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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-2023/00014, 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 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 ML11308A4712011-10-28028 October 2011 Applicant'S Environmental Report, Operating License Renewal Stage, Attachment C - Clean Water Act Documentation, Part 2 of 4 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 2024-05-07
[Table view] Category:Technical Specification
MONTHYEARML24116A0372024-04-25025 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 ML23033A0492023-02-0101 February 2023 Emergency Action Level (EAL) Technical Bases Document Revision 3 ML22223A0512022-08-11011 August 2022 Report of Technical Specification Bases Changes CNRO-2022-00015, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process2022-05-26026 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process 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 ML21105A0522021-04-15015 April 2021 EAL Technical Bases Document Revision 1 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 ML20262H2252020-09-18018 September 2020 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program Using the Consolidated Line Item Improvement GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes ML20134H8872020-05-12012 May 2020 Technical Specification Bases 3.2 ML20134H9592020-05-12012 May 2020 Technical Specification Bases 3.10 ML20134H9562020-05-12012 May 2020 Technical Specification Bases 3.9 ML20134H9532020-05-12012 May 2020 Technical Specification Bases 3.8 ML20134H9502020-05-12012 May 2020 Technical Specification Bases 3.7 ML20134H9372020-05-12012 May 2020 Technical Specification Bases 3.6 ML20134H9352020-05-12012 May 2020 Technical Specification Bases 3.5 ML20134H9312020-05-12012 May 2020 Technical Specification Bases 3.4 ML20134H8892020-05-12012 May 2020 Technical Specification Bases 3.3 ML20134H8772020-05-12012 May 2020 Technical Specification Bases 3.0 ML20134H8802020-05-12012 May 2020 Technical Specification Bases 3.1 ML20134H8672020-05-12012 May 2020 Technical Specification Bases 2.0 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-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-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes 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. ML18085A5792018-03-26026 March 2018 Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals GNRO-2015/00002, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/20142015-03-27027 March 2015 Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/2014 GNRO-2015/00020, Revision to Letter GNRO-2014/00091 Dated January 6,2015 to Add Revision Number Eight (8) to Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density2015-03-27027 March 2015 Revision to Letter GNRO-2014/00091 Dated January 6,2015 to Add Revision Number Eight (8) to Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density GNRO-2014/00058, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)2014-08-29029 August 2014 Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330) GNRO-2014/00057, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)2014-08-29029 August 2014 Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330) 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-2014/00050, Correction of Technical Specification Typographical Error2014-07-31031 July 2014 Correction of Technical Specification Typographical Error ML13316B0242013-11-0808 November 2013 Application for Technical Specification Changes: Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-423, Technical Specifications End States GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update2012-12-21021 December 2012 Technical Requirements Manual and Technical Specification Bases Update ML12277A0812012-10-0202 October 2012 Proposed Techincal Specification Changes ML11308A1032011-10-28028 October 2011 License Renewal Application - Appendix D - Technical Specification Changes GNRO-2011/00004, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0606 April 2011 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. GNRO-2010/00042, Technical Specification Bases & Technical Requirements Manual Update2010-05-27027 May 2010 Technical Specification Bases & Technical Requirements Manual Update GNRO-2010/00009, Technical Specification Bases Update to the NRC for Period Dated January 20, 20092010-01-20020 January 2010 Technical Specification Bases Update to the NRC for Period Dated January 20, 2009 GNRO-2009/00062, License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits2009-10-27027 October 2009 License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions GNRO-2009/00028, Technical Specification Bases Update to the NRC for Period Dated April 22, 20092009-04-22022 April 2009 Technical Specification Bases Update to the NRC for Period Dated April 22, 2009 GNRO-2009/00017, Technical Specification Bases Update to the NRC for Period Dated March 4, 20092009-03-0404 March 2009 Technical Specification Bases Update to the NRC for Period Dated March 4, 2009 GNRO-2009/00008, Technical Specification Bases Update to the NRC for Period Dated January 23, 20092009-01-23023 January 2009 Technical Specification Bases Update to the NRC for Period Dated January 23, 2009 GNRO-2008/00069, Technical Specification Bases and Technical Requirements Manual Update to the NRC for Period Dated October 22, 20082008-10-22022 October 2008 Technical Specification Bases and Technical Requirements Manual Update to the NRC for Period Dated October 22, 2008 GNRO-2008/00013, License Amendment Request, Technical Specification Surveillance Requirements for Diesel Generator Slow Start Testing2008-09-11011 September 2008 License Amendment Request, Technical Specification Surveillance Requirements for Diesel Generator Slow Start Testing 2024-04-25
