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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Mr. Kevin Mulligan Vice President, Site Entergy Operations, Inc. P.O. Box 756 Port Gibson, MS 39150 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August28, 2013
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME7493)-SET 47
Dear Mr. Mulligan:
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license, NPF-29, for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC) 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, outlined in the enclosure, were discussed with Ted Ivy and Chris Robinson, 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) 415-3873 or by mail at john.daily@nrc.gov.
Sincerely, -ror<.. John Daily, 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 Mr. Kevin Mulligan Vice President, Site Entergy Operations, Inc. P.O. Box 756 Port Gibson, MS 39150 August 28, 2013
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME7493)-SET 47
Dear Mr. Mulligan:
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license, NPF-29, for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC) 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, outlined in the enclosure, were discussed with Ted Ivy and Chris Robinson, 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) 415-3873 or mail at john.daily@nrc.gov.
Docket No. 50-416
Enclosure:
Requests for Additional Information cc w/encl: Listserv DISTRIBUTION:
See following pages ADAMS Accession No
- ML 13227 A394 .. OFFICE LA:RPB1 :DLR PM:SRXB:DORL NAME I King* B Parks DATE 8/20/2013 8/15/13 Sincerely, IRA by Emmanuel Sayoc for/ John Daily, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
- concurred via email PM:RPB1 :DLR BC:RPB1 :DLR PM: RPB1 :DLR E Say_oc Y Diaz-Sanabria J Daily 8/23/2013 8/28/2013 8/27/2013 OFFICIAL RECORD COPY GGNS RAI 4.2.1-2c
Background:
GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION The applicant has provided information in response to several staff-issued requests for additional information (RAis) that pertain to the reactor vessel neutron fluence calculations.
Although the license renewal application states, "the neutron fluence for the welds and shells of the reactor pressure vessel beltline region was determined using the General Electric-Hitachi method for neutron flux calculation documented in report NEDC-32983P-A and approved by the NRC," an additional method was also used. The applicant stated in a letter dated July 25, 2012, that, "Pre-EPU fluence values were generated from the MPM Technologies, Inc. (MPM) analysis.
MPM analysis is consistent with the guidance contained in RG 1.190 and is approved by the NRC in TAG No. MB6687, Nine Mile Point Nuclear Station, Unit No. 1-lssuance of Amendment RE: Pressure-Temperature Limit Curves and Tables, October 27, 2003 ... " (ML 12208A 166). The applicant also stated that the uncertainty associated with using a combination of the MPM calculations with the General Electric-Hitachi (GEH) fluence calculations would fall between the uncertainty associated with either method (ML 13022A474).
The NRC staff does not agree that this information and evaluation adhere to the guidance contained in NRC Regulatory Guide (RG) 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence." Regulatory Position 1.4, "Methodology Qualification and Uncertainty Estimates," provides guidance concerning the qualification of an acceptable fluence method, stating the following:
The methods qualification consists of three parts: ( 1) the analytic uncertainty analysis (Regulatory Position 1.4.1 ), (2) the comparison with benchmarks and operating reactor measurements (Regulatory Position 1.4.2), and (3) the estimate of uncertainty in the calculated fluence (Regulatory Position 1.4.3). The NRC staff notes that the GEH fluence calculations adhere to a methodology that has received generic NRC staff approval, and is acceptable for referencing in licensing actions. This approval is documented in the NRC staff safety evaluation (SE) approving NEDC-32983P-A.
The SE also documents generic adherence of the GEH calculative method to the guidance, listed above, in RG 1.190. The GEH methodology qualification adequately addresses the three aspects noted above and consists of an analytic uncertainty analysis (described in Chapter 7 of NEDC-32983P-A), comparisons to the Oak Ridge National Laboratory Pool Critical Assembly (PCA) benchmark, solution of the generic boiling-water reactor (BWR) benchmark fluence problem documented in NUREG/CR 6115, code-to-code comparisons of the BWR benchmark fluence problem, and an extensive database of comparisons to BWR surveillance capsule dosimetry analyses.
The database includes blind benchmark calculations.
The staff also notes that its review of fluence calculations as presented in BWR license amendments have been of the type where one methodology is applied throughout a reactor vessel's life (i.e., from 0 effective full-power year (EFPY) to the desired endpoint EFPY); the staff could not locate any successful amendment where one methodology was used from 0 EFPY to (for example), 32 EFPY, and a different methodology from 32 EFPY to the end of the period of extended operation (typically around 54 EFPY). Although the applicant stated that the MPM calculation was approved by the NRC, the NRC staff does not agree with this characterization insofar as it applies to Grand Gulf Nuclear Station (GGNS). The approval noted above pertains to a BWR/2 facility.
The staff notes that GGNS is a BWR/6 design. Issues: Regulatory Position 1.4.2.1, "Operating Reactor Measurements," of RG 1.190 states, in part, "Comparisons of measurements and calculations must be performed for the specific reactor being analyzed or for reactors of similar design." The BWR/2 design lacks jet pumps and cannot be considered to be similar in design to a BWR/6 such as GGNS 1. Therefore, the basis on which the NRC staff approved the reactor vessel pressure temperature limits revision at Nine Mile Point Station, Unit 1, does not pertain to GGNS. Furthermore, since the method used to perform the MPM calculations is not documented in an NRC-approved methodology, a detailed description of the calculative methods, and their qualification, as both pertain to GGNS, must be submitted for NRC staff review and approval for referencing in the license renewal application.
This will enable the staff to reach a determination regarding whether the MPM fluence calculations are adherent to RG 1.190, or are otherwise acceptable.
Similarly, the NRC staff has determined that the applicability of the GEH fluence methodology to GGNS should also be established.
This effort may include plant-specific dosimetry comparisons, or establishing that the existing qualification contained in NEDC-32983P-A is adequate.
