Letter Sequence Other |
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TAC:ME4679, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting
Results
Other: GNRO-2012/00150, Final Report for Replacement Steam Dryer, GNRO-2017/00039, Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages, ML102660403, ML111720830, ML112560396, ML12167A257, ML12167A269, ML12177A287, ML13108A217, NRC-2012-0105, Environmental Assessment and Finding of No Significant Impact Related Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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MONTHYEARML1026604002010-08-20020 August 2010 GE-Hitachi Nuclear Energy Americas LLC - Affidavit of Edward Schrull Withholding from Public Disclosure Proprietary Report NEDC-33477P Project stage: Request ML1026603992010-08-31031 August 2010 NEDO-33477, Revision 0, Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate. Project stage: Request ML1026604032010-09-0808 September 2010 License Amendment Request Extended Power Uprate Project stage: Other GNRO-2010/00056, NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix E Through Appendix G2010-09-30030 September 2010 NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix E Through Appendix G Project stage: Request ML1026604062010-09-30030 September 2010 NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix B Through Appendix D Project stage: Request ML1026604012010-09-30030 September 2010 NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Cover Through Appendix a Project stage: Request ML1030102002010-11-0909 November 2010 Supplemental Information Needed for Acceptance of License Amendment Request, Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Megawatts Thermal Project stage: Acceptance Review GNRO-2010/00071, Supplemental Information, License Amendment Request, Extended Power Uprate2010-11-18018 November 2010 Supplemental Information, License Amendment Request, Extended Power Uprate Project stage: Supplement GNRO-2010/00073, Supplemental Information License Amendment Request, Extended Power Uprate2010-11-23023 November 2010 Supplemental Information License Amendment Request, Extended Power Uprate Project stage: Supplement ML1034201082010-12-16016 December 2010 Request for Withholding Information from Public Disclosure, 9/7/10 Affidavit Executed by E. Schrull, GEH Re NEDC-33601P Project stage: Withholding Request Acceptance ML1034705862011-01-0505 January 2011 Request for Withholding Information from Public Disclosure, 11/19/10 Affidavit Executed by E. Schrull, GE-Hitachi, Regarding NEDC-33621P Project stage: Withholding Request Acceptance ML1102602812011-01-26026 January 2011 E-mail, Request for Additional Information Instrument and Controls, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1102602872011-01-26026 January 2011 E-mail, Request for Additional Information Fire Protection, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1102701872011-01-27027 January 2011 Request for Additional Information, Emcb Non-Steam Dryer Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1103103902011-01-31031 January 2011 E-mail, Request for Additional Information, Vessels and Internal Integrity Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1103901732011-02-0808 February 2011 Email, Request for Additional Information, Nrr/Dci/Csgb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00012, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request GNRO-2011/00011, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request ML1105407052011-02-23023 February 2011 E-mail, Request for Additional Information, Nrr/Dirs/Ihpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1105407122011-02-23023 February 2011 E-mail, Request for Additional Information, Nrr/Dra/Apla Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00013, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request ML1034200962011-02-25025 February 2011 Request for Withholding Information from Public Disclosure, 8/20/10 Affidavit Executed by E. Schrull, GEH, for NEDC-33477P Project stage: Withholding Request Acceptance ML1106007172011-03-0101 March 2011 Email Request for Additional Information, Round 2, Nrr/Dci/Cvib Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00016, Request for Additional Information Regarding Extended Power Uprate2011-03-0909 March 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request ML1107501322011-03-16016 March 2011 Email, Dose Assessment Branch, Request for Additional Information, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1108202242011-03-23023 March 2011 Email, Request for Additional Information, Nrr/Dss/Srxb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1108202272011-03-23023 March 2011 Request for Additional Information, Nrr/Dss/Srxb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00018, Request for Additional Information Regarding Extended Power Uprate2011-03-30030 March 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request