ML14148A262
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| ML14148A262 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/30/2014 |
| From: | Broaddus D A Plant Licensing Branch IV |
| To: | Entergy Operations |
| Wang A B | |
| References | |
| TAC MF2357 | |
| Download: ML14148A262 (13) | |
Similar Documents at Grand Gulf | |
|---|---|
Category:Code Relief or Alternative
MONTHYEARML23270B9932023-09-29029 September 2023
[Table view]Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML21294A0672021-10-28028 October 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency ML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 ML17285A7942017-10-30030 October 2017 Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031) ML17235A5332017-08-31031 August 2017 Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection ML16160A0922016-06-16016 June 2016 Relief Request GG-IST-2015-1 Related to the Inservice Testing Program ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML14184A7822014-08-0101 August 2014 Relief Request GG-ISI-017, Alternative to Reactor Vessel Internal Structure Examination, Use of BWRVIP Guidelines, B13.10, Categories B-N-1 and B-N-2, Third 10-Year Inservice Inspection Interval ML14148A2622014-06-30030 June 2014 Relief Request GG-ISI-017, Alternative to Reactor Vessel Internal Structure Examination, Use of BWRVIP Guidelines, Third 10 -Year Inservice Inspection Interval ML12326A3312012-11-30030 November 2012 Relief Requests GG-ISI-014, GG-ISI-015, and GG-ISI-016, Pressure Retaining Welds in Control Rod Housings, Pumps and Valves, and Supports, 2nd 10-Year Inservice Inspection Interval ML12214A3182012-08-17017 August 2012 Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval ML1213804832012-05-22022 May 2012 Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval GNRO-2012/00040, Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB2012-05-0202 May 2012 Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB ML1127103282011-11-0404 November 2011 Request for Alternative GG-ISI-013 from Examination Requirements for Reactor Pressure Vessel Weld Inspections for Third 10-Year Inservice Inspection Interval GNRO-2011/00009, Request for Alternative GG-ISI-013 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections2011-04-0606 April 2011 Request for Alternative GG-ISI-013 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections ML1005401832010-03-15015 March 2010 Relief Request to Use a Portion of a Later Edition of the ASME OM Code for Main Steam Safety Relief Valve Inservice Testing 2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010 Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 ML0906304692009-03-30030 March 2009 Request for Alternative CEP-CISI-001, Use Alternative Requirements in ASME Code Case N-739-1 ML0903708982009-03-0606 March 2009 Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753 CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009 Relief Requests for Third 120 Month Inservice Inspection Interval ML0816200052008-07-11011 July 2008 Relief Request VRR-GGNS-2007-01 and -02, Alternative Inservice Test Requirement, Extension to ASME OM Code 5-Year IST Interval for Main Steam Safety Relief Valve ML0724300052007-09-21021 September 2007 Request for Alternative GG-ISI-002 - to Implement Risk-Informed Inservice Inspection Program Based on the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-716 ML0703004142007-02-13013 February 2007 Relief, Request for Alternative GG-ISI-003 to Extend the Current Inservice Inspection Interval ML0701200812007-02-0202 February 2007 River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403) ML0522402612005-08-31031 August 2005 Request 1st-2005-1, Use of Subsequent American Society of Mechanical Engineers Operation and Maintenance Code Edition and Addenda for Condition Monitoring Check Valves ML0435702742004-12-21021 December 2004 ANO Units 1 and 2; Grand Gulf; River Bend and Waterford Unit 3 ML0420304392004-07-21021 July 2004 Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code, Section XI, Inservice Testing Program ML0323901902003-08-26026 August 2003 Ltr. to M.A. Krupa ANO-1, Grand Gulf River Bend Station & Waterford Steam Electric Station, Unit 3, Request to Use American Society of Mechanical Engineers Boiler & Pressure Vessel (Code) Case N-663 CNRO-2002-00059, Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-052002-12-18018 December 2002 Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-05 2023-09-29 Category:Letter MONTHYEARIR 05000416/20240112024-10-16016 October 2024
[Table view]– Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 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) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 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 IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 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 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 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System 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 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 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 ML24087A1962024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close 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 IR 05000416/20234012024-01-18018 January 2024 Cyber Security Inspection Report 05000416/2023401 (Public) 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 2024-09-09 Category:Safety Evaluation MONTHYEARML24185A1522024-08-13013 August 2024
[Table view]Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 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 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 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 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 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21294A0672021-10-28028 October 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20101G0542020-04-15015 April 2020 Issuance of Amendment No. 224 One Cycle Extension of Appendix J Integrated Leakage Test and Drywell Bypass Test Interval (Exigent Circumstances) 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) ML19266A5862019-10-11011 October 2019 Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 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 ML19123A0142019-06-18018 June 2019 Issuance of Amendment No. 220, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19094A7992019-06-11011 June 2019 Issuance of Amendment No. 219 to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML19084A2182019-05-23023 May 2019 Issuance of Amendment No. 218 to Revise Technical Specification to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19018A2692019-03-12012 March 2019 Safety Evaluation Input for Grand Gulf Nuclear Station Unit 1, License Amendment Request to Implement Technical Specification Task Force-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control ML19025A0232019-03-12012 March 2019 Issuance of Amendment No. 216 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML18215A1962019-03-12012 March 2019 Issuance of Amendment No. 217 to Modify the Updated Safety Analysis Report to Replace Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML17285A7942017-10-30030 October 2017 Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031) 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) ML17235A5332017-08-31031 August 2017 Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection ML17116A0322017-06-0707 June 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 212 to Adopt Technical Specifications Task Force-427, Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability (CAC No. MF8692.) ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16253A3222016-09-27027 September 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16140A1332016-08-0404 August 2016 Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application ML16160A0922016-06-16016 June 2016 Relief Request GG-IST-2015-1 Related to the Inservice Testing Program ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16119A1482016-05-25025 May 2016 Issuance of Amendment No. 210 Re. Cyber Security Plan Milestone 8 Full Implementation Schedule ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing ML15336A2562015-12-17017 December 2015 Issuance of Amendment No. 208 Adoption of Technical Specification Task Force Traveler TSTF-522 ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request 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 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 ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 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 2024-08-13 |
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