[Table view] Category:Amendment
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 CNRO-2022-00015, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process2022-05-26026 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process 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 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-2015/00002, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/20142015-03-27027 March 2015 Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/2014 GNRO-2014/00050, Correction of Technical Specification Typographical Error2014-07-31031 July 2014 Correction of Technical Specification Typographical Error ML12277A0812012-10-0202 October 2012 Proposed Techincal Specification Changes GNRO-2009/00062, License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits2009-10-27027 October 2009 License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions GNRO-2008/00013, License Amendment Request, Technical Specification Surveillance Requirements for Diesel Generator Slow Start Testing2008-09-11011 September 2008 License Amendment Request, Technical Specification Surveillance Requirements for Diesel Generator Slow Start Testing GNRO-2007/00050, Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability2007-08-0707 August 2007 Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability GNRO-2007/00004, License Amendment Request, Request for a Technical Specification Change to Allow Use of Control Rod Assemblies with Different Control Material2007-01-18018 January 2007 License Amendment Request, Request for a Technical Specification Change to Allow Use of Control Rod Assemblies with Different Control Material GNRO-2006/00036, License Amendment Request, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372)2006-11-0101 November 2006 License Amendment Request, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372) GNRO-2004/00013, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process, LDC-2003/1022004-02-18018 February 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process, LDC-2003/102 GNRO-2003/00053, Application for Technical Specification (TS) Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process.2003-10-24024 October 2003 Application for Technical Specification (TS) Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process. GNRO-2003/00044, Supplement to Amendment Request Removal of Mode Restrictions for Surveillance Testing of the Division 3 Battery2003-08-0707 August 2003 Supplement to Amendment Request Removal of Mode Restrictions for Surveillance Testing of the Division 3 Battery GNRO-2003/00025, License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-0332003-05-0808 May 2003 License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-033 RBG-46072, Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Division 1 & 2 Emergency Diesel Generator Load Reject Testing2003-03-14014 March 2003 Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Division 1 & 2 Emergency Diesel Generator Load Reject Testing ML0225604002002-09-0606 September 2002 New Special Operations Limiting Condition of Operation Suppression Pool Makeup-Mode 3. Revised TS Page 3.6-34 and the New Additional TS Page 3.10-23, 3.10-24, 3.10-25 & 3.10-26 2023-07-27
[Table view] |
Text
GNRO-2008/00013 September 11, 2008 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
SUBJECT:
License Amendment Request Technical Specification Surveillance Requirements for Diesel Generator Slow Start Testing Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29
Dear Sir or Madam:
Pursuant to 10CFR50.90, Entergy Operations, Inc. (Entergy) hereby requests the following amendment to the Grand Gulf Nuclear Station Unit 1 (GGNS) Operating License pursuant to 10 CFR 50.91 (a)(6).
The proposed change will affect Surveillance Requirements for Technical Specification (TS) Limiting Condition for Operation (LCO) 3.8.1 and 3.8.2 and is based on NUREG 1434, "Standard Technical Specifications General Electric Plants, BWR/6" and Generic Letter 84-15, "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability." The proposed change provides for the implementation of a slow-start testing sequence for the standby Diesel Generators (DGs) on a monthly frequency in order to reduce stress and wear on the equipment. The DGs will continue to receive a fast-start test on a 184 day frequency. The NRC has previously approved similar Technical Specification Amendments for other nuclear power plants, including River Bend Unit 1 and Hope Creek Unit 1.
The proposed change has been evaluated in accordance with 10CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that this change involves no significant hazards considerations. The bases for these determinations are included in the attached submittal.
There are no commitments associated with this license amendment request.
