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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:Technical Specification
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 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 ML20134H9592020-05-12012 May 2020 Technical Specification Bases 3.10 ML20134H8802020-05-12012 May 2020 Technical Specification Bases 3.1 ML20134H8672020-05-12012 May 2020 Technical Specification Bases 2.0 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 ML20134H8772020-05-12012 May 2020 Technical Specification Bases 3.0 ML20134H8872020-05-12012 May 2020 Technical Specification Bases 3.2 ML20134H9372020-05-12012 May 2020 Technical Specification Bases 3.6 ML20134H8892020-05-12012 May 2020 Technical Specification Bases 3.3 ML20134H9312020-05-12012 May 2020 Technical Specification Bases 3.4 ML20134H9352020-05-12012 May 2020 Technical Specification Bases 3.5 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 GNRO-2008/00049, Supplemental No. 2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-4482008-09-0202 September 2008 Supplemental No. 2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-448 2023-07-27
[Table view] Category:Bases Change
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 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 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 ML21105A0522021-04-15015 April 2021 EAL Technical Bases Document 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 ML20134H8892020-05-12012 May 2020 Technical Specification Bases 3.3 ML20134H9312020-05-12012 May 2020 Technical Specification Bases 3.4 ML20134H8872020-05-12012 May 2020 Technical Specification Bases 3.2 ML20134H8772020-05-12012 May 2020 Technical Specification Bases 3.0 ML20134H8672020-05-12012 May 2020 Technical Specification Bases 2.0 ML20134H9352020-05-12012 May 2020 Technical Specification Bases 3.5 ML20134H9372020-05-12012 May 2020 Technical Specification Bases 3.6 ML20134H9502020-05-12012 May 2020 Technical Specification Bases 3.7 ML20134H9532020-05-12012 May 2020 Technical Specification Bases 3.8 ML20134H9562020-05-12012 May 2020 Technical Specification Bases 3.9 ML20134H9592020-05-12012 May 2020 Technical Specification Bases 3.10 ML20134H8802020-05-12012 May 2020 Technical Specification Bases 3.1 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-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-2015/00020, 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 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 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-2009/00028, 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-2008/00049, Supplemental No. 2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-4482008-09-0202 September 2008 Supplemental No. 2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-448 GNRO-2008/00025, Technical Specification Bases Update to the NRC for Period Dated March 5, 20082008-03-0505 March 2008 Technical Specification Bases Update to the NRC for Period Dated March 5, 2008 GNRO-2007/00073, Technical Specification Bases Update to the NRC for Period Dated December 03, 20072007-12-0303 December 2007 Technical Specification Bases Update to the NRC for Period Dated December 03, 2007 GNRO-2007/00049, Technical Specification Bases Update to the NRC for Period Dated July 25, 20072007-07-25025 July 2007 Technical Specification Bases Update to the NRC for Period Dated July 25, 2007 GNRO-2007/00043, Technical Specification Bases Update to the NRC for Period Dated June 13, 20072007-06-13013 June 2007 Technical Specification Bases Update to the NRC for Period Dated June 13, 2007 GNRO-2007/00021, Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 20072007-04-11011 April 2007 Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 2007 GNRO-2007/00019, Technical Specification Bases Update to the NRC for Period Dated March 30, 20072007-03-30030 March 2007 Technical Specification Bases Update to the NRC for Period Dated March 30, 2007 GNRO-2006/00054, Technical Specification Bases Update to the NRC for Period Dated September 28, 20062006-09-28028 September 2006 Technical Specification Bases Update to the NRC for Period Dated September 28, 2006 GNRO-2006/00030, Technical Specification Bases Update to the NRC for Period Dated February 16, 20062006-05-15015 May 2006 Technical Specification Bases Update to the NRC for Period Dated February 16, 2006 GNRO-2006/00008, Technical Specification Bases Update to the NRC for Period Dated February 16, 20062006-02-16016 February 2006 Technical Specification Bases Update to the NRC for Period Dated February 16, 2006 GNRO-2006/00003, Technical Requirements Manual Update to the NRC for Period Dated January 17, 20062006-01-17017 January 2006 Technical Requirements Manual Update to the NRC for Period Dated January 17, 2006 2023-07-27
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ter Waterloo Road P.0. BOX756 Port Gibson, Ails 39150 Tel 601 4376299 rles er Manager Plant Licensing September 12, 2002 U.S. Nuclear Regulatory Commission Washington, D,C. 20555 Attention: Document Control Desk
Subject:
Technical Specification Bases Update to the NRC for Period Dated September 12, 2002 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2002/00083 Ladies and Gentlemen:
Pursuant to Grand Gulf Nuclear Station (GGNS) Technical Specification 5.5.11, Entergy Operations, Inc. hereby submits an update of all changes made to GGNS Technical Specification Bases since the last submittal (GNRO-2002/00064 letter dated July 23, 2002 to the NRC from GGNS). This update is consistent with update frequency listed in 10CFR50.71(e).
