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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
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23208A2112023-07-27027 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 ML11308A4852011-10-28028 October 2011 Applicant'S Environmental Report, Operating License Renewal Stage, Attachment C - Clean Water Act Documentation, Part 4 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 ML11308A0982011-10-28028 October 2011 License Renewal Application Technical Information - Appendix C - Response to BWRVIP Applicant Action Items ML11308A2442011-10-28028 October 2011 Applicant'S Environmental Report, Operating License Renewal Stage, Attachment a - Threatened and Endangered Species Correspondence, Part 2 of 3 2023-07-27
[Table view] |
Text
l-i Entergy Operations, Inc.
P 0 Box 756 Port Gibson, MS 39150
- En er Z Tel 601 437 6409 Fax 601 437 2795 William A. Eaton Vice President, Operations Grand Gulf Nuclear Station GNRO-2003/00019 March 19, 2003 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling Stations for Boiling Water Reactors Using the Consolidated Line Item Improvement Process (CLIIP) (LDC-2002/066)
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Operations Inc., (Entergy) hereby requests amendment of Facility Operating License for Grand Gulf Nuclear Station, Unit 1 (GGNS).
The proposed amendment would delete Technical Specification (TS) 5.5.3, "Post Accident Sampling" (PASS), Section 2.C (33) (c) of the Operating License (OL) and add the following phrase to the reference to PASS in TS 5.5.2: "(until such time as a modification eliminates the PASS penetration as a potential leakage path)." This change will eliminate the TS requirement to have and maintain the Post Accident Sampling Station at GGNS. The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-413, "Elimination of Requirements for a Post Accident Sampling System." The availability of this TS improvement was announced in the Federal Register on March 20, 2002 as part of the Consolidated Line Item Improvement Process (CLIIP). In accordance with 10 CFR 50.91 a copy of this application, with attachments, is being provided to the State of Mississippi.
Essential details and information to support this request are provided in the Attachments to this letter. Attachment 1 provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications. The OL and TS pages annotating the proposed changes are provided in Attachment 2 and a list of regulatory commitments is provided in Attachment 3. Entergy is respectfully requesting review and approval of this request by September 01, 2003. Once approved, the amendment will be implemented within 120 days.
March 19, 2003 GNRO-2003/00019 Page 2 of 2 If you have any questions or require additional information, please contact Bill Brice at 601-368-5076.
I declare under penalty of perjury that the forgoing is true and correct. Executed on March 19, 2003 Yours truly, WAEAWBB/amt attachments:
- 1. Analysis of Proposed Operating License and Technical Specification Changes
- 2. Proposed Operating License and Technical Specification Changes (mark-up)
- 3. List of Regulatory Commitments cc: U. S. Nuclear Regulatory Commission ATTN: Mr. Ellis W. Merschoff Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. D. H. Jaffe, NRR/DLPM (w/2)
ATTN: FOR ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN/7D-1 Washington DC 20555-0001 Mr. T. L. Hoeg (GGNS Senior Resident Inspector)
Mr. D. E. Levanway (Wise Carter)
Mr. L. J. Smith (Wise Carter)
Mr. N. S. Reynolds Mr. H. L. Thomas
ATTACHMENT 1 TO GNRO-2003/00019 ANALYSIS OF PROPOSED OPERATING LICENSE AND TECHNICAL SPECIFICATION CHANGES
Attachment I to GNRO-2003/00019 Page 1 of 2
1.0 DESCRIPTION
This letter is a request to amend Operating License (OL) NPF-29 for Grand Gulf Nuclear Station, Unit I (GGNS). The proposed amendment deletes the program requirements of Technical Specification (TS) 5.5.3, "Post Accident Sampling."; Section 2C (33) (c), "Post Accident Sampling", of the OL; and incorporates a caveat into TS 5.5.2, "Primary Coolant Sources Outside Containment", that would permit the elimination of the PASS as a potential leakage path if a system modification is pursued.
The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-413. The availability of this technical specification improvement was announced in the Federal Register on March 20, 2002 as part of the Consolidated Line Item Improvement Process (CLIIP).
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation Entergy Operations Inc, (Entergy) has reviewed the safety evaluation published on December 27, 2001 (66 FR 66949) as part of the CLIIP. This verification included a review of the NRC staff's evaluation (as modified slightly by the notice of availability) as well as the supporting information provided to support TSTF-413 (i.e., NEDO-32991, "Regulatory Relaxation for BWR Post Accident Sampling Stations (PASS)," submitted November 30, 2000, and the associated NRC safety evaluation dated June 12, 2001). Entergy has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to GGNS and justify this amendment for the incorporation of the changes to the GGNS OL and TS.