GNRO-2011/00021, Response to Request for Additional Information Regarding Extended Power Uprate2011-03-31031 March 2011 Response to Request for Additional Information Regarding Extended Power Uprate Project stage: Response to RAI ML1109401362011-04-0404 April 2011 Email, Request for Additional Information, Nrr/Dci/Csgb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1109502722011-04-0505 April 2011 Email, Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1109502812011-04-0505 April 2011 Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1110301112011-04-12012 April 2011 Email, Request for Additional Information, Nrr/Dss/Snpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00024, Response to Request for Additional Information Regarding Extended Power Uprate2011-04-14014 April 2011 Response to Request for Additional Information Regarding Extended Power Uprate Project stage: Response to RAI ML11112A0982011-04-21021 April 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request ML1110401002011-04-27027 April 2011 Request for Withholding Information from Public Disclosure, 3/28/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00018 Project stage: Withholding Request Acceptance ML1110401252011-04-27027 April 2011 Request for Withholding Information from Public Disclosure, 2/20/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00013 Project stage: Withholding Request Acceptance ML1110401132011-04-27027 April 2011 Request for Withholding Information from Public Disclosure, 2/20/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00011 Project stage: Withholding Request Acceptance ML1110401072011-04-27027 April 2011 Request for Withholding Information from Public Disclosure, 2/17/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00012 Project stage: Withholding Request Acceptance ML1110401162011-04-27027 April 2011 Request for Withholding Information from Public Disclosure, 3/30/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00021 Project stage: Withholding Request Acceptance GNRO-2011/00035, Response to Request for Additional Information Regarding Extended Power Uprate2011-05-0505 May 2011 Response to Request for Additional Information Regarding Extended Power Uprate Project stage: Response to RAI ML1113001562011-05-10010 May 2011 Email, Request for Additional Information, Nrr/Dss/Scvb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00037, Request for Additional Information Regarding Extended Power Uprate2011-05-11011 May 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request ML1114002992011-05-20020 May 2011 E-mail, Request for Additional Information, Nrr/Dci/Emcb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1113905252011-05-31031 May 2011 Request for Withholding Information from Public Disclosure, 4/21/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00025 Project stage: Withholding Request Acceptance ML1115204582011-06-0101 June 2011 Email, Request for Additional Information, Nrr/Dra/Aadb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI ML1115304392011-06-0606 June 2011 (Redacted) Request for Additional Information from Nrr/De/Emcb Steam Dryer, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt Project stage: RAI GNRO-2011/00043, Request for Additional Information Regarding Extended Power Uprate2011-06-0808 June 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request GNRO-2011/00046, Response to Request for Additional Information Regarding Extended Power Uprate2011-06-15015 June 2011 Response to Request for Additional Information Regarding Extended Power Uprate Project stage: Response to RAI ML1117200422011-06-20020 June 2011 Licensee Response Regarding Request for Additional Information on Training for Prnms (TAC No. 4679) Project stage: Request 2011-03-30
[Table View] |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML22209A0602022-07-28028 July 2022 2022 Inservice Inspection Summary Report GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2017/00039, Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages2017-06-30030 June 2017 Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages GNRO-2016/00033, Submittal of 2016 Inservice Inspection Summary Report2016-06-20020 June 2016 Submittal of 2016 Inservice Inspection Summary Report GNRO-2014/00043, Inservice Inspection Summary Report2014-06-12012 June 2014 Inservice Inspection Summary Report GNRO-2012/00110, Submittal of Inservice Inspection Summary Report2012-09-11011 September 2012 Submittal of Inservice Inspection Summary Report GNRO-2009/00070, Supplement to Request to Use Portion of Later Edition to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants for Main Steam Safety Relief Valve Inservice Testing2009-12-14014 December 2009 Supplement to Request to Use Portion of Later Edition to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants for Main Steam Safety Relief Valve Inservice Testing CNRO-2009-00002, Relief Request CEP-ISI-011 for Third 120 Month Inservice