This letter does not contain any commitments.
Should you have any questions, please contact James Owens at (601) 437-6219.
Yours truly, JEO/jeo attachment: GGNS Technical Specification Bases Revised Pages cc: (See Next Page)
September 12,2002 GNRO-2002/00083 PAGE 2 of 2 Hoeg T. L. (GGNS Senior Resident) (w/a)
Levanway D. E. (Wise Carter) (w/a)
ReynoIds N. S. (w/a)
Smith L.-J. (Wise Carter) (w/a)
Thomas
~-~ H. L. (w/o)
U.S. Nuclear Regulatory Commission ALL LETTERS ATTN: Mr. E. W. Merschoff (w/2) 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 7601 1-4005 U.S. Nuclear Regulatory Commission ALL LETTERS - COURIER ATTN: Mr. David H. Jaffe, NRR/DLPM (w/2) DELIVERY (FEDEX, ETC.)
ATTN: ADDRESSEE ONLY ADDRESS ONLY - ***
ATTN: Courier Delivery Only Mail Stop OWFN/7D-1 11555 Rockville Pike Rockville, MD 20852-2378 I
ATTACHMENT to GNRO-2002100083 GGNS Gulf Technical Specification Bases Revised Pages dated September 12,2002 LDC# BASES PAGES AFFECTED TOPIC of CHANGE 02006 B 3.6-64,65, and 65a; B Implementation of Technical Specification Amendment 3.10-38, 39,40,41,42, 154 -Reactor Cavity Pool Draindown
SPMU System B 3.6.2.4 BASES SURVEILLANCE SR 3.6.2.4.2 REQUIREMENTS
( c o n t i nued 1 The upper containment pool water temperature i s r e g u l a r l y monitored t o ensure t h a t t h e r e q u i r e d l i m i t i s s a t i s f i e d .
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency was developed based on operating experience r e l a t e d t o upper containment pool temperature v a r i a t i o n s during t h e appl i cab1 e MODES.
SR 3.6.2.4.3 Verifying t h e c o r r e c t alignment f o r manual, power o p e r a t e d ,
a n d automatic valves i n t h e SPMU System flow p a t h provides assurance t h a t t h e proper flow p a t h s w i l l e x i s t f o r system o p e r a t i o n . This SR does n o t apply t o valves t h a t a r e 1 ocked, seal ed, or otherwi s e secured i n posi t i on, s i n c e t h e s e valves a r e v e r i f i e d t o be i n t h e c o r r e c t p o s i t i o n p r i o r t o being locked, s e a l e d , or s e c u r e d , This SR does n o t r e q u i r e any t e s t i n g or valve manipulation. Rather, i t i n v o l ves v e r i f i c a t i o n t h a t t h o s e V a l ves capabl e of p o t e n t i a1 l y being m i sposi t i oned a r e i n t h e c o r r e c t posi t i o n .
This SR does n o t a p p l y t o valves t h a t cannot be i n a d v e r t e n t l y misaligned, such as check v a l v e s .
