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
MONTHYEARIR 05000416/20240112024-10-16016 October 2024 – Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 IR 05000416/20234012024-01-18018 January 2024 Cyber Security Inspection Report 05000416/2023401 (Public) ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 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 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24088A0092024-03-27027 March 2024 NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054) ML23348A1222023-12-14014 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 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 ML13353A6572013-12-19019 December 2013 Licensed Operator Positive Fitness-For-Duty Test 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) 2024-03-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 27,2012 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 nathanieLferrer@nrc.gov.
Sincerely,
~-----------
Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
Requests for Additional Information cc w/encl: Listserv
GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION SET 24 RAI 3.3.2.15-1
Background:
License renewal application (LRA) Tables 3.3.2-15, "Standby Diesel Generator System," and 3.3.2-16, "HPCS Diesel Generator System," contain aging management review (AMR) items which specify the Service Water Integrity program to manage loss of material due to wear for copper alloy with greater than 15 percent zinc heat exchanger tubes externally exposed to treated water. The AMR items cite generic note H indicating that this aging effect is not in the Generic Aging Lessons Learned (GALL) Report for this component, material, and environment combination.
LRA Section B.2.1.14 states that the applicant's Service Water Integrity Program is consistent with GALL Report aging management program (AMP) XI.M20, "Open-Cycle Cooling Water System." GALL Report AMP XI.M20 manages aging effects on components exposed to raw water systems using a combination of (a) surveillance and control techniques, (b) inspections, and (c) heat transfer capability testing of heat exchangers. The GALL Report AMP XI,M20 "detection of aging effects" program element states that visual or nondestructive examinations may be performed to identify degradation and that nondestructive testing, such as ultrasonic testing and eddy current testing, are effective methods to measure surface conditions or the extent of wall loss associated with service water system piping and components.
Issue: The GALL Report identifies loss of material due to various types of corrosion as an aging effect requiring management for copper alloy heat exchanger components; but does not identify loss of material due to wear as an aging effect requirement management. The nature of the loss of material due to wear aging mechanism for these items is not clear to the staff.
The applicant proposes to manage the external surface of heat exchange tubes exposed to treated water using a program that is intended to manage aging for components exposed to raw water. While it is possible to detect loss of material on the external portion of heat exchanger tubes by performing certain nondestructive examinations of the internal surfaces, the LRA did not describe the nondestructive examination method that will be used to manage the aging effects for these items.
Request: For the items in Tables 3.3.2-15 and 3.3.2-16 that are being managed for loss of material due to wear, describe the nature of the aging mechanism and discuss the associated plant-specific or industry operating experience associated with the identification of the additional aging mechanism for these items. Also, provide a description of the nondestructive examination method to be used by the Service Water Integrity Program and justification that the method being used will adequately manage loss of material from the treated water side of the associated heat exchanger tubes.
RAI 3.5.1.87-1
Background:
The GALL Report recommends that structural bolting in any environment should be managed for loss of preload due to self-loosening (e.g., GALL Report items III.B1.1.TP-229 and III.A1.TP-261). Standard Review Plan for License Renewal (SRP-LR) Table 3.5-1, items 87
- 2 and 88, recommends the ASME Section XI, Subsection IWF and Structures Monitoring Program, respectively, to manage this aging effect.
Issue: LRA Table 3.5.1, items 87 and 88, state that this aging effect is not applicable and does not require management. No further discussion is provided.
Request: Explain why loss of preload is not an aging effect for structural bolting within the scope of license renewal, or provide an acceptable AMP to manage loss of preload during the period of extended operation. The response should address both the ASME Section XI, Subsection IWF and the Structures Monitoring Programs.
RAI 3.5.2.1-1
Background:
LRA Table 3.5.2-1 addresses elastomer containment building electrical seals and sealant that will be managed for the aging effects of cracking and change in material properties by the Containment Leak Rate Program and references SRP-LR Table 3.5.1, item 26. The GALL Report recommends using GALL Report AMP XI.S1, "ASME Section XI, Subsection IWE," to ensure that these aging effects are adequately managed.
