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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
MONTHYEARML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24012A1422024-01-31031 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 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 ML23340A2222023-12-13013 December 2023 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 GNRO-2013/00079, 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013)2023-10-11011 October 2023 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013) 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-2023/00015, 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 2024-07-09
[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 April 3, 2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150 SUB,JECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)
Dear Mr. Perito:
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulation, Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1 (GGNS) for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301- 415-1045 or e-mail nathanieLferrer@nrc.gov.
Si~ _.-,//~-:?
Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50- 416
Enclosure:
Requests for Additional Information cc w/encl: Listserv
GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION SET 1 RAI8.1.6-1 Background. LRA Section B.1.6 states that the Boiling Water Reactor (BWR) Control Rod Drive (CRD) Return Line Nozzle Program is an existing program that manages cracking of the CRD return line nozzle. In comparison, Generic Aging Lessons Learned (GALL) Report AMP XI.M6, "BWR Control Rod Drive Return Line Nozzle," states that the program is a condition monitoring program based on the staff's recommended position in NUREG-0619 for thermal fatigue and the program is also intended to address stress corrosion cracking (SCC) discussed in NRC information notice (IN) 2004-08. IN 2004-08 addresses cracking due to SCC stress of capped CRD return lines.
In addition, the GALL Report AMP XI.M6 "parameters monitored/inspected" program element states that the AMP manages the effects of cracking on the intended function of the reactor vessel, the CRD return line nozzle, and for capped nozzles, the nozzle caps, and cap-to-nozzle welds. GALL Report AMP XI.M6 states that for the volumetric ultrasonic test (UT) examinations that are performed in accordance with this aging management program (AMP), the AMP monitors and evaluates signals that may indicate the presence of a planar flaw (crack).
Issue. During the audit and in interviews with the applicant, the staff noted that the CRD return line was capped to prevent cracking due to cyclic loading. The staff also noted that the applicant's current inservice inspection plan includes the CRD return line nozzle in its scope and sample population. However, the current inservice inspection plan does not have a specific inspection schedule for the capped CRD return line, which indicates that the capped CRD return line is not selected for inspections during the current inservice inspection interval. Therefore, the staff found a concern that the lack of a specific inspection schedule for this component does not ensure adequate detection and management of cracking due to SCC.
Request
- a. Provide additional information on the size, material, number of associated welds, and configuration of the capped CRD return line (e.g., 3.5 inches in diameter and Alloy 82/182 nozzle-to-cap butt weld from the low alloy steel nozzle to the Alloy 600 cap).
- b. Clarify why the BWR CRD Return Line Nozzle Program is consistent with the GALL Report given the fact that the current inservice inspection plan does not have a specific inspection schedule for the capped CRD return line. As part of the response, clarify if the CRD return line nozzle cap and cap-to-nozzle weld(s) will be examined prior to or during the period of extended operation, and describe the method and schedule of these inspections. Alternatively, provide justification why it is not necessary to examine the CRD return line nozzle cap and cap-to-nozzle weld(s) to detect and manage cracking due to SCC in light of the industry operating experience of cracking due to SCC as described in NRC IN 2004-08.
ENCLOSURE
-2 RAI8.1.7-1 Background. GALL Report AMP XLM5, "BWR Feedwater Nozzle," recommends enhanced inspections in accordance with General Electric (GE) NE-523-A71-0594, Revision 1, "Alternate BWR Feedwater Nozzle Inspection Requirements."
Issue. During its audit, the staff noted that in the applicant's program basis document for the BWR Feedwater Nozzle Program, the applicant referenced GE-NE-523-A71-0594, Revision 1, consistent with the recommendation in GALL Report AMP XLM5. However, both LRA Sections 8.1.7 and A.1. 7 state that the program augments the examinations specified in the ASME Code Section XI, with the recommendation of GE-NE-523-A71-0594. The staff noted that the descriptions in these two sections do not identify the recommended revision of the GE-NE-523-A71-0594 report.
Reguest. Clarify the revision of the GE-NE-523-A71-0594 report that is used in the BWR Feedwater Nozzle Program and ensure the applicable LRA Sections and Updated Final Safety Analysis Report (UFSAR) supplement accurately reflect this revision. Justify the use of any revision that is not consistent with the recommendation of GALL Report AMP XI.M5.
