Letter Sequence RAI |
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MONTHYEARML11350A0532012-01-0404 January 2012 Plan for the Scoping and Screening Regulatory Audit Regarding the Grand Gulf Nuclear Station, Unit 1 License Renewal Application Review Project stage: Other ML12009A1052012-01-18018 January 2012 Plan for the Aging Management Program Regulatory Audit Regarding the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Review Project stage: Other ML12067A2352012-04-0303 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12068A2332012-04-0404 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12080A1912012-04-11011 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Grand Gulf LRA RAI Set 3 Project stage: RAI ML12074A0082012-04-12012 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12076A0142012-04-16016 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA Draft RAI Set 5 Project stage: Draft RAI ML12076A0092012-04-17017 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal (TAC ME7493) Grand Gulf LRA Draft RAI Set 6 Project stage: Draft RAI ML12087A0012012-04-18018 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC ME7493)Grand Gulf LRA RAI Set 07 Project stage: RAI ML12094A0092012-04-25025 April 2012 Requests for Additional Information for the Review of the Grand Gulf Nulcear Station Licesne Renewal Application Project stage: RAI ML12101A3602012-04-26026 April 2012 Request for Additional Information for the Review of Th Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 09 Project stage: RAI ML12104A2192012-04-30030 April 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)LRA RAI Set 10 Project stage: RAI GNRO-2012/00029, Response to Request for Additional Information (RAI) Regarding the License Renewal Application2012-05-0101 May 2012 Response to Request for Additional Information (RAI) Regarding the License Renewal Application Project stage: Response to RAI ML12109A2132012-05-0303 May 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 11 Project stage: RAI GNRO-2012/00036, Response to Request for Additional Information (RAI) Dated April 12, 20122012-05-0909 May 2012 Response to Request for Additional Information (RAI) Dated April 12, 2012 Project stage: Response to RAI ML12118A5392012-05-15015 May 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12125A3732012-05-24024 May 2012 Requests for Additional Information for the Review of the Grant Gulf Nuclear Station License Renewal Application (TAC No. ME7493)Grand Gulf LRA RAI Set 17 Project stage: RAI ML12139A0552012-05-29029 May 2012 LRA RAI Set 19 Project stage: RAI ML12151A2652012-06-15015 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493) Grand Gulf LRA RAI Set 20 Project stage: RAI ML12165A3872012-06-20020 June 2012 Scoping and Screening Methodology Audit Report Regarding the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Project stage: Other ML12151A3682012-06-20020 June 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12152A3932012-06-22022 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12152A3452012-06-22022 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (Tac No. ME7493) Project stage: RAI ML12157A0562012-06-27027 June 2012 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)Grand Gulf LRA RAI Set 24 Project stage: RAI ML12164A7262012-06-27027 June 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12180A5412012-07-17017 July 2012 Summary of Telephone Conference Call Held on March 14, 2012, Between NRC and Entergy Operations, Inc., Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12188A7062012-07-17017 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12188A5162012-07-23023 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12200A1382012-07-27027 July 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B4762012-07-27027 July 2012 LRA RAI Set 30 Project stage: RAI ML12191A1872012-07-31031 July 2012 LRA RAI Telecon 2012-04-13 Project stage: RAI ML12208A2672012-08-0707 August 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12193A0712012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12220A3372012-08-15015 August 2012 RAI for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B5042012-08-15015 August 2012 Summary of Telephone Conference Call Held on 5/23/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning the RAIs Pertaining to the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12202A2142012-08-15015 August 2012 5/30/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12230A3102012-08-21021 August 2012 Correction to Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12201B5452012-08-28028 August 2012 Summary of Telephone Conference Call Held on 6/5/12, Between NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12209A1482012-08-28028 August 2012 6/8/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12234A6712012-09-0505 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12242A5452012-09-0707 September 2012 Revision of Schedule for the Conduct of Review of the Grand Gulf Nuclear Station, LRA Project stage: Approval ML12230A2472012-09-0707 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12214A5482012-09-14014 September 2012 7/18/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12248A1582012-09-14014 September 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12270A2492012-10-0303 October 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12278A0362012-10-17017 October 2012 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application Project stage: RAI ML12286A0242012-10-19019 October 2012 RAI for the Review of the Grand Gulf Nuclear Station LRA Project stage: RAI GNRO-2012/00128, Response to Requests for Additional Information (RAI) Set 38 Dated 10/03/20122012-10-22022 October 2012 Response to Requests for Additional Information (RAI) Set 38 Dated 10/03/2012 Project stage: Response to RAI ML12264A3872012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/21/12, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI ML12250A1052012-10-31031 October 2012 Summary of Telephone Conference Call Held on 8/15/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA Project stage: RAI 2012-05-15
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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
[Table view] Category: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 September 5, 2012 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 Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, 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 bye-mail at nathaniel.ferrer@nrc.gov.
