Revise FOL to Delete 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML13207A1242013-07-30030 July 2013 Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) ML13149A3662013-05-29029 May 2013 Request for Additional Information Email Decommissioning Funding Status Report 2023-04-26
[Table view] Category:Meeting Summary
MONTHYEARML23193A8412023-07-17017 July 2023 Summary of Entergy Operations, Inc. Regulatory Conference: GGNS, Calibration Failures of Drywell/Containment High Range Radiation Monitors Resulting in White Finding July 6, 2023 ML23125A0752023-05-0808 May 2023 May 3, 2023, Summary of Public Meeting with Entergy Operations, Inc., to Discuss Planned Submittals of 10 CFR 50.69 and TSTF-505 for Grand Gulf Nuclear Station, Unit 1 ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML22167A0882022-06-24024 June 2022 Summary of June 14, 2022, Public Meeting with Entergy Operations, Inc. to Discuss Upcoming Relief Request to Use Code Case N-752 for Grand Gulf Nuclear Station, Unit 1, River Bend Station, Unit 1, and Waterford Steam Electric Station, Unit ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML21323A0472021-12-0606 December 2021 Summary of Public Meeting on November 5, 2021, with the National Organization of Test, Research, and Training Reactors on Operator Licensing for Research and Test Reactors ML21285A1352021-10-13013 October 2021 Summary of Regulatory Performance Meeting with Entergy Operations, Inc. to Discuss the Results of the Nrc'S Supplemental 95002 Inspection of Grand Gulf Nuclear Station ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21131A0042021-05-11011 May 2021 May 10, 2021, Summary of Public Meeting with Entergy Operations, Incorporated to Discuss Upcoming Relief Request to Adopt Performance-Based Testing for Pressure Isolation Valves for Grand Gulf Nuclear Station, Unit 1 ML21092A1542021-04-0202 April 2021 GG 2020 EOC Public Meeting Summary of Public Meeting with Entergy Operations, Inc ML20353A4372020-12-18018 December 2020 Regulatory Conference Summary, December 10, 2020 ML20218A7512020-08-0707 August 2020 Summary of June 25, 2020 Teleconference with Grand Gulf Nuclear Station ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML19122A4202019-05-0202 May 2019 Summary of Public Meeting with Entergy Operations, Inc ML18094A2632018-08-17017 August 2018 Summary of 01/18/2018, Public Meeting with Nuclear Energy Institute, Duke Energy, Southern Nuclear Operating Co., Entergy Operations, Inc. to Discuss Development of Tornado Missile Risk Evaluator Methodology ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements ML18099A0712018-04-16016 April 2018 March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program ML18092A4422018-03-28028 March 2018 Summary of Public Meeting with Entergy Operations, Inc. Regarding Results of the Annual Assessment of Safety Performance at Grand Gulf Nuclear Station ML17353A1542017-12-22022 December 2017 Summary of Public Meeting with Entergy Operations, Inc., on Proposed Changes to Emergency Plans to Revise Emergency Action Levels for Arkansas; Grand Gulf; River Bend; and Waterford (EPID-L-2017-LRM-0060) ML17340A0612017-12-0808 December 2017 11/8/17 Summary of Teleconference with Entergy Operations, Inc., Tornado Missile Risk Evaluator with Applicability to Submittals from Duke Energy and Southern Nuclear Operating Co, Inc. ML17244A0742017-09-28028 September 2017 8/17/2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2 ML17257A0992017-09-26026 September 2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2 ML17101A4402017-04-11011 April 2017 Summary of Public Meeting with Entergy Operations, Inc. to Discuss Results of the Annual Assessment of Safety Performance at Grand Gulf Nuclear Station for 2016 ML16280A5062016-10-19019 October 2016 Summary of Teleconference Held on September 28, 2016, Between the NRC and Entergy Co. Concerning Containment Leak Rate Program Pertaining to the Grand Gulf Nuclear Station Unit 1 ML16286A6222016-10-14014 October 2016 Report on the Safety Aspects of the License Renewal Application of the Grand Gulf Nuclear Station, Unit 1 ML16179A3852016-06-27027 June 2016 U.S. Nuclear Regulatory Commission Public Meeting Summary - Open House Meeting with Members of the Public - Grand Gulf Nuclear Station ML15355A0342016-01-12012 January 2016 12/8/2015 Summary of Teleconference for GGNS Set 53 RAI Responses ML15215A0412015-10-14014 October 2015 Summary of Conference Call for GGNS Fire Water System RAI Responses ML14258A1452015-02-19019 February 2015 August 21, 2014, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning RAI Set 51 for the Grand Gulf, Unit 1, License Renewal Application ML14184B1832014-07-10010 July 2014 Summary of Telephone Conference Call Held on June 18, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Draft RAI 3.0.5-1E (Operating Experience Follow-Up) for the Grand Gulf, Unit 1, License Rene ML14156A3782014-06-25025 June 2014 Summary of Meeting Between Representatives of the Nuclear Regulatory Commission and Entergy Operations Inc. to Discuss Flooding Analysis Associated with Grand Gulf Nuclear Station Unit 1 ML14043A1102014-02-28028 February 2014 01/29/2014 Summary of Public Meetings to Discuss Draft Supplement 50 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Grand Gulf, Unit 1, (TAC Nos ME7385 and ME7386) ML13064A0582013-04-0303 April 2013 Summary of Telephone Conference Call Held on February 19, 2013, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, Licens ML12338A6502013-01-14014 January 2013 LRA RAI Telecon 2012-10-26 ML12334A3472013-01-0303 January 2013 Summary of Telephone Conference Call Held on September 28, 2012, Between the NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA ML12264A6492012-11-15015 November 2012 Summary of Telephone Conference Call Held on August 29, 2012, Between the NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA ML12271A2522012-11-0909 November 2012 Summary of Telephone Conference Call Held on 08/22/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12264A3872012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/21/12, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12250A1052012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML12214A5482012-09-14014 September 2012 7/18/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12209A1482012-08-28028 August 2012 6/8/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12201B5452012-08-28028 August 2012 Summary of Telephone Conference Call Held on 6/5/12, Between NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA ML12240A4162012-08-27027 August 2012 Public Meeting with Entergy Operations, Inc to Discuss the Performance of the Subject Facilities and Current Regulatory Issues ML12193A0712012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12201B5042012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/23/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning the RAIs Pertaining to the Grand Gulf Nuclear Station License Renewal Application ML12202A2142012-08-15015 August 2012 5/30/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML12180A5412012-07-17017 July 2012 Summary of Telephone Conference Call Held on March 14, 2012, Between NRC and Entergy Operations, Inc., Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA 2023-07-17
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- August 15, 2012
LICENSEE: Entergy Operations, Inc.
FACILITY: Grand Gulf Nuclear Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 23,2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC. NO. ME7493)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Operations, Inc., (Entergy) held a telephone conference call on May 23,2012, to discuss and clarify the staff's requests for additional information (RAls) concerning the Grand Gulf Nuclear Station, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's RAls.
Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the RAls discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosures:
As stated cc w/encls: Listserv
TELEPHONE CONFERENCE CALL GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 23,2012 PARTICIPANTS AFFILIATIONS Nate Ferrer U.S. Nuclear Regulatory Commission (NRC)
Bill Rogers NRC OnYee NRC Bill Holston NRC Bart Fu NRC Mark Yoo NRC John Wise NRC Jeff Seiter Entergy Ted Ivy Entergy Andy Taylor Entergy Alan Cox Entergy Bill Nichols Entergy Julie Robinson Entergy Jack Lingenfelter Entergy Tony Ploplis Entergy Wayne Bichlmeir Entergy Reza Ahrabli Entergy ENCLOSURE 1
REQUESTS FOR ADDITIONAL INFORMATION (SETS 20 AND 21)
LICENSE RENEWAL APPLICATION May 23,2012 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Operations, Inc., held a telephone conference call on May 23, 2012, to discuss and clarify the following requests for additional information (RAls) concerning the license renewal application (LRA).
Draft RAI2.1-1 Background. 10 CFR 54.4, "Scope," states, in part:
(a) Plant systems, structures and components [SSCs] within the scope of this part are (1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1>> to ensure the following functions (i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1),
10 CFR 50.67(b)(2), or 10 CFR 100.11, as applicable.
LRA Section 2.1.1.1, "Application of Safety-Related Scoping Criteria," states, in part, relative to the scoping criteria of 10 CFR 54.4(a)(1 )(iii), "[t]he capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the applicable guideline exposures set forth in 10 CFR 50.34(a)(1), 10 CFR 50.67, or 10 CFR 100.11, as applicable."
