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Issue date | Title | Topic | |
---|---|---|---|
ML23270B993 | 29 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 | |
ML23117A217 | 1 May 2023 | Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment | |
ML22342B280 | 28 December 2022 | Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 | |
ML22104A222 | 12 May 2022 | Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 | Shutdown Margin Packing leak Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Surveillance Frequency Control Program Process Control Program Pressure Boundary Leakage |
ML22083A124 | 28 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 | Ultimate heat sink Water Inventory Control Surveillance Frequency Control Program Recently irradiated fuel |
ML22007A317 | 18 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 | Incorporated by reference |
ML21294A067 | 28 October 2021 | Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency | Incorporated by reference Power-Operated Valves |
ML21258A408 | 21 September 2021 | Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines | Aging Management EVT-1 |
ML21146A018 | 8 June 2021 | Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program | Probabilistic Risk Assessment Surveillance Frequency Control Program Large early release frequency |
ML21040A292 | 4 March 2021 | Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control | Surveillance Frequency Control Program |
ML21019A219 | 24 February 2021 | Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval | Probabilistic Risk Assessment Coatings Incorporated by reference Aging Management Surveillance Frequency Control Program Foreign Material Exclusion Large early release frequency COVID-19 |
ML21011A068 | 2 February 2021 | Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure | Safe Shutdown Anticipated operational occurrence Significance Determination Process Maintenance Rule Program Offsite Circuit |
ML21011A048 | 1 February 2021 | Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems | Surveillance Frequency Control Program |
ML20226A272 | 18 August 2020 | Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI | Incorporated by reference |
ML20101G054 | 15 April 2020 | Issuance of Amendment No. 224 One Cycle Extension of Appendix J Integrated Leakage Test and Drywell Bypass Test Interval (Exigent Circumstances) | Probabilistic Risk Assessment Coatings Aging Management Surveillance Frequency Control Program Foreign Material Exclusion Large early release frequency Pandemic COVID-19 |
ML19308B107 | 11 December 2019 | Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) | Reactor Vessel Water Level Anticipated operational occurrence Annual Radiological Environmental Operating Report Process Control Program Fuel cladding |
ML19266A586 | 11 October 2019 | Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds | VT-2 Incorporated by reference Large early release frequency Liquid penetrant Dissimilar Metal Weld |
ML19254A603 | 19 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 | |
ML19175A042 | 11 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 | Time of Discovery Fire Protection Program |
ML19123A014 | 18 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 | Safe Shutdown High winds Mission time Tornado Missile Internal Flooding Probabilistic Risk Assessment Incorporated by reference FLEX Tornado Generated Missile Tornado Missile Protection Large early release frequency TORMIS Tornado Missile Risk Evaluator Fuel cladding |
ML19094A799 | 11 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 | High winds Reactor Vessel Water Level High Radiation Area Water Inventory Control Internal Flooding Hydrostatic Probabilistic Risk Assessment Surveillance Frequency Control Program Scram Discharge Volume Large early release frequency Spiral reload Overtravel Maintenance Rule Program Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Backfit |
ML19084A218 | 23 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 | Reactor Vessel Water Level Stroke time Anticipated operational occurrence Water Inventory Control Hydrostatic Fuel cladding Recently irradiated fuel Scaffolding |
ML18215A196 | 12 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 | Anticipated operational occurrence Probabilistic Risk Assessment Abnormal operational transient |
ML19018A269 | 12 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 | High winds Internal Flooding Probabilistic Risk Assessment Surveillance Frequency Control Program Large early release frequency Maintenance Rule Program Backfit |
ML19025A023 | 12 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 | |
ML18128A067 | 8 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 | Incorporated by reference Through-Wall Leak Through-Wall Leakage |
ML17285A794 | 30 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) | |
ML17240A232 | 4 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) | |
ML17235A533 | 31 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 | VT-2 Incorporated by reference Through-Wall Leak |
ML17116A032 | 7 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.) | |
ML16278A017 | 19 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 | Nondestructive Examination Incorporated by reference |
ML16253A322 | 27 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 | Safe Shutdown High winds Shutdown Margin Ultimate heat sink Safe Shutdown Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake Fire Protection Program |
ML16251A620 | 13 September 2016 | Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) | |
ML16140A133 | 4 August 2016 | Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application | Time of Discovery High Radiation Area |
ML16160A092 | 16 June 2016 | Relief Request GG-IST-2015-1 Related to the Inservice Testing Program | Grace period |
ML16096A269 | 6 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 | Functionality Assessment Liquid penetrant |
ML16093A028 | 31 May 2016 | Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 | Liquid penetrant |
ML16119A148 | 25 May 2016 | Issuance of Amendment No. 210 Re. Cyber Security Plan Milestone 8 Full Implementation Schedule | Cyber Security |
ML16011A247 | 17 February 2016 | Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing | MELLLA Grace period |
ML15336A256 | 17 December 2015 | Issuance of Amendment No. 208 Adoption of Technical Specification Task Force Traveler TSTF-522 | |
ML15195A355 | 31 August 2015 | Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values | Reactor Vessel Water Level Anticipated operational occurrence Probabilistic Risk Assessment |
ML15180A170 | 31 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 | MELLLA |
ML15229A219 | 31 August 2015 | Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Internal Flooding Hydrostatic Probabilistic Risk Assessment Cyber Security Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report Process Control Program Feedwater Controller Failure Large early release frequency MELLLA Time Critical Operator Action Earthquake Fuel cladding Power change |
ML15229A213 | 18 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) | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence |
ML15229A218 | 18 August 2015 | Redacted, Issuance of Amendment Adoption of Single Fluence Methodology | |
ML15104A623 | 12 May 2015 | Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 | |
ML14311A479 | 12 December 2014 | Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date | Cyber Security |
ML14162A378 | 25 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 | |
ML14210A266 | 8 August 2014 | Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & | |
ML14184A782 | 1 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 | Incorporated by reference |