Letter Sequence Request |
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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
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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
When Attachment 1 is removed, the entire letter is non-proprietary.
Attachment 1 contains proprietary information.
GNRO-2011/00105 November 25, 2011
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Request for Additional Information Regarding Extended Power Uprate Grand Gulf Nuclear Station, Unit 1
Docket No. 50-416
License No.
NPF-29
REFERENCES:
- 1. Entergy Operations, Inc. letter to the NRC (GNRO-2010/00056), License Amendment Request - Extended Power Uprate , September 8, 2010 (ADAMS Accession No. ML102660403) 2. NRC Steam Dryer Audit (September 19 - 20, 2011), NRC Audit Report, October 19, 2011 (ADAMS Accession No. ML112790370)
- 3. Entergy Operations, Inc. letter to the NRC (GNRO-2011/00088), Request for Additional Information Regarding Extended Power Uprate , October 10, 2011 (ADAMS Accession No. ML112840174) 4. Entergy Operations, Inc. letter to the NRC (GNRO-2011/00101), Request for Additional Information Regarding Extended Power Uprate , November 14, 2011 (ADAMS Accession No. ML113190403)
Dear Sir or Madam:
In Reference 1, Entergy submitted a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC), which proposes an extended power uprate for Grand Gulf Nuclear Station, Unit 1 (GGNS). As part of the uprate, Entergy is replacing the current steam dryer, as discussed in the LAR.
The Nuclear Regulatory Commission (NRC) conducted an audit of the steam dryer design activities on September 19 and 20, 2011. In their report of this audit (Reference 2), they requested additional information regarding the steam dryer. Responses to those Requests for Additional Information (RAIs) were provided in Reference 3. The NRC has requested additional Entergy Operations, Inc. P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6694 GNRO-2011/00105 Page 2 of 3 information based on those responses. Reference 4 provided responses to RAI items 1, 3, 4, 7, and 8 requested by the Mechanical and Civil Engineering Branch. Responses to items 5, 6, and 9 are provided in the attachment to this letter. Response to remaining RAI 2 will be provided by November 29, 2011.
GE-Hitachi Nuclear Energy Americas, LLC (GEH) considers portions of the information provided in support of the responses to the RAIs in Attachment 1 to be proprietary and, therefore, exempt from public disclosure pursuant to 10 CFR 2.390. An affidavit for withholding information, executed by GEH, is provided in Attachment 3. The proprietary information was provided to Entergy in a GEH transmittal letter that is referenced in the affidavit. Therefore, on behalf of GEH, Entergy requests the NRC withhold Attachm ent 1 from public disclosure in accordance with 10 CFR 2.390(b)(1). A non-proprietary version of the RAI responses is provided in .
No change is needed to the no significant hazards consideration included in the initial LAR (Reference 1) as a result of the additional information provided. This letter contains new commitments, which are identified in Attachment 4.
If you have any questions or require additional information, please contact Jerry Burford at 601-368-5755.
I declare under penalty of perjury that the foregoing is true and correct. Executed on November 25, 2011.
Sincerely, MAK/FGB Attachments: 1. Response to Request for Additional Information, Mechanical and Civil Engineering Branch, Steam Dryer (Proprietary Version) 2. Response to Request for Additional Information, Mechanical and Civil Engineering Branch, Steam Dryer (Non-Proprietary Version) 3. GEH Affidavit for Withholding Information from Public Disclosure
- 4. List of Regulatory Commitments GNRO-2011/00105 Page 3 of 3 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2) ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700
Attachment 2 GNRO-2011/00105 Grand Gulf Nuclear Station Extended Power Uprate Response to Request for Additional Information Mechanical and Civil Engineering Branch, Steam Dryer (Non-Proprietary)
This is a non-proprietary version of Attachment 1 from which the proprietary information has been removed. The proprietary portions that have been removed are indicated by double square brackets as shown here: [[ ]].
to GNRO-2011/00105
Page 1 of 10 Non-Proprietary Response to Request for Additional Information Mechanical and Civil Engineering Branch By letter dated September 8, 2010, Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) for an Extended Power Uprate (EPU) for Grand Gulf Nuclear Station, Unit 1 (GGNS). By letters dated March 30, 2011 and July 6, 2011 (U.S. Nuclear Regulatory
Commission (NRC) ADAMS Accession No. ML110900275 and ML111880138, respectively), Entergy submitted responses to requests for additional information (RAI) from the Mechanical and Civil Engineering Branch related to the steam dryer. Subsequently, on September 19-20, 2011 the NRC staff conducted an audit of the replacement steam dryer calculations, in which several open items were identified. Entergy provided responses to those items in a letter to the staff dated October 10, 2011. The NRC has requested further additional clar ification; responses to RAIs 1, 3, 4, 7, and 8 were provided in a letter dates November 14, 2011. Responses to
RAIs 5, 6 and 9 are provided below.