Issue: In the LRA, the applicant references SRP-LR Table 3.5.1, item 26, and credits the Containment Leak Rate Program to manage the aging effect of cracking and change in material properties of elastomer containment building electrical seals and sealant in an air - indoor uncontrolled environment. Since the Containment Leak Rate Program is a performance monitoring program that monitors parameters related to leakage rates and does not by itself provide information that would indicate aging degradation has initiated, the staff is unable to determine how the Containment Leak Rate Program will evaluate change in material properties, or if visual examinations are performed of the elastomer containment building electrical penetration seals and sealants to manage aging in the form of cracking or change in material properties.
Request: Describe how the Containment Leakage Rate Program meets the recommendations in GALL Report item II.B4.CP-40 with respect to managing the aging effect of cracking and change in material properties of elastomer containment building electrical seals and sealant in an air - indoor uncontrolled environment.
RAI 3.5.2.4-4
Background:
LRA Table 3.5.2-4 addresses carbon steel fire hose reels that will be managed for loss of material by the Fire Water System Program and references SRP-LR Table 3.5.1, item 3.5.1-92. The GALL Report recommends using GALL Report AMP XI.S6, "Structures Monitoring Program," to ensure that these aging effects are adequately managed.
Issue: The staff notes that the applicant's Fire Water System Program has been enhanced to include periodic inspection of fire hose reels; however, GALL Report AMP XI.M27, "Fire Water System," focuses on the inspection of internal system corrosion conditions. The staff is unclear how the applicant's Fire Water System Program will be utilized to address the structure/aging effect combination, during the period of extended operation.
- 3 Request: Describe how the Fire Water System Program meets the recommendations provided in GALL Report AMP XLS6, with respect to frequency of inspections, qualifications of inspection personnel, and acceptance criteria.
RAI 3.5.2.4-5
Background:
LRA Table 3.5.2-4 states that rubber water stops exposed to an air - indoor uncontrolled environment have no aging effects requiring management and no proposed AMP.
GALL Report Section IX.F, "Selected Definitions & Use of Terms for Describing and Standardizing Aging Mechanisms," identifies elastomer (Le., rubber) degradation mechanisms as cracking, crazing, fatigue breakdown, abrasion, chemical attacks, and weathering. The GALL Report states that for rubber materials, hardening and loss of strength of elastomers can be induced by elevated temperature (over about 95°F (35°C>>, and additional aging factors such as exposure to ozone, oxidation, and radiation. The staff notes that GALL Report item AP-102 states that elastomers exposed to an air-indoor uncontrolled environment are subject to hardening and loss of strength due to degradation, and can be managed by GALL Report AMP XI.M36, "External Surfaces Monitoring of Mechanical Components." The staff also notes that SRP-LR Table 3.5-1, item 72, identifies loss of sealing due to deterioration of seals, gaskets, and moisture barriers (caulking, flashing, and other sealants) as an aging effect/mechanism that will be managed by the Structures Monitoring Program.
Issue: The staff lacks sufficient information to determine whether these rubber water stops are exposed to sufficient levels of ozone, oxidation, and radiation to cause aging effects requiring management.
Request: Provide a technical basis as to why there are no aging effects requiring management or AMP for these rubber water stops or propose an AMP to manage the aging effects.
RAJ 3.5.2.2.1.3-1
Background:
SRP-LR Section 3.5.2.2.1.3 addresses loss of material due to general, pitting and crevice corrosion for steel elements of accessible and inaccessible areas of containments. The SRP-LR recommends further evaluation if the four following GALL Report conditions cannot be satisfied:
- 1. Concrete meeting the specifications of ACI318 or 349 and the guidance of AC1201.2R was used for the containment concrete in contact with the embedded containment shell or liner.
- 2. The concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.
- 3. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.
- 4. Water ponding on the containment concrete floor is not common and when detected is cleaned up in a timely manner.
Issue: The staff agrees that conditions 2 and 4 were addressed adequately by the applicant; however, the LRA did not specify that condition 1 was met, or for condition 3, if a moisture
- 4 barrier was present at the junction where the liner becomes embedded in the concrete and, if present, is it subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.
Request:
- a. Confirm that the containment concrete in contact with the embedded steel liner meets the guidance contained in ACI 201.2R as specified in the GALL Report.
- b. State whether a moisture barrier is or is not present at the junction where the liner becomes embedded in the concrete and, if present, that it is subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.
