Letter Sequence Supplement |
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TAC:MD6153, Control Room Habitability (Approved, Closed) |
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Category:Letter
MONTHYEARML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 “Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000416/20220042024-03-19019 March 2024 – Amended Integrated Inspection Report 05000416/2022004 and Exercise of Enforcement Discretion ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 2024-08-22
[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 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 2024-04-25
[Table view] Category:Bases Change
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 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 2024-04-25
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22073A1752022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications 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 ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21039A3292021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML21039A2642021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML17240A2322017-10-0404 October 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 213 for Administrative Name Change to Licensee South Mississippi Electric Power Association (CAC No. MF9588) ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing GNRO-2015/00091, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing/2015-12-10010 December 2015 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing/ GNRO-2015/00077, Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours.2015-11-24024 November 2015 Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours. 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 ML15180A1702015-08-31031 August 2015 Issuance of Amendment Revision to Technical Specification 5.65.B to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request ML15229A2132015-08-18018 August 2015 Redacted, Issuance of Amendment Regarding Technical Specification 2.1.1.2 of Technical Specification Section 2.1.1.2, Reactor SLs (Safety Limits) ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology GNRO-2015/00059, Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/20132015-08-14014 August 2015 Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013 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 ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 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 ML14311A4792014-12-12012 December 2014 Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date GNRO-2014/00068, License Amendment Request to Revise Technical Specification 2.1.1.22014-11-21021 November 2014 License Amendment Request to Revise Technical Specification 2.1.1.2 ML14162A3782014-09-25025 September 2014 Redacted, Issuance of Amendment No. 199, Delete Operating License Condition 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML14106A1332014-06-30030 June 2014 Issuance of Amendment No. 198, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, as Part of Consolidated Line Item Improvement Process ML13343A1092013-12-26026 December 2013 Issuance of Amendment No. 197, Revise Technical Specifications and Surveillance Requirements to Support Operation with 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications 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-2012/00124, Response to NRC Request for Additional Information - GGNS Criticality Safety Analysis License Amendment Request2012-10-22022 October 2012 Response to NRC Request for Additional Information - GGNS Criticality Safety Analysis License Amendment Request ML1207202832012-04-20020 April 2012 Issuance of Amendment No. 189, Revise Minimum Critical Power Ratio Safety Limit in Technical Specification 2.1.1.2 for Two-Loop and Single Recirculation Loop GNRO-2012/00014, Supplemental Information Pertaining to License Amendment Request for Standby Liquid Control System2012-03-21021 March 2012 Supplemental Information Pertaining to License Amendment Request for Standby Liquid Control System GNRO-2012/00001, License Amendment Request - Standby Liquid Control System2012-01-23023 January 2012 License Amendment Request - Standby Liquid Control System GNRO-2011/00064, License Amendment Request to Revise Technical Specification 2.1.1.22011-10-28028 October 2011 License Amendment Request to Revise Technical Specification 2.1.1.2 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. ML1026604032010-09-0808 September 2010 License Amendment Request Extended Power Uprate ML0931404632009-11-0303 November 2009 License Amendment Request Regarding Power Range Neutron Monitoring System Upgrade GNRO-2009/00042, Supplement to ENOC-09-00009, License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions, Letter Dated April 27, 20092009-07-10010 July 2009 Supplement to ENOC-09-00009, License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions, Letter Dated April 27, 2009 ML0909804292009-04-13013 April 2009 Correction to Amendment No. 182, Surveillance Requirements for Diesel Generator Slow - Start Testing (MD9641) ML0817600232008-10-14014 October 2008 Issuance of Amendment No. 178, Adoption of Technical Specifications Task Force (TSTF) Traveler No. 448, Revision 3, Control Room Envelope Habitability. 