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Category:Letter type:GNRO
MONTHYEARGNRO-2013/00079, 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013)2023-10-11011 October 2023 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013) 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-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-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-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report 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-2018/00054, 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-2018/00055, 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-2018/00052, 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-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report 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-2018/00048, 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 2023-06-06
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes 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 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 ML23033A0492023-02-0101 February 2023 Emergency Action Level (EAL) Technical Bases Document Revision 3 ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated ML21062A1982021-03-0303 March 2021 Supplement to License Amendment Request to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 1 ML20091M3632020-03-31031 March 2020 Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test CNRO-2020-00009, Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 12020-02-26026 February 2020 Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 1 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 CNRO-2020-00008, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process CNRO-2020-00006, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 22020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 2 GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 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. ML19072A2812019-03-13013 March 2019 Supplement 1 to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 22019-03-0707 March 2019 Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2 CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 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-2018/00051, 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-2018/00029, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-06-0707 June 2018 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) GNRO-2018/00008, (GGNS) - License Amendment Request: Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62018-04-27027 April 2018 (GGNS) - License Amendment Request: Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 GNRO-2018/00013, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-04-12012 April 2018 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) GNRO-2018/00007, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-04-10010 April 2018 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control. GNRO-2017/00061, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-11-0303 November 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis ML17268A2132017-09-21021 September 2017 ISFSI, River Bend Station Unit 1 & ISFSI, Waterford 3 Steam Electric Station & ISFSI, Grand Gulf Nuclear Station & ISFSI, Application for Order Approving Transfers of Licenses and Conforming License Amendments CNRO-2017-00005, and Isfsl - License Amendment Request for Administrative Change to Licensee Name2017-03-29029 March 2017 and Isfsl - License Amendment Request for Administrative Change to Licensee Name GNRO-2016/00062, License Amendment Request (LAR) for One Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass2016-12-29029 December 2016 License Amendment Request (LAR) for One Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass GNRO-2016/00051, Application to Revise the Technical Specifications to Allow the Adoption of Technical Specification Task Force Traveler TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System..2016-10-26026 October 2016 Application to Revise the Technical Specifications to Allow the Adoption of Technical Specification Task Force Traveler TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System.. GNRO-2016/00034, License Renewal Documents to Support Review of Application for Renewal2016-10-10010 October 2016 License Renewal Documents to Support Review of Application for Renewal GNRO-2015/00087, Supplemental Letter to Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing to Provide Relief Request in Format Requested By..2015-12-0202 December 2015 Supplemental Letter to Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing to Provide Relief Request in Format Requested By.. GNRO-2015/00037, Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing2015-09-15015 September 2015 Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing GNRO-2015/00029, License Amendment Request - Cyber Security Plan Implementation2015-06-29029 June 2015 License Amendment Request - Cyber Security Plan Implementation GNRO-2015/00038, Response to Request for Additional Information Regarding Fluence License Amendment Request, Request for Commitment2015-06-11011 June 2015 Response to Request for Additional Information Regarding Fluence License Amendment Request, Request for Commitment GNRO-2015/00026, Application to Revise Technical Specifications for Permanent Extension of Type C Leak Rate Testing Frequency and Reduction of Type B and C Grace Intervals2015-05-27027 May 2015 Application to Revise Technical Specifications for Permanent Extension of Type C Leak Rate Testing Frequency and Reduction of Type B and C Grace Intervals GNRO-2014/00078, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month2014-12-15015 December 2014 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month GNRO-2014/00014, License Amendment Request for Revision of Five Technical Specification Allowable Value