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Issue date | Title | |
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ML24012A142 | 31 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)) |
ML23166B066 | 15 June 2023 | Response to NRC Integrated Inspection Report 05000416/2023001 |
IR 05000416/2023001 | 10 May 2023 | Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 |
ML23110A800 | 10 May 2023 | Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 |
ML23033A049 | 1 February 2023 | Emergency Action Level (EAL) Technical Bases Document Revision 3 |
ML21105A052 | 15 April 2021 | EAL Technical Bases Document Revision 1 |
ML20333A000 | 27 November 2020 | Emergency Plan, Revision 81 and Revision 0 of the EAL Technical Bases Document |
ML20258A282 | 14 September 2020 | Submittal 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 Related | 28 February 2020 | 3 to Emergency Plan Implementing Procedure 10-S-01-1, Activation of the Emergency Plan Safety Related |
ML20058H618 | 10 February 2020 | GG-2020-02 Draft Written Examination |
ML20058H624 | 10 February 2020 | GG-2020-02 Final Written Examination |
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 |
CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 | 31 January 2019 | Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 |
ML16140A133 | 4 August 2016 | Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application |
IR 05000416/2015004 | 11 February 2016 | NRC Integrated Inspection Report 05000416/2015004 and 07200050/2015001 |
IR 05000416/2015008 | 20 November 2015 | NRC Problem Identification and Resolution IR 05000416/2015008 |
ML14310A408 | 24 October 2014 | 2014-10 - Draft Written Exam |
ML14308A043 | 24 October 2014 | 2014-10 - Final Written Examination |
GNRO-2013/00038, Response to Request for Additional Information Regarding 18 to 24 Month License Amendment Request (TAC ME9764) Dated May 1, 2013 | 4 June 2013 | Response to Request for Additional Information Regarding 18 to 24 Month License Amendment Request (TAC ME9764) Dated May 1, 2013 |
GNRO-2013/00001, Response to Electronic Request for Additional Information Supporting Completion of Safety Evaluation for the License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell... | 30 January 2013 | Response to Electronic Request for Additional Information Supporting Completion of Safety Evaluation for the License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell... |
ML090700248 | 11 March 2009 | 2009-03 - Final Written Exam |
ML090700415 | 11 March 2009 | GG-2009-03 - Draft Written Exam |
ML082390008 | 4 September 2008 | Enclosure 4 - FAQ Log July 2008 |
ML040970157 | 25 March 2004 | Enclosures to Ltr. to Grand Gulf Corrections the Licensee'S Record Copy of FOL & Appendices |
ML022460449 | 26 August 2002 | Technical Specification Pages 3.0-4 & 3.0-4a Grand Gulf |
ML20198N934 | 14 January 1998 | Submits Response to Violations Noted in Insp Rept 50-416/97-18.Util Denies Violations & Lists Bases for Denial |
Information Notice 1996-44, Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly | 5 August 1996 | Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly |
ML20087F183 | 11 August 1995 | Forwards Fitness for Duty Program Performance six-month Rept,For 950101-0630,per 10CFR26 |
ML20059B035 | 15 October 1993 | Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 |
05000416/LER-1993-007 | 26 August 1993 | LER 93-007-00:on 930723,violation of OL Condition 2.C.(38) Occurred Due to Access Points Not Clearly Marked to Identify Envelope Boundary.Marked Access panels.W/930826 Ltr |
ML20045G791 | 8 July 1993 | LER 93-005-00:on 930608,indicated That Response Time Test for RCIC Low Steam Pressure Isolation Instrumentation Invalid.Caused by Inappropriate Test Method.Procedures Governing Method of Testing Will Be revised.W/930708 Ltr |
NUREG-1434, Forwards Preliminary,Unedited Copy of Section 3.6 Bases for BWR Owners Group BWR/4 & BWR/6 Versions of New STS | 2 June 1992 | Forwards Preliminary,Unedited Copy of Section 3.6 Bases for BWR Owners Group BWR/4 & BWR/6 Versions of New STS |
05000416/LER-1990-008 | 20 June 1990 | LER 90-008-00:on 900521,discovered That Fire Rated Door Required by Tech Spec 3/4.7.7 Not Designated as Tech Spec Door in Ssurveillance Procedures.Caused by Incorrect Interpretation of Tech Spec requirements.W/900620 Ltr |
ML20006E452 | 15 February 1990 | LER 89-015-01:on 891030,no Data or Evidence Found That Stroke Time Test Performed on Bettis Actuator for Isolation Damper Following Maint.Caused by Programmatic Weaknesses.New Computer Field Data Added to Work orders.W/900215 Ltr |
ML20006E046 | 9 February 1990 | LER 90-001-00:on 900112,determined That Tech Spec Reactor Coolant Cooldown Rate Limit of 100 Degrees F Exceeded in Reactor Bottom Head Drain Pipe.Caused by Programmatic Deficiencies.Incident Rept Form improved.W/900209 Ltr |
ML19332F073 | 29 November 1989 | LER 89-015-00:on 891030,no Data or Evidence Found for Stroke Time Test Required to Be Performed Following Maint on Bettis Actuator for Isolation Damper QSZ51F001.Caused by Personnel Error.Programmatic Enhancements initiated.W/891129 Ltr |
ML20154E651 | 14 September 1988 | Summary of 880815 Meeting W/Util Re Potential Changes to Tech Specs.Other Actions Discussed Includes,Status of Completion of Conditions in Operating License & Actions Taken Re Problems Identified in Info Notices |
AECM-87-0201, Application for Amend to License NPF-29,changing Tech Specs to Support Design Change to Divisional Power Supplies for RWCU Sys Containment & Drywell Isolation Valves.Fee Paid | 28 October 1987 | Application for Amend to License NPF-29,changing Tech Specs to Support Design Change to Divisional Power Supplies for RWCU Sys Containment & Drywell Isolation Valves.Fee Paid |
ML20137S940 | 4 February 1986 | Insp Rept 50-416/85-46 on 851221-860117.Violation Noted: Failure to Follow Procedures for Placing Shutdown Cooling in Effect & to Maintain Reactor Vessel Water Level & Feedwater Pump Discharge Pressure |
AECM-85-0344, Responds to Violations Noted in Insp Rept 50-416/85-33. Corrective Actions:Ltr Issued Re Compliance w/safety-related Procedures & Surveillance Procedures Revised to Include Test Port Flanges | 1 November 1985 | Responds to Violations Noted in Insp Rept 50-416/85-33. Corrective Actions:Ltr Issued Re Compliance w/safety-related Procedures & Surveillance Procedures Revised to Include Test Port Flanges |
ML20072E114 | 18 February 1983 | Responds to NRC Re Violations Noted in IE Insp Rept 50-417/83-01.Corrective Actions:Concrete Wall Pour Q2T22-W-22183WIA Completed on 830104.QC Verified That Curing Process Initiated at Proper Time |