RAI8.1.8-1 Background. The "parameters monitored/inspected" program element of GALL Report, Rev. 2, AMP XLMa, "BWR Penetrations," states that the program manages the effects of cracking due to SCC and intergranular stress corrosion cracking (IGSCC) on the intended function of the BWR instrumentation nozzles, CRD housing and incore-monitoring housing (ICMH) penetrations, and BWR standby liquid control (SLC) nozzles/Core llP nozzles. The GALL Report also states that the program accomplishes this by inspection for cracks in accordance with the guidelines of approved BWRVIP-49-A, BWRVIP-47-A or BWRVIP-27-A and the requirements of the ASME Code,Section XI, Table IWB 2500-1.
In addition, Section 3.2.5, "Other Inspections," in BWRVIP-47-A indicates that the BWRVIP has determined that removing or dismantling of internal components for the purpose of performing inspections is not warranted to assure safe operation; however, on occasion, utilities may have access to the lower plenum due to maintenance activities not part of normal refueling outage activities. BWRVIP-47-A further states that in such cases, utilities will perform a visual inspection to the extent practical.
Issue. During the audit, the staff noted that in contrast with BWRVIP-47-A. the site documentation for BWR Penetrations Program indicates that the baseline inspections for the CRD housing do not require access to the lower plenum area and currently no additional inspections are recommended beyond the baseline inspections. Additionally, the site documentation shows that if access is gained to the lower plenum (areas below the core plate),
accessible areas of the incore flux monitor housing, guide tubes and guide tube stabilizer should be inspected by the VT-3 method. However, it is not clear whether these additional inspections are applied to the incore monitoring housing penetration.
- 3 Request.
- a. Provide information regarding when the lower plenum housing and penetration are accessible during maintenance activities not part of normal refueling outage activities.
- b. Justify why the BWR Penetrations Program does not include the additional inspections of the CRD housing and housing penetration (including stub tubes) described in BWRVIP-47-A, Section 3.2.5. In addition, clarify if the additional inspections are applied to the incore flux monitoring housing penetrations.
- c. Ensure the LRA and site documentation are consistent with the response to this RAI.
RAI8.1.8-2 Background. SRP-LR, Table 3.0-1 provides an example of the summary descriptions of aging management programs for the UFSAR Supplement. The summary description for the BWR Penetrations Program in SRP-LR, Table 3.0-1 states that the program includes inspection and flaw evaluation in conformance with the guidelines of staff-approved boiling water reactor vessel and internals project documents BWRVIP-47-A, BWRVIP-49-A, and BWRVIP-27-A, to ensure the long-term integrity and safe operation of BWR vessel internal components.
The UFSAR supplement in LRA Section A.1.8 states that the BWR Penetrations Program manages cracking of BWR vessel penetrations using inspection and flaw evaluation activities and that applicable industry standards and staff-approved BWRVIP documents are used to delineate the program. In addition, LRA Section B.1.8 states that the BWR Penetrations Program is an existing program that manages cracking of BWR vessel penetrations using inspection and flaw evaluation activities and that applicable industry standards and staff approved BWRVIP documents are used to delineate the program.
Issue. The applicant's summary description of the BWR Penetrations Program for the UFSAR supplement does not include a specific reference to relevant BWRVIP documents for the program. The UFSAR supplement for the program may not be adequate to ensure program effectiveness due to the omission of specific references to relevant BWRVIP documents for this program. Similarly, LRA Section 8.1.8 does not include a specific reference to relevant BWRVIP documents for the program Request. Justify why LRA Sections A.1.8 and B.1.8 do not include specific references to relevant BWRVIP documents for the BWR Penetrations Program. Alternatively, revise LRA Sections A.1.8 and B.1.8 to include relevant BWRVIP documents for this program.
RAI8.1.8-3 Background. In LRA Appendix C, "Responses to BWRVIP Applicant Action Items Grand Gulf Nuclear Station," the applicant indicated that the core plate differential pressure and standby liquid control (l1P/SLC) lines inside the reactor vessel have no license renewal intended function and are not subject to aging management review. The applicant also indicated that there is no fatigue time-limited aging analysis (TLAA) applicable to GGNS in BWRVIP-27-A.
-4 During the audit, the staff noted that the site documentation for the Reactor Vessel Internals Program indicates that the design for the flP/SLC penetration utilizes an Alloy 600 stub tube set into the bottom head and welded to an Alloy 600 housing. The staff also noted that the flP/SLC penetration/nozzle and safe-end assembly forms the reactor coolant pressure boundary (RCPB). In addition, the staff noted that LRA Table 4.3-2, "Cumulative Usage Factors for the Reactor Vessel," includes the 40-year cumulative usage factor for the liquid control-flP nozzle, which appears contrary the applicant's claim that there is no fatigue TLAA applicable to GGNS in BWRVIP-27-A.