2.2 Optional Changes and Variations The GGNS TS include an administrative requirement for a program to minimize the leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident. PASS is specifically listed in TS 5.5.2 as falling under the scope of this requirement. As described in the Staffs model safety evaluation published on December 27, 2001, Entergy may implement a modification that would eliminate PASS as a potential leakage path. Entergy proposes to add the following phrase to the reference to PASS in TS 5.5.2: "(until such time as a modification eliminates the PASS penetration as a potential leakage path)."
Also as described in the model safety evaluation, the elimination of the TS and other regulatory requirements for PASS results in a change to the OL. The change would eliminate Section 2.C (33) (c) of the OL. The change is necessary due to the removal of the TS section on PASS.
The above changes do not revise technical requirements beyond that addressed by the NRC staff in the model safety evaluation published on December 27, 2001.
Attachment I to GNRO-2003/00019 Page 2 of 2
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination Entergy has reviewed the proposed no significant hazards consideration determination published on December 27, 2001 (66 FR 66949) as part of the CLIIP. Entergy has concluded that the proposed determination presented in the notice is applicable to GGNS and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).
3.2 Verification and Commitments Entergy verified it has contingency plans for obtaining and analyzing highly radioactive samples from the Reactor Coolant System (RCS), suppression pool, and containment atmosphere. The contingency plans are in plant procedures and implementation is complete. Establishment and maintenance of these plans is considered a regulatory commitment.
The capability for classifying fuel damage events at the Alert level threshold will be established for Grand Gulf Nuclear Station, Unit 1 at the 300 pCi/cc dose equivalent iodine level. This capability will be described in plant procedures and implementation will be complete within 120 days of amendment issuance. The capability for classifying fuel damage events is considered a regulatory commitment.
Entergy verified that it has an 1-131 site survey detection capability, including an ability to assess radioactive iodines released to offsite environs, by using effluent monitoring systems or portable sampling equipment. The capability for monitoring iodines will be maintained within the plant's procedures, therefore, implementation is complete. The capability to monitor radioactive iodines is considered a regulatory commitment.
4.0 ENVIRONMENTAL EVALUATION Entergy has reviewed the environmental evaluation included in the model safety evaluation published on December 27, 2001 (66 FR 66949) as part of the CLIIP. Entergy has concluded that the staffs findings presented in that evaluation are applicable to GGNS and the evaluation is hereby incorporated by reference for this application.
ATTACHMENT 2 TO GNRO-2003/00019 PROPOSED OPERATING LICENSE AND TECHNICAL SPECIFICATION CHANGES (MARK-UP)
TABLE OF CONTENTS 3.9 REFUELING OPERATIONS (continued)
TR3.9.5 Control Rod Scram Accumulator Alarms 3. 9-7-I 3.9.6 Reactor Pressure Vessel (RPV) Water Level 3.9-8
-Irradiated Fuel 3.9.7 Reactor Pressure Vessel (RPV) Water Level 3 .9-9
- New Fuel or Control Rods 3.9.8 Residual Heat Removal (RHR) - High Water 3.9-10 Level 3.9.9 Residual Heat Removal (RHR) - Low Water 3.9-12 Level 3.10 SPECIAL OPERATIONS 3. 10-1 3.10.1 Inservice Leak and Hydrostatic Testing 3.10-1 Operation 3.10 2 Reactor Mode Switch Interlock Testing 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot 3.10-6 Shutdown 3.10.4 Single Control Rod Withdrawal - Cold 3.10-9 Shutdown 3.10.5 Single Control Rod Drive (CRD) Removal - 3.10-13 Refueling 3.10.6 Multiple Control Rod Withdrawal - 3.10-16 Refueling 3.10.7 Control Rod Testing - Operating 3.10-18 3.10.8 Shutdown Margin (SDM) Test - Refueling 3.10-19 3.10.9 Suppression Pool Makeup - MODE 3 3.10-23 I
4.0 DESIGN FEATURES 4.0-1 4.1 Site Location 4.0-1 4.2 Reactor Core 4.0-1 4.3 Fuel Storage 4.0-1 5.0 ADMINISTRATIVE CONTROLS 5.0-1 5.1 Responsibility 5.0-1 5.2 organization 5.0-2 5.2.1 Onsite and Offsite Organizations 5.0-2 5.2.2 Unit Staff 5.0-3 5.3 Unit Staff Qualifications 5.0-5 5.4 Procedures 5.0-6 5.5 Programs and Manuals 5.0-7 5.5.1 Offsite Dose Calculation Manual (ODCM) 5.0-7 5.5.2 Primary Coolant Sources Outside 5.0-8 Containment )
5.5.3 *Poet i- ccel ~aipii )eIeteel 5.0-9 I 5.5.4 Radioactive Effluent Controls Program 5.0-9 5.5.5 Component Cyclic or Transient Limit 5.0-11 5.5.6 Inservice Testing Program 5.0-11 GRAND GULF v 9/11/2002
(32) PartialVFeedwater Heating (Section 15.1, SER, SSER #2)
Operation of the plant in the partial feedwater heating mode for the purpose of extending the normal fuel cycle shall be prohibited until analyses which justify that operation are provided to and approved by the NRC staff.
