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MONTHYEARML11350A0532012-01-0404 January 2012 Plan for the Scoping and Screening Regulatory Audit Regarding the Grand Gulf Nuclear Station, Unit 1 License Renewal Application Review Project stage: Other ML12009A1052012-01-18018 January 2012 Plan for the Aging Management Program Regulatory Audit Regarding the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Review Project stage: Other ML12067A2352012-04-0303 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12068A2332012-04-0404 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12080A1912012-04-11011 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Grand Gulf LRA RAI Set 3 Project stage: RAI ML12074A0082012-04-12012 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12076A0142012-04-16016 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA Draft RAI Set 5 Project stage: Draft RAI ML12076A0092012-04-17017 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal (TAC ME7493) Grand Gulf LRA Draft RAI Set 6 Project stage: Draft RAI ML12087A0012012-04-18018 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC ME7493)Grand Gulf LRA RAI Set 07 Project stage: RAI ML12094A0092012-04-25025 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nulcear Station Licesne Renewal Application Project stage: RAI ML12101A3602012-04-26026 April 2012 Request for Additional Information for the Review of Th Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 09 Project stage: RAI ML12104A2192012-04-30030 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)LRA RAI Set 10 Project stage: RAI GNRO-2012/00029, Response to Request for Additional Information (RAI) Regarding the License Renewal Application2012-05-0101 May 2012 Response to Request for Additional Information (RAI) Regarding the License Renewal Application Project stage: Response to RAI ML12109A2132012-05-0303 May 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 11 Project stage: RAI GNRO-2012/00036, Response to Request for Additional Information (RAI) Dated April 12, 20122012-05-0909 May 2012 Response to Request for Additional Information (RAI) Dated April 12, 2012 Project stage: Response to RAI ML12118A5392012-05-15015 May 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12125A3732012-05-24024 May 2012 Requests for Additional Information for the Review of the Grant Gulf Nuclear Station License Renewal Application (TAC No. ME7493)Grand Gulf LRA RAI Set 17 Project stage: RAI ML12139A0552012-05-29029 May 2012 LRA RAI Set 19 Project stage: RAI ML12151A2652012-06-15015 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 20 Project stage: RAI ML12165A3872012-06-20020 June 2012 Scoping and Screening Methodology Audit Report Regarding the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Project stage: Other ML12151A3682012-06-20020 June 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12152A3932012-06-22022 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12152A3452012-06-22022 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (Tac No. ME7493) Project stage: RAI ML12157A0562012-06-27027 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)Grand Gulf LRA RAI Set 24 Project stage: RAI ML12164A7262012-06-27027 June 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12180A5412012-07-17017 July 2012 Summary of Telephone Conference Call Held on March 14, 2012, Between NRC and Entergy Operations, Inc., Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12188A7062012-07-17017 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12188A5162012-07-23023 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12200A1382012-07-27027 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B4762012-07-27027 July 2012 LRA RAI Set 30 Project stage: RAI ML12191A1872012-07-31031 July 2012 LRA RAI Telecon 2012-04-13 Project stage: RAI ML12208A2672012-08-0707 August 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12193A0712012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12220A3372012-08-15015 August 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B5042012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/23/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning the RAIs Pertaining to the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12202A2142012-08-15015 August 2012 5/30/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12230A3102012-08-21021 August 2012 Correction to Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B5452012-08-28028 August 2012 Summary of Telephone Conference Call Held on 6/5/12, Between NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12209A1482012-08-28028 August 2012 6/8/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12234A6712012-09-0505 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12242A5452012-09-0707 September 2012 Revision of Schedule for the Conduct of Review of the Grand Gulf Nuclear Station, LRA Project stage: Approval ML12230A2472012-09-0707 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12214A5482012-09-14014 September 2012 7/18/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12248A1582012-09-14014 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12270A2492012-10-0303 October 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12278A0362012-10-17017 October 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12286A0242012-10-19019 October 2012 RAI for the Review of the Grand Gulf Nuclear Station LRA Project stage: RAI GNRO-2012/00128, Response to Requests for Additional Information (RAI) Set 38 Dated 10/03/20122012-10-22022 October 2012 Response to Requests for Additional Information (RAI) Set 38 Dated 10/03/2012 Project stage: Response to RAI ML12264A3872012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/21/12, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12250A1052012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI 2012-05-15