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 ML0724900082007-10-24024 October 2007 Technical Specifications, Issuance of Amendment No. 177 Changes to Technical Specifications Surveillance Requirement 3.3.1.1.7, the Local Power Range Monitor Calibration Frequency ML0734401152007-09-30030 September 2007 NEDC-33383, Revision 0, GEXL97 Correlation Applicable to ATRIUM-10 Fuel, (Non-Proprietary), Attachment 2 ML0721905072007-08-24024 August 2007 Tech Spec Pages for Amendment 176 Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices ML0712900082007-05-30030 May 2007 Technical Specifications, Issuance of Amendment 175 Re Technical Specifications Change Regarding Mode Change Limitations (TSTF-359) Using Consolidated Line Item Improvement Process, & Correct Example 1.4-1 (TSTF-485) ML0705306542007-03-16016 March 2007 Tech Spec Pages for Amendment No. 174 a Technical Specification Change to Allow Use of Control Rod Assemblies with Different Control Material GNRO-2007/00011, License Amendment Request, Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices2007-03-0101 March 2007 License Amendment Request, Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices 2023-12-14
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GNRO-2008/00049 September 02,2008 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
References:
Supplemental NO.2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-448 Grand Gulf Nuclear Station, Unit 1 Docket No.50-416 License No.NPF-29 1.GNRO-2007/00050
-Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability dated August 07, 2007 (ML072250092) 2.GNRO-2007/00040
-Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process, dated July 17, 2007 (ML072060522)
Dear Sir or Madam:
On July 17, 2007, Entergy Operations, Inc.filed an application to amend the operating license for Grand Gulf Nuclear Station, Unit 1 (GGNS)(above Reference).
The proposed amendment would modify the Technical Specification related to Control Room Envelope Habitability in accordance with TSTF-448, Revision 3 under the Consolidated Line Item Improvement Program.This letter provides supplemental information to clarify and correct certain items in the application at the request of NRC reviewers.
Attachment 1 revises the description and assessment on affected pages from the above referenced submittal.
The changes are noted with change bars in the right hand column.Attachment 2 provides certain replacement pages for the affected Technical Specification and Operating License Condition pages.Attachment 3 provides revised Technical Specification Bases pages.The proposed change has been evaluated in accordance with 1 OCFR50.91 (a)(1)using criteria in 10CFR50.92(c) and it has been determined that this change involves no significant hazards consideration.
The bases for these determinations are included in the attached submittal.
GNRO-2008/00049 Page 2 The proposed change does not include any new commitments.
If you have any questions or require additional information, please contact Michael J.Larson at 601-437-6685 or email mlarson@entergy.com.
I declare under penalty of perjury that the foregoing is true and correct.Executed on September 02, 2008.Sincerely, MAKlMJL/amm Attachments:
1.Description and Assessment (Markup)2.Technical Specification and Operating License Condition (Markup)3.Technical Specification Bases (Markup)NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 Dr.Ed Thompson, MD, MHA, MPH Mississippi Department of Health P.O.Box 1700 Jackson, MS 39215-1700 U.S.Nuclear Regulatory Commission ATTN: Mr.Elmo E.Collins (w/2)611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S.Nuclear Regulatory Commission ATTN: Mr.Jack N.Donohew, NRR/DORL (w/2)ATTN: ADDRESSEE ONLY ATTN: U.S.Postal Delivery Address Only Mail Stop OWFN/8 G14 Washington, DC 20555-0001 Attachment 1 GNRO-2008/00049 Description and Assessment (Markup)
Attachment 1 to GNRO-2008/00049 Page 1 of 6
1.0 DESCRIPTION
This letter is a supplement to a request to amend Operating License NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS).The proposed supplement to the proposed amendment would modify Technical Specification (TS)requirements related to control room envelope habitability in TS 3.7.3,"Control Room Fresh Air (CRFA)System" and TS Section 5.5,"ProgramsandManuals." The changes are consistent with the Nuclear Regulatory Commission (NRC)approved Industry/Technical Specification Task Force (TSTF)STS change TSTF-448 Revision 3.The availability of the TS improvement was published in the Federal Register on January 17, 2007 (FR 722022)as part of the Consolidated Line Item Improvement Process (CUIP).2.0 ASSESSMENT
2.1 Applicability
of Published Safety Evaluation Entergy has reviewed the safety evaluation dated January 17, 2007 as part of the CUIP.This review included a review of the NRC staff's evaluation, as well as the supporting information provided to support TSTF-448.Entergy has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC is applicable to GGNS and justify this amendment for the incorporation of the changes to the GGNS TS.2.2 Optional Changes and Variations Entergy is not proposing any significant variations or deviations from the TS changes described in the TSTF-448, Revision 3, or the applicable parts of the NRC staff's model safety evaluation dated January 17, 2007.Variation and deviations were previously discussed in the following letters: GNRO-2007/00050
-Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability dated August 07, 2007 GNRO-2007/00040
-License Amendment Request Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process, dated June 17, 2007 Submitted information in these letters is still valid to this supplement.