Setpoints2014-08-0101 August 2014 License Amendment Request for Revision of Five Technical Specification Allowable Value Setpoints GNRO-2013/00090, License Amendment Request - Cyber Security Plan Implementation Schedule2013-12-19019 December 2013 License Amendment Request - Cyber Security Plan Implementation Schedule GNRO-2013/00067, LAR Application for Technical Specification Changes; Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel..2013-11-0808 November 2013 LAR Application for Technical Specification Changes; Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel.. CNRO-2013-00008, Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-04-16016 April 2013 Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments GNRO-2012/00132, License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low.2012-11-0909 November 2012 License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low. GNRO-2012/00125, Final Feedwater Temperature Reduction License Amendment Request2012-10-26026 October 2012 Final Feedwater Temperature Reduction License Amendment Request GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 12012-10-0202 October 2012 License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1 GNRO-2012/00102, Request to Revise the Standby Service Water Passive Failure Methodology2012-09-14014 September 2012 Request to Revise the Standby Service Water Passive Failure Methodology ML12157A1792012-05-23023 May 2012 Attachment 6 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment I Labeled GGNS NPDES Permit Renewal Application (2007) GNRO-2012/00001, License Amendment Request - Standby Liquid Control System2012-01-23023 January 2012 License Amendment Request - Standby Liquid Control System ML11308A4842011-10-28028 October 2011 Applicant'S Environmental Report, Operating License Renewal Stage, Attachment C - Clean Water Act Documentation, Part 3 of 4 GNRO-2011/00064, License Amendment Request to Revise Technical Specification 2.1.1.22011-10-28028 October 2011 License Amendment Request to Revise Technical Specification 2.1.1.2 ML11308A0952011-10-28028 October 2011 License Renewal Application Technical Information - Appendix a - Updated Final Safety Analysis Report Supplement 2024-05-07
[Table view] |
Text
Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 10 CFR 50.90 GNR0-2018/00051 October 23, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542," Reactor Pressure Vessel Water Inventory Control" Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. Entergy Operations Inc. (EOI) letter to the Nuclear Regulatory Commission (NRG) dated April 10, 2018, "Application to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, 'Reactor Pressure Vessel Water Inventory 111 Control (NRG ADAMS Accession No. ML181008304)
Dear Sir or Madam:
In Reference 1, Entergy Operations Inc. (EOI) requested an amendment to Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS). The proposed change will replace existing Technical Specification (TS) requirements related to Operations with a Potential for Draining the Reactor Vessel (OPDRV) with new requirements on Reactor Pressure Vessel Water Inventory Control to protect Safety Limit 2.1.1.3. This supplement provides cqrrected pages that supplant equivalent-pages provided in Reference 1, and corrects minor editorial discrepancies that were subsequently identified. In order to implement this TS change, EOI requests a 120 day implementation period.
GNR0-2018/00051 Page 2 of 2 of this letter provides the mark-up editorial corrections to previously submitted GGNS Technical Specifications (TS). Attachment 2 of this letter provides clean-typed, corrected pages to previously submitted GGNS TS. Attachment 3 of this letter provides the editorial correction to previously submitted GGNS TS Bases, these are provided to the Nf3C for information purposes only.
No new regulatory commitments are made in this submittal. The editorial corrections provided in this supplement do not impact the No Significant Hazards Consideration analysis that was performed in the Reference 1 submittal.
In accordance with 10 CFR 50.91, "Notice for Public Comment; State Consultation," paragraph (b), a copy of this supplement, with attachment, is being provided to the ,designated State Officials.
If you should have any questions regarding this submittal, please contact Douglas A. Neve, Manager Regulatory Assurance, at 601-437..:2103.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 23, 2018.
Sincerely, Eric A. Larson EAUrws Attachments: 1. Editorial Corrections Made to Original Submittal Technical Specifications (Mark-up Pages)
- 2. Editorial Corrections Made to Original Submittal Technical Specifications (Clean-Typed Pages)
- 3. Correct Technical Specification Bases (For Information
- Purposes Only) cc: NRC Region IV - Regional Administrator NRC Senior Resident Inspector, Grand Gulf Nuclear Station Dr. Mary Currier, State Health Officer, Mississippi Department of Health NRR Project Manager
Attachment 1 to GNR0-2018/00051 Editorial Corrections Made to Original Submittal Technical Specifications (Mark-Up Pages)
Page 1 is a revision of Technical Specification (TS) 3.3.5.1 (TS page 3.3-32)
Page 2 is a revision of Technical Specification (TS) 3.3.5.2 (TS page 3.3-43d)
Page 3 is a revision of Technical Specification (TS) 3.3.5.2 (TS page 3.3-43e)
Page 4 is a revision of Technical Specification (TS) 3.5.2 (TS page 3.5-8)
ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS} Instrumentation LCO 3.3.5.1. The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.5.1-1.
ACTIONS
NOTE-------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A. I Enter the Condition Immediately channels inoperable. referenced in Table 3.3.5.1-1 for the channel.
B. As required by 8.1 I' --------NOTES--------
Required Action A.I l. Only appl i cable .
and referenced in iA MQQ~S l, a, Table 3.3.5.1-1. and 3.
I I
2-.--0nly applicable for Functions I.a, l.b, 2.a and 2.b.
