Letter Sequence RAI |
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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: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
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 31,2012 LICENSEE: Entergy Operations, Inc.
FACILITY: Grand Gulf Nuclear Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 21, 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 August 21,2012, 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 staffs RAls. 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:
- 1. List of Participants
- 2. List of Requests for Additional Information cc w/encls: Listserv
TELEPHONE CONFERENCE CALL GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 21,2012 PARTICIPANTS AFFILIATIONS Nate Ferrer U.S. Nuclear Regulatory Commission (NRC)
Jim Gavula NRC Alice Erickson NRC Jim Medoff NRC Ted Ivy Entergy Operations, Inc. (Entergy)
Andy Taylor Entergy Alan Cox Entergy Kirk Ehren Entergy Jacque Lingenfelter Entergy ENCLOSURE 1
REQUESTS FOR ADDITIONAL INFORMATION (SET 33)
LICENSE RENEWAL APPLICATION AUGUST 21, 2012 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Operations, Inc., held a telephone conference call on August 21, 2012, to discuss and clarify the following requests for additional information (RAls) concerning the license renewal application (LRA).
Draft RAI 4.1-2a Background. In the response to RAI4.1-2 dated July 3,2012, the applicant stated that the spent fuel cask crane, new fuel handling crane, and polar crane are designed for a minimum of 100,000 cycles in accordance with CMAA-70, and that the allowable cycles based on CMAA-70 allowable stress ranges are not time-limited and are well above the estimated number of cycles for the aforementioned cranes during 60 years of plant operation. Based on this information the applicant concluded that there are not any time-limited aging analysis (TLAAs) associated with these cranes.
Issue. The staff concurs that the CMAA-70 allowable stress ranges for the analysis of these cranes is not a time-dependent variable defined by the life of the plant. However, the staff also noted that the monitoring of load cycle lifts against the upper bound CMAA-70 design limit for these load cycle lifts may be a time-dependent assessment defined by the life of the plant.
Therefore, the staff does not have sufficient information to conclude that the current licensing basis (CLB) does not include any assessments for these cranes that would need to be identified as TLAAs for the LRA because the analyses may include a time-dependency.
Request.
- a. Provide an explanation and the basis why the analyses of loading cycle lifts for the spent fuel cask crane, new fuel handling crane, and polar crane do not need to be identified as TLAAs for the LRA when compared to the six criteria for defining TLAAs in 10 CFR 54.3(a). In the response, specifically clarify and justify why the assessment of load cycle lifts against the design limits set for these lifts per the CMAA-70 criteria would not be time-dependent defined by the life of the plant or why the number of load lift cycles would not need to be monitored during the period of extended operation. Include in the response a clear explanation on how the analyses compare to each of the six criteria for defining TLAAs in 10 CFR 54.3(a) and provide the basis on why the analyses are either in conformance or out of conformance with each of the six criteria for defining TLAAs.
- b. If it is determined that the analyses of loading cycle lifts for the spent fuel cask crane, new fuel handling crane, and polar crane do need to be identified as TLAAs, amend the LRA to include an assessment of these TLAAs and provide the basis for accepting each of the TLAAs in compliance with one of three TLAA acceptance requirements in 10 CFR21 (c)(1)(i), (ii), or (iii). In addition, provide the applicable changes to both the aging management review (AMR) results in LRA Section 3 and updated final safety analysis review (UFSAR) Supplement in LRA Appendix A.
ENCLOSURE 2
- 2 Discuss: The applicant stated that the issue section was unclear because of the statements of life of plant. The staff was referring to the current operating term of the plant and will reword the issue section as follows:
Issue. The staff concurs that the CMAA-70 allowable stress ranges for the analysis of these cranes is not a time-dependent variable defined by the life of the plant. However, the staff also noted that the monitoring of load cycle lifts against the upper bound CMAA-70 design limit for these load cycle lifts may be a time-dependent assessment defined by the current operating term. Therefore, the staff does not have sufficient information to conclude that the CLB does not include any assessments for these cranes that would need to be identified as TLAAs for the LRA because the analyses may include a time-dependency.
The staff will issue the reworded question as a formal RAI.