A NRC requested variation is requested to Technical Specification Section 5.5.13 and is discussed in Sections 2.4 and 3.2.2.3 License Condition Regarding Initial Performance of New Surveillance and Assessment Requirements Entergy proposes the following additional license condition to support implementation of the NRC proposed TS changes:
Attachment 1 to GNRO-2008/00049 Page 2 of 6 (c)The first performance of the periodic assessment of the CRE boundary, Specification 5.5.13.d, shall be within the next 18 months, plus the 136 days allowed by SR 3.0.2, as measured from the date of issuance of this amendment.
This additional license condition supplements license conditions previously submitted in the following letters: GNRO-2007/00050
-Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability dated August 07, 2007 GNRO-2007/00040
-License Amendment Request Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process, dated July 17, 2007 2.4 Revision of TS Surveillance 3.7.3.4 and TS 5.5.13 Entergy proposes the following revisions and additions to TS Surveillance (SR)R 3.7.3.4 and TS 5.5.13.Technical Specification Surveillance 3.7.3.4 is editorial revised to add the word"with" so that it states that the testing will be done"in accordance with the Control Room Envelope Habitability Program.The word"with" had been inadvertently left out of the SR and the change is made to comply with the wording specified in TSTF-448.Additionally a new paragraph"d" added to TS 5.5.13 to: (1)Incorporate the responses to the NRC questions in Section 3.2 detailing how the control room envelope (CRE)is maintained.
(2)Define when the periodic assessment of the CRE boundary in Specification 5.5.13.d should be performed.
This assessment has previously been performed as discussed in Section 3.2.First performance of the assessment is also discussed in the proposed License Condition in Section 2.3 that specifies that the assessment is performed within the 18 months, plus the 136 days allowed by SR 3.0.2, from the date of issuance of this amendment.
3.0 Regulatory
Analysis 3.1 No Significant Hazards Consideration Determination The no significant hazards consideration determination (NSHCD)performed as submitted in letter GNRO-2007/00040
-License Amendment Request Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, using the Consolidated Line Item Improvement Process, dated July 17, 2007 remains valid for this supplement.
Attachment 1 to GNRO-2008/00049 Page 3 of 6 3.2 NRC Requested Information is included The NRC staff had the following questions, which were sent by email As follows.Based on the NRC staffs review of the application dated July 17, 2007 (GNRO-2007/00040)(Agency wide Documents and Access Management System (ADAMS)Accession No.ML072060522), and the licensee's statement that the GGNS CRE is not pressurized, the staff has the following question.TSTF-448 Revision 3 was developed for plants with pressurized control room envelopes; however, as stated in the licensee's application GGNS has apressurized CRE.Note that in the programs and manuals section of the standard technical specifications (STS)as modified by TSTF-448 revision 3, paragraph (d)of Section[5.5.18],"Control Room Envelope Habitability Program", specifies a differential pressure (dp)test to be conducted between performances of inleakage testing for the purpose of providing input to a periodic assessment of the control room envelope (CRE)boundary.The NRC staff recognizes that non-pressurized control room envelopes may not be able to conduct a dp test, nevertheless, the NRC staff believes that all plants requesting the adoption of TSTF-448 should include in their request, a method to collect data that will serve as input to a periodic assessment of the CRE boundary.This position is supported by the technical analysis section of TSTF-448 revision 3 on page 8 where an explanation of the basis for paragraph (d)is provided.Consequently, the NRC staff is requesting that the licensee provide a method to collect data, and an explanation of how it is intended to be used, that can be used to make a periodic assessment of the GGNS CRE boundary.The method should, to the extent practicable, provide information that can be used in a manner similar to the manner in which the dp information is to be used that is requested by paragraph (d)of section[5.5.18]of the programs and manuals section of the STS as modified by TSTF-448R3.