Inspection Interval2009-03-0404 March 2009 Relief Request CEP-ISI-011 for Third 120 Month Inservice Inspection Interval GNRO-2009/00004, Inservice Inspection Summary Report2009-01-19019 January 2009 Inservice Inspection Summary Report GNRO-2008/00071, Inservice Inspection (ISI) Program Third 10-Year Interval, Rev. 02008-10-29029 October 2008 Inservice Inspection (ISI) Program Third 10-Year Interval, Rev. 0 GNRO-2008/00057, Transmittal of Inservice Inspection Program Third 10-Year Interval, Revision 02008-07-31031 July 2008 Transmittal of Inservice Inspection Program Third 10-Year Interval, Revision 0 ML0815700022008-06-27027 June 2008 Relief Request GGNS-ISI-004 to Extend 2nd 10-Year Inservice Inspection Interval 4 Months Beyond 1-year Extension Allowed by ASME Code CNRO-2008-00016, Relief Requests for Third 120 Month Inservice Testing Interval2008-05-20020 May 2008 Relief Requests for Third 120 Month Inservice Testing Interval 1CAN030804, Revised Relief Request for 10 Year Update to the 120 Month Inservice Testing Interval, Arkansas Nuclear One, Unit 12008-03-13013 March 2008 Revised Relief Request for 10 Year Update to the 120 Month Inservice Testing Interval, Arkansas Nuclear One, Unit 1 CNRO-2007-00044, Unit 1 and Arkansas Nuclear One, Units 1 & 2 - Inservice Testing Plan2007-11-30030 November 2007 Unit 1 and Arkansas Nuclear One, Units 1 & 2 - Inservice Testing Plan CNRO-2007-00042, Entergy Operations, Inc. - Relief Requests for 10 Year Updates to the 120 Month Inservice Testing Intervals2007-11-29029 November 2007 Entergy Operations, Inc. - Relief Requests for 10 Year Updates to the 120 Month Inservice Testing Intervals GNRO-2007/00046, Inservice Inspection Summary Report2007-07-10010 July 2007 Inservice Inspection Summary Report GNRO-2006/00044, Corrections to Inservice Inspection Summary Report2006-08-10010 August 2006 Corrections to Inservice Inspection Summary Report GNRO-2006/00002, Lnservice Inspection Summary Report for Grand Gulf Nuclear Station Unit 12006-01-13013 January 2006 Lnservice Inspection Summary Report for Grand Gulf Nuclear Station Unit 1 GNRO-2004/00019, Transmittal of Inservice Inspection Summary Reports2004-03-0808 March 2004 Transmittal of Inservice Inspection Summary Reports ML0404901792003-12-18018 December 2003 to CEP-IST-2, Inservice Testing Plan, Entergy Nuclear South Central Engineering Programs GNRO-2003/00022, Boiling Water Reactor (BWR) Feedwater Nozzle Inservice Inspection Report for Grand Gulf Nuclear Station2003-04-0202 April 2003 Boiling Water Reactor (BWR) Feedwater Nozzle Inservice Inspection Report for Grand Gulf Nuclear Station CNRO-2003-00009, Entergy Operations, Referenced Paper for Request to Use ASME Code Case N-6632003-03-14014 March 2003 Entergy Operations, Referenced Paper for Request to Use ASME Code Case N-663 2022-07-28
[Table view] Category:Letter type:GNRO
MONTHYEARGNRO-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 GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019 Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation. GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
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Text
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~Entergy Entergy Operations, Inc.
P.o. Box 756 Port Gibson, MS 39150 Eric A. Larson Vice President, Operations Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2017/00039 June 30, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages Grand Gulf Nuclear Station - Unit 1 Docket Nos. 50-416 License Nos. NPF-29
REFERENCES:
- 1. Entergy letter to NRC, License Amendment Request, Extended Power Uprate, dated September 8, 2010 (GNRO-2010/00056, Accession Number ML102660403)
- 2. NRC Letter to Entergy Operations, Inc., Grand Gulf Nuclear Station, Unit 1- Request for Additional Information Regarding Extended Power Uprate Application License Amendment Request (TAC NO. ME4679) dated March 2,2011 (Accession Number ML110550475)
- 3. Entergy letter to NRC, [Response to] Request for Additional Information Regarding Extended Power Uprate, Grand Gulf Nuclear Station, Unit 1, dated March 30, 2011 (GNRO-2011/00018) (ML110900275)
- 4. NRC Letter to Entergy Operations, Inc., Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment RE: Extended Power Uprate, dated July 18, 2012 (TAC NO. ME4679)
(ML121210020)
- 5. BWRVIP-139-A BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines, 1018794, July 2009
Dear Sir or Madam:
Grand Gulf Nuclear Station (GGNS) conducted visual inspections of all accessible locations of the steam dryer in accordance with the BWRVIP-139-A, Steam Dryer Inspection and Flaw Evaluation Guidelines, and General Electric's (GE) inspection guidelines. Attached are the summary results of the visual inspections conducted in the first two refueling outages (RF19; 2014 and RF20; 2016) after reaching full Extended Power Uprate (EPU) conditions. This letter is being submitted in accordance with Operating License No. NPF-29, Condition 2.C(46)(f).