GNRO-2008/00013 Page 2 Although this request is neither exigent nor emergent, your prompt review is requested upon receipt since the change is seen as an improvement in the long-term reliability of the Diesel Generators. Plant modifications necessary to accomplish the slow-starting sequence for the Division 1 and 2 Diesel Generators are planned to be completed during the next scheduled refueling outage during (RF16) which is scheduled to start in September of 2008. Once approved, the amendment shall be implemented post outage and after approval.
If you have any questions or require additional information, please contact Michael Larson at 601-437-6685.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September 11, 2008 Sincerely, MAKlMJL/amm Attachments: 1. Analysis of Proposed Technical Specification Change
- 2. Proposed Technical Specification Changes (mark-up)
- 3. Proposed Technical Specification Bases (mark-up)
CC: Mr. Elmo Collins Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. Jack N. Donohew, Jr., NRR/APRO/DORL (w/2)
ATTN: ADDRESSEE ONLY ATIN: U.S. Postal Delivery Address Only Mail Stop OWFN/O-8G 14 Washington, D.C. 20555-0001 Dr. Ed Thompson, MD, MPH Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment 1 GNRO-2008/00013 Analysis of Proposed Technical Specification Change to GNRO-2008/00013 Page 1 of 4
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS).
2.0 PROPOSED CHANGE
The proposed change will revise Technical Specification (TS) Surveillance Requirements (SR) for Limiting Condition for Operation (LCO) 3.8.1 and 3.8.2 and add a new SR to TS LCO 3.8.1 to require monthly Diesel Generator (DG) testing by idling and gradually accelerating each DG to operating speed. The actual time to reach stable conditions will be determined in post-modification testing. The purpose of the change to a monthly slow start test mode is to reduce stress and wear on the equipment. The proposed changes are as follows:
- 1. SR 3.8.1.2 would be revised to eliminate the start time requirements. Additionally, two Notes would be added to the revised SR 3.8.1.2. Note 1 will indicate that performance of the new SR 3.8.1.21 (which will be identical to the original SR 3.8.1.2 with the exception of a 184 day Frequency and which is more restrictive than revised SR 3.8.1.2) would satisfy the requirements of the revised SR 3.8.1.2. The second, added as Note 3, will clarify that if modified procedures, which result in gradual acceleration to synchronous speed are not used, then the start time requirements of the new SR 3.8.1.21 would apply.
- 2. Change to SR 3.8.1.3 is an editorial change to reflect the addition of the new SR 3.8.1.21, i.e., that SR 3.8.1.2 or SR 3.8.1.21 may be used to start the DG for the purposes of performing SR 3.8.1.3.
- 3. New SR 3.8.1.21 is being added. New SR 3.8.1.21 is identical to original SR 3.8.1.2 with the exception of the new Frequency of 184 days.
- 4. Editorial changes to SR 3.8.2.1 are being made to reflect the addition of the new SR 3.8.1.21.
The TS surveillances which require verification of a fast start on an 18 month frequency are not affected by the proposed changes. In addition, a new surveillance is added to test the fast start on a 184 day frequency. Therefore, the ability of the DGs to achieve the start times assumed in the accident analyses will continue to be periodically verified.
3.0 BACKGROUND
At GGNS, the existing Division 1 and 2 DG governors are being replaced with a model that will accelerate the engines to operating speed within a range of approximately 15 to 40 seconds in the test mode. This is considered a slow start for these DGs which are designed to start in less than 10 seconds and typically start in less than 8 seconds. The Technical Specification Surveillance Requirements and accompanying Notes indicate that the fast start shall be utilized if slow start procedures are not employed.
At this time, there are no specific plans for making changes to the operation of Division 3 HPCS (High Pressure Core Spray) DG which is manufactured by a different vendor than Division 1 and 2 DGs. However, this licensing amendment has been developed to accommodate slow starting of all three DGs if the slow start capability is available. The Technical Specification Surveillance Requirements and accompanying Notes indicate that the fast start shall be utilized if slow start procedures are not employed.
to GNRO 2008-00013 Page 2 of 4
4.0 TECHNICAL ANALYSIS
As stated above, the Division 1 and Division 2 DG governors are being replaced with a model that has design provisions to allow the engines to be slowly accelerated to operating speed within a range of approximately 15 to 40 seconds in the test mode. When the DGs are in standby for emergency operation, they will continue to fast start in accordance with their emergency function. This is consistent with the NUREG 1434, "Standard Technical Specifications'General Electric Plants, BWR/6" and Regulatory Guide (RG) 1.9, Revision 3.