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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML23116A1462023-04-26026 April 2023 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23059A0742023-02-27027 February 2023 Information Request, Security IR 2023402 ML22353A6122022-12-19019 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22271A8572022-10-0303 October 2022 Notification of Commercial Grade Dedication Inspection (05000416/2023011) and Request for Information ML22110A1172022-04-19019 April 2022 (GG) 2022 Emergency Preparedness (EP) Program Inspection RFI Sdh 041922 ML21179A1202021-06-28028 June 2021 Notification of NRC Supplemental Inspection of Action Matrix Column 3 (Degraded Performance) Inputs and Request for Information ML21074A0822021-03-15015 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000416/2021002) and Request for Information ML20363A1462020-12-22022 December 2020 Request for Information: Grand Gulf EP Exercise Inspection - March 2021 ML20258A0202020-09-0909 September 2020 EP Program Inspection RFI, Request for Information to Support and Prepare for Emergency Preparedness (EP) Program Inspection Scheduled to Occur the Week of November 16, 2020 ML20260H4422020-09-0808 September 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Official RAIs for RR Associated with Updating ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20155K7172020-06-0303 June 2020 Notification of NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000416/2020013) and Request for Information ML20150A6012020-05-29029 May 2020 NRR E-mail Capture - Grand Gulf - Official RAI for LAR Associated with Containment ILRT Interval Change from 10 Years to 15 Years ML19302E1082019-10-29029 October 2019 Document Request - GG 95001 - August 2 2019 ML19078A3772019-03-19019 March 2019 NRR E-mail Capture - Grand Gulf - Official Rais for Relief Request GG-ISI-023, Inservice Inspection Impracticality, Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval ML19063B4882019-03-0404 March 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000416/2019002) and Request for Information ML18304A4602018-10-31031 October 2018 NRR E-mail Capture - Final Request for Additional Information - TSTF-425 (L-2018-LLA-0106) ML18250A3042018-08-30030 August 2018 NRR E-mail Capture - Final Request for Additional Information - Emergency Action Level Scheme Change (L-2018-LLA-0116) ML18250A3032018-08-0101 August 2018 NRR E-mail Capture - Correction: Draft RAI - EAL Scheme Change (L-2018-LLA-0116) ML18187A3292018-07-20020 July 2018 Request for Additional Information, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18138A4682018-05-23023 May 2018 Supplemental Information Needed for Acceptance of Request for Licensing Action Adoption of TSTF-425, Relocate Surveillance Frequencies to License Control ML18058A0572018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update) ML17257A1422017-09-14014 September 2017 NRR E-mail Capture - Grand Gulf - Official Requests for Additional Information (Rais) for RR GG-ISI-020 to Use BWRVIP Guidelines ML17235B1752017-08-23023 August 2017 NRR E-mail Capture - Grand Gulf - Official RAI for Relief Request GG-ISI-021 Associated with Fourth Interval Inservice Inspection Using Code Case N-702 ML17214A0992017-08-0202 August 2017 NRR E-mail Capture - Grand Gulf - Official RAIs for LAR Associated with One Cycle Extension of Appendix J Type a ILRT and Drywell Bypass Test Interval ML17142A2582017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000416/2017007) and Initial Request for Information ML16181A1122016-07-12012 July 2016 Request for Additional Information on Severe Accident Mitigation Alternatives for the Review of the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Environmental Review ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15286A1082015-10-28028 October 2015 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application ML15261A5652015-09-24024 September 2015 Request for Additional Information Regarding Proposed Revision of Technical Specifications for Containment Leak Rate Testing ML15085A4932015-04-0606 April 2015 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application, Set 52 GNRO-2015/00002, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/20142015-03-27027 March 2015 Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/2014 ML15036A5642015-02-18018 February 2015 Updated Fluence Methodology License Amendment Request Unacceptable with Opportunity to Supplement GNRO-2014/00079, Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186)2014-11-13013 November 2014 Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186) GNRO-2014/00076, Response to Request for Additional (RAI) Set 51 Dated September 11, 20142014-11-0606 November 2014 Response to Request for Additional (RAI) Set 51 Dated September 11, 2014 GNRO-2014/00031, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-04-11011 April 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 ML13318A8052014-01-0202 January 2014 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 50 ML13353A6572013-12-19019 December 2013 Licensed Operator Positive Fitness-For-Duty Test ML13345A1822013-12-19019 December 2013 Supplemental Information Needed for Acceptance of Licensing Action, Request to Revise Technical Specification to Allow Operation in Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Domain ML13316B9862013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13263A2252013-11-21021 November 2013 LRA Draft RAI Set 48 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13260A0062013-09-16016 September 2013 Email, Request for Additional Information, Round 3, Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 ML13238A2342013-09-12012 September 2013 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 49 ML13227A3942013-08-28028 August 2013 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 47 ML13226A1902013-08-14014 August 2013 Request for Additional Information Email, Round 2, Request to Revise FOL to Delete 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML13207A1242013-07-30030 July 2013 Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) ML13149A3662013-05-29029 May 2013 Request for Additional Information Email Decommissioning Funding Status Report 2023-04-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 21, 2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
CORRECTION TO REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)
Dear Mr. Perito:
On August 15, 2012, the Nuclear Regulatory Commission (NRC) issued requests for additional information (RAls) Agencywide Documents and Management System (ADAMS) Accession No. ML12220A337, in regards to your application to renew the operating license for Grand Gulf Nuclear Station, Unit 1.