GNRO-2017/00039 Paqe 2 of 3 This letter contains no new Regulatory Commitments.
Should you have any questions concerning the content of this letter, please contact James Nadeau at 601-437-2103.
I declare under penalty of perjury that the foregoing is true and correct. Executed on June 30, 2017.
Sincerely, Eric A. Larson Site Vice President Grand Gulf Nuclear Station EAUsas
Attachment:
Grand Gulf Nuclear Station Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages after Reaching Full EPU Conditions cc: see next page
GNRO-2017/00039 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Siva Lingham Mail Stop OWFN 8 81 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss M. Kennedy Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2017/00039 Grand Gulf Nuclear Station Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages after Reaching Full EPU Conditions
Attachment to GNRO-2017/00039 Page 1 of 5 Introduction As required by the staff's Safety Evaluation (SE) for Amendment 191 to the Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 dated July 18, 2012, Grand Gulf conducted visual inspections of all accessible locations of the steam dryer in accordance with the BWRVIP-139-A, Steam Dryer Inspection and Flaw Evaluation Guidelines, and General Electric's inspection guidelines. These inspections were conducted during the first two scheduled refueling outages (RF19; 2014 and RF20; 2016) after reaching full Extended Power Uprate (EPU) conditions. Grand Gulf's proposed long term steam dryer inspections plan will be submitted in a separate report.
In total over 500 inspections were recorded on the steam dryer outer diameter, and over 350 inspections were recorded on the steam dryer inner diameter. The inspection method used for the steam dryer inspections were VT-3 and VT-1. The VT-1 inspections were performed using the VT-1-1/32 method which is a VT-1 quality examination that visually resolves a 1/32" black line on an 18% neutral gray card as required by BWRVIP-139-A.
RF19 (2014) Inspection Results The first scheduled refueling outage after reaching full EPU conditions was RF19. During this refueling outage, the first set of baseline inspections on the replacement steam dryer was conducted. No relevant indications were observed on any of the steam dryer inner diameter inspection locations in RF19. Relevant indications on steam dryer outer diameter inspection locations are listed below in Table 1. Re-inspections of the indications were scheduled for and completed in RF20 to confirm no significant changes occurred.
Table 1: RF19 Relevant Indications Component Name Component Inspection Results Corrective Actions Description Type and Re-Inspection SDOD BC TRB 01 Bank C Azimuth VT-1-1/32 Abnormal Trend. Indication due 0° Tie Rod discoloration on the to construction Bolting bottom weld and damage on the washer bolt head and subsequent crud buildup on the damaged washer Re-inspect in RF20 SDOD LG 000 0° Azimuth Lower VT-1-1/32 Witness/rub marks Trend. No evidence of Guide Surfaces were observed on metal slivers or rolled the inner surfaces metal Indications consistent with steam dryer installation and/or removal from the vessel Re-inspect in RF20
Attachment to GNRO-2017/00039 Page 2 of 5 SDOD SSB 120 120 0 Azimuth VT-1-1/32 Wear observed on Seismic Support Block Seismic Support the lead in surfaces polished to remove the Block metal slivers.
Indications consistent with handling marks during steam dryer installation and/or removal from the vessel.
Re-inspect in RF20 SDOD SSB 185 185 0 Azimuth VT-1-1/32 Wear observed on Seismic Support Block Seismic Support the lead in surfaces polished to remove the Block metal slivers.
Indications consistent with handling marks during steam dryer installation and/or removal from the vessel.
Re-inspect in RF20 SDOD SSB 240 240 0 Azimuth VT-1-1/32 Wear and gouges Seismic Support Block Seismic Support observed on the polished to remove the Block lead in surfaces metal slivers.
Indications consistent with handling marks during steam dryer installation and/or removal from the vessel.
Re-inspect in RF20
Attachment to GNRO-2017/00039 Page 3 of 5 RF20 (2016) Inspection Results The second scheduled refueling outage after reaching full EPU conditions was RF20. During this refueling outage, the second and final set of baseline inspections on the replacement steam dryer was conducted. No relevant indications were observed on any of the steam dryer inner diameter inspection locations in RF20. Two new relevant indications were observed on steam dryer outer diameter inspection locations. These indications are listed below in Table 2.
