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 Issue dateTitle
ML23033A0491 February 2023Emergency Action Level (EAL) Technical Bases Document Revision 3
ML22223A05111 August 2022Report of Technical Specification Bases Changes
ML22305A51522 February 2022EN 56192 - Grand Gulf Nuclear Station Re Elevation Outer Containment Personnel Airlock Door Failed Its Technical Specification Leakage Test
ML21105A05215 April 2021EAL Technical Bases Document Revision 1
ML20333A00027 November 2020Emergency Plan, Revision 81 and Revision 0 of the EAL Technical Bases Document
ML20258A28214 September 2020Submittal of Changes to Emergency Plan Implementing Procedures
GNRO-2020/00026, 3 to Emergency Plan Implementing Procedure 10-S-01-1, Activation of the Emergency Plan Safety Related28 February 20203 to Emergency Plan Implementing Procedure 10-S-01-1, Activation of the Emergency Plan Safety Related
ML18200A1798 August 2018Documentation of the Completion of Required Actions Taken in Response to Fukushima Lessons Learned
IR 05000416/201500820 November 2015NRC Problem Identification and Resolution IR 05000416/2015008
ML14245A38629 August 2014NRDC V. NRC Et. Al., No. 13-1311 (Scheduled Oral Argument November. 21, 2014)
ML14147A37423 June 2014Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14098A1751 May 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident
ML13325A89123 December 2013Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns
GNRO-2013/00012, Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request25 September 2013Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request
GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update21 December 2012Technical Requirements Manual and Technical Specification Bases Update
ML12352A07115 November 2012Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Cover Through Attachment C, Seismic Walkdown Checklists (Swcs), Page 150 of 345
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML1026604038 September 2010License Amendment Request Extended Power Uprate
IR 05000416/200800815 December 2008IR 05000416-08-008 & 07200050-08-002 on 11/17/2008 - 11/19/2008 for Grand Gulf Nuclear Station
ML0824907685 November 2008Staff Evaluation Providing Basis for Partial Denial of License Amendment Request, Technical Specifications Changes for Condensate Storage Tank Level-Low Instrumentation
GNRO-2007/00034, Report of 10 CFR50.59 Safety Evaluations and Commitment Changes - April 1, 2006 Through March 31, 200722 May 2007Report of 10 CFR50.59 Safety Evaluations and Commitment Changes - April 1, 2006 Through March 31, 2007
ML02301048019 September 2002Part 2 of 7 - GE BWR/4 Advanced Course R-504B
ML02301059719 September 2002Part 5 of 7 - GE BWR/4 Advanced Course R-504B
ML20154Q45116 October 1998TS Bases Update for Period of 970410 Through 981015
ML20198N93414 January 1998Submits Response to Violations Noted in Insp Rept 50-416/97-18.Util Denies Violations & Lists Bases for Denial
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML20137C92020 March 1997Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement
ML20148G10331 December 1996Rept of 10CFR50.59 Safety Evaluations for Period,950701- 961231
ML20134E12622 October 1996Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls
05000416/LER-1994-002, Forwards LER 94-002-02.Revises Reportable Status of This LER to Voluntary Which Is Reinforced by NUREG 102228 June 1996Forwards LER 94-002-02.Revises Reportable Status of This LER to Voluntary Which Is Reinforced by NUREG 1022
ML20078N66110 February 1995Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML20046D20411 August 1993Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
ML20073K84531 March 1991Entergy Nuclear Performance Rept,Mar 1991
ML20055G03416 July 1990Safety Evaluation Re Boraflex Gaps in Spent Fuel Racks. Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 Fuel.Storage Rack Surveillance Program Acceptable for long-term Storage of Spent Fuel
ML20043C86131 May 1990Forwards Preliminary Drafts of Plant Specific Tech Specs in Order to Facilitate NRC Validation of BWR Owners Group Improved Tech Specs,Per NRC Request.Understands That Util & NRC Will Meet During Wk of 900716 to Discuss NRC Review
ML20006B27816 January 1990LER 89-017-00:on 890718,determined That Isolation for Postulated RWCU Blowdown Line Breaks in Piping Cold Rooms Was 80 S,Causing Plant to Operate in Unanalyzed Condition. Tech Spec Change Request Will Be submitted.W/900116 Ltr
IR 05000416/198901911 September 1989Insp Rept 50-416/89-19 on 890715-0825.Violations Noted.Major Areas Inspected:Operational Safety Verification,Surveillance Observation,Maint Observation,Instrument Air Sys Walkdown, Action on Previous Insp Findings & ROs
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break30 June 1989Degradation of Containment Isolation Capability by a High-Energy Line Break
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11
NRC Generic Letter 1987-129 July 1987NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled
AECM-87-0106, Responds to NRC Re Violations Noted in Insp Rept 50-416/87-10.Corrective Actions:Training Session Conducted by QA Dept for All QA Insp & Audit Personnel & Procedure 01-S-06-3 Re Temporary Alterations Will Be Revised29 May 1987Responds to NRC Re Violations Noted in Insp Rept 50-416/87-10.Corrective Actions:Training Session Conducted by QA Dept for All QA Insp & Audit Personnel & Procedure 01-S-06-3 Re Temporary Alterations Will Be Revised
ML20214A11830 April 1987Notice of Violation from Insp on 870314-0417
IR 05000416/198700526 March 1987Insp Rept 50-416/87-05 on 870214-0313.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Enforcement Matters,Operational Safety Verification,Maint Observation & Surveillance
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