Paragraph 2.2.1, "Start Test", of RG 1.9, Revision 3, states that for these tests the emergency diesel generator can be slow started and reach rated speed on a prescribed schedule that is selected to minimize stress and wear. GGNS complies with Revisions 2 and 3 of RG 1.9 as detailed in GGNS UFSAR 8.3.1.2.1 "Compliance".
NRC sponsored aging research work on nuclear service diesel generators, documented in NUREG/CR-5057, "Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators," has identified fast starting and fast loading tests of DGs as an aging stressor.
Section 2.4.1 of this report states that a correctly managed monthly testing program involving slow starting and loading would induce little aging effects in the emergency DG. By contrast, a fast starting and loading test program can produce substantial harm and significant aging effects through the production of large mechanical and thermal stresses, inadequate lubrication during initial acceleration, high rotating and sliding pressures, and overspeeding. The slow start is also consistent with recommendations of ASME/ANSI Operations and Maintenance Standards and Guides Part 16. (Note that NUREG-1366 states a concern that this feature may be incorporated at the cost of reducing DG reliability by eliminating a redundant overspeed protection in the form of the backup mechanical governor. At GGNS, the backup mechanical governor will remain in service during the slow start.)
The governors for the Division 1 and 2 DGs are scheduled to be replaced during the Fall 2008 refueling outage (RF16) scheduled to begin in September 2008. Routine monthly testing on the DGs will consist of fast starts until such time as the governors are replaced and the License Amendment is issued.
5.0 REGULATORY ANALYSIS
5.1 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. The change will maintain compliance with 10 CFR 50 Appendix A, General Design Criteria (GDC) 17 and 18. Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and does not affect conformance with any GDC described in the Updated Final Safety Analysis Report (UFSAR).
to GNRO 2008-00013 Page 3 of 4 5.2 No Significant Hazards Considerations Entergy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment", as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change affects the surveillance requirements for the Diesel Generators (DGs). The DGs are onsite standby power sources intended to provide redundant and reliable power to ESF systems credited as accident mitigating features in design basis analyses. Per NRC Regulatory Guide (RG) 1.9, Revision 3, which is referenced in Grand Gulf Nuclear Station (GGNS) UFSAR 8.3.1.2.1, the proposed change is intended to allow slower starts of the DGs during testing in order to reduce DG aging effects due to excessive testing conditions. As such, the proposed change will result in improved DG reliability and availability, thereby providing additional assurance that the DGs will be capable of performing their safety function. The method of starting the emergency diesel generators for testing purposes does not affect the probability of any previously evaluated accident. Although the change allows slower starts for the monthly tests, the more rapid start function, assumed in the accident analysis, is unchanged and will be verified on a 184 day frequency. Therefore the accident analysis consequences are not affected.
Therefore, the proposed change does not involve a significant increase in the probability of consequences of any accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change affects the surveillance requirements for the onsite ac sources, i.e. the Diesel Generators. Accordingly, the proposed change does not involve any change to the configuration or method of operation of any plant equipment that could cause an accident. In addition, no new failure modes have been created nor has any new limiting failure been introduced as a result of the proposed surveillance changes.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
to GNRO 2008-00013 Page 4 of 4
- 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change is intended to bring the existing GGNS TS requirements for the onsite AC sources in line with regulatory guidance. Under the proposed change, the DGs will remain cap'able of performing their safety function, and the effects of aging on the DGs will be reduced by eliminating unnecessary testing. The DG start times assumed in the current accident analyses are unchanged and will be verified on a 184 day frequency.
Therefore, the proposed change does not involve a significant reduction in the margin of safety.
Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22 (b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
6.0 PRECEDENCE There is precedence for requesting the proposed amendment to allow slow start testing of the emergency Diesel Generators. Refer to the approved amendment packages provided below.