Declare supported 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from feature(s} inoperable discovery of
- when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable. feature(s} in both divisions AND
\
u (cont'inued}
GRAND GULF 3.3-32 Amendment No. 12-Q Page 1 of 4
RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 2)
Rf?V Water Inventory Control Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE
. FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Sgray (LPCS} Subsystems
- a. Reactor Vessel 1.....§. 3(a) .Q SR 3.3.5.2.1 ~ 452 gsig and Pressure - Low SR 3.3.5.2.2 ~ 534 QSig (Injection Permissive}
- b. LPCS Pumg Discharge Flow - Low 1.....§. ~ £ SR 3.3.5.2.1 21285 ggm (Bygass} SR 3.3.5.2.2
- c. LPCI Pumg A 1.....§. ~ £ SR 3.3.5.2.1 2 1133 ggm Discharge Flow - Low SR 3.3.5.2.2 (Bygass}
- d. Manual Initiation 1.....§. ~ £ SR 3.3.5.2.3 NA
- 2. LPCI Band LPCI C Subsystems
- a. Reactor Vessel 1.....§. 3(a) .Q SR 3.3.5.2.1 ~ 452 gsig and
- Pressure - Low SR 3.3.5.2.2 ~ 534 QSig (Injection Permissive)
- b. LPCI Pumg B 1.....§. 1._Qfil £ SR 3.3.5.2.1 2 1133 ggm and LPCI Pumg C gump(a) SR 3.3.5.2.2 Discharge Flow - Low (Bygass}
- c. Manual Initiation 1.....§. ~ £ SR 3.3.5.2.3 NA (continued}
(a} Associated with an ECCS subsystem reguired to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel (RPV} Water lnvento[Y Control."
GRAND GULF 3.3-43d Amendment No.
Page 2 of 4
~
RPV Water lnventor:y Control Instrumentation 3:3.5.2 Table 3.3.5.2-1 (Qage 2 of 2}
RPV.Water Inventory Control Instrumentation
- j APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE
- ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 3. High Pressure Core SQray (HPCS} System 4(b) 5(b)
- a. Condensate Storage ~ Q SR 3.3.5.2.1 2 4.7 ft Tank Level - Low SR 3.3.5.2.2
- b. HPCS Pump Discharge Pressure 1.....§. ')
~ s SR 3.3.5.2.1 :::: 108 psig and SR 3.3.5.2.2 ::;; 1282 psig
- High (Bypass}
- c. HPCS System Flow Rate - Low 1.....§. ~ s SR 3.3.5.2.1 :::: 1124 gpm SR 3.3.5.2.2 and (Bypass} ::;; 1327 gpm
- 4. RHR System Isolation
- a. Reactor Vessel 19 2 in one trip ~ SR 3.3.5.2.1 :::: 10.8 inches Water Level - Low, system SR 3.3.5.2.2 Level3
- 5. Reactor Water Cleanup (RWCU} System Isolation
- a. Reactor Vessel 19 2 in one trip ~ SR 3.3.5.2.1 :::: -43.8 inches Water Level - Low system SR 3.3.5.2.2 Low, Level 2 (a} Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel (RPV} Water Inventory Control."
(b} When HPCS is OPERABLE for compliance with LCO 3.5.2, "Reactor Pressure Vessel (RPV} Water Inventory Control," and aligned to the condensate storage tank.
(c} When automatic isolation of the associated penetration flow path(s} is credited in calculating DRAIN TIME.
GRAND GULF 3.3-43e Amendment No.
Page 3 of 4
SURVEILLANCE REQUIREMENTS (contfoued)
SURVEILLANCE FREQUENCY SR 3. 5. 2 .-2 Verify, for the required High Pressure Core 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Iel Spray (HPCS} System, the:
- a. Suppression pool water level is 2: 12 ft 8 inches; or
- b. Condensates water level is 2 18 ft.
lL SR 3. 5. 2 .-3 Verify, for e-a*eh required ECCS injection/ 31 qays
/I spray subsystem, locations susceptible_to gas accumulation are suf ficently_ filled
~ with water.
SR 3.5.2.-4 ------------------ NOTE------------ .. * ----
Not required to be met Jor system vent flow I
paths opened under administrative control.
\
Verif efrefl required ECCS inje.ct:Lon/spray 31 days sub ~em manual, power operated, and tomatic,~alve in. the flow path, that is not lock.e, sealed, or otherwise secured in position, *sin the correct position.
( continued.)
GRANP GULF 3.5-8 Amendment No. ~ , tt9-, ~
Page 4 of 4 r*.
Attachment 2 to GNR0-2018/00051 Editorial Corrections Made to Original Submittal Technical Specifications (Clean Typed Pages)
Page 1 is a revision of Technical Specification (TS) 3.3.5.2 (TS page 3.3-43d)
Page 2 is a revision of Technical Specification (TS) 3.3.5.2 (TS page 3.3-43e)
Page 3 is a revision of Technical Specification (TS) 3.5.2 (TS page 3.5-8)
Table 3.3.5.2-1 (page 1 of 2)
RPV Water Inventory Control Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS) Subsystems
- a. Reactor Vessel 4, 5 3(a) c SR 3.3.5.2.1 ~ 452 psig and Pressure - Low SR 3.3.5.2.2 ::;;; 534 psig (Injection Permissive)
- b. LPCS Pump Discharge Flow - 4, 5 1(a) E SR 3.3.5.2.1 2 1285 gpm tow (Bypass) SR 3.3.5.2.2
- c. LPCI Pump A 4, 5 1(a) E SR 3.3.5.2.1 2 1133 gpm Discharge Flow - SR 3.3.5.2.2 Low (Bypass)
- d. Manual Initiation 4, 5 1(a) E SR 3.3.5.2.3 NA
.)