Grand Gulf Response to NRC email dated March 12, 2008 Grand Gulf Nuclear Station response to the NRC regarding compliance to NRC Regulatory Guide 1.197 would be performed was documented in GNRO-2007/00040 and 00050, Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3.In the response, GGNS indicated that the Control Room Envelope is NOT pressurized during its isolation mode of operation.
The CRE becomes neutral with respect to areas adjacent to the envelope boundary.Facilities with a positive pressure CRE generally have implemented testing programs that verify that the CRE is at a positive differential pressure relative to adjacent areas.This testing method has been implemented via TechnicalSpecificationsurveillance requirements for the control room emergency ventilation filtration system.Plants with a CRE design based on isolation without intentional pressurization, i.e., neutral pressure, typically do not have a similar surveillance requirement.
As such, the initial proposed responses for Technical Specification 5.5.13, Control Room Envelope Habitability Program did NOT include measurement at designated locations of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation.
The NRC review of our submittals recognizes that differential pressure tests may not be the appropriate testing for plants with a non-pressurized CRE.However, with Grand Gulf Nuclear Station's adoption of TSTF-448, information should be provided regarding how Grand Gulf collects data and uses this data as input to the periodic assessment between periodic testing of the CRE.
Attachment 1 to GNRO-2008/00049 Page 4 of 6 Below is a summary of how Grand Gulf Nuclear Station currently controls gradual degradation of equipment designed to maintain the CRE boundary.This also includes items such as modification, rework, and preventative maintenance activities that could potentially affect the CRE boundary.Since the CRE is at a positive pressure during normal fresh air operation and neutral pressure during isolation mode, only the components on the suction side, Le., at negative pressures, of the system will be addressed:
1.Plant maintenance activities such as modifications, rework, and preventive maintenance tasks on components that could affect the CRE are controlled under fleet and plant specific procedures to ensure that the CRE boundary is not degraded by such activities.
This is done by design reviews, post maintenance inspections and retests in addition to how these work activities are to be performed.
Administrative procedures controlling performance of work are as follows: o Fleet Procedures
- EN-DC-105, Configuration Management
- EN-DC-115, Engineering Change Development
- EN-DC-116, Engineering Installation
- EN-DC-117, Post Modification Testing and Special Instructions
- EN-DC-134, Design Verification
- EN-DC-141, Design Inputs*EN-MA-125, Troubleshooting Control of Maintenance Activities o Plant Specific Procedures
- 01-S-07-1, Control Of Work On Plant Equipment And Facilities
- 01-S-07-37, Control Of Work For Penetrations, Painting, Snubbers, Insulation and Control Room Envelope Breaches*07-S-01-205, Conduct of Maintenance Activities, although designated a maintenance procedure, is used to ensure that plant equipment is available and capable of performing its intended function and as such, details departmental responsibilities and work ethics.2.Testing of Standby Fresh Air Unit (SBFAU)sealing areas are performed following maintenance activities (rework and preventative) and on set frequencies to ensure that the areas of negative pressures do not leak bypassing emergency filtration system components.
o System Specific Procedures
- 06-ME-1Z51-R-0006, (Surveillance)
In-Place Testing of Control Room Emergency Filtration System, tests mechanical leak by following maintenance activities in which filtration components were disturbed and every 18 months.
Attachment 1 to GNRO-2008/00049 Page 5 of 6*17-S-06-Z51-1, Control Room SBFAU Leakage Test, Engineering task performed every 18 months, which involves smoke testing the SPFAU fan housing and filter train doors.3.Fire damper inspection procedures that require opening of duct panels and doors ensures that upon restoration no leakage path exists.o System Specific Procedure*06-ME-SP64-R-0045, ventilation System Fire Dampers Inspection (Surveillance) cautions entry into CRE boundaries and ensures that the requirements for penetrations and maintenance breaches are adhered to per 01-S-07-37, Control of Work for Penetrations, Painting, Snubbers, Insulation and Control Room Envelope Breaches.4.The remainder of ducting components such as plenum access doors, duct access doors (rectangular and round), flex connections (vent glass, etc.), plugs, and patches have been fabricated and installed per Mechanical Standard (MS)32.Programs and processes that ensure that these types of components that are routinely accessed maintain a leak tight barrier in areas of negative pressures are listed below.o System condition monitoring is currently performed on a predetermined frequency by the System Engineer for category I and quarterly for category II systems.Monitoring may be performed by plant data system (PDS)monitoring and/or system walkdowns as specified and controlled by the following procedures.
