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 Issue dateTitle
05000416/FIN-2010004-07Licensee-Identified Violation
05000416/LER-2005-001
05000416/LER-2013-003Reactor Protection System and Reactor Core Isolation Cooling Actuation Due to a High Reactor Pressure Transient
AECM-81-467, Final Deficiency Rept Re Incorrect Reactor Water Level Measuring Devices Initially Reported 810823.Wide Range Instrumentation Removed & Replaced W/Narrow Range Instrumentation.Also Reported Per Part 217 December 1981Final Deficiency Rept Re Incorrect Reactor Water Level Measuring Devices Initially Reported 810823.Wide Range Instrumentation Removed & Replaced W/Narrow Range Instrumentation.Also Reported Per Part 21
AECM-82-368, Forwards Review of NUREG-0737,Item II.F.2,Instrumentation for Detection of Inadequate Core Cooling, Per Supplemental SER 2,Item 22.230 August 1982Forwards Review of NUREG-0737,Item II.F.2,Instrumentation for Detection of Inadequate Core Cooling, Per Supplemental SER 2,Item 22.2
AECM-83-0565, Forwards marked-up Proposed Changes to Tech Specs Per 821020 Confirmation of Action Ltr.Changes Intended to Enhance Clarity or Provide Consistency W/Plant Design & Operation. Justification for NSHC Encl9 September 1983Forwards marked-up Proposed Changes to Tech Specs Per 821020 Confirmation of Action Ltr.Changes Intended to Enhance Clarity or Provide Consistency W/Plant Design & Operation. Justification for NSHC Encl
AECM-84-0093, Forwards Definitions of Channel,Trip Sys & Trip Function for Remaining Instrumentation in Tech Spec Section 3/4.3, Incorporating Secondary Containment Isolation & Corrects 831213 Submittal Re Terminology8 May 1984Forwards Definitions of Channel,Trip Sys & Trip Function for Remaining Instrumentation in Tech Spec Section 3/4.3, Incorporating Secondary Containment Isolation & Corrects 831213 Submittal Re Terminology
AECM-84-0205, Submits Addl Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment. Insp & Surveillance of Containment Sumps,Drywell,Piping & Closed Coolant Water Sys Discussed.Action Completed8 May 1984Submits Addl Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment. Insp & Surveillance of Containment Sumps,Drywell,Piping & Closed Coolant Water Sys Discussed.Action Completed
AECM-84-0226, Responds to 840323 Confirmation of Action Ltr Re Verifying Removal of Certain Individuals from Licensed Duties.Util Has Evaluated Licensed Operators to Determine If Deficiency Identified Applicable to Other Operators.Related Info Encl16 April 1984Responds to 840323 Confirmation of Action Ltr Re Verifying Removal of Certain Individuals from Licensed Duties.Util Has Evaluated Licensed Operators to Determine If Deficiency Identified Applicable to Other Operators.Related Info Encl
AECM-84-0318, Application for Amend to License NPF-13,revising Tech Specs to Correct Typographical Errors,To Implement Editorial Changes & to Provide Clarification of Basic Meaning & Intent of Tech Spec changes.Marked-up Tech Specs Encl21 June 1984Application for Amend to License NPF-13,revising Tech Specs to Correct Typographical Errors,To Implement Editorial Changes & to Provide Clarification of Basic Meaning & Intent of Tech Spec changes.Marked-up Tech Specs Encl
AECM-84-0465, Forwards Response to Generic Ltr 83-28,Items 1.1 & 1.2 Re post-trip Review Program Description & Procedure & Data & Info Capability,Respectively2 November 1984Forwards Response to Generic Ltr 83-28,Items 1.1 & 1.2 Re post-trip Review Program Description & Procedure & Data & Info Capability,Respectively
AECM-84-0521, Responds to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs. No Mods Necessary.License Condition 2.c.(33)(e) Resolved Based on Response6 December 1984Responds to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs. No Mods Necessary.License Condition 2.c.(33)(e) Resolved Based on Response
AECM-85-0145, Responds to NRC Re Violations Noted in Insp Rept 50-416/85-06.Corrective Actions:Reactor Vessel Instrument Control Procedures Revised & Withdrawal of Commitment to Submit Annual ECCS Outage Data Per NUREG-0737 Requested6 May 1985Responds to NRC Re Violations Noted in Insp Rept 50-416/85-06.Corrective Actions:Reactor Vessel Instrument Control Procedures Revised & Withdrawal of Commitment to Submit Annual ECCS Outage Data Per NUREG-0737 Requested
AECM-86-0160, Forwards Final Proposed Tech Specs for Core Stability Single Loop Operation & Max Extended Operating Domain2 June 1986Forwards Final Proposed Tech Specs for Core Stability Single Loop Operation & Max Extended Operating Domain
AECM-87-0152, Application for Amend to License NPF-29,making Alternative Rod Insertion Design Mods to Comply w/10CFR50.62 ATWS Requirements.Description of Alternate Rod Insertion Sys to Be Installed & Testing Commitments Encl.Fee Paid13 August 1987Application for Amend to License NPF-29,making Alternative Rod Insertion Design Mods to Comply w/10CFR50.62 ATWS Requirements.Description of Alternate Rod Insertion Sys to Be Installed & Testing Commitments Encl.Fee Paid
AECM-88-0218, Submits Addl Info Re 880819 Application for Amend to License NPF-29,per NRC 881006 Request.Proposed Administrative Changes to Fire Protection Specs Per Generic Ltr 87-09, Included in Amend Request9 November 1988Submits Addl Info Re 880819 Application for Amend to License NPF-29,per NRC 881006 Request.Proposed Administrative Changes to Fire Protection Specs Per Generic Ltr 87-09, Included in Amend Request