Issue. During the on-site scoping and screening methodology audit, the staff reviewed the definitions of the term safety-related contained in fleet procedures, the Updated Final Safety Analysis Report (UFSAR) and the license renewal application (LRA), used to identify SSCs within the scope of license renewal. The staff determined that the applicability of 10 CFR 50.67 to Grand Gulf Nuclear Station (GGNS) was not specifically addressed in the definitions of the term safety-related in the fleet procedures, the UFSAR or the LRA.
Request. The staff requests that the applicant confirm the definition of the term safety-related used in the development of the LRA and address the applicability of 10 CFR 50.67 to GGNS, as it relates to identifying SSCs within the scope of license renewal in accordance with 10 CFR 54.4(a)(1 )(iii). The staff requests that the applicant perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which aging management reviews were ENCLOSURE 2
-2 performed, and any additional information related to material and environment combinations.
For each structure and component for which aging management reviews were performed, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
Discussion: The applicant stated that the request section of this question is unclear because the request for additional information related to material and environment combinations was not specific. The staff is requesting the results of the applicants additional aging management reviews (AMRs) and will reword the request section of this question as follows:
Request. Confirm the definition of the term safety-related used in the development of the LRA and address the applicability of 10 CFR 50.67 to GGNS, as it relates to identifying SSCs within the scope of license renewal in accordance with 10 CFR 54.4(a)(1 )(iii). Perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which aging management reviews (AMR) were performed, and the results of the AMR. For each structure and component for which AMRs were performed, identify the aging management programs, as applicable, to be credited for managing the identified aging effects.
The staff will issue the revised question as a formal RAI.
Draft RAI 2.1-2 Background. 10 CFR 54.4, "Scope," states, in part:
(a) Plant systems, structures and components [SSCs] within the scope of this part are (1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1>> to ensure the following functions (i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1),
10 CFR 50.67(b)(2), or 10 CFR 100.11, as applicable.
Issue. During the on-site scoping and screening methodology audit the staff determined that certain SSCs identified as safety-related in the plant equipment database were not included within the scope of license renewal in accordance with 10 CFR 54.4(a)(1).
Request. The staff requests that the applicant provide the bases for not including any SSCs, identified as safety-related in the plant equipment database, within the scope of license renewal
-3 in accordance with 10 CFR 54.4(a)(1). The staff requests that the applicant perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which aging management reviews were performed, and any additional information related to material and environment combinations. For each structure and component for which aging management reviews were performed, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
Discussion: The applicant stated that the request section of this question is unclear because the request for additional information related to material and environment combinations was not specific. The staff is requesting the results of the applicants additional AMRs and will reword the request section of this question as follows:
Request. Provide the bases for not including any SSCs, identified as safety related in the plant equipment database, within the scope of license renewal in accordance with 10 CFR 54.4(a)(1). Perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which AMR were performed, and the results of the AMR. For each structure and component for which AMRs were performed, identify the aging management programs, as applicable, to be credited for managing the identified aging effects.
The staff will issue the revised question as a formal RAI.
Draft RAI 2.1-3 Background. 10 CFR 54.4, "Scope," states, in part:
(a) Plant systems, structures and components [SSCs] within the scope of this part are (1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions (i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a){1),
10 CFR 50.67(b)(2), or 10 CFR 100.11, as applicable.
- 4 (2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the functions identified in (a)(1 )(i), (ii), or (iii) of this section.
Issue. During the on-site scoping and screening methodology audit the staff reviewed the license renewal application, the 10 CFR 54.4(a)(2) implementing documents and license renewal drawings, and also performed plant walkdowns. The staff determined through the audit activities and discussion with the applicant that equipment that was no longer required had been placed in an abandoned state.
Request. The staff requests that the applicant provide details on the activities performed to confirm that all abandoned equipment, that at any time contained fluids and is in the proximity of safety-related SSCs, has been verified to be drained or included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). If abandoned equipment has not been verified to be drained or is not included within the scope of license renewal, provide a technical basis for not including the abandoned equipment within the scope of license renewal in accordance with 10CFR 54.4(a)(2). The staff requests that the applicant perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which aging management reviews were performed, and any additional information related to material and environment combinations.