The Frequency of 31 days i s j u s t i f i e d because t h e valves a r e operated under procedural control a n d because improper valve p o s i t i o n w o u l d a f f e c t only a s i n g l e subsystem. This Frequency has been shown t o be a c c e p t a b l e through o p e r a t i n g experience.
SR 3.6.2.4.4 The upper containment p o o l has two g a t e s used t o s e p a r a t e t h e p o o l i n t o d i s t i n c t s e c t i o n s t o f a c i l i t a t e fuel t r a n s f e r a n d maintenance during r e f u e l i n g o p e r a t i o n s a n d two a d d i t i o n a l g a t e s i n t h e s e p a r a t o r pool weir wall e x t e n s i o n ,
which, when i n s t a l l e d , l i m i t personnel exposure a n d ensure adequate water submergence of t h e s e p a r a t o r when t h e s e p a r a t o r i s s t o r e d i n t h e p o o l . The SPMU System dump l i n e p e n e t r a t i o n s a r e l o c a t e d i n t h e steam s e p a r a t o r s t o r a g e s e c t i o n of t h e pool. To provide t h e required SPMU System dump volume t o t h e suppression p o o l , t h e g a t e s must be removed ( o r placed i n t h e i r s t o r e d p o s i t i o n ) t o allow communi c a t i on between t h e vari ous pool s e c t i o n s . The S u r v e i l l a n c e i s modified by a Note t h a t allows leaving I GRAND G U L F B 3.6-64 LDC 02006
S P M U System B 3.6.2.4 BASES SURVEILLANCE SR 3.6.2.4.4 (continued)
REQUIREMENTS t h e g a t e s i n s t a l l e d i f t h e Suppression Pool Low Level l i m i t i s i n c r e a s e d t o 18 f t 5 1/12 i n c h e s . (See Reference 3 ) .
The 31 d a y Frequency i s a p p r o p r i a t e because t h e g a t e s a r e moved under procedural c o n t r o l a n d o n l y t h e i n f r e q u e n t movement of t h e s e g a t e s i s required i n MODES 1, 2 , a n d 3 .
The provision t o allow g a t e i n s t a l l a t i o n i n MODES 1, 2 , a n d 3 r e s u l t s i n i s o l a t i n g a portion of t h e SPMU System dump volume. This p r o v i s i o n does n o t a p p l y t o t h e s e p a r a t o r pool weir wall extension g a t e s . These g a t e s a r e n o t r e a d i l y a c c e s s i b l e w i t h t h e upper containment pool a t i t s r e q u i r e d l e v e l . Supporting a n a l y s e s have shown t h a t i n c r e a s i n g t h e minimum suppression pool l e v e l adequately compensates f o r water trapped by i s o l a t i n g t h e f u e l s t o r a g e and/or f u e l t r a n s f e r canal a r e a s .
SR 3.6.2.4.5 This SR r e q u i r e s a v e r i f i c a t i o n t h a t each SPMU subsystem automatic valve a c t u a t e s t o i t s c o r r e c t p o s i t i o n on r e c e i p t of a n a c t u a l o r simulated automatic i n i t i a t i o n s i g n a l . This i ncl udes v e r i f i c a t i o n of t h e c o r r e c t automati c p o s i t i o n i n g of t h e valves a n d of t h e o p e r a t i o n of each i n t e r l o c k a n d t i m e r . As noted, a c t u a l makeup t o t h e suppression pool may be excluded. The L O G I C SYSTEM FUNCTIONAL TEST i n SR 3 . 3 . 6 . 4 . 6 o v e r l a p s t h i s SR t o provide complete t e s t i n g of t h e s a f e t y f u n c t i o n . The 18 m o n t h Frequency i s based on t h e need t o perform t h i s S u r v e i l l a n c e under t h e c o n d i t i o n s t h a t a p p l y during a p l a n t outage a n d t h e p o t e n t i a l f o r a n u n p l anned t r a n s i e n t i f t h e Survei 1 1 ance were performed w i t h t h e r e a c t o r a t power. Operating experience has shown t h a t t h e s e components u s u a l l y pass t h e S u r v e i l l a n c e when performed a t t h e 18 m o n t h Frequency. T h e r e f o r e , t h e Frequency was concluded t o be a c c e p t a b l e from a r e l i a b i l i t y standpoint.