The use of a combined method-using fluence from two separate methods-requires an additional analytic uncertainty analysis and an extensive amount of further validation and verification.
The staff is not aware of any such combined method being approved in the past, and therefore such a proposal would require significant review to determine whether this approach could be found to comply acceptably with NRC guidance or not. For example, any dependent terms in the uncertainty associated with either method must be appropriately treated in the analysis, and any uncertainties associated with either method that could propagate must be investigated.
In addition, the significant difference in flux values associated with each method (limiting location flux values differ by approximately 70 percent) warrants a thorough investigation of the causes, and GGNS would need to provide extensive justification.
The results of this investigation need to be adequately explained in order to establish that both calculations are reasonably accurate.
In addition, the staff noted that the applicant's response to RAI 4.2.1-2b dated January 18, 2013, did not clearly address why the modeling variation between the MPM and GEH methods resulted in the MPM method yielding conservative bounding-case flux values for core shroud welds H1, V1, V2, V3, and V4. 1 The presence or lack of jet pumps is not the only defining characteristic.
Other relevant design considerations, including but not limited to vessel diameter and material composition, number of jet pumps, locations of welds, nozzles and other appurtenances, must also be addressed in establishing a valid calculational benchmark. Section 5.2 of MPM-402781, Revision 1, "Benchmarking of Nine Mile Point Unit 1 and Unit 2 Neutron Transport Calculations," September, 2003 (ADAMS Accession Number ML032681023), indicates that in neutron flux calculations using the MPM method, the region above the reactor core may be approximated using water without modeling the stainless steel top guide so that the MPM method generates conservative values of high-energy neutron flux for the locations above the bottom of the top guide. Therefore, the staff needs further clarification whether each of the applicant's analyses (i.e., MPM and GEH methods) approximates the region above the reactor core as water without explicitly modeling the stainless steel top guide. Finally, the applicant's response dated January 18, 2013, indicates that the fluence values for the reactor vessel internals are calculated by using several different calculational methods depending on the availability of pre-EPU fluence values, the internal components' locations, and the perceived validity of the chosen methods. The staff needs additional information to determine whether the use of these different calculational methods is adequate to calculate the fluence values of reactor vessel internals.
Request: 1) Provide the following information regarding reactor vessel fluence: (a) Provide a detailed description of the MPM fluence calculations.
Include a description of the methods and data sets used to perform the calculations, describe the analytic representation of the reactor geometry, and provide a detailed description of the problem setup, execution, and post-processing.
Also provide detailed results from the analysis. (b) Provide a description of the qualification of the MPM fluence calculational methods in sufficient detail to establish adherence to RG 1.190 as it applies to the BWR/6 design and GGNS in particular, or provide sufficient details to demonstrate to the staff that the calculations are otherwise acceptable for use at GGNS. (c) Provide information to demonstrate that the GEH analytic method is suitably qualified for analysis of the GGNS reactor vessel. (d) Provide a detailed, analytic uncertainty analysis of that accounts for any additional uncertainty or bias associated with adding fluence values together from these two methods. Also provide benchmarking information to show that the results of the vessel fluence analyses remain valid when combined. (e) Provide information to establish that the difference between the two flux values calculated using the different methods is valid. For example, compare the two methods in calculational benchmarks:
provide an estimate of the pre-extended power uprate (EPU) fluence using GEH calculational methods and provide an estimate of the EPU fluence using MPM calculational methods. 2) Provide a description, including a technical basis, for each of the different calculational methods that are used to determine the fluence values of the reactor vessel internals.
For each of the reactor vessel internal components, describe the fluence calculational method used for the component.
In addition, explain why the use of different calculational methods is adequate to determine the fluence values of the reactor vessel internals.
- 3) Justify the acceptability of using different methods to calculate related phenomena (e.g., neutron fluence) that all stem from the same source (e.g., the GGNS reactor core), for different surfaces (i.e., nozzles, beltline welds, vessel surface, and upper internals), as opposed to choosing one method to apply to all the surfaces.
- 4) Provide additional information to clarify why the modeling variation between the MPM and GEH methods results in conservative bounding-case flux values for the core shroud weld locations (H1, V1, V2, V3, and V4) using the MPM method. As part of the response, clarify whether the analysis with the MPM method approximates the region above the reactor core as water, without explicitly modeling the stainless steel top guide. In addition, clarify whether the analysis with the GEH method uses this approximation as well. 5) As an alternative to Items 1-3 above, please provide: a) Fluence values that have been determined from Beginning Of Life to End of Life Extended in accordance with a single method. i) If the method is NRC-approved insofar as it applies to vessel fluence calculations, provide the reference to the staff-accepted methodology.
ii) If the method is not NRC-approved, provide the plant-specific calculations and documentation, and include sufficient information, to enable the NRC staff to determine whether the calculation adheres to NRC Regulatory Guide (RG) 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," or other justification as required to establish that the fluence calculation is acceptable.
iii) Refer to Regulatory Position 3, "Reporting," for the specific documentation required to establish adherence to NRC RG 1.190. b) Finally, confirm whether, and describe how, the remaining neutron fluence-related limited aging analyses are affected by this new fluence calculation.
Letter to K. Mulligan from J. Daily, dated August 28, 2013
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME7493)-SET 47. DISTRIBUTION:
HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsNrrDirRerb Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource RidsNrrDirRapb Resource RidsNrrDirRpob Resource john.daily@nrc.gov emmanuel.sayoc@nrc.gov david.drucker@nrc.gov david. wrona@nrc.gov melanie. wong@nrc.gov yoira.diaz-sanabria@nrc.gov dennis.morey@nrc.gov rich.smith@nrc.gov blake.rice@nrc.gov greg.pick@nrc.gov
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