Draft RAI 4.1*2b Background. In the response to RAI 4.1-2 dated July 3, 2012, the applicant stated that the containment hatchway crane load bearing parts were analyzed by GGNS for all applicable loads per the requirements of the AISC Steel Construction Manual (hence AISC standard), ]'h Edition and that the evaluation of the crane per the AISC standard criteria did not include any time dependent evaluation defined by the life of the plant. Therefore, the applicant concluded that there are not any TLAAs for the containment hatchway crane because the evaluations of crane were not based on time-dependent criteria defined by the life of the plant.
Issue. Based on its review of this AISC standard, the staff noted that the crane rails were required to be designed in accordance with requirements for crane rail designs in Section 1 of the AISC standard and that the load bearing parts of the cranes were required to be evaluated in accordance with the specification requirements in Section 5 of the AISC standard. This includes a potential evaluation of the crane load bearing parts for possible fatigue loading conditions per Chapter 5, Section 1.7 of AISC standard and Section 1.7 of Appendix B of the AISC standard. SpeCifically, the staff noted that Table B1 "Number of Loading Cycles," in Appendix B of the AISC standard would establish a loading condition for each of the crane load bearing parts based on the following load cycle ranges for the cranes: (a) 20,000 -100,000 loading cycles establish cranes for loading condition 1; (b) 100000 - 500000 loading cycles establish cranes for loading condition 2; (c) 500,000 - 2,000,000 loading cycles establish cranes for loading condition 3; and (d) over 2,000,000 loading cycles establish cranes for loading condition 4. The staff noted that the Tables B2 and B3 in Appendix B of the AISC specification then used the loading condition category for each of the load bearing parts to establish maximum allowable stresses for these components.
In addition, UFSAR Section 90.3.1 states that the evaluation of load bearing parts for the containment hatchway crane was used to perform structural modifications of the crane and to "derate" the crane. However, the UFSAR Section 90.3.1 does not identify speCifically what modifications were made to the deSign of this crane or which criteria in the AISC standard or other NRC requirements applicable to the crane were specifically "derated" per the crane analysis, or whether the specific evaluation or evaluations used for "derating" of the crane was
-3 (or were) based on a TLAA. Thus, the staff does not have sufficient information to conclude that evaluation of the containment hatchway crane does not include any time-dependent analyses that conformed to the definition of a TLAA in 10 CFR 54.3(a).
Request.
- a. Provide a full explanation on how the load bearing parts for the containment hatchway crane were assessed to potential fatigue bearing loads, or else to provide a complete explanation why the crane bearing would not have been required to be assessed for fatigue if fatigue analyses were not performed for the containment hatchway crane load bearing parts as part of the GGNS CLB.
- b. If the CLB does include a applicable fatigue analysis or analyses for the containment hatchway crane load bearing parts, provide your basis why the analysis or analyses would not need to be identified as a TLAA or TLAAs for the LRA based on a comparison to the six criteria for TLAAs in 10 CFR 54.3(a). If the CLB does include such evaluations, provide a clear explanation on why the evaluation or evaluations in the CLB is either in conformance or out of conformance with each of the six criteria for defining TLAAs in 10 CFR 54.3(a). Amend the LRA appropriately if it is determined that CLB does include such a fatigue analysis or analyses and the analysis or analyses are determined to conform to the definition of a TLAA.
- c. Identify all modifications of the containment hatchway crane that were made per the AISC standard evaluation of the crane and specifically what is meant by the term "derating" of the crane. In addition, identify all specific AISC standard subpart evaluations that were used to either modify the structure of the crane or to "derate" this crane and the specific AISC criteria or other NRC requirements that the crane was "derated" from and explain the basis for such "derating" objectives. Explain and justify why the specific AISC standard subpart evaluations that were used either modify the containment hatchway crane or used to "derate" the containment hatchway crane would not need to be identified as TLAAs when compared to the six criteria for defining TLAAs in 10 CFR 54.3(a).