Due to an inadvertent error, the RAls were labeled as draft RAls. The corrections are marked in the enclosure. No other changes were made.
We regret any inconvenience this may have caused.
Sincerely, Nathaniel Ferrer, Project Manager Projects Branch 1 Division of license Renewal Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
As stated cc w/encl: Listserv
GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION SET 32 0Fa.ft RAI 3.5.1.12-1 Background. NRC Information Notice (IN) 2011-20 "Concrete Degradation by Alkali-Silica Reaction (ASR)" was issued to inform industry of operating experience related to concrete degradation due to ASR. IN 2011-20 was issued on November 18, 2011, which is after the NRC received the Grand Gulf Nuclear Station (GGNS) license renewal application (LRA) on November 1,2011. IN 2011-20 states that the American Society for Testing and Materials (ASTM) updated standards, ASTM C1260 and ASTM C1293, and guidance provided in the appendices of ASTM C289 and ASTM C1293, cautions that the tests described in ASTM C227 and ASTM C289 may not accurately predict aggregate reactivity when dealing with late- or slow-expanding aggregates containing strained quartz or microcrystalline quartz.
The Generic Aging Lessons Learned (GALL) Report recommends using the XLS2 "ASME Section XI, Subsection IWL," XI.S6 "Structures Monitoring," and XI.S7, "Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" or the Federal Energy Regulatory Commission (FERC)/US Army Corp of Engineers dam inspections and maintenance aging management programs (AMPs) to manage cracking due to expansion from reaction with aggregates for those accessible areas of concrete structures within the scope of the respective programs. However, for inaccessible areas, further evaluation is required to determine if a plant-specific AMP is needed.
The following discussions for items with same aging-effect/mechanism "cracking due to expansion from reaction with aggregates" were provided in LRA Table 3.5.1:
LRA Table 3.5.1, item 12, states that this item is not applicable and the listed aging effects do not require management at GGNS. Nonetheless, components are included in the Containment Inservice Inspection -IWL program to verify the absence of other aging effects, such as loss of material, for components in this listing.
LRA Table 3.5.1, item 19, states that this item is not applicable and the listed aging effects do not require management at GGNS. Nonetheless, components are included in the Containment Inservice Inspection -IWL program to verify the absence of other aging effects, such as cracking, for components in this listing.
LRA Table 3.5.1, item 43, states that this item is consistent with the GALL Report. The Structures Monitoring program will manage the effects of cracking for the components in this listing.
LRA Table 3.5.1, item 50, states that this item is not applicable. Listed aging effects do not require management at GGNS. Nonetheless, components are included in the RG 1.127 and Structures Monitoring programs to verify the absence of other aging effects, such as cracking, for components in this listing.
LRA Table 3.5.1, item 54, states that cracking due to expansion due to reaction with aggregates does not require aging management for concrete for these groups of structures at GGNS, ENCLOSURE
-2 because concrete is constructed in accordance with the recommendation in ACI 318.
Nonetheless, components are included in the Structures Monitoring program.