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 34 RAI B.1.22-1a
Background:
Based on information from Grand Gulf Nuclear Station (GGNS) calculation MC Q1111-08011, the staff issued request for additional information (RAI) B.1.22-1 questioning whether the Flow-Accelerated Corrosion (FAC) Program manages wall thinning for components in the low pressure core spray (LPCS) and high pressure core spray (HPCS) systems. The applicant's response, dated May 25, 2012, states that these systems are not susceptible to FAC because they experience two phase flow less than two percent of the time and that the referenced calculation confirmed the conclusion that the FAC Program is not required to manage wall thinning in the LPCS and HPCS systems. The response also stated that no other systems have aging effects being managed by the FAC Program that were not identified in the license renewal application (LRA).
Information obtained during the staff's aging management program audit appears to indicate that several items in the LPCS (Le., #333, #403, #661, #662) and HPCS (i.e., #253, #285, #301,
- 307, #402, #605) systems were being monitored through inspections performed by the FAC Program. In addition, the staff identified an excess of 40 items in the residual heat removal (RHR) system that appeared to be monitored through inspections performed by the FAC Program. However these components appear to be in portions of the RHR system that the CSI Technology evaluation No. 0700.104-10, "GGNS FAC System Susceptibility Evaluation," had excluded from susceptibility for FAC for an unspecified reason.
Issue: It is not clear to the staff whether the System Susceptibility Evaluation improperly excluded systems or portions of systems that were susceptible to FAC, or the inspections being performed by the FAC Program are monitoring components that are susceptible to an aging mechanism other than FAC, or components that were previously monitored by the FAC Program have been determined to be acceptable until the end of the period of extended operation and no longer need to be monitored.
Request: Review the components contained in the FAC Program's reinspection list for future outages (specifically, items 333, 403, 661, 662, 253, 285, 301, 307, 402, and 605) and determine whether the inspections conducted on these components were for wall thinning due to FAC or for some other wall thinning mechanism.
If these components are no longer being inspected through the FAC Program, either identify the program that now monitors wall thinning for these components or provide details showing that these components had previously been determined to be acceptable through the end of the period of extended operation.
If these or any other components are being inspected through the FAC Program and were previously excluded through the System Susceptibility Evaluation, explain why the System Susceptibility Evaluation inappropriately excluded these components and revise the LRA to justify the use of the FAC Program to monitor aging mechanisms other than FAC.
ENCLOSURE
- 2 RAI B.1.22-2a
Background:
GGNS Procedure EN-DC-315, "Flow-Accelerated Corrosion Program,"
Section 5.1.1, "Components Failing to Meet Initial Screening Criteria," states that a condition report shall be generated when "significant wall thinning," is detected in a system or when wall thinning is below T accpt [acceptable wall thickness]. "Significant wall thinning" is defined in Section 3.0.39 as the largest of a) a thickness less than 60 percent of nominal pipe wall thickness (T nom), b) a thickness less than Y:z (0.875 T nom + T accpt), or c) T accPt+0.020 inches.
The staff issued RAI B.1.22-2 requesting GGNS to confirm that significant wall thinning, as defined in EN-DC-315, had not been detected in recent outages and condition reports were not required to be generated. The response to RAI B.1.22-2, dated May 25, 2012, stated:
A review of program documentation and data from the Fall 2008 and Spring 2010 refueling outages determined that no significant wall thinning has been detected other than the wall thinning documented in the condition reports referenced in the background of this request for information, which had resulted in wall thickness below the minimum acceptable wall thickness. Thus no additional condition reports on significant wall thinning as defined in EN-DC-315 were required to be generated.