Discussion: The applicant stated that the second paragraph of the issue section was unclear in its description of the UFSAR section. The staff's concern was what derating involved and if modifications were made to the design of the crane. The applicant also stated that request (a) was unclear in its description. The staff was referring to potential loads on the containment hatchway crane. The staff will reword the applicable portions of the issue and request sections as follows:
In addition, UFSAR Section 90.3.1 states that the evaluation of load bearing parts for the containment hatchway crane was used to perform structural modifications of the crane and to "derate" the crane. The staff is not clear if modifications were made to the design of this crane or what "derating" the crane involved. Thus, the staff does not have sufficient information to conclude that evaluation of the containment hatchway crane does not include any time dependent analysis that conformed to the definition of a TLAA in 10 CFR 54.3(a).
-4 Request.
- a. Provide a full explanation on how the load bearinq parts for the containment hatchway crane were assessed for potential loads, or else provide a complete explanation why the crane loads would not have been required to be assessed for fatigue if fatigue analyses were not performed for the containment hatchway crane load bearing parts as part of the GGNS CLB.
The staff will issue the reworded question as a formal RAt Draft RAJ 4.1-4a Background. In the response to RAI4.1-4 dated July 3,2012, the applicant stated that the plant-specific fracture mechanics evaluation does not need to be identified as a TlAA because the analysis does not include a time dependency and therefore is not a time-dependent analysis defined by the life of the plant. The applicant further stated that the intent of the plant-specific fracture mechanics evaluation was to justify the inspection intervals in the GE generic evaluation.
The applicant stated that the specific evaluation concluded that the results presented therein were valid for use in establishing future feed water nozzle inspection intervals based on the alternate requirements specified in the generic evaluation, and therefore that the plant-specific evaluation did not qualify the feedwater nozzles for a fixed term and is not a TlAA.
Issue. The staff does not agree with the applicant on that the plant-specific flaw tolerance analysis does not need to be identified as a TlAA for the GGNS LRA. As has been confirmed by the applicant, the applicant is using the plant-specific flaw tolerance as the safety basis for establishing the inspection frequency of its alternative inservice inspections for the FW nozzles, which involve recommended alternative ultrasonic test examination techniques.
The applicant claimed that the inspection interval serves as a basis (or input) for the plant specific flaw tolerance analysis. In contrast, the staff noted that the inspection interval is part of the safety basis determination for the nozzles because it is part of the basis for establishing acceptable alternative inservice requirements for the nozzle under the requirements of 10 CFR 50.55a. Since the inspection interval is part of the safety basis determination, it cannot serve as a basis (or input) for establishing the time frame assumed for the plant-specific flaw tolerance analysis.
Thus, the staffs position is that the applicant should have identified the plant-specific flaw tolerance analysis as a TlAA because it meets all six of the criteria in 10 CFR 54.3(a). This includes conformance with TlAA identification Criterion 3 in that the evaluation is based on time-dependent assumptions defined by the life of the plant.
Request.
- a. Provide the basis why the plant-specific cycle-dependent flaw tolerance analysis does not need to be identified as a TlAA in accordance with10 CFR 54.21(c)(1).
- b. If the response to request (a) concludes that the plant-specific analysis needs to be identified as a TlAA, provide the necessary information and LRA revision to support the TlAA disposition in accordance with 10 CFR 54.21 (c)(1 )(i), (ii), or (iii). Assess and
- 5 justify if the inservice inspection interval for the alternative FW nozzle examinations under the BWR Feedwater Nozzle Program will need to be adjusted for inspections on FW nozzle during the period of extended operation, based on the justification that is used to disposition the TLAA in accordance with 10 CFR 54.21{c)(1){i), (ii), or (iii),
Discussion: The applicant stated that the second paragraph to the issue section was unclear because it described the issue in the same manner as the first paragraph of the section. The staff determined that the paragraph was not needed to describe the issue and will remove it from the question. The staff will issue the reworded question as a formal RAI.
Draft RAI4.7.1-1a Background. By letter dated June 5, 2012, the staff issued RAI 4.7.1-1 requesting that the results of the projected analyses be provided to demonstrate that the intended functions of the main steam line (MSL) flow restrictors are maintained in accordance with the current licensing basis during the period of extended operation. The response, dated July 3, 2012, stated that the erosion rate of 0.004 inches per year stated in UFSAR Section 5.4.4.4 was highly conservative, and that information from a "later evaluation" shows that the expected erosion of the flow restrictors would be less than the 0.160 inches derived from the 0.004 inches per year for 40 years of operation. The response also provided several attributes to explain the reduction in the erosion-corrosion rate from the 0.004 inches per year given in the UFSAR, including:
(a) materials with minimal chromium content are resistant to erosion-corrosion damage, (b) the relative erosion-corrosion rate for steels begins to decrease above 300F, and (c) the Grade CF8 stainless steel material will not experience pitting or stress corrosion cracking due to chloride ions.