Issue. In comparison with the applicant's claim that the flP/SLC lines inside the reactor vessel have no license renewal intended function, the flP/SLC penetration/nozzle and safe-end assembly is part of the reactor coolant pressure boundary. Therefore, it is not clear why no fatigue TLAA is applicable to these components even though this penetration assembly is part of the reactor coolant pressure boundary. In addition, the staff noted that the applicant's claim that no fatigue TLAA is applicable to the flP/SLC penetration/nozzle and safe-end assembly is in conflict with the applicant's inclusion of the liquid control-flP nozzle in LRA Table 4.3-2 for cumulative usage factors.
Request.
- a. Clarify why there is no applicable TLAA for the flP/SLC penetration/nozzle and safe-end assembly. As part of the response, resolve the apparent conflict between the applicant's inclusion of the liquid control-flP nozzle in LRA Table 4.3-2 and the applicant's claim that there is no TLAA applicable to GGNS in BWRVIP-27-A.
- b. Clarify which component is specifically referred to by the "liquid control-flP nozzle" among the flP/SLC penetration/nozzle and safe-end assembly (e.g., the stub tube and its weld to the penetration). In addition, justify why the "liquid control-flP nozzle" is the representative component of the flP/SLC penetration/nozzle and safe-end assembly for the fatigue TLAA, and why the other components of the assembly do not need to be addressed in LRA Table 4.3-2.
RAI B.1.9-1 Background. The "scope of program" program element of GALL Report AMP XI.M7, "BWR Stress Corrosion Cracking," states that the program is applicable to all BWR piping and piping welds made of austenitic stainless steel and nickel alloy that are 4 inches or larger in nominal diameter containing reactor coolant at a temperature above 93°C (200 OF) during power operation, regardless of code classification. The GALL Report recommends the BWR Stress Corrosion Cracking Program to manage cracking due to SCC and IGSCC of stainless steel piping, piping components, and piping elements exposed to treated water greater than 60°C (140 OF).
LRA Section B.1.9 states that the BWR Stress Corrosion Cracking Program is an existing program that manages cracking of the RCPB using preventive measures, inspection, and flaw evaluation. In addition, LRA 3.2.1-54 indicates that SRP-LR, Table 3.2-1, item 54, was not used and the stainless steel components of the engineered safety features (ESF) subject to
-5 evaluation under the BWR Stress Corrosion Cracking Program were reviewed as part of the Class 1 RCPB in LRA Table 3.1.2-3.
Issue. The staff noted that in LRA Table 3.1.2-3 for the RCPB components, the applicant credited the BWR Stress Corrosion Cracking Program to manage the aging effect of RCPB components only. The LRA does not clearly address whether or not the scope of the program includes augmented inspections of non-Class-1 stainless steel piping and its associated welds.
Request. Clarify if the scope of the BWR Stress Corrosion Cracking Program includes non Class-1 piping and piping welds made of austenitic stainless steel or nickel alloy materials. If the scope of the program does not include non-Class-1 piping and piping welds, justify why non Class-1 piping and piping welds are excluded from the program scope.
If non-Class 1 piping and welds are within the scope of the BWR Stress Corrosion Cracking Program, revise LRA Sections 8.1.9 and A.1.9, as necessary, to clarify that the scope of the program includes the relevant piping and piping welds regardless of code classification.
RAI8.1.9-2 Background. GALL Report AMP XLM7 states that NUREG-0313, Revision 2 and NRC Generic Letter (GL) 88-01 delineate the guidance for the inspections and the selection of resistant materials and processes that provide resistance to IGSCC. LRA Section B.1.9 states that the BWR Stress Corrosion Cracking Program implements the program delineated in NUREG-0313, Revision 2; GL 88-01; and Supplement 1 of GL 88-01.
Issue. During the audit, the staff noted that the site documentation indicates that the applicant's "detection of aging effects" program element is credited to manage cracking of the following components as well as piping and piping welds: (1) stainless steel thermal sleeves and nickel alloy thermal sleeve extensions of reactor vessel nozzles (recirculation inlet, core spray inlet and RHRlLPCI nozzles), and (2) stainless steel pump casings, valve bodies, and thermowells.
However, the inspections recommended in GALL Report AMP XI.M7 and in GL 88-01 apply mainly to piping made of stainless steel or nickel alloy and their associated welds. Therefore, it is not clear what type of inspections will be performed on the thermal sleeves, thermal sleeves extensions, pump casings, valve bodies, and thermowells as part of the BWR Stress Corrosion Cracking Program.