RAI 5 In response to audit action item 11, the applic ant provided a summary of all adjustments made to their GGNS replacement dryer stress calculations, and a table updating the maximum stresses and stress ratios. The licensee also stated that based on the reanalysis, the [[
]] The licensee is requested to revise this table based on the licensee's responses to the follow-up questions for audit ac tion items 1, 3, 5, and 7 noted above.
RESPONSE As discussed during the audit, a reanalysis of the GGNS steam dryer was performed in May, 2011. This is the reanalysis that resu lted in the improved Minimum Alternating Stress Ratio (MASR) of [[
]] that is described in this cu rrent RAI. The revised stress table reflecting that result was presented in Table 3 in the response to audit action item 11 in the October 10, 2011 letter. The re sults of a new reanalysis considering the impact of the audit findings was also included in the response to audit action item 11 as Table 2. The revised stress table in that response showed a new limiting [[
]] component. This result is an improvement on the margin compared to [[
]] from the original GGNS dryer analysis submission.
to GNRO-2011/00105
Page 2 of 10 Non-Proprietary The responses to the recent follow-up NRC questions (RAIs 1 through 4) on audit action items 1, 3, 5 and 7 do not result in any additional changes to t he stress table. Similarly, the design change to [[
]] do not result in any additional changes to the stress table.
However, in preparing the response to RAI 6, the stresses in four components were reevaluated: [[
]]
[[
]] In this table, not e that positive values indicate an increase in the MASR from the response to audit action item 11 Table 2 values. Note also that the
[[
]] to GNRO-2011/00105
Page 3 of 10 Non-Proprietary
[[ {3}]] to GNRO-2011/00105
Page 4 of 10 Non-Proprietary RAI 6 In Section 3.3.2.4 of the GEH report NEDC-33601P, the applicant discusses [[
]] (Section 3.3.2.4.5, see Node 26 data in Table 3-22 ). (a) The licensee is requested to explain whether [[
]] and also explain how does one determine whether to perform sub-modeling at a given high stress location. (b) The licensee is requested to explain why the [[
]] (c) It appears that the strength of materials approach determines the [[
]] The licensee is requested to explain whether this stress is compared with the [[
]] Response [[
]] (a) [[
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]] (b) [[
]] (c) [[
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Page 8 of 10 Non-Proprietary RAI 9 (a) The licensee is requested to identify the ASME Code requirements that are followed for the design and fabrication of the partial penetration welds in the GGNS replacement steam dryer. (b) The licensee is requested to describe how the fatigue assessment of the partial penetration weld is performed. (c) If the size of the partial penetration weld is smaller than that required by the ASME code, the licensee is requested to describe how the undersize effect of the partial penetration weld is accounted for in the fatigue assessment of the GGNS dryer.
Response (a) The steam dryer, includi ng the dryer units, is a non-safety related item and is classified as an Internal Structure as defined in the ASME BPV Code Section III, Subsection NG, Paragraph NG-1122. T he steam dryer is not an ASME Code component, but the structural evaluation methodology uses the Code as a design guide with the exception [[
]] as discussed in Subsections 3.3.4.3 and 3.3.
4.4 of NEDC-33601 (Reference 2).
The Grand Gulf Replacement Steam Dryer (RSD) uses partial joint penetration groove welds as allowed by the ASME Section III Subsection NG, Paragraphs NG-3352.4 (Type IV joints) and NG-3352.6 Ty pe (VI Joints) (Reference 1). It is noted that NG-3351(a) states, in part, "Joints whose design functions are neither to restrain nor support the core do not fall into any category." Subparagraph NG-3350 is typically applied to welded joints in structures whose function is to either restrain or support the core struct ures. For reactor internal components that do not fall into the core support struct ure category, such as the steam dryer, some flexibility is allowed to accommodate additional design and manufacturing considerations. The RSD is manufactured and examined with Subsection NG-4000 and NG-5000 guidance. The dryer is also manufac tured from materials inspected per NG-2500. To ensure high quality welds, the replacement dryer employs weld processes that are fully qualified, including thorough metallurgical evaluation with the requirements of ASME Code Section IX. [[
]], robust weld process qualifications are conducted to prevent weld defects fr om occurring during fabrication. Metallurgical evaluations demonstrating an acceptable weld root are required prior to weld procedure approval as described in NEDC-33601 Appendix E paragraph 4.2 (Reference 2). to GNRO-2011/00105
Page 9 of 10 Non-Proprietary (b) For partial penetration welds, peak stre ss intensities are obtained from the shell finite element model time history analysis. Because the shell finite element model of the full steam dryer is no t capable of predicting the full stress concentrations in partial penetration welds, weld fatigue factors and, if necessary, weld size reduction factors for partial penetration welds are applied to the calculated peak stress intensities to determine the fatigue stress. Partial penetration welds are treated similarly to f illet welds; the weld factors for fillet welds are described in Section 3.3.2.