(33) NUREG-0737 Conditions (Section 22.2)
The following conditions shall be completed to the satisfaction of the NRC. These conditions reference the appropriate items in Section 22.2, "TMI Action Plan Requirements for Applicants for Operating Licenses," in the Safety Evaluation Report and Supplements 1, 2, 3, 4, and 5 to NUREG-0831.
(a) Control Room Design Review (I.D.1, SER; Appendix E, SSER #2, SSER #4, 5SER #5)
Prior to startup following the first refueling outage, SERI shall demonstrate the ability to maintain an effective temperature" condition of 850 F or less in the remote shutdown panel (RSP) room for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with an ambient outdoor temperature of at least 950 F.
(b) Training During Low-Power Testing (I.G.1, SER)
Prior to restart following the first refueling outage, MPLL shall complete the additional training and testing related to TMI Action Plan I.G.1 as described in Section 2.3 of the MP&L submittal dated April 3, 1986.
(c I Aecidcnt vPost Samp14ng (11.0.3, SER,;SSER Y , SSER#4,S prior to startup following th first -refueatng outage, MP&L shall
-incor~pratp the additional reguircrens nt t-kheep roccr f-X>
.relating radionuclide gaseo'.s and ionic species to estima.te wor-e (d) ydrogen Control (Section 11.8.7, SER, SSER #2, SSER #3, 55ER #4, USER #5)
(1) During the first cycle of operation, MP&L shall maintain a suitable program of analysis and testing of the installed hydrogen ignition system. EOI shall submit to the NRC quarterly reports on the status of their research programs.
12 Amendment No. 65
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued) affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the:
- a. LPCS System;
- b. HPCS System;
- c. RHR System outside containment containing steam or water, except the line to the liquid radwaste system and headers that are isolated by manual valves;
- d. RCIC System outside containment containing steam or water, except the drain line to the main condenser;
- e. Hydrogen analyzers of the Combustible Gas Lo ol System;
- f. Post Accident Sampling System, d
- g. Feedwater Leakage Control System; and
- h. Suppression pool level detection portion of the Suppression Pool Makeup System.
The program shall include the following:
- a. Preventive maintenance and periodic visual inspection requirements; and
- b. Integrated leak test requirements for each system at refueling cycle intervals or less.
(continued)
GRAND GULF S.0-8 Amendment No. 120
Insert A (until such time as a modification eliminates the PASS penetration as a potential leakage path);
Programs and Manuals 5.5 5.5 Programs and Manual (continued) 5.5.3 Post Accident Sam linq D e-/rte This program pro ides controls that ensure the capability to obtain and analy e reactor coolant, radioactive gases, and particulates in lant gaseous effluents and containment atmosphere samples under ac ident conditions. The program shall include the following:
- a. Training o personnel;
- b. Procedures for sampling and analysis; and
- c. Provisions for maintenance of sampling and analysis equipment 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;
- b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in 10 CFR 20, Appendix B, Table 2, Column 2;
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;
- d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the unit to unrestricted areas, conforming to 10 CFR 50, Appendix I; (continued)
GRAND GULF 5 .0-9 Amendment No. 120
ATTACHMENT 3 TO GNRO-2003/00019 LIST OF REGULATORY COMMITMENTS to GNRO-2003/00019 Page 1 of I 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 (C eck one) SCHEDULED COMMITMENT COMPLETION ONE- CONTINUING DATE TIME COMPLIANCE (If Required)
ACTION Contingency plans for obtaining and analyzing Yes Verify item highly radioactive samples from the Reactor complete and Coolant System (RCS), suppression pool, and enter into containment atmosphere are in plant procedures commitment and implementation is complete. tracking system within 120 days of issuance The capability for classifying fuel damage events at Yes Within 120 days the Alert level threshold will be established at the of amendment 300 pCi/cc dose equivalent iodine level. This issuance capability will be described in plant procedures and implementation will be complete within 120 days of amendment issuance.
1-131 site survey detection capability, including an Yes Verify item ability to assess radioactive iodines released to complete and offsite environs, by using effluent monitoring enter into systems or portable sampling equipment has been commitment verified and will be maintained within the plant's tracking system procedures, therefore, implementation is complete. within 120 days of issuance