Information obtained during the staff's aging management program audit appears to indicate several instances where the measured wall thickness (T meas) was less than 60 percent of T nom, which meets the criteria for "significant wall thinning" in EN-DC-315. Specifically, in calculation MC-Q111-08011, "Evaluation of RF16 Flow Accelerated Corrosion Wall Thickness Data," for the refueling outage in fall 2008:
Item 314A, 4-inch pipe to downstream tee: T nom = 0.237, T meas= 0.122 [51%]
Item 353, 3x6 expander: T nom = 0.280, T meas = 0.163 [58%]
Item 795, 2-inch elbow and pipe: T nom = 0.218, T meas = 0.095 [44%]
Issue: Inspections apparently identified significant wall thinning, but GGNS did not issue condition reports as required by the controlling procedure. Since the current program is not being implemented in accordance with the controlling procedure, the staff cannot reasonably conclude that the program will be implemented in accordance with the controlling procedure during the period of extended operation.
Reguest: Re-review the program documentation and data from recent outages to confirm that no significant wall thinning, as defined in EN-DC-315, "Flow-Accelerated Corrosion Program" had been identified and condition reports were not required to be generated. Specifically discuss items 314,353, and 795 to explain why these are not examples of "significant wall thinning."
If significant wall thinning was identified, but condition reports were not generated, then provide information to demonstrate that there is reasonable assurance the program will be implemented in accordance with the controlling procedures during the period of extended operation.
-3 RAI8.1.24-1a
Background:
In its response to RAI B.1.24-1, and the updated list of commitments, the applicant stated that it will enhance the Inservice Inspection-IWF Program to identify the component supports that contain high-strength bolting in sizes greater than 1 inch nominal diameter, and that the extent of examination will be as specified in ASME Code Section XI, Subsection IWF (Table IWF-2500-1).
Issue: It is not clear whether the applicant plans to assess the plant for all component supports applicable to the Inservice Inspection-IWF Program that contain high strength structural bolting and then establish a sample based upon the criteria specified in ASME Code Section XI, Table IWF-2500-1, or if the applicant plans to identify the high strength bolts among the component supports already identified as part of the IWF examination sample.
Request: Clarify whether the applicant will identify all of the high strength bolts that are eligible to be part of the IWF inspection population and establish a new sample for high strength bolts based on the ASME Table IWF-2500-1 or it if it is going to identify high strength bolts from the already-established set of IWF supports. If the latter, explain how that approach will ensure that the ASME Code criteria for sample size will be met.
RAI8.1.24-2a
Background:
In RAI B.1.24-2, the staff requested that the applicant provide information regarding degraded components in the standby service water basins and any corrective actions that were taken in accordance with the ASME code. The staff reviewed the response and noted that the applicant expanded the scope and frequency of inspections in accordance with the ASME Section XI, Subsection IWF requirements; however, the staff noted that the expanded scope and frequency of inspections was limited to the standby service water system.
Issue: The staff is concerned that there may be similar aging of IWF components in systems other than the standby service water system with the same material and environment combination.
Request: Provide information on whether there are IWF supports in other areas of the plant that may be subject to similar age-related degradation. If so, provide information as to whether the applicant performed additional examinations extending to other systems in the plant, if any, or provide justification for not determining the potential extent of the degraded condition to other areas.
RAI 8.1.24-3a
Background:
The ASME Code,Section XI, Subsection IWF Program requires the inspection of the same sample of the total population of component supports each inspection interval. The staff noted in the applicant's program operating experience, the applicant discovered degraded conditions that were significant enough that the applicant chose to repair or re-work the component to as-new condition. However, the degradation was not enough to exceed the IWF-3000 acceptance criteria for expansion in scope or additional inspections.
-4 Issue: The staff's concern, as stated in RAI B.1.24-3, is that if IWF supports and components are re-worked to as-new condition, they are no longer representative of the age-related degradation to the remaining components in the population of the IWF scope but that are not in the inspection sample.
Request: Explain how the applicant plans to ensure that the IWF inspection sample components represent the age-related degradation of the rest of the population. If applicable, state whether the program will include an evaluation for the need to substitute components that are re-worked with another that may be more representative of the general population, or to include additional components in the inspection sample.
RAI B.1.24-5a
Background:
In its response to RAls B.1.24-1 and 8.1.24-5, the applicant references the Generic Aging Lesson's Learned (GALL) Report statement that ASTM A-325, F-1852, and ASTM A-490 bolts used in civil structural applications have not shown to be prone to stress corrosion cracking (SCC). In its response to RAI B.1.24-5, the applicant also states that "cracking due to SCC is an applicable aging effect on high-strength bolting greater than one inch and having a yield strength greater than 150 ksi exposed to sustained high tensile stress in a corrosive environment" and that "high-strength bolting is not exposed to a corrosive environment at Grand Gulf Nuclear Station."