Request. Identify the types of inspections performed on the following components in accordance with the applicant's BWR Stress Corrosion Cracking Program: (1) stainless steel sleeves and nickel alloy thermal sleeve extensions of reactor vessel nozzles (recirculation inlet, core spray inlet, RHRlLPCI nozzles), and (2) stainless steel pump casings, valve bodies, and thermowells. Specifically, identify the inspection methods, sample sizes, and inspection frequencies that will be applied to the inspections of these components during the period of extended operation and justify why inspection methods, sample sizes, and inspection frequencies selected are considered to be capable of detecting and managing cracking in the components during the period of extended operation.
- 6 RAI8.1.10-1 Background. LRA Section B.1.1 0, states that the BWR Vessel Inside Diameter (10) Attachment Welds Program is an existing program that manages cracking of structural welds for BWR reactor vessel integral attachments. The LRA states that the program is consistent with GALL Report AMP XI.M4, "BWR Vessel 10 Attachment Welds," and the inspection of reactor vessel internal attachment welds is governed by the BWRVIP-48-A report. GALL Report AMP XI.M4 indicates that the program includes inspection and flaw evaluation in accordance with the guidelines in the BWRVIP-48-A report.
a Issue. The UFSAR Supplement in LRA Section A.1.1 states that applicable industry standards and staff-approved BWRVIP documents are used to delineate the program. The staff noted that the summary description for this program in the UFSAR Supplement does not identify the use of the BWRVIP-48-A report, which is recommended by GALL Report AMP XI.M4.
Request. Justify why the BWRVIP-48-A report does not need to be identified in LRA Section a
A.1.10, or revise LRA Section A.1.1 to indicate that the BWR Vessel 10 Attachment Welds Program uses inspections and flaw evaluation in accordance with the guidelines in the BWRVIP-48-A report.
RAI 8.1.23-1 Background. LRA Section B.1.23, "Inservice Inspection," states that, "lSI Program Summary Reports between 2004 and 2010 reveal compliance and provide evidence that the program is effective for managing aging effects in accordance with the ASME Boiler Pressure Vessel Code Section XI."
GALL AMP XI.M1, "ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD,"
states that the program "has been shown to be generally effective in managing aging effects in Class 1, 2, or 3 components and their integral attachments in light-water cooled power plants."
It also provides industry operating experience cases in the "operating experience" program element.
Issue. The "operating experience" program element of the Inservice Inspection (lSI) Program indicates that the program is consistent with the GALL Report and is in compliance with the ASME Code. However, the LRA does not provide any detailed discussion, beyond the general statement about the Code compliance, to demonstrate the effectiveness of the program in detecting and managing the aging effects of Class 1, 2, or 3 components. The applicant's lSI Program Summary Reports between 2004 and 2010 provide brief inspection results to establish the program's compliance with the ASME Code, but do not provide any discussion to demonstrate program effectiveness in the context of monitoring, detecting, and correcting aging degradation. It is not clear how the applicant's plant-specific operating experience demonstrates the effectiveness of the program (e.g., detection of aging effects and directing corrective actions in a timely manner).
-7 Request.
- a. Provide detailed representative operating experience related to the Inservice Inspection Program in order to demonstrate that the program is effective in managing aging effects in accordance with ASME Code Section XI. The discussion should provide context for any specific example in terms of (1) detection of aging effects such as indications of cracking or loss of material, (2) monitoring and trending of aging effects such as results of flaw evaluation and subsequent inspections, and (3) timely corrective actions such as inspection sample expansion and repairireplacement activities.
- b. If a need is identified for expanding the program elements based on the plant-specific operating experience review, enhance the program accordingly. In addition, revise the applicable LRA sections, as necessary, consistent with this RAI response.
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARDCOPY:
DLR RF E-MAIL:
PUBLIC [or NON-PUBLIC. if applicable]
RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV DMclntyre, OPA
Mr. Michael Perito Vice President, Site Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)
Dear Mr. Perito:
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulation, Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1 (GGNS) for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301- 415-1045 or e-mail nathanieIJerrer@nrc.gov.
Sincerely, I RAJ Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50- 416
Enclosure:
Requests for Additional Information cc w/encl: Listserv DISTRIBUTION: See following pages ADAMS Accession No ..'ML12067a235 OFFICE LA:RPB1 :DLR rPM:RPB1 :DLR BC:RPB1:DLR PM:RPB1 :DLR NAME YEdmonds NFerrer DMorey NFerrer DATE 03/23/12 03/27/12 03/28/12 04/3112 OFFICIAL RECORD COpy