For each structure and component for which aging management reviews were performed, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
Discussion: The applicant stated that the request section of this question is unclear because the request for additional information related to material and environment combinations was not specific. The staff is requesting the results of the applicants additional AMRs and will reword the request section of this question as follows:
Request. Provide details on the activities performed to confirm that all abandoned equipment, that at any time contained fluids and is in the proximity of safety-related SSCs, has been verified to be drained or included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). If abandoned equipment has not been verified to be drained and is not included within the scope of license renewal, provide a technical basis for not including the abandoned equipment within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which AMRs were performed, and the results of the AMRs.
For each structure and component for which AMRs were performed, identify the aging management programs, as applicable, to be credited for managing the identified aging effects.
-5 Additionally, the applicant stated that the phrase "placed in an abandoned state" within the issue section was unclear. The staff was referring to the "abandoned in place" and will reword the issue section accordingly. The staff will issue the revised question as a formal RAI.
Draft RAI 2.1-4 Background. 10 CFR 54.4, "Scope," states, in part:
(a) Plant systems, structures and components [SSCs] within the scope of this part are (1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1>> to ensure the following functions (i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) The capability to prevent or mitigate the consequences of which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1), 10 CFR 50.67(b)(2), or 10 CFR 100.11, as applicable.
(2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the functions identified in (a)(1 )(i), (ii), or (iii) of this section.
Issue. During the on-site scoping and screening methodology audit the staff reviewed the license renewal application, license renewal implementing documents, current licensing basis documentation and performed walkdowns of the incomplete and abandoned Unit 2 turbine building and other adjacent structures.
The staff determined that the Unit 2 turbine building, which is adjacent to the Grand Gulf Nuclear Station (GGNS) turbine building and control building, both of which are within the scope of license renewal in accordance with 10 CFR 54.4(a)(1), is not included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). In addition, the staff noted that the radioactive waste building, which is also adjacent to the GGNS turbine building (but not the control building), is included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for an intended function that includes, "Maintain structural integrity of non safety related components such that safety functions are not affected and no impact on in-scope structures."
During the audit the applicant indicated that the basis for not including the incomplete and abandoned Unit 2 turbine building within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) was an analysis that demonstrated that the Unit 2 turbine building would not move in a way that impacts adjacent buildings following flooding and earthquake events.
However, the applicant did not provide information that demonstrated that the Unit 2 turbine building would not be subject to the effects of aging similar to other buildings of the same construction that the applicant had included within the scope of license renewal and made subject to an aging management program.
-6 Request. The staff requests that the applicant provide a technical basis for not including the incomplete and abandoned Unit 2 turbine building, located adjacent to the GGNS turbine building and the control building, within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). If an analysis is cited as the technical basis for not including the Unit 2 turbine building within the scope of license renewal, demonstrate how the analysis considers the effects of aging relative to other buildings of similar construction that are included within the scope of license renewal. The staff requests that the applicant perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a} criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which aging management reviews were performed, and any additional information related to material and environment combinations. For each structure and component for which aging management reviews were performed, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.
Discussion: The applicant stated that the request section of this question is unclear because the request for additional information related to material and environment combinations was not specific. The staff is requesting the results of the applicants additional AMRs and will reword the request section of this question as follows:
Request. Provide a technical basis for not including the incomplete and abandoned Unit 2 turbine building, located adjacent to the GGNS turbine building and the control building, within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). If an analysis is cited as the technical basis for not including the Unit 2 turbine building within the scope of license renewal, demonstrate how the analysis considers the effects of aging relative to other buildings of similar construction that are included within the scope of license renewal. Perform a review of this issue and indicate if the review concludes that use of the scoping methodology precluded the identification of SSCs that should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations performed to address the 10 CFR 54.4(a) criteria. List any additional SSCs included within the scope of license renewal as a result of the review, structures and components for which aging management reviews were performed, and the results of the AMR. For each structure and component for which aging management reviews were performed, identify the aging management programs, as applicable, to be credited for managing the identified aging effects.
The staff will issue the revised question as a formal RAI.
Draft RAI 3.1.2.1-1 Background. SRP-LR Section A.1.2.1, item 7, states that applicable aging effects to be considered for license renewal include those that could result from normal plant operation, including plant/system operating transients and plant shutdown.