Table 2: RF20 Relevant Indications Component Component Inspection Results Corrective Actions Description Type and Re-inspection SDOD SSB 240 240 0 Azimuth VT-1-1/32 New wear observed Seismic Support Block Seismic Support on the lead in polished to remove the Block surfaces (this wear metal slivers.
is in a different location on the lead Indications consistent in surface than the with handling marks previously identified during steam dryer indication) installation and/or removal from the vessel.
Re-inspection scheduled for RF21 SDOD SSB 300 300 0 Azimuth VT-1-1/32 Wear observed on Seismic Support Block Seismic Support the lead in surfaces polished to remove the Block metal slivers.
Indications consistent with handling marks during steam dryer installation and/or removal from the vessel.
Re-inspection scheduled for RF21
Attachment to GNRO-20 17/00039 Page 4 of 5 Re-Inspection of Previously Identified Indications All relevant indications observed in RF19 were re-inspected in RF20 to identify any changes.
The re-inspection results are shown below in Table 3. In summary, the indication on SDOD SSB 120 showed additional wear on the lead in surfaces, and all other indications showed no discernable changes. All indications are scheduled for re-inspection in RF21 to confirm no significant changes have occurred. Relevant indications will continue to be inspected each refueling outage until the indication is shown to have stabilized. This is typically established with two subsequent re-inspections with no changes noted after the indication is initially identified.
Once an indication is shown to have stabilized, inspections will continue at the regularly scheduled frequency.
Table 3: RF20 Re-Inspection of Previously Identified Indications Component Component Inspectio Results Corrective Actions Descri ption n Type and Re-inspection SDOD BC TRB 01 Bank C Azimuth VT-1-1/32 No discern able Trend 0 Tie Rod Bolting 0
changes noted Re-inspection scheduled for RF21 SDOD LG 000 0 0 Azimuth Lower VT-1-1/32 No discernable Trend Guide Surfaces changes noted Re-inspection scheduled for RF21 SDOD SSB 120 120 0 Azimuth VT-1-1/32 Additional wear Seismic Support Block Seismic Support observed on the lead polished to remove the Block in surfaces metal slivers.
Indications consistent with handling marks during steam dryer installation and/or removal from the vessel.
Re-inspection scheduled for RF21 SDOD SSB 185 185 0 Azimuth VT-1-1/32 No discern able Trend Seismic Support changes noted Block Re-inspection scheduled for RF21 SDOD SSB 240 240 0 Azimuth VT-1-1/32 No discernable Trend Seismic Support changes noted on Block the original location. Re-inspection scheduled for RF21 Additional wear observed on the lead in surfaces as noted in Table 2.
Attachment to GNRO-2017/00039 Page 5 of 5 Conclusion A complete baseline inspection of the Gran Gulf replacement steam dryer was performed during the two subsequent refueling outages (RF19 and RF20) following full EPU conditions. The baseline inspections were consistent with the guidance provided in BWRVI P-139-A, Steam Dryer Inspection and Flaw Evaluation Guidelines, and General Electric's inspection guidelines.
Based on engineering evaluation, it was concluded that none of the steam dryer indications identified in RF19 or RF20 challenge the structural integrity or function of the steam dryer. This completes the required baseline inspections and report of results for the replacement steam dryer. Grand Gulf's proposed long term steam dryer inspection plan will be submitted in a separate report.
References
- 1. Grand Gulf Nuclear Station, Unit 1- Issuance of Amendment RE: Extended Power Uprate (TAC No. ME4679), Nuclear Regulatory Correspondence ML121210020, July 18, 2012.
- 2. BWRVIP-139-A BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines, 1018794, July 2009.
- 3. BWRVIP-03 BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines, TR-1 05696-R 19, December 2016.
- 4. General Electric Service Information Letter (SIL) 644, "BWR Steam Dryer Integrity."
- 5. Grand Gulf Nuclear Station Recommendations for Future Inspection- Replacement Steam Dryer, General Electric Report 0000-0125-6316-R 1, December 2013.
- 6. In Vessel Visual Inspection (IVVI) of Grand Gulf Nuclear Station during the Spring 2014 Outage (GGNS RF19), GEH-7480-316097-JB1-IVVI, February 2014.
- 7. In Vessel Visual Inspection (IVVI) of Grand Gulf Nuclear Station during the Spring 2016 Outage (GGNS RF20), GEH-7480-318931-JB1-IVVI, February 2016.