This SR i s modified by a NOTE t h a t excludes makeup t o t h e suppression pool . Since a1 1 a c t i v e components a r e t e s t a b l e ,
makeup t o t h e suppression p o o l i s n o t r e q u i r e d .
(continued)
GRAND G U L F B 3.6-65 LDC 02006
SPMU System B 3.6.2.4 BASES (continued)
REFERENCES 1. UFSAR, S e c t i o n 6 . 2 .
- 2. UFSAR, C h a p t e r 1 5 .
- 3. GNRO-2002/00011.
GRAND GULF B 3.6-65a LDG 02006 I
THIS PAGE INTENTIONALLY LEFT BLANK Suppression Pool Makeup-MODE 3 3.10.9 I B 3.10 S P E C I A L OPERATIONS B 3.10.9 S u p p r e s s i o n Pool Makeup System BASES BACKGROUND M a i n t a i n i n g t h e SPMU i n v e n t o r y i n t h e Upper Containment Pools w i l l l e a d t o d e l a y s i n completing outage work i n a t i m e l y manner, p a r t i c u l a r l y w i t h t h e advent of t h i n g s l i k e Noble Metal a d d i t i o n technology h a s l e d t o t h e need f o r h o l d i n g t e m p e r a t u r e a n d p r e s s u r e a t a p o i n t above t h e MODE 4 d e f i n i t i o n of Table 1.1-1.
The purpose of t h i s S p e c i a l O p e r a t i o n s LCO i s t o allow t h e Upper C o n t a i n m e n t Pool t o be d r a i n e d below i t s normal l e v e l such t h a t c e r t a i n r e f u e l i n g a c t i v i t i e s can proceed p r i o r t o r e a c h i n g MODE 4 . These a c t i v i t i es i ncl ude i n s t a l 1 a t i on of t h e g a t e between t h e r e f u e l i n g c a v i t y a n d t h e upper containment ( f u e l s t o r a g e p o o l ) a n d completely d r a i n i n g t h e reactor cavity.
APPLICABLE S u p p o r t i n g a n a l y s e s a n d engi n e e r i n g c a l cul a t i o n s determi ned SAFETY ANALYSES t h e required water inventory t o ensure t h a t the suppression pool makeup f u n c t i o n i s s a t i s f i e d i f t h e s p e c i f i e d c o n d i t i o n s of t h i s S p e c i a l O p e r a t i o n s LCO a r e met.
S u p p o r t i n g a n a l y s e s d i f f e r from t h o s e f o r TS 3 . 6 . 2 . 4 i n t h a t a p o r t i o n of t h e SPMU volume i s assumed t o have a l r e a d y been t r a n s f e r r e d t o t h e s u p p r e s s i o n pool w i t h t h e remainder a v a i l a b l e from t h e s e p a r a t o r s t o r a g e pool p o r t i o n of t h e Upper C o n t a i n m e n t Pool. These a n a l y s e s d e m o n s t r a t e t h a t t h e c o n t a i nment s p r a y f u n c t i o n of R H R i s n o t requi red f o l 1 o w i n g a d e s i g n b a s i s LOCA t o p r o t e c t t h e containment given t h e reduced t e m p e r a t u r e a n d p r e s s u r e s t i p u l a t e d by t h e LCO. An empty r e a c t o r c a v i t y c r e a t e s a l a r g e hold-up volume t h a t woul d s i g n i f i c a n t l y d e p l e t e t h e s u p p r e s s i o n pool i nventory i f containment s p r a y o p e r a t i o n were t o o c c u r . The a n a l y s i s r e s u l t s demonstrate t h a t t h e containment p r e s s u r e i n c r e a s e f o l l o w i n g a DBA LOCA w i l l n o t be s u f f i c i e n t t o r e s u l t i n t h e a u t o - i n i t i a t i o n o f containment s p r a y .