Issue: The statement in the GALL Report that ASTM A-325, F-1852, and ASTM A-490 bolts have not been shown to be prone to SCC does not apply to high strength structural bolting for ASME Class 1, 2 and 3 piping and component supports. The GALL Report also does not define or specify criteria for a "corrosive environment" that must be met for age-management of high strength structural bolting, rather it defines the applicable environment as air-indoor, uncontrolled, to manage high strength structural bolting for cracking due to SCC. The GALL Report recommends that the ASME Section XI, Subsection IWF Program is augmented to include consideration of the guidance applicable in EPRI NP-5769, EPRI TR-104213, and the additional recommendations of NUREG-1339 for selection of bolting material installation torque or tension and the use of lubricants and sealants to prevent or mitigate degradation and failure of structural bolting. In addition, the GALL Report recommends that for high strength structural bolting, the preventive actions for storage, lubricants, and SCC potential discussed in Section 2 of Research Council for Structural Connections (RCSC) publication "Specification for Structural Joints using ASTM A325 or A490 Bolts" need to be used. The applicant's response to RAI B.1.24-1 does not indicate whether the applicant's procedures implement the recommended guidance or consider the preventive actions for storage, lubricants, and SCC potential discussed in Section 2 of the RCSC publication "Specification for Structural Joints using ASTM A325 or A490 Bolts."
Request: Specify whether the Inservice Inspection-IWF Program will be enhanced in accordance with the GALL Report such that:
- a. The guidance applicable in EPRI NP-5769, EPRI TR-104213, and NUREG-1339 for selection of bolting material and the use of lubricants and sealants will be used to prevent or mitigate degradation and failure of safety-related bolting
- b. The preventive actions addressed in Section 2 of RCSC publication "Specification for Structural Joints using ASTM A325 or A490 Bolts" will be followed for structural bolting consisting of ASTM A325, ASTM F1852, and/or ASTM A490 bolts If this guidance will not be used, provide technical justification for not following the guidelines recommended in the GALL Report.
RAI8.1.41-1a
Background:
The operating experience discussion for the Service Water Integrity Program states that degraded areas of coatings were identified on the submerged piping in the standby service water (SSW) basins. Based on the degree of degradation noted after 12 months, the staff issued RAI 8.1.41-1 questioning the adequacy of the 36-month inspection frequency specified in the coatings procedure 07-S-07-211, "Service Levell Coatings Conditions Assessment. "
The response to RAI B.1.41-1, states that procedure 07 -S-07 -211 applies to the underwater coatings in the SSW basin, including the coatings on concrete structures, and that the 36-month inspection frequency is appropriate for these concrete structures. The response also stated:
"In addition to the SSW basin inspections specified in Procedure 07-S-07-211, GGNS performs SSW basin pipe coating inspections annually."
The Service Water Integrity Program descriptions in LRA Section B.1.41 and the updated final safety analysis report (UFSAR) supplement in LRA Section A.1.41 state that the Service Water Integrity Program manages loss of material and fouling as described in the GGNS response to GL 89-13. However, the GGNS generic letter (GL) response, dated January 29, 1990, states that for protective coatings, "accessible external piping surface coatings are maintained by routine plant painting efforts." The GGNS response to GL 89-13 did not address submerged piping in the SSW basins, and GGNS Commitment Change Evaluations (CCEs) 2004-0002, 2006-0002, 2006-0004, and 2007-0001, for GL 89-13 commitments did not discuss protective coatings.
Issue: Based on the response to the RAI, it is not clear whether the SSW basin pipe coating inspections are controlled through procedure 07-S-07-211, through some other procedure, or through a combination of procedures. Since the SSW basin pipe coatings are currently inspected annually due to past piping degradation, it is not clear where the inspection frequency is specified and how the inspection frequency is controlled.
In addition, since the GGNS response to GL 89-13 stated that external surfaces are maintained by routine plant painting efforts, but the current inspection and maintenance of submerged piping do not appear to be routine painting activities, the LRA's program description and UFSAR supplement for the Service Water Integrity program do not reflect current GGNS aging management activities for the Service Water Integrity program.
- 6 Request:
- a. Clarify which GGNS procedure controls the coating inspections for submerged piping in the SSW basin, the frequency of these inspections, and how inspection frequencies are adjusted based on plant-specific operating experience.