These procedures give guidance regarding expectations for monitoring system health and identifying deficiencies.
- EN-DC-159, System Monitoring Program*EN-DC-178, System Walkdowns Summary: The initial control room envelope integrity testing was performed in April 2005.GGNS configuration in isolate mode is neutral and the TS operating limit (OL)for in leakage is 2000 cfm plus 10 cfm ingress/egress.
The analysis assumptions for GGNS are 2010 cfm applied in the radiological analyses based on isolated configuration and 4060 cfm applied in the toxic gas analyses based on unisolated configuration.
The results of the tests conducted in April 2005 were: Test CREVS Mode In leakage (cfm)1 A and B Train Isolation 351+/-19 2 A Train Isolation 238+/-13 3 A Train Normal (Fresh Air)812+/-48 Attachment 1 to GNRO-2008/00049 Page 6 of 6 It is reasonable to assume that with the available margin the work practices and programs currently in place have proven sufficient in maintaining the CRE integrity between periodic testing.4.0 Environmental Evaluation Entergy has reviewed the environmental evaluation included in the model safety evaluation dated January 17, 2007 as part of the CUIP.Entergy has concluded that the staff's findings presented in that evaluation are applicable to GGNS and the evaluation is hereby incorporated by reference for this application.
The proposed changes have been evaluated to determine whether applicable regulations and requirements continue to be met.Entergy has determined that the proposed changes do not require any exemptions or relief from regulatory requirements, other than the TS, and do not affect conformance with any General Design Criterion (GOC)differently than described in the Updated Final Safety Analysis Report (UFSAR).
Attachment 2 GNRO-2008/00049 Technical Specification and Operating License Condition (Mark-up)
Attachment 2 to GNRO*2008/00049 Page 1 of6 SURVEILLANCE REQUIREMENTS SURVEILLANCE CRFA System 3.7.3 FREQUENCY SR 3.7.3.1 SR 3.7.3.2 SR 3.7.3.3 SR 3.7.3.4 Operate each CRFA subsystem for10 continuous hours with the heaters operating.
Perform required CRFA filter testing in accordance with the Ventilation Filter Testing Program (VFTP).Verify each CRFA subsystem actuates on an actual or simulated initiation signal.Perform required CRE unfiltered air inleakage testing in Control Room Envelope Habitabil ity 7 31 days In accordance with the VFTP 18 months In accordance with the Control Room envelope Habitability Program GRAND GULF 3.7-8 Amendment No. l!2 Attachment 2 to GNRO-2008/00049 Page 2 of 6 Programs and Manuals 5.5 Programs and Manuals (continued) 5.5.13 Control Room Envelope Habitability Program A Control Room Envelope (CRE)Habitability Program shall be established and implemented to ensure thatCREhabitability is maintained such that, with an OPERABLE Control Room Fresh Air (CRFA)System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge.
The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under Design Basis Accident (DBA)conditions without personnel receiving radiation exposures in excess of 5 rem Total Effective Dose Equivalent (TEDE)for the duration of the accident.The program shall include the following elements: a.The definition of the CRE and the CRE boundary.b.Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
c.Requirements for (i)determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197,"Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii)assessingCREhabitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision O.d.Since the CRE is at a neutral pressure during isolation mode, the CRE will be maintained, including the following:
1.Plant maintenance activities such as modifications, rework, and preventive maintenance tasks on components that could affect the CRE shall be controlled under fleet, plant and system specific procedures to ensure that the CRE boundary is not degraded by such activities.
2.Testing of CRF A system sealing areas shall be performed following maintenance activities (rework and preventative) and periodically to ensure that the areas of negative pressures do not leak bypassing emergency filtration system components.