EPR11011231, "Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement, and Solid Particle Erosion," states that while materials such as stainless steel are immune to flow-accelerated corrosion, erosive mechanisms will eventually damage virtually any material.
Issue. Although the flow restrictors are constructed from stainless steel, the chrome content in stainless steel does not prevent loss of material due to erosion in all situations. In addition, the response to RAI 4.7.1-1 did not provide the results of the projected analyses or the bases for the conclusion in the "later evaluation" that the erosion-corrosion projected through the period of extended operation will be less than the total originally projected for 40 years. The applicant stated that the evaluation is proprietary; however, this does not preclude the information from being provided to the NRC.
Request. Provide the evaluation discussed in the response to RAI4.7.1-1 that shows the expected erosion of the flow restrictors would be less than 0.160 inches for 60 years of operation.
Discussion: The applicant indicated that the question is clear. The staff will issue the question as a formal RAI.
-6 Draft RAI 4.7.1-2 Background. The components addressed in LRA Table 3.1.2-3, "Reactor Coolant Pressure Boundary," include cast austenitic stainless steel (CASS) flow elements, which appear to be the MSL flow restrictors. The table indicates that these components are being managed for cracking through LRA Table 3.4.1, item 11, and for loss of material through LRA Table 3.1.1, item 79 using the Water Chemistry - BWR program, with verification of the program's effectiveness through the One-Time Inspection program.
UFSAR Section 5.4.4.3 states that ASTM A351 (Type 304) CASS material was selected for the MSL flow restrictors based on its excellent resistance to erosion-corrosion in a high velocity steam environment. In addition, LRA Section 4.7.1 includes a plant-specific time limited aging analysis for evaluating erosion of the MSL flow restrictors.
Issue. 10 CFR 54.21 (a) states, in part, that license renewal applications must identify and list components within scope that are subject to an aging management review and must describe and justify the methods used to demonstrate that the effects of aging will be adequately managed.
The staff reviewed the applicant's AMR results in LRA Table 3.1.2-3 "Reactor Coolant Pressure Boundary," and noted it did not include an AMR item for the TLAA associated with erosion of the MSL flow restrictors. It is not clear to the staff why these components evaluated by the TLAA and discussed in LRA Section 4.7.1 are not included as AMR items in the applicable table.
Request. Provide an AMR item for the MSL flow elements in LRA Table 3.1.2-3 that credit the TLAA for evaluating loss of material in the components by an erosion-corrosion mechanism, or provide the bases for why the MSL flow elements are not included.
Discussion: The applicant stated that the second paragraph of the background section was unclear in its description of the LRA section. The staff was highlighting that the LRA section describes a plant-specific TLAA and will reword the applicable portions of the background section as follows:
UFSAR Section 5.4.4.3 states that ASTM A351 (Type 304) CASS material was selected for the MSL flow restrictors based on its excellent resistance to erosion corrosion in a high velocity steam environment. In addition, LRA Section 4.7.1 describes the evaluation of a plant-specific TLAA for erosion of the MSL flow restrictors.
The staff will issue the reworded question as a formal RAI.
October 31,2012 LICENSEE: Entergy Operations, Inc.
FACILITY: Grand Gulf Nuclear Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 21, 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 August 21, 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. 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.
IRA!
Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosures:
- 1. List of Participants
- 2. List of Requests for Additional Information cc w/encls: Listserv DISTRIBUTION: See next page ADAMS Accession No " . M L 12264A387 *concurrence via email OFFICE LA:RPB1 :DLR* PM:RPB1:DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME YEdmonds NFerrer DMorey NFerrer DATE 10/02/12 10/15/12 10/31/12 10/31/12 OFFICIAL RECORD COpy
Memorandum to Entergy Operations, Inc. from N. Ferrer dated October 31,2012
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 21, 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:
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