Issue. The GALL Report identifies cracking due to expansion from reaction with aggregates as a possible aging effect for concrete structures in any environment; and industry operating experience, communicated through IN 2011-20, has shown that tests described in ASTM C227 and ASTM C289 may not accurately predict aggregate reactivity when dealing with late- or slow-expanding aggregates containing strained quartz or microcrystalline quartz. The staff notes that LRA Section 3.5.2.2.1.8 states potential reactivity of aggregates were tested in accordance with ASTM C 289 and ASTM C 227.
It is also unclear why cracking due to expansion from reaction with late- or slow-expanding aggregates would not be an applicable aging effect at GGNS for LRA Table 3.5.1, items 12, 19, 50, and 54, but is consistent with the GALL Report for item 3.5.1-43 as stated above from the discussion column of Table 3.5-1.
Request.
- a. State if operating experience for cracking due to expansion from reaction with aggregates is applicable to GGNS; and, if applicable, provide action(s) and/or program to manage this aging effect during the period of extended operation.
- b. Provide the technical justification as to why the aging management review (AMR) items associated with cracking due to expansion from reaction with late- or slow-expanding aggregates are not applicable, and why this aging effect does not require aging management at GGNS.
- c. If revisions to LRA Table 3.5.1, items 12,43, and 50 are needed, ensure LRA Sections 3.5.2.2.1.8, 3.5.2.2.2.1.2, and 3.5.2.2.2.3.2 are consistent, to provide clarification in the evaluation of these sections.
I)Rlft RAI 3.5.1.94-1 Background. The GALL report (item III. B 1.1.TP-1 0) states that non-metallic vibration isolation elements exposed to air-indoor, uncontrolled or air-outdoor should be managed for reduction or loss of isolation function due to radiation hardening, temperature, humidity, and sustained vibratory loading using the ASME Section XI, Subsection IWF Program. In LRA table 3.5-1, item 94, the applicant states that age management of vibration isolation elements is not applicable because no vibration isolation elements at GGNS are in scope and subject to aging management review. The staff reviewed the applicant's Inservice Inspection-IWF Program in LRA Section B.1.24 and noted that there is an enhancement to the parameters monitored or inspected program element that states, "Elastomeric vibration elements will be monitored for cracking, loss of material, and hardening." Further, the staff reviewed LRA Section A.1.42 and noted that the Structures Monitoring Program is enhanced with inspection requirements for vibration isolators to include augmented inspections by feel or touch to detect hardening if the vibration isolation function is suspect.
Issue. The applicant's statement that there are no vibration isolation elements in scope is not consistent with the applicant's proposed enhancement to the "parameters monitored or inspected" ISI-IWF program element stated in LRA Section B.1.24 or the applicant's proposed
- 3 enhancement to the Structures Monitoring program in LRA Section A.1.42 for age management of vibration isolation elements.
Request.
- a. Clarify if there are vibration isolation elements at GGNS included in scope for license renewal. If not included in scope, provide justification to support that determination.
- b. If vibration isolation elements will be managed as stated in the Structures Monitoring and/or Inservice Inspection-IWF Programs, confirm that the statements in the LRA accurately reflect the planned enhancements to those programs.
{Haft RAI 81.14-2a Background. In response to RAI B1.14-2 dated July 25,2012, the applicant described the acceptance criteria used for the GGNS containment concrete surface visual examination. The applicant also stated that the GGNS acceptance criteria used for the containment concrete surface visual examination are consistent with the quantitative acceptance criteria recommended in Chapter 5 of ACI 349.3R-02.
Issue. The staff reviewed the applicant's response of RAI B 1.14-2, and noted that the detai/ed acceptance criteria described in RAI B1.14-2 response for the GGNS containment concrete surface is based on the quantitative limits of the second tier acceptance criteria in Subchapter 5.2.1 of ACI 349.3R-02. This does not appear to be consistent with the guidelines recommended in Chapter 5 of ACI 349.3R-02, which require further evaluation if concrete surface conditions did not meet the quantitative limits of first tier acceptance criteria in Subchapter 5.1.1. The applicant did not provide any justification for excluding the first tear evaluation criteria of the ACI 349.3R-02 for the GGNS containment concrete surface examination.
Request. Explain the reason for not using the first tier evaluation criteria as defined in Subchapter 5.1 of the ACI 349.3R-02 for the GGNS containment concrete surface examination.