3.Fire damper inspection procedures that require opening of duct panels and doors shall ensure that upon restoration no leakage path exists.4.The remainder of ducting components such as plenum access doors, duct access doors (rectangular and round), flex connections (ventglass, etc.), plugs, and patches will be maintained per paragraph b.5.An assessment of the CRE Boundary will be conducted every I8-months.
The results of assessing items 1 through 4 shall be trended and used as part of the assessment of the CRE boundary as indicated in paragraph c.
Attachment 2 to GNRO-200B/00049 Page 3 of 6 Programs and Manuals 5.5 e.The quantitative limits on unfiltered air inleakage into the CRE.These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.
Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.f.The provisions of SR 3.0.2 are applicable totheFrequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and assessing the CRE boundary as required by paragraphs c and d, respectively.
Attachment 2 to GNRO-2007100050 Page 4 af6 Attachment 2 to GNRO-2008/00049 Mark-up as submitted in GNRO-2007/00050 Page 4 of 6 (41)Fjre ProtectiQn Program Entergy Operations, Inc.shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in Revision 5 to the Updated Final Safety Analysis Report, and as approved in the Safety Evaluations dated August 23, 1991.and September 29, 2006, subject to the following provisions:
The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.(42)Mitigation Strategy License Condition The Licensee shall develop and maintain strategies for addresslng large fires and explosions and that include the following key areas: (a)Fire fighting response strategy with the following elements: 1.Pre-defined coordinated fire response strategy and guidance 2.Assessment of mutual aid fire fighting assets 3.Designated staging areas for equipment and materia's 4.Command and control 5.Training of response personnel (b)Operations to mitigate fuel damage considering the follOWing:
1.Protection and use of personnel assets 2.Communications 3.Minimizing fire spread 4.Procedures for implementing integrated fire response strategy 5.Identification of readily-available pre-staged equipment 6.Training on integrated fire response strategy 7.Spent fuel pool mitigation measures{c)Actions to minimize release to include consideration of: 1.Water spray scrubbing 2.Dose to onsite responders Control Room Habitability Upon implementation of Amendment No.xxx adopting TSTF-448, Revision 3.the determination of Control Room Envelope (eRE)unfiltered air inleakage as required by SR 3.7.3.4.in accordance with TS 5.5.13.c.ti), dnd the assessment of eRE habitability 16 Amendment No.170 Revised by Letter dated July 18, 2007 Attachment 2 to GNRO-2007/00050 Page 50f6 Attachment 2 to GNRO-2008/00049 Mark-up as submitted in GNRO-2007/00050 Page 5 of6 as reQuired by Specification 5.5.13.c.(;1), sha11 be considered met.Following implementation: (a)The first performance of SR 3.7.3.4, in accordance with Speclfication 5.5.:3.c.1 il, shall be within the speclfiec Frequency of 6 years, plus the IS-month allowance of SR 3.0.2, as measured from March 2005.the date of the most
r-,.: successful tracer gas test, as stated in the June letter response to Generic letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.(b)The first performance of the periodic assessment of CRE habitability, Specification 5.5.13_c.(ii J, shall be within 3 years, plus the 9-month allowance of SR 3.0.2.as measured from March 2005, the date of the most recent successfu' tracer gas test.as stated in the June 30.2005 letter response to Generic Letter 2003-01.or within the next 9 months if the time perioa since the most recent successful tracer gas test is greater than 3 years.O.The facility required exemptions from certain requirements of Appendices A and J to 10 CFR Part 50 and from certain requirements of 10 (FR Part 100.These include: (a)exemption from General Design Criterion 17 of Appendix A until startup following the first refueling outage, for (1)the emergency override of the test mode for the Division J diesel engine, (2)the second level undervoltage protection for the Division 3 diesel engine, and (3)the generator ground over current trip function for the Division 1 and 2 diesel generators (Section 8.3.1 of SSfR#7)and (b)exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix J for the containment airlock testing following normal door opening when containment integrity is not required (Section 6.2.6 of SSER#7).These exemptions are duthoriled by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.In addition, by exemption dated December 20, 1986, the Commission exempted licensees from 10 CFR 100.11(a)(I), insofar as it incorporates the definition of exclusion area in 10 CFR 100.3(a), until April 30.1987 regarding demDnstrat\on of authority to control all activities within the exclusion area (safety evaluation accompanying Amendment No.27 to License (NPF*29L This exemptfon is authorized by law, and w1l1 not present an undue risk to the public hea1th and safety, and is consistent with the common defense and security.In addition, special circumstances have been found justifying the exemption.
