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ML22257A0408 September 2022Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML22257A0378 September 2022Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML22257A0168 September 2022Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML22257A0118 September 2022Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML22257A0078 September 2022Updated Final Safety Analysis Report, Chapter 6, Engineering Safety Features
IR 05000416/202200211 August 2022Integrated Inspection Report 05000416/2022002
ML22073A1788 March 2022Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML22073A1738 March 2022Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
IR 05000416/202104018 November 2021NRC Supplemental Inspection Report 05000416/2021040 and Assessment Follow-Up Letter
ML21039A33127 January 2021Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML21039A32727 January 2021Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML21039A26627 January 2021Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML21039A26127 January 2021Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
IR 05000416/201900413 February 2020Integrated Inspection Report 05000416/2019004 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2019001
ML19266A58611 October 2019Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds
GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval30 November 2018Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval
ML16096A2696 June 2016Arkansas; 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
ML16093A02831 May 2016Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1
CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 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 Water Service, Secti29 January 2016Entergy - Relief Request Number RR EN-15-1, Rev. 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 Water Service, Section Xl,
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, D5 June 2015Entergy 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
IR 05000416/201300312 August 2013IR 05000416-13-003; 04/07/2013 - 06/28/2013; Grand Gulf Nuclear Station, Unit 1, Integrated Resident and Regional Report; Fire Protection, Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications, Surveillance Testin
ML12214A31817 August 2012Relief 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-2012/00051, Day Report of Nozzle N06B-KB Weld Overlay Examination Results Following Completion of Repair24 May 2012Day Report of Nozzle N06B-KB Weld Overlay Examination Results Following Completion of Repair
GNRO-2012/00032, Response to Request for Additional Information (RAI) Dated April 11, 20129 May 2012Response to Request for Additional Information (RAI) Dated April 11, 2012
IR 05000416/20120024 May 2012IR 05000416-12-002; 01/01/2012 03/23/2012, Grand Gulf Nuclear Station, Unit 1, Integrated Resident and Regional Report; Flood Protection Measures, Licensed Operator Requalification Program, Maintenance Risk Assessment and Emergent Work Cont
GNRO-2012/00040, Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB2 May 2012Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB
GNRO-2011/00053, Response to Request for Additional Information Regarding Extended Power Uprate6 July 2011Response to Request for Additional Information Regarding Extended Power Uprate
ML1115304396 June 2011(Redacted) Request for Additional Information from Nrr/De/Emcb Steam Dryer, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
GNRO-2011/00018, Request for Additional Information Regarding Extended Power Uprate30 March 2011Request for Additional Information Regarding Extended Power Uprate
IR 05000416/20060133 October 2006IR 050-00416-06-013 & IR 07200050-06-002; on 09/13-15/06, Entergy Operations Inc., Grand Gulf Nuclear Station
IR 05000416/200600910 April 2006IR 05000416-06-009 and 07200050-06-001, Conducted on 03/21-24/2006, Grand Gulf Nuclear Station
IR 05000416/200200424 October 2002IR 05000416-02-004, on 06/30/2002 - 09/28/2002, Entergy Operations, Inc., Grand Gulf Nuclear Station. Postmaintenance Testing, Surveillance Testing
IR 05000416/19980045 May 1998Insp Rept 50-416/98-04 on 980414-16.No Violations Noted. Major Areas Inspected:Maint & Plant Support
ML20141G42325 June 1997Rev 10 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan
ML20149M42212 December 1996Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl
IR 05000416/199601829 November 1996Insp Rept 50-416/96-18 on 961028-1108.No Violations Noted. Major Areas Inspected:Maint,Nondestructive Exams, Documentation Reviews.Discussions W/Plant Personnel Associated W/Maint & Inservice Insp Programs Were Held
ML20128G07026 September 1996Informs That Util Revising Relief Request I-00014,rev 1 Per NRC Request to Incorporate Changes to Pressure Testing Program Resulting from Approval of Code Case N-498-1
ML20117H13321 May 1996Rev 3 to Grand Gulf Nuclear Station ISI for 10-Yr Program
ML20092J5328 September 1995ISI Summary Rept for Grand Gulf Nuclear Station Unit 1
ML18010B0845 May 1993NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.
ML18010A95230 November 1992NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.
Information Notice 1991-32, Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering15 May 1991Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering
Information Notice 1991-05, Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles30 January 1991Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles
ML20062A19416 October 1990Safety Evaluation Granting Relief Request from Inservice Insp Requirements
Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head30 April 1990Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head
Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm23 January 1990Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm
ML20246D80221 August 1989Safety Evaluation Granting 880524 Requests for Relief from Certain Requirements of ASME Code,Section XI
ML20247G57615 August 1989Inservice Insp Summary Rept for Grand Gulf Nuclear Station Unit 1
IR 05000416/198901126 April 1989Insp Rept 50-416/89-11 on 890410-14.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp, Including Review of Procedures,Nrc Bulletin 87-001,Generic Ltr 88-01,Info Notices 88-003 & 89-001 & Feedwater Valves
AECM-88-0104, Forwards Requests for Relief from Inservice Insp Plan Requirements of ASME Section Xi,Including Rev 1 to Relief Request I-00007 Re Amount of Exam Coverage Obtainable,Rev 2 to I-00010 & Rev 0 to I-0001924 May 1988Forwards Requests for Relief from Inservice Insp Plan Requirements of ASME Section Xi,Including Rev 1 to Relief Request I-00007 Re Amount of Exam Coverage Obtainable,Rev 2 to I-00010 & Rev 0 to I-00019
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