In LRA Tables 3.1.2-1 and 3.1.2-3, the applicant stated that the carbon steel low alloy steel components including nozzles, nozzle safe ends and extensions, nozzle flanges, reactor vessel upper head, piping, flow elements, thermal sleeves, and valve bodies exposed to air - indoor
-7 (external) do not require any aging effect to be managed. The related AMR items cite generic note G, indicating this environment is not in the GALL Report for the aging effects of this component and material combination. Also, the associated plant-specific note, 102, states that high component surface temperature precludes moisture accumulation that could result in corrosion.
Issue. In its review, the staff found that identical material and environment combinations were found in the GALL report, albeit not in the reactor coolant system. The staff noted that the applicant's basis for not managing the aging effect is that the temperature of the components under consideration is above the dew point. The GALL Report states that the aging effect of loss of material due to exposure of steel surfaces to indoor air, which can result in condensation but only rarely, should be considered. The staff also noted that during refueling outages, these components will be at ambient temperatures for prolonged periods of time, which mayor may not be above the dew point.
Request. Provide the technical basis to justify why aging management is not necessary for the subject components given that, during normal plant events such as refueling outages, these components will be at or near ambient temperatures.
Discussion: The applicant stated that the request section of this question is unclear based on what was being asked to be justified. The staff is referencing the aging effects requiring management for the subject components and will reword the request section of this question as follows:
Request. Provide the technical basis to justify why there are no aging effects requiring management for the subject components given that, during normal plant events such as refueling outages, these components will be at or near ambient temperatures.
The staff will issue the revised question as a formal RAJ.
Draft RAI 3.3.1.82-1 Background. LRA Item 3.3.1-82, associated with elastomer seals and components exposed to air - indoor, uncontrolled (external) being managed for loss of material due to wear, was not used. The justification for not using the item is, "[w]ear of elastomer components is considered an event driven condition rather than an aging effect. If the elastomer component is properly designed, installed and maintained, contact with other surfaces leading to wear will not occur."
Likewise, LRA Item 3.3.1-96, elastomers seals and components exposed to air - indoor, uncontrolled (internal) being managed for loss of material due to wear, was not used.
GALL Report Section IX.F defines wear "as the removal of surface layers due to relative motion between two surfaces or under the influence of hard, abrasive particles. Wear occurs in parts that experience intermittent relative motion, frequent manipulation, or in clamped joints where relative motion is not intended, but may occur due to a loss of the clamping force."
Issue. The conclusion that properly designed, installed, and maintained components will not experience wear is not consistent with the GALL Report definition of wear. Within the definition of the term "wear" in GALL Report Section IX.F, there are three factors to consider that could cause age-related wear due to the design of the joint, including (a) relative motion between two surfaces under the influence of hard abrasive particles. (b) frequent manipulation, or (c) in
- 8 clamped joints where relative motion is not intended but may occur due to a loss of the clamping force. It is unclear to the staff whether there are any in-scope components that are designed in such a way that they could be impacted by the three age-related factors considered in the definition of wear.
Request.
- a. State whether any in-scope elastomeric components which are designed with relative motion are exposed to an internal or external environment that includes hard abrasive particles.
- b. State whether there are any in-scope elastomeric components that are susceptible to wear that over time, due to their frequent manipulation, could challenge the CLB function(s) of the component.
- c. State whether there are any in-scope elastomeric components designed with clamped joints where relative motion is not intended; however, they are susceptible to wear over time due to a loss of the clamping force and could wear and challenge the CLB function(s) of the component.
- d. If an AERM is applicable based on the configurations or aging mechanisms described in items (1) through (3), discuss how the AERM will be managed.
Discussion: The applicant stated that the LRA item references in the background section of this question were unclear. The staff is referencing LRA Table 3.3.1, items 82 and 96 and will reword the request section of this question as follows:
Background. LRA Table 3.3.1, items 82 and 96, associated with elastomer seals and components, was not used. The justification for not using the item is, "[w]ear of elastomer components is considered an event driven condition rather than an aging effect. If the elastomer component is properly designed, installed and maintained, contact with other surfaces leading to wear will not occur."
GALL Report Section IX.F defines wear "as the removal of surface layers due to relative motion between two surfaces or under the influence of hard, abrasive particles. Wear occurs in parts that experience intermittent relative motion, frequent manipulation, or in clamped joints where relative motion is not intended, but may occur due to a loss of the clamping force."