Therefore.
these exemptions are hereby granted pursuant to 10 CFR 50.12.With the granting of these exemptions, the facility will operate, to the extent author\red herein, in conformity with the application, as amended, the provisions of the Act and the rules and regulations of the Commission.
16a Re'i sea 9:)'letter Elates JaFll:IJry 24, 2Q07 P""'<"flrlf)V Letter rfat.ed July 18, 2007 INSERT"An TO LICENSE CONDITION AS SUBMITIED IN GNRO-2007/00050 Attachment 2 to GNRO-2007/00050 Page 6of6 New Page Attachment 2 to GNRO-2008/00049 Mark-up as submitted in GNRO-2007/00050 Page 6 of 6 E.The licensee shall fully implement and maintain in effect all provIsion of the Commission*approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments ana Search Requirements revisions to 10 eFR 73.55 (51 FR 27817 and 27822)and to the authority of to eFR 50.90 and 10 eFR 50.54(p}.The plans.which contain Safeguards Information protected under 10 eFR 73.21, are entitled: "Physical Security, Safeguards Contingency and Training and Qualification Plan," and were submitted to the NRC on May 18.2006.160 Attachment 3 GNRO-2008/00049 Technical Specification Bases (Mark-up)
Attachment 3 to G NRO-2008/00049 Page 1 of 2 CRFA System B 3.7.3 BASES SURVEILLANCE REQUIREMENTS (continued)....SR 3.7.3.3 usually pass the Surveillance when performed at the 18 month Frequency.
is based on the refueling cycle.Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
REFERENCES 1.UFSAR, Section 6.5.1.2.UFSAR, Section 9.4.1.3.UFSAR, Chapter 6.4.UFSAR, Chapter 15.5.Del eted 6.Engineering Evaluation Request 95/6213, Engineering Evaluation Request Response Partial Response dated 12/18/95.7.Amendmentto GGNS Operating License.8.UFSAR, Section 9.5 9.NEI 99-93, Control Room Habitability Assessment, June 2091.10.Letter from Eric J.Leeds (NRC)to James W.Davis (NEI)Use of Generic Letter 91-18 Process and Alternative Source Terms in the Context of Control Room Habitability." (ADAMS Accession No.ML04300694).
GRAND GULF B 3.7-17 LDC 05050 Attachment 3 to GNRO-2008/00049 Page 2 of2 INSERT"A" TO TECHNICAL SPECIFICATION BASES PAGE B 3.7-17 This SR verifies the OPERABILITY of the CRE boundary by testing for unfiltered air inleakage past the CRE boundary and into the CRE.The details of the testing are specified in the Control Room Envelope Habitability Program.SR 3.7.3.4 The CRE is considered habitable when the radiological dose to CRE occupants calculated in the licensing basis analyses of DBA consequences is no more than 5 rem TEDE and the CRE occupants are protected from hazardous chemicals and smoke.This SR verifies that the unfiltered air inleakage into the CRE is no greater than the flow rate assumed in the licensing basis analyses of DBA consequences.
When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered.Required Action B.3 allows time to restore the CRE boundary to OPERABLE status provided mitigating actions can ensure that the CRE remains within the licensing basis habitability limits for the occupants following an accident.Compensatory measures are discussed in Regulatory Guide 1.196, Section C.2.7.3, which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref.9).These compensatory measures may also be used as mitigating actions as required by Required Action B.2.Temporary analytical methods may also be used as compensatory measures to restore OPERABILITY (Ref.10).Options for restoring the CRE boundary to OPERABLE status include changing the licensing basis DBA consequence analysis, repairing the CRE boundary, or a combination of these actions.Depending upon the nature of the problem and the corrective action, a full scope inleakage test may not be necessary to establish that the CRE boundary has been restored to OPERABLE status.