{Haft RAI 8.1.15-1 Background. The GGNS Containment Leak Rate Program, states that GGNS has implemented Option B for the 10 CFR Part 50, Appendix J testing and is consistent with GALL Report AMP XI.S4, "10 CFR Part 50, Appendix J. n The GALL Report AMP XI.S4 "scope of program" program element states, "[t]he scope of the containment LRT program includes all containment boundary pressure-retaining components."
Issue. The GGNS Technical Specifications state, "10 CFR Part 50, Appendix J program establishes the leakage rate testing program of the containment as required by 10 CFR 50.54(0)
[conditions of licenses] and 10 CFR Part 50, Appendix J Option B as modified by approved exemptions." In addition, Section 6.2.6.3, "Primary Containment Isolation Valve Leakage Rate Tests," of the UFSAR states, "[c]ertain valves are not required to be Type C tested by Appendix J although they meet the GDC definitions of containment isolation valves." It is not clear how the applicant will manage aging effects of exempted/excluded components (valves, penetrations, and other components) from the 10 CFR Part 50, Appendix J testing for the period of extended operation.
-4 Request. For those components (valves, penetrations, and other components) that have been exempted/excluded from the 10 CFR Part 50, Appendix J testing, identify how aging effects will be managed during the period of extended operation. Indicate which AMPs will be used to manage the aging effects for each of the exempted/excluded components, or justify why an AMP is not necessary for the period of extended operation.
DFaft-RAI B.1.15-2 Background. The GGNS Containment Leak Rate Program, states that GGNS has implemented Option B for the 10 CFR Part 50, Appendix J testing and is consistent with GALL Report AMP XI.S4. The GALL Report AMP XI.S4 "monitoring and trending" program element states:
Because the LRT program is repeated throughout the operating license period, the entire pressure boundary is monitored over time. The frequency of these tests depends on which option (A or B) is selected. With Option A, testing is performed on a regular fixed time interval as defined in 10 CFR Part 50, Appendix J. In the case of Option B, the interval for testing may be adjusted on the basis of acceptable performance in meeting leakage limits in prior tests.
Additional details for implementing Option B are provided in NRC RG 1.163 and NEI94-01.
Issue. The GGNS Technical Specifications, referencing the 10 CFR Part 50, Appendix J Testing Program, state that the performance characteristics of the program are implemented in accordance with Amendment 135 to the Operating License. The NRC's staff safety evaluation report for Amendment 135, dated April 6, 1998, states that the applicant does not use NRC RG 1.163, which establishes the performance criteria per GALL Report XI.S4, for "10 CFR Part 50, Appendix J Program," for implementation of Option B. There appears to be an inconsistency between the proposed AMP and the recommendations in GALL (Le., use of guidance in NRC RG 1.163 for implementation of Option B for containment leak rate testing).
Request
- a. For the Containment Leak Rate Program, identify the exceptions and/or enhancements needed to make the program consistent with GALL and identify whether the program should be either evaluated as:
- 1. Consistent with exceptions,
- 2. Consistent with enhancements, or
- 3. Consistent with exceptions and enhancements.
- b. If the program is not consistent, consistent with exceptions, or consistent with enhancements with GALL, then expand the summary description of the program sufficiently, so it can be reviewed as a plant-specific program.
0Faft RAI B.1.22-7a Background. In addressing an error report associated with the CHECWORKS software, GGNS condition report CR201 0-00823 stated that CHECWORKS is only one of the tools used by the Flow-Accelerated Corrosion Program to determine component wear. In its initial response to the RAI for this issue, the staff requested GGNS to provide a description of other in-place
-5 processes or verification methods used by the Flow-Accelerated Corrosion Program to determine component wear that could validate or detect errors in the CHECWORKS software.
The response dated May 25, 2012, stated that the results of component inspections are the primary input used to calculate the next scheduled inspection, and that this approach provides reasonable assurance that an error in the CHECWORKS software will not prevent the GGNS Flow-Accelerated Corrosion Program from providing reasonable assurance that the intended function of components will be maintained. The response concluded that as more actual inspection data is acquired, the already limited reliance of CHECWORKS becomes less.