RAI4.S.2-1
Background:
LRA Section 4.6.2 states that calculations were identified for the bellows on the containment penetration guard pipes and the fuel transfer tube that analyzed a large number of cycles of flexure due to normal operation and earthquakes. The LRA also states that the number of analyzed cycles is significantly higher than the total number of cycles projected for the period of extended operation. The LRA further states that the applicant will use the Fatigue Monitoring Program to manage the aging effects due to fatigue in accordance with 10 CFR 54.21 (1)(c)(iii).
Issue: The LRA does not provide additional information regarding the calculations performed for the fatigue analysis, such as the number of analyzed cycles or the included transients. The staff needs further information to confirm that an evaluation for the fatigue analysis is valid for the period of extended operation Request: Identify the number of cycles of the bellows for the guard pipes and fuel transfer tube were designed for and explain how that number was developed. Also identify which transients were included in the original evaluation and which transients will be monitored under the Fatigue Monitoring Program.
RAI81.14-1
Background:
LRA Section B.1.14, states that the Containment Inservice Inspection -IWL Program is consistent with GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL." The GALL Report AMP XI.S2 "parameters monitored or inspected" program element recommends that the containment concrete surfaces be examined for evidence of damage or degradation, such as those defined in ACI 201.1 Rand ACI 349.3R.
Issue: Grand Gulf Nuclear Station (GGNS) License Renewal Project, Aging Management Program Evaluation Report for Civil/Structural for Containment Inservice Inspection (CII) - IWL, only identifies ACI 349.3R criteria for the concrete containment surface examination, and does not refer to ACI 201.1 R, "Guide for Conducting a Visual Inspection of Concrete in Service," for conducting containment concrete surface visual examination.
-5 Request: Describe the methods that will be used for conducting containment concrete visual surface examination. In addition, describe if these methods are consistent with the guidance provided in ACI 201.1 R RAI81.14-2
Background:
LRA Section B.1.14, states that the Containment Inservice Inspection -IWL Program is consistent with GALL Report AMP XI.S2. The GALL Report AMP XI.S2 "acceptance criteria" program element recommends that quantitative acceptance criteria based on the "Evaluation Criteria" provided in Chapter 5 of ACI 349.3R-02, may be used to augment the qualitative assessment of the Responsible Engineer.
Issue: The applicant's Containment Inservice Inspection (CISI) Program Plan provides examination process of IWL Program in Appendix B - "CII Examination Process Flowchart" and Appendix C - "GGNS Recording and Screening Criteria" in the applicant's procedure of CEP-CII-004, Rev. 302 "General and Detailed Visual Examinations of Concrete Containments."
It is not clear if the quantitative acceptance criterion for containment concrete surface visual examination is included in the applicant's program.
Request: Describe the acceptance criteria used for the containment concrete surface visual examination and describe if the acceptance criteria are consistent with the quantitative acceptance criteria recommended in Chapter 5 of the ACI 349.3R-02.
RAI81.14-3
Background:
LRA Section B.1.14, states that the Containment Inservice Inspection -IWL Program is consistent with the GALL Report AMP XI.S2. The GALL Report AMP XI.S2 "scope of program" program element recommends that scope of the AMP should be in accordance with ASME Section XI, Subsection IWL-1000. According to IWL-1100, steel embedded plates that are backed by concrete are within the scope of the containment concrete in service inspection program. In addition, the GALL Report AMP XI,S2 "operating experience" program element states that the implementation of Subsection IWL, in accordance with 10 CFR 50.55a, is a necessary element of aging management for concrete containments through the period of extended operation.
Issue: During the walkdown of GGNS containment structure on January 31,2012, the staff noted embedded steel plates in the concrete containment's exterior surface. These embedded steel plates had signs of corrosion and the concrete surface adjacent to these embedded plates had rust stains.
Request: Please describe how the aging of the embedded steel plates located on the exterior surface of the concrete containment will be managed.
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARDCOPY:
DLR RF E-MAIL:
PUBLIC [or NON-PUBLIC, if applicable]
RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV GPick, RIV DMclntyre, OPA
Mr. Michael Perito Vice President, Site Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150 SUB~'ECT: 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, IRA!
Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
Requests for Additional Information cc w/encl: Listserv DISTRIBUTION: See following pages ADAMS Accession No ..'ML12157a056 i OFFICE LA:RPB1 :DLR PM:RPB1 :DLR BC:RPB1:DLR PM: RPB1 :DLR
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~ATE 06/7/12 06/20/12 06/26/12 06/27/12 OFFICIAL RECORD COpy