The proposed change is consistent with NUREG 1434, "Standard Technical Specifications General Electric Plants, BWR/6" and Generic Letter 84-15, "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability." The proposed amendment is based on Regulatory Guide 1.9, Revision 3, "Selection, Design, Qualification, And Testing Of Emergency Diesel Generating Units Used As Class 1E Onsite Electric Power Systems At Nuclear Power Plants".
7.0 REFERENCES
- 1. River Bend Station, Unit 1, Issuance of Amendment No. 121 to Facility Operating License No. NPF-47 by USNRC in letter to Randall K. Edington dated September 27, 2001 (TAC No. MB1117).
- 2. Hope Creek Generating Station, Unit 1, Issuance of Amendment No. 144 to Facility Operating License No. NPF-57 by USNRC in letter to Harold W. Keiser dated March 17, 2003 (TAC No. MB6084).
Attachment 2 GNRO*2008/00013 Proposed Technical Specification Change (mark-up)
Attachment 2 to GNRO 2008-00013 Page 1 017 (b) SERl is required to notify the NRC in writing prior to any change in (i) the terms or conditions of any new or existing sale or lease agreements executed as part of the above authorized financial transactions, (ii) the GGNS Unit 1 operating agreement, (iii) the existing property insurance coverage for GGNS Unit 1 that would materially alter the representations and conditions set forth in the Staff's Safety Evaluation Report dated December 19 1988 attached to Amendment No. 54.
1 In addition, SERI is required to notify the NRC of any action by a lessor or other successor in interest to SERl that may have an effect on the operation of the facility.
C. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10CFR Chapter I and is subject to all applicable provisions of the Act and to the ruies l regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(l) Maximum Power Level Entergy Operations Inc. is authorized to operate l
the facility at reactor cor.e power levels not in excess of 3898 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
Insert New (2) Technical Specifications Amendment No.
The Technical Specifications contained in Appendi and the 'ironmental Protection Plan contained Appendix as revised through Amendment No. ~ are hereby incorporated into this license. Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveilla~ce Requirements (SRs) for Diesel Generator 12 contained in the Technical Specifications and listed below, are not required to be performed immediately upon implementation of Amendment No. 1il The SRs listed below shall be successfully demonstrated at the next regularly scheduled performance.
SR 3.8.1.9, SR 3.8.1.10, and SR 3.8.1.14 Amendmen t 177 4
Attachment 2 to GNRO 2008-00013 Page 2 of 7 AC Sou rees - Opel" at i ng 3.8.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. Three or more requi red H.1 Enter LCD 3.0.3. Immediately AC sources inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability tor each requi red offsite circuit.
SR 3.8.1.2 -.------~----------NOTE-------------------*
All DG starts may be preceded by an englne
- I .... --1INSERT I prelube peri od and followed by a warmup period prior to loading.
-~---------------~-----~------~------------
Verify each DG starts from standby 31 days conditions and achieve 1
IDELETE ~~ if! ~ 10 SeCeI98S, velta§ ~ 3744 \I i aflG fl eqt:\efley <2 58.8 liz, 8nd
-~. ;IsteadY state voltage, 3744 V and ~
~, 4576 V and frequency 2 58.8 Hz and :s: 61.2 Hz.
(continued)
GRAND GULF 3.8-5 Amendment No. +34, 142
Attachment 2 to GNRO 2008-00013 Page 3 of 7 INSERT for TS 3.8.1 (SR 3.8.1.2)
N 0 TES-------------------------------------
- 1. Performance of SR 3.8.1.21 satisfies this SR.
- 2. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
- 3. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.21 must be met.
Attachment 2 to GNRO 2008-00013 Page 4 of7 AC Sources -Operat i 09 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1. 3 -------------------NOTES-------------------
- 1. OS loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not inva1idate this test.
- 3. This Surveillance shall be conducted on only one DG at a time.
- 4. This SR shall be preceded by, and immediately follow t without shutdown, a succe'ssful oerformance of ~I-I I ADD I
_____ ~~_~:~:~:~j.JorSR 38.1. 21 1... __
I Delete"." I Verify each DG operates for ~ 60 minutes 31 days at a load e!:: 5450 kW and s 5740 kW for DG 11 and OG 12, and e!:: 3300 kW for DG 13.