The staff will issue the revised question as a formal RAI.
Draft RAI 3.3.1.76-1 Background. LRA Item 3.3.1-76, associated with elastomeric duct flexible connection exposed to interior indoor air states that hardening and loss of strength due to elastomer degradation should be managed with the External Surfaces Monitoring program. LRA Table 3.3.2-17, Control Room Ventilation System, lists an item for elastomeric duct flexible connections exposed to internal indoor air which cites item 3.3.1-76, generic note I and plant-specific note 306. This item states that there are no AERM and proposed AMP. Plant-specific note 306 states, "Changes of material properties and cracking in elastomers are results of exposure to ultra-violet light or elevated temperatures (> 95°F). The interior surfaces of these components are not exposed to ultra-violet light and are part of the control room HVAC system that is not exposed to elevated temperatures."
-9 GALL Report Section Ix.e states, U[h]ardening and loss of strength of elastomers can be induced by elevated temperature (over about 95°F or 35°C), and additional aging factors (e.g.,
exposure to ozone, oxidation, and radiation)."
Issue. The staff could not confirm that there are no aging effects for this component, material and environment combination because 95°F is a general guideline and does not necessarily apply to all elastomeric material types.
Request. State the specific material type for these elastomeric duct flexible connections and state the basis why there are no AERM and no proposed AMP. If the specific elastomeric material type does age despite being in an environment below 95°F, state how the item will be managed for aging.
Discussion: The applicant stated that the items being referenced in the request section of this question were unclear. The staff is referencing the effects of aging for the component and will reword the request section of this question as follows:
Request. State the specific material type for these elastomeric duct flexible connections and state the basis why there are no AERM and no proposed AMP.
If the specific elastomeric material type does age despite being in an environment below 95°F, state how the effects of aging will be managed.
The staff will issue the revised question as a formal RAI.
Draft RAI 3.3.2.19-3 Background. LRA Table 3.3.2-19-8 states that for Teflon flexible connections exposed to treated water (internal), there is no aging effect and no AMP is proposed.
Issue. While Teflon is resistant to temperatures higher than that encountered in spent fuel cooling systems, there are studies which demonstrate that certain grades of Teflon degrade when exposed to radiation.
Request. State the specific Teflon material type for these flexible connections and state the basis why there are no AERM and no proposed AMP. If the speci'fic Teflon material type does age, state how the item will be managed for aging.
Discussion: The applicant stated that the items being referenced in the request section of this question were unclear. The staff is referencing the effects of aging for the component and will reword the request section of this question as follows:
Request. State the specific Teflon material type for these flexible connections and state the basis for why there are no AERM and, therefore, no proposed AMP. If the specific Teflon material type does age, state how the effects of aging will be managed.
The staff will issue the revised question as a formal RAI.
-10 RAI 3.4.2.2.8-1 Background. The staff reviewed a sample of 35 components, material and environment combinatio'ns, selected from the license renewal application (LRA) during the aging management program (AMP) audit conducted January 22, 2012. These components were randomly selected for the staff to verify the accuracy of the information provided in the aging management review (AMR). The staff also performed walkdowns during the audit to determine whether the selected components material and environment combinations, as listed in the LRA were consistent with the descriptions in the LRA.
Issue. A stainless steel flexible connection in the lube oil system, LRA (Table 3.4.2-2-8), is listed as stainless steel, however, the staff could not verify this material as a stainless steel flexible connection during the audit, either by walkdown or subsequent review of documentation provided by the applicant.
Request. The staff requests that the applicant verify the material composition of the component described above and, if necessary provide the results of an updated aging management review, in accordance with 10 CFR 54.21 (a)(1).
Discussion: The applicant stated that the updated aging management review was submitted by letter dated May 1, 2012, based on discussion during the onsite audit. The staff has verified the update and will not issue this RAI.
'.. ML12201B504 OFFICE PM:RPB1 :DLR LA:RPB1 :DLR BC:RPB1 :DLR NAME NFerrer YEdmonds DMorey DATE 8/3/12 7/31/12 8/15/12
Memorandum to Entergy Operations, Inc. from Nathaniel Ferrer dated August 15, 2012
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 23,2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC. NO. ME7493)
DISTRIBUTION:
E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV DMclntyre, OPA