I n a d d i t i o n t o t h e design b a s i s a n a l y s e s , drywell bypass c a p a b i l i t y a n a l y s e s ( R e f e r e n c e 1) i n d i c a t e t h a t containment p r e s s u r e could exceed t h e containment s p r a y a u t o - a c t u a t i o n s e t p o i n t . S t e a m bypass l e a k a g e a n d t h e a s s o c i a t e d c a p a b i l i t y a n a l y s e s a r e d i s c u s s e d i n Reference 4 . For t h e GRAND G U L F B 3.10-38 LDC 02006
Suppression Pool Makeup-MODE 3 3.10.9 BASES APPLICABLE most 1 imi t i n g 1 arge break bypass 1 eakage capabi 1 i t y analysi s SAFETY ANALYSES (Ref. 11, operator a c t i o n t o control reactor water level i s (continued) c r e d i t e d i n ensuring t h a t s u f f i c i e n t inventory i s avai 1 able f o r containment spray o p e r a t i o n .
The contai nment 1 oads eval uati on performed f o r t h i s speci a1 operati on i ncl udi n g t h e el evated suppression pool 1 evel s demonstrates t h a t a t t h e decay time a n d reactor pressure s p e c i f i e d by t h e LCO, t h e containment loads are bounded by those ca7culated f o r the DBA LOCA.
S p e c i f i c analyses demonstrate containment temperature a n d pressure as well as radiological consequences a r e bounded by those following l a r g e a n d small break LOCAs a t f u l l power conditions. The appl i cab1 e analyses supporting t h e LCO a r e contained in References 1 , 2 a n d 3 . During these events, the SPMU System i s r e l i e d upon t o dump the separator pool water t o m a i n t a i n drywell horizontal vent coverage a n d a n adequate suppression pool heat sink volume t o ensure t h a t the primary containment i n t e r n a l pressure a n d temperature stay within design l i m i t s .
As described in LCO 3 . 0 . 7 , compliance with t h i s Special Operations LCO i s o p t i o n a l , a n d t h e r e f o r e , no c r i t e r i a of the NRC Policy Statement apply. Speci a 1 Operations LCOs provide f l exi bi 1 i t y t o perform c e r t a i n operations by appropri ate1 y modifying requi rements of other LCOs. A discussion of t h e c r i t e r i a s a t i s f i e d f o r the other LCOs i s provided in t h e i r respective Bases.
LCO A s described in LCO 3 . 0 . 7 , compliance with t h i s Special Operations LCO i s o p t i o n a l . Operation with the Upper Containment Pool l e v e l s below those specified in SR 3 . 6 . 2 . 4 . 1 c a n be achieved by e x i t i n g t h e condition where L C O 3.6.2.4 a p p l i e s . Operation with elevated suppression pool l e v e l s i s a l s o optional as operation a t l e v e l s above those specified in LCO 3.6.2.2 can be achieved by e x i t i n g the condition where the LCO a p p l i e s .
Compl i ance wi t h the Fi gure 3.10.9 - 1 1 evel requi rements ensure t h a t t h e r e i s s u f f i c i e n t overlap with t h e requirements of L C O 3.6.2.2 a n d 3.6.2.4 such t h a t the volume in containment during t h e t r a n s i t i o n t o a drained r e f u e l i n g GRAND GULF B 3.10-39 LDC 02006
Suppression Pool Makeup-MODE 3 3.10.9 BASES LCO c a v i t y f u l f i 1 1 s t h e contai nment water i n v e n t o r y requi rements (continued) assumed i n t h e a n a l y s i s . Once t h e l e v e l of t h e weir wall s e p a r a t i n g t h e r e f u e l i n g c a v i t y from t h e s e p a r a t o r s t o r a g e pool i s reached, Figure 3.10.9-1 only a p p l i e s t o t h e s e p a r a t o r pool. Supporting analyses assume t h a t t h e weir wall g a t e s a r e n o t i n s t a l l e d .