SR 3.8.1.4 Verify each OG day tank contains ~ 220 gal 31 days of fuel oil.
SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank.
SR 3.8.1.6 Verify the fuel oil transfer system 31 days operates to automatically transfer fuel oil from the storage tank to the day tank.
SR 3.8.1. 7 Verify the load shedding and sequencing 31 days panels respond within design criteria.
(continued)
GRANO GULF 3.8-6 Amendment No. ~t 134
Attachment 2 to GNRO 2008-00013 Page 5 of7 AC Sources - Operati ng 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY*
SR 3.8.1.20 -------------------NOTE--------------------
All DG starts may be preceded by an engine prelube period.
Verify, when started simultaneously from 10 years standby condition, each DG achieves:
- a. in:>: 10 seconds, vol tage z 3744 V and frequency z 58.8 Hz; and
- b. steady state voltage ~ 3744 V and s 4576 V and frequency z 58.8 Hz and s 61. 2 Hz.
SR 3.8. 1.21 GRAND GULF 3.8-16 Amendment No. ~, 142
Attachment 2 te GNRO 2008-00013 Page 6 of 7 INSERT for TS 3.8.1 (SR 3.8.1.21)
SR 3.8. 1.21 --------------------------------N aTE-----------------------------------
All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
Verify each DG starts from standby conditions and achieves: 184 days
- a. in S 10 seconds, voltage ~ 3744 V and frequency ~ 58.8 Hz; and
- b. steady state voltage ~ 3744 V and S 4576 V and frequency ~ 58.8 Hz and S 61.2 Hz.
Attachment 2 to GNRO 2008-00013 Page 7 of 7 AC Sources-Shutdown 3.8.2 SURVE1LLANCE REOUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -_**_*_*_-_*_-*-~--NOTES-------_* __ *_------
- 1. The following SRs are not required to be performed: SR 3.8.1.3. SR 3.8.1.9 through SR 3.8.1.11. SR 3.8.1.13 through SR 3.8.1.16, SR 3.8.1.18, and SR 3.8.1.19.
- 2. SR 3.8.1.12 and SR 3.8.1.19 are not required to be met when the associated ECCS subsystemCs) are not required to be OPERABLE per LeO 3.5.2, "EGeS -
Shutdown."
For AC sources reqUired to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.8.1.1 SR 3.8.1.7 SR 3.8.1.14 SR 3.8. 1. 2 SR 3.8.1.9 SR 3.8.1.15 SR 3.8.1.3 SR 3.8.1.10 SR 3.8.1.16 SR 3.8.1. 4 SR 3.8.1.11 SR 3.8.1.18 SR 3.8.1. 5 SR 3.8.1.12 SR 3.8.1.19 SR 3.8.1.6 SR 3.8.1.13 ISR 3. 8. 1. 21 I GRAND GULF 3.8-21 Amendment No. ~, ~
Attachment 3 GNRO-2008/00013 Technical Specification Bases Changes (mark-up)
Attachment 3 to GNRO 2008-00013 Page 1 of 4 AC Sources - Operati ng B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2IandSR 3.8.1.21 ~
REQUIREMENTS (continued) ~ helps to ensure the availability of the standby electrical power supply to mitigate DBAs and transients and REPLACE WITH: maintain the unit in a safe shutdown condition. ~------------~
These REPLACE WITH:
wea r on mavi n9 pa rts that do not get These SRs have been the engine is not running, iRis SR is ADD: s a.:ll"1'HH'o" to indicate that all DG starts for~
may be preceded by an engine prelube period and REPLACE WITH: a warmup period prior to loading. ~--~----~
REPLACE WITH:
Notes (the Note for SR 3.8.1.21 these and Note 2 for SR 3.8.1.2) purposes of this testing. the DGs are started from standby conditions. Standby conditions for a DG mean that ~--------~
the diesel engine coolant and oil are be4ng continuously ADD: s circulated and temperature is being maintained consistent with manufacturer recommendations for DG 11 and DG 12. For DG 13, standby conditions mean that the lube oil is heated by the jacket water and continuously circulated through a portion of the system as recommended by the vendor.. Engine
. jacket water ; s heated by an immersi on heater and ci rcul ates L...-I_N_S_ER_T_A--J.~ through the system by natural ci reul ati on. ADD at a 184 day frequency,
- r IREPLACE WITH: 21 I SR ~ requi res that the DG starts from standby I conditions and achieves required voltage and frequency within 10 seconds. The DG's ability to maintain the required voltage and frequency is tested by those SRs which require DG loading~ The 10 second start requirement ADD: The start requirements supports the assumptions in the design basis LDCA analysis may not be applicable to (Ket. 5). In addi t i on to the SR requi rements, the ti me* for (INSERT B) the DG to reach steady state operation is periqdically .