2.3 in NEDC-33601 (Reference 2).
A weld size reduction factor may be needed as stated above. When using the traditional Strength of Materi als formulas, the effective weld size is taken into account in the weld section properties. [[
]] As described in the NEDC-33601 (Referenc e 2), the requirement for acceptance of a steam dryer component is that its maximum stress intensity has to be less than the fatigue limit. The Minimum Alternating Stress Ratio (MASR) is calculated and reported for eac h of the steam dryer comp onents. The MASR is defined as the Fatigue Stress Limit divi ded by the Maximum Service Stress. A minimum alternating stress ratio less than 1.0 indicates the stress in the steam dryer component has exceeded its fatigue lim it. For the GGNS RSD, a MASR of 2.0 is specified as t he acceptance criterion. (c) All partial penetration welds in the RSD have been evaluated. Only one weld was not analyzed in accordance with (b) above.
This is a small anti-rotation weld on the adjusting ring to splice bar that is needed during installation of the splice bar. Following installation of the splice bar this weld does not perform any function. Any analyzed partial penetrati on welds that do not meet the fatigue stress criterion are redesigne d as full-depth groove welds.
As part of the final dryer fabrication, it was determined that the partial penetration welds in three areas in the dryer bank assembly did not meet the fatigue acceptance criterion. These three areas are: 1) top c ap to top cap (with divider plate) joints, 2) the top cap to bank end plate joints, and 3) bank end plate to trough joints. These welds are being r edesigned as full-depth groove welds.
Because the weld extends through the fu ll section thickness, the joint is to GNRO-2011/00105
Page 10 of 10 Non-Proprietary consistent with the global shell finite element model and no further stress adjustment is needed to account for the size of the weld.
References
- 1. ASME Boiler & Pressure Vessel Code,Section III, Subsection NG, 2004 Edition.
- 2. NEDC-33601P Rev. 0 "Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using PBLE Methodology", September 2010. This document is Attachment 11 to the GGNS Extended Power Uprate License Amendment Request, submitted on September 8, 2010.
Attachment 3 GNRO-2011/00105 Grand Gulf Nuclear Station Extended Power Uprate Response to Request for Additional Information Mechanical and Civil Engineering Branch, Steam Dryer GEH Affidavit for Withholding Information from Public Disclosure GE-Hitachi Nuclear Energy Americas LLC Affidavit for 173280-JB-050 Affidavit Page 1 of 3 AFFIDAVIT I, Edward D. Schrull, PE state as follows:
(1) I am the Vice President, Regulatory Affairs, Services Licensing, GE-Hitachi Nuclear Energy Americas LLC ("GEH"), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GEH letter, 173280-JB-050, "Grand Gulf Steam Dryer: Transmittal of Steam Dryer Requests for Additional Information 5, 6 and 9," dated November 25, 2011. The GEH proprietary information in Enclosure 1, which is entitled "GEH Responses to Requests for Additional Information 5, 6 and 9, Mechanical and Civil Engineering Branch - Steam Dryer, GEH Proprietary Information - Cla ss III (Confidential)" is identified by a dotted underline inside double square brackets. [[This sentence is an example.
{3}]] In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exempti on 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group
- v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies; b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential pr oducts to GEH; GE-Hitachi Nuclear Energy Americas LLC Affidavit for 173280-JB-050 Affidavit Page 2 of 3
- d. Information that discloses trade secret and/or potentially patentable subject matter for which it may be desirable to obtain patent protection.
(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary and/or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited to a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory
provisions or proprietary and/or confidentiality agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains detailed GEH design information of the methodology used in the design and analysis of the steam dryers for the GEH Boiling Water Reactor (BWR). Development of these methods, techniques, and information and their application for the design, modification, and analyses methodologies and processes was achieved at a significant cost to GEH.
The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience databases that constitute major GEH asset.
GE-Hitachi Nuclear Energy Americas LLC Affidavit for 173280-JB-050 Affidavit Page 3 of 3 (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and
technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing a nd obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 25 th day of November 2011.
Edward D. Schrull, PE Vice President, Regulatory Affairs Services Licensing GE-Hitachi Nuclear Energy Americas LLC
3901 Castle Hayne Rd.
Wilmington, NC 28401
Edward.Schrull@ge.com
Attachment 4 GNRO-2011/00105 Grand Gulf Nuclear Station Extended Power Uprate List of Regulatory Commitments to GNRO- 2011/00105
Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check one)
COMMITMENT ONE-TIME ACTIONCONTINUING COMPLIANCE SCHEDULED COMPLETION DATE (If Required) 1. Response to remaining RAI 2 will be provided. 11/29/11 2. The final machined pad for each tie bar will be confirmed to be of sufficient thickness to ensure the stresses in the pad remain within the final stress results. 12/31/11