Maintaining t h e f u e l s t o r a g e a n d t r a n s f e r canal area pools e n s u r e s t h a t water t r a p s i n s i d e containment a r e minimized consi s t e n t with t h e supporting analysi s .
The r e a c t o r subcri t i cal time, suppressi on p o o l average t e m p e r a t u r e , a n d r e a c t o r steam dome p r e s s u r e a r e assumptions of t h e supporting analyses.
Entry i n t o MODE 4 operation does n o t r e q u i r e t h e use of t h i s Special Operations LCO or i t s ACTIONS.
APPLICABILITY The MODE 3 requirements may o n l y be modified f o r allowing e a r l y drain-down of t h e Upper Containment Pool while performing Noble Metal a d d i t i o n or during a r e a c t o r cool down f o r a r e f u e l i n g outage. The requirements of t h i s LCO provide conservatism i n t h e response of t h e u n i t t o a n y event t h a t may occur. Operations i n a l l o t h e r MODES a r e unaffected by t h i s LCO.
ACTIONS A Note has been provided t o modify t h e ACTIONS r e l a t e d t o drain-down of Upper Containment Pools-MODE 3. Section 1 . 3 ,
Completion Times, s p e c i f i e s once a Condition has been e n t e r e d , subsequent d i v i s i o n s , subsystems, components, or v a r i a b l e s expressed i n t h e Condition discovered t o be i n o p e r a b l e or n o t within l i m i t s , will n o t r e s u l t i n s e p a r a t e e n t r y i n t o t h e Condition. Section 1 . 3 a l s o s p e c i f i e s t h a t Required Actions of t h e Condition c o n t i n u e t o apply f o r each a d d i t i o n a l f a i 1 u r e , with Completion Times based on i ni t i a 1 e n t r y i n t o t h e Condition. However, t h e Required Actions f o r each requirement of t h e LCO n o t met provide a p p r o p r i a t e compensatory measures f o r s e p a r a t e requirements t h a t a r e n o t met. As such, a Note has been provided t h a t allows s e p a r a t e e n t r y f o r each requirement of t h e LCO.
GRAND G U L F B 3.10-40 LDC 02006
Suppression Pool Makeup -'MODE 3 3.10.9 BASES ACTIONS -
A. 1 (continued)
With t h e requirements of t h e LCO n o t met ( e . g . , Upper Containment Pool l e v e l n o t w i t h i n l i m i t s ) , t h e d r a i n i n g of t h e Upper Containment Pool i s t o be suspended. Thereby, a worsening of t h e circumstances w i l l be prevented.
I f one or more of t h e requirements of t h i s Special Operations LCO a r e n o t met, t h e immediate implementation of t h e Requi red Action commences a c t i vi t i e s , which wi 11 r e s t o r e o p e r a t i o n consi s t e n t w i t h t h e Speci a1 Operations LCO. The Completion Time i s intended t o r e q u i r e t h a t t h e s e Required Actions be implemented i n a very s h o r t time a n d c a r r i e d through i n a n e x p e d i t i o u s manner.
Required Action A . 2 . 2 i s a n a l t e r n a t i v e Required Action t h a t can be taken i n s t e a d of Required Action A . 2 . 1 t o r e s t o r e compliance with t h e normal MODE 3 requirements, thereby e x i t i n g t h i s Speci a1 Operations LCOs Appl i cabi 1 i t y . The allowed Completion Time allows s u f f i c i e n t time t o r e e s t a b l i sh compl i ance with t h e appropri a t e Technical Specification.
B.2 I f t h e requirements of t h i s Special Operations LCO o r t h e normal MODE 3 requirements cannot be met within t h e required Completion Time, t h e p l a n t must be brought t o a MODE i n which t h e LCO does n o t a p p l y . The allowed Completion Time i s reasonable, based on o p e r a t i n g e x p e r i e n c e , t o reach t h e required p l a n t c o n d i t i o n s a n d i s c o n s i s t e n t with t h e time provided i n LCO 3 . 0 . 3 f o r reaching MODE 4 from MODE 3.