monitored (data is taken ~ lQ~s~ceper 6 months during the performance of SR 3.8.1.~ and the trend evaluated to identify degradation of governo and voltage regulator performance.
IREPLACE WITH: 21 The DGs are started for this test by using one of the followi~g signals: manual. simulated loss of offsite power by itself, simulated loss of offsite power in conjunction with an ESF actuation test signal, or an ESF actuation test signal by itself.
(continued)
GRAND GULF B 3.8-15 LDC 99050
Attachment 3 to GNRO 2008-00013 Page 2 of 4 INSERT "A" for Bases 3.8.1 (SR 3.8.1.2 and SR 3.8.1.21)
In order to reduce stress and wear on diesel engines, the manufacturer recommends that the DGs be gradually accelerated to synchronous speed prior to loading. These modified start procedures are the intent of Note 3 of SR 3.8.1.2, which is only applicable when such procedures are used.
INSERT "B" for Basis 3.8.1 (SR 3.8.1.2 and SR 3.8.1.21 (continued))
3.8.1.2 (see Note 3 of SR 3.8.1.2), when a modified start procedure as described above is used. If a modified start is not used, the start requirements of SR 3.8.1.21 apply. Since SR 3.8.1.21 does require a 10 second start for each DG, it is more restrictive than SR 3.8.1.2, and it may be performed in lieu of SR 3.8.1.2. This is the intent of Note 1 of SR 3.8.1.2.
Similarly, the performance of SR 3.8.1.12 or SR 3.8.1.19 also satisfies the requirements of SR 3.8.1.2 and SR 3.8.1.21.
Attachment 3 to GNRO 2008-00013 Page 3 of 4
/i.e Sources - Operati ng B 3.8.1 ADD: and SR 3. 8.1.21 BASES REPLACE WITH:
SURV EI LLANCE SR 3.8.1.2 These Frequencies REQUIREMENTS The 31 day Frequency for SR 3.8.1.2 is consistent with the ADD: The 184 day frequency for industry guidelines for assessment of diesel generator SR 3. 8. 1. 21 is a reduction in performance (Ref. 14)~ This ~PQ~WeAGY provides adequate cold testing consistent with assurance of DG OPERABILITY, while minimizing degradation Generic Letter 84-15 (Ref. 7) resulting from testing.
SR 3.8.1.3 This Surveillance demonstrates that the DGs are capable of synchronizing and accepting greater than or equal to the equivalent of the maximum expected accident loads. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the DG is connected to the offsite source.
(continued).
GRAND GULF B 3.8-15a LOC 99050
Attachment 3 to GNRO 2008-00013 Page 4 of 4 AC Sources - Operati ng B 3.8.1 BASES SURVEILLANCE SR 3.8.1.20 (continued)
REQUIREMENTS This surveillance is performed when the unit is shut down and its 10 year Frequency is consistent with the recommendations of Regulatory Guide 1.9 (Ref. 3).
This SR is modified by a Note. The reason for the Note is to minimize wear on the DG during testing. For the purpose of this testing, the DGs must be started from standby conditions, that is, with the engine coolant and oil continuously circulated and temperature maintained consistent with manufacturer recommendations for DG 11 and DG 12. For DG 13, standby conditions mean that the lube oil is heated by the jacket water and continuously circulated through a portion of the system as recommended by the vendor. Engine jacket water ;s heated by an immersion heater and circulates through the system by natural circulation.
ADD:
(See SR 3. 8.1.2)
(continued)
GRAND GULF B 3.8-33 LOC 02003