- b. Update the program description in LRA Sections A.1.41 and 8.1.41 for the Service Water Integrity program to reflect current aging management activities or provide justification that the program described in GGNS response to GL 89-13, as modified through the commitment change process, adequately describes current GGNS aging management activities.
RAI B.1.41-3a
Background:
Based on information in GGNS condition report CR-GGN-201 0-01344, the staff issued RAI 8.1.41-3 requesting information regarding whether components that are being managed for loss of material by the Service Water Integrity program are also being managed for loss of material by GGNS MS-46, "Program Plan for Monitoring Internal Erosion/Corrosion in Moderated Energy Piping Components (Safety Related)." In addition, based on the similarity in definitions between "flow-accelerated corrosion," and "erosion/corrosion," the staff issued RAI B.1.22-3 requesting information regarding the aging effects being managed by GGNS MS-46.
The response to RAI B.1.41-3, dated May 25, 2012, states:
'The GGNS MS-46 procedure for moderate energy piping is not an aging management program that is necessary or credited to manage the effects of aging for components that are included in the Service Water Integrity program." [emphasis added]
By contrast, the response to RAI B.1.22-3, dated May 25,2012, states:
"These inspections [described in GGNS MS-46] are not credited as part of the aging management program described in LRA B.1.22, Flow-Accelerated Corrosion Program.
However, inspections specified in GGNS MS-46 are credited as part of the aging management program for managing loss of material described in LRA B.1.21 Fire Water System Program and LRA B.1.41 Service Water Integrity. Furthermore, the inspections described in GGNS MS-46 may be used, where applicable, as opportunistic or periodic inspections defined in other aging management programs at GGNS." [emphasis added]
GALL Report AMP XI.M20, Open-Cycle Cooling Water System, states that this program manages aging effects caused by mechanisms including erosion. Although the GGNS response to GL 89-13, Action III, Item 7, stated that the SSW system did not meet the selection criteria of the erosion/corrosion monitoring program, the GGNS review for GL 89-13 appears to have used the criteria for NRC Bulletin 87-01, which is for FAC (as clarified in NSAC-202L, "Recommendations for an Effective Flow-Accelerated Corrosion Program"). Erosion as described in GL 89-13 relates to solid particle erosion, but as discussed in DRAFT Interim Staff Guidance 2012-001, "Wall Thinning Due to Erosion Mechanisms," erosion can be caused by other mechanisms, such as cavitation, flashing and droplet impingement.
-7 Issue: Statements that were provided in response to RAI 8.1.41-3 and RAI 8.1.22-3 appear to be in conflict with each other. In addition, since the condition report and the response to RAI 8.1.22-3 discuss MS-46, wall thickness inspections of pipe components are being performed at GGNS for erosion/corrosion. However, it is not clear whether these are one-time inspections that confirm the components are acceptable until the end of the period of extended operation, or whether these are ongoing monitoring activities that verify the acceptability of components for a time period less than the period of extended operation. In that regard, any one-time inspections performed early in plant life may have only considered a 40-year operating license.
Request:
- a. Reconcile the apparent disparity between the responses to RAI 8.1.41-3 and RAI 8.1.22-2 regarding whether the inspections specified in GGNS MS-46, "Program Plan for Monitoring Internal Erosion/Corrosion in Moderated Energy Piping Components (Safety Related)," are or are not credited in the Service Water Integrity Program. In addition, if inspections performed through MS-46 are credited by any aging management program, include appropriate changes to the related sections of the LRA.
- b. Provide information regarding all components that are being monitored for erosion/corrosion through GGNS MS-46 to demonstrate that these components are not within the scope of license renewal; or if components are within the scope of license renewal, that the monitoring activities are limited to one-time inspections which have verified the components are acceptable until the end of the period of extended operation or are credited by an aging management program in the LRA.
September 5,2012 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 Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, 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 bye-mail at nathaniel.ferrer@nrc.gov.
Sincerely, IRAJ 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
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ADAMS Accession No* ML12234A671 *concurred via email OFFICE LARPB1 :DLR* PM:RPB1 :DLR BC:RPB1 :DLR PM: RPB1 :DLR NAME IKing NFerrer DMorey NFerrer DATE 8/27/12 8/29/12 8/30/12 9/5112 OFFICIAL RECORD COpy
Letter to M. Perito from N. Ferrer dated September 5, 2012
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:
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