- 2. LPCI B and LPCI C Subsystems
- a. Reactor Vessel 4, 5 3(a) c SR 3.3.5.2.1 ~ 452 psig and Pressure - Low SR 3.3.5.2.2 ::;;; 534 psig (Injection Permissive)
- b. LPCI Pump B 4, 5 1 per E SR 3.3.5.2.1 2 1133 gpm and LPCI Pump C pump(a) SR 3.3.5.2.2 Discharge Flow -
Low (Bypass)
- c. Manual Initiation 4, 5 1(a) E SR 3.3.5.2.3 NA (continued)
(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel (RPV) Water Inventory Control."
Page 1 of 3
Table 3.3.5.2~1 (page 2 of 2)
RPV Water Inventory Control Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 3. High Pressure Core Spray (HPCS) System
- a. ,condensate Storage 4(b), 5(b) 1(a) D SR 3.3.52.1 ~4.7 ft Tank Level - Low SR 3.3.5.2.2
- b. HPCS Pump 4, 5 1(a) E SR 3.3.5.2.1 ~ 108 psig and Discharge Pressure SR 3.3.5.2.2 ::;; 1282 psig
- High (Bypass)
- c. HPCS System Flow 4, 5 1(a) E SR 3.3.5.2.1 ~ 1124 gpm
\ Rate - Low SR 3.3.5.2.2 and (Bypass) ::;; 1327 gpm
- 4. RHR System Isolation
- a. Reactor Vessel (c) 2 in one B SR 3.3.5.2.1 ~ 10.8 inches Water Level - Low, trip system SR 3.3.5.2.2 Level3
- 5. Reactor vyater Cleanup (RWCU) System Isolation
- a. Reactor Vessel (c) 2 in one B SR 3.3.5.2.1 ~ -43.8 inches Water Level - Low trip system SR 3.3.5.2.2 Low, Level 2 (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel (RPV) Water Inventory Control."
(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "Reactor Pressure Vessel (RPV) Water Inventory Control," and aligned to the condensate storage tank.
(c) When automatic isolation of the ~ssociated' penetration flow path(s) is credited in calculating DRAIN TIME.
Page 2 of 3
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for the required High Pressure Core Spray 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (HPCS) System, the:
- a. Suppression pool water level is ~ 12 ft 8 inches; or
- b. Condensate storage tank water level is ~ 18 ft.
SR 3.5.2.4 Verify, for the required ECCS injection/ spray 31 days subsystem, locations susceptible to gas accumulation are sufficently fiUed with water.
SR 3.5.2.5 -------------------------------N()TE------------------------------
Not required to be met for system vent flow paths opened under a9ministrative control.
Verify, for the required ECCS injection/spray 31 days subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
(continued)
Page 3 of 3
Attachment 3 to GNR0-2018/00051 I
Correct Technical Specification Bases (For Information Purposes Only)
BASES SURVEILLANCE SR 3.5.2.5~ (continued)
REQUIREMENTS initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is appropriate because the valves are operated under procedural control and the prpbability of their being mispositioned during this time period is low.
In MODES 4 and 5, the RHR System may operate in the shutdown cooling mode, or be aligned to allow alternate means to remove decay heat and sensible heat from the reactor. Therefore, RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal.
One LPCI subsystem of the RHR System may be considered OPERABLE for the ECCS function if all. the required valves in the LPCI flow path can be manually realigned (remote or local) to allow injection into the RPV and the system is not otherwiie inoperable. This will ensure adequate core cooling if an inadvertent vessel draindown should occur.
The Surveillance is modified by a Note which exempts system vent flow paths opened under administrative control. The administrative control should be proceduralized and include stationing a dedicated individual at the system vent flow path who is in continuous communication with the operators in the control robm. This individual will have a method to rapidly close the system vent flow path if directed.
SR 3.5.2.6 Verifying that the required ECCS injection/spray subsystem can be manually started and operate for at least 10 minutes demonstrates that the subsystem is available to mitigate a draining event. Testing the ECCS injection/spray subsystem through the test return line is necessary to avoid overfilling the refueling cavity. The minimum operating time of 10 minutes was based on engineering judgement. The performance frequency of 92 days is consistent with similar at-power testing required by SR 3.5.1.7. 1 SR 3.5.2.7 Verifying that each valve credited for automatically isolating a penetration flow path actuates to the isolation position -on an actual or simulated RPV water level isolation signal is required to prevent RPV water inventory from dropping below the T AF should an unexpected draining event occur.
The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed *at the 24 Page 1 of 1