Issue. The condition report discussed above documented an error in the CHECWORKS software and the resolution of this issue stated that CHECWORKS is only one of the tools used by the Flow-Accelerated Corrosion Program to predict component wear. The response appears to state that GGNS calculates the next scheduled inspection primarily using the results of component inspections independently from CHECWORKS. It is not clear to the staff how GGNS calculates the next scheduled inspection using the results of component inspections without CHECWORKS. Further, it is not clear to staff how reliance on the component inspection results reduces the effects of the errors in CHECKWORKS. Since the condition report stated that CHECWORKS is only one of the tools used by the Flow-Accelerated Corrosion Program to determine component wear, the staff needs additional information about the other tools that are used to calculate component wear.
Request. Provide a description of the other tools (i.e., any in-place process or verification method), which are used in the Flow-Accelerated Corrosion Program to determine component wear that could detect or validate errors in the CHECWORKS software. If CHECWORKS is the only prediction tool being used, then explain how the use of component inspection results reduces the effects of any errors in CHECWORKS.
Df!aft RAJ B.1.43-1a Background. GALL Report AMP XI.M2, "Water Chemistry," states that the water chemistry program for bOiling-water reactors (BWRs) relies on monitoring and control of reactor water chemistry based on industry guidelines in the BWR Vessel and Internals Project (BWRVIP)-190.
The response to RAI 8.1.43-1, dated May 25, 2012, regarding the methods used to determine the effectiveness of hydrogen water chemistry (HWC) at GGNS, states that platinum loading will be verified by using an artifact that had been removed from the reactor core, because an electrochemical corrosion potential (ECP) mitigation monitoring system was not available during the last operating cycle. The response continued by stating that BWRVIP-62, Revision 1, "Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection,"
does not require platinum deposition measurements on coupons to demonstrate mitigation for reactors that use on-line noble chemistry (OLNC). The response also stated that the recommendations by the NRC in the safety evaluation to BWRVIP-62 were incorporated into BWRVIP-62-A, which have been incorporated into BWRVIP-62, Revision 1. The applicant further stated that continuous ECP monitoring will be installed during the spring 2012 outage, which will meet the recommendations of BWRVIP-62, Revision 1.
Issue. The NRC has not reviewed BWRVIP-62, Revision 1, and there are differences between the NRC's recommendations for verification of noble metal loading in the safety evaluation
-6 related to BWRVIP-62-A, and the guidance given in BWRVIP-62, Revision 1. Specifically, BWRVIP-62-A states that noble metal (platinum) loading shall be monitored by periodic removal of durability monitors or by removal and analysis of deposits from artifacts within the vessel. In addition, the staff noted that BWRVIP-190, states that for plants using noble metal chemical application with ECP probes, catalyst (platinum) loading on durability monitors or vessel artifacts are to be monitored to demonstrate the effective implementation of HWC. Furthermore, although BWRVIP-190 discusses OLNC, it does not address any difference for platinum deposition measurements on coupons for plants using this technique. It is not clear to the staff whether the applicant will continue to monitor noble metal loading during the period of extended operation or whether continuous ECP monitoring has been installed.
Request. Confirm that, during the period of extended operation, the Water Chemistry Control BWR program will monitor noble metal loading by either periodic removal of durability monitors or by removal and analysis of deposits from artifacts within the vessel. If not, justify the difference with BWRVIP-190 for monitoring catalyst loading to demonstrate effective implementation of HWC. Additionally, confirm that continuous ECP monitoring has been installed.
August 21,2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150 SUB~IECT: CORRECTION TO REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)
Dear Mr. Perito:
On August 15, 2012, the Nuclear Regulatory Commission (NRC) issued requests for additional information (RAls) Agencywide Documents and Management System (ADAMS) Accession No. ML12220A337, in regards to your application to renew the operating license for Grand Gulf Nuclear Station, Unit 1.
Due to an inadvertent error, the RAls were labeled as draft RAls. The corrections are marked in the enclosure. No other changes were made.
We regret any inconvenience this may have caused.
Sincerely, IRA!
Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
As stated cc w/encl: Listserv DISTRIBUTION: See following pages ADAMS Accession No.: ML12230A310 I OFFICE PM:RPB1:DLR BC:RPB1 :DLR
!
NAME NFerrer DMorey DATE 8/20/12 8/21/12 OFFICIAL RECORD COpy
Letter to M. Perito from N. Ferrer dated August 21,2012
SUBJECT:
CORRECTION TO REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION DISTRIBUTION:
E-MAIL:
PUBLIC 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 GPick, RIV DMclntyre,OPA