( c o n t i nued 1 GRAND GULF B 3.10-41 LDC 02006
Suppress! on Pool Makeup - MODE 3 3.10.9 BASES (continued)
SURVEILLANCE SR 3 . 1 0 . 9 . 1 a n d SR 3.10.9.2 REQUIREMENTS V e r i f i c a t i o n of t h e Suppressi o n Pool t e m p e r a t u r e a n d Steam Dome p r e s s u r e e n s u r e s t h a t a s s u m p t i o n s of t h e s u p p o r t i n g a n a l y s e s f o r t h i s Speci a1 Operations LCO a r e c o n t i n u a l l y met. T h e r e f o r e , t h e p l a n t response t o a n a c c i d e n t while i n t h i s Special Operations LCO w i l l remain bounded by t h e Design Basis Loss of Coolant Accident.
The Frequency of 1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i s based on e n g i n e e r i n g judgement a n d i s c o n s i d e r e d adequate due t o t h e u n l i k e l y e v e n t of unknowingly a d d i n g h e a t t o t h e Suppression Pool o r i n c r e a s i n g Reactor p r e s s u r e .
SR 3.10.9.3 V e r i f i c a t i o n of t h e requi red Upper Containment Pool a n d Suppression Pool l e v e l s t o be w i t h i n l i m i t s e n s u r e s t h a t t h e e n g i n e e r i n g assumptions f o r t h e c a l cul a t i o n s s u p p o r t i n g t h i s Special O p e r a t i o n s LCO a r e c o n t i n u a l l y met. These assumptions e n s u r e s u f f i c i e n t i n v e n t o r y i s a v a i l a b l e such t h a t Drywell v e n t submergence a n d Suppression Pool h e a t s i n k requi rements a r e met.
The Frequency of 1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i s based on e n g i n e e r i n g judgement a n d i s c o n s i d e r e d adequate i n view of t h e l a r g e volume of water a n d t h e normal procedural c o n t r o l s on v a l v e p o s i t i o n s ,
which make s i gni f i c a n t unpl anned 1 eve1 changes unl i kel y .
SR 3 . 1 0 . 9 . 4 V e r i f i c a t i o n of t h e r e q u i r e d Fuel S t o r a g e a n d T r a n s f e r Canal Pool l e v e l s t o be w i t h i n l i m i t s e n s u r e s t h a t t h e e n g i n e e r i n g assumptions f o r t h e c a l cul a t i o n s s u p p o r t i n g t h i s Speci a 1 Operations LCO a r e c o n t i n u a l l y met. These assumptions e n s u r e s u f f i c i e n t i n v e n t o r y i s a v a i l a b l e such t h a t Drywell v e n t submergence a n d Suppression Pool h e a t s i n k requirements a r e met.
The Frequency of 1 2 h o u r s i s based on e n g i n e e r i n g judgement a n d i s c o n s i d e r e d adequate i n view o f t h e l a r g e volume of water a n d t h e normal procedural c o n t r o l s on v a l v e p o s i t i o n s ,
which make s i g n i f i c a n t unplanned l e v e l changes u n l i k e l y .
( c o n t i nued GRAND GULF B 3.10-42 LDC 02006
S u p p r e s s i o n P o o l Makeup-MODE 3 3.10.9 BASES (continued)
REFERENCES 1. C a l c u l a t i on XC-QlM10-01012, MODE 3 C o n t a i n m e n t A n a l y s i s a t Reduced R e a c t o r P r e s s u r e .
- 2. C a l c u l a t i o n XC-QlE30-01004, S u p p r e s s i o n P o o l Makeup System - MODE 3 .
- 3. C a l c u l a t i o n XC-Q1111-01011, MODE 3 LOCA Dose A n a l y s i s .
- 4. UFSAR 6 . 2 . 1 . 1 . 5 .
GRAND GULF B 3.10-43 LDC 02006