AECM-89-0038, Application for Amend to License NPF-29,allowing one-time Exceptions to Tech Spec 3.0.4 in Lieu of Much Broader Scope Changes Associated W/Generic Ltr 87-0920 February 1989Application for Amend to License NPF-29,allowing one-time Exceptions to Tech Spec 3.0.4 in Lieu of Much Broader Scope Changes Associated W/Generic Ltr 87-09
AECM-90-0165, Forwards Addl Info on NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount12 September 1990Forwards Addl Info on NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount
AECM-90-0177, Responds to NRC Re Violations Noted in Insp Rept 50-416/90-15.Corrective Actions:Surveillance Procedure 06-IC-1C34-m-001 Changed to Move Terminal Points More Easily2 October 1990Responds to NRC Re Violations Noted in Insp Rept 50-416/90-15.Corrective Actions:Surveillance Procedure 06-IC-1C34-m-001 Changed to Move Terminal Points More Easily
AECM-90-0198, Forwards Response to Recommendations Noted in NRC Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping7 December 1990Forwards Response to Recommendations Noted in NRC Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 27 March 2019Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2
ENS 47679Manual Reactor Scram During Shutdown Due to Lowering Reactor Vessel Water Level (Rvwl)
GNRO-2002/00011, Request for License Amendment to Add Limiting Condition for Operation25 February 2002Request for License Amendment to Add Limiting Condition for Operation
GNRO-2002/00072, Supplement to Amendment Request, Response to Request for Additional Information Concerning New Special Operations Limiting Condition for Operation Suppression Pool Makeup-Mode 316 August 2002Supplement to Amendment Request, Response to Request for Additional Information Concerning New Special Operations Limiting Condition for Operation Suppression Pool Makeup-Mode 3
GNRO-2003/00025, License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-0338 May 2003License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-033
GNRO-2003/00027, Technical Specification Bases Update to the NRC for Period Dated April 25, 200325 April 2003Technical Specification Bases Update to the NRC for Period Dated April 25, 2003
GNRO-2003/00032, Amendment Request Modification of Technical Specification 3.3.6.1 Re Shutdown Cooling System Isolation Instrumentation12 May 2003Amendment Request Modification of Technical Specification 3.3.6.1 Re Shutdown Cooling System Isolation Instrumentation
GNRO-2003/00035, Technical Specification Bases Update to the NRC for Period Dated 06/06/20036 June 2003Technical Specification Bases Update to the NRC for Period Dated 06/06/2003
GNRO-2003/00067, Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology-LDC 2003-09316 December 2003Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology-LDC 2003-093
GNRO-2003/00072, Revised License Amendment Request Regarding Shutdown Cooling System Isolation Instrumentation5 December 2003Revised License Amendment Request Regarding Shutdown Cooling System Isolation Instrumentation
GNRO-2003/00075, Response to Request for Additional Information Shutdown Cooling System Isolation Instrumentation18 December 2003Response to Request for Additional Information Shutdown Cooling System Isolation Instrumentation
GNRO-2004/00002, Technical Specification Bases Update to the NRC for Period Dated January 22, 200422 January 2004Technical Specification Bases Update to the NRC for Period Dated January 22, 2004
GNRO-2004/00057, Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology19 November 2004Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology
GNRO-2006/00052, Technical Requirements Manual Update to NRC for Period Dated September 21, 200621 September 2006Technical Requirements Manual Update to NRC for Period Dated September 21, 2006
GNRO-2007/00061, (Ggns), Supplement to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints5 September 2007(Ggns), Supplement to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints
GNRO-2008/00006, to Amendment Request Condensate Storage Tank Setpoint Change, Grand Gulf Nuclear Station, Unit 114 February 2008to Amendment Request Condensate Storage Tank Setpoint Change, Grand Gulf Nuclear Station, Unit 1
GNRO-2008/00078, Response to Basis for Denial of Condensate Storage Tank Setpoint Change Letter Dated November 5, 200819 January 2009Response to Basis for Denial of Condensate Storage Tank Setpoint Change Letter Dated November 5, 2008
GNRO-2009/00062, License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits27 October 2009License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits
GNRO-2010/00009, Technical Specification Bases Update to the NRC for Period Dated January 20, 200920 January 2010Technical Specification Bases Update to the NRC for Period Dated January 20, 2009
GNRO-2010/00067, License Amendment Request to Implement TSTF-493 for Condensate Storage Tank Low Level Setpoint8 November 2010License Amendment Request to Implement TSTF-493 for Condensate Storage Tank Low Level Setpoint
GNRO-2011/00043, Request for Additional Information Regarding Extended Power Uprate8 June 2011Request for Additional Information Regarding Extended Power Uprate
GNRO-2011/00064, License Amendment Request to Revise Technical Specification 2.1.1.228 October 2011License Amendment Request to Revise Technical Specification 2.1.1.2
GNRO-2011/00072, Technical Requirements Manual and Technical Specification Bases Update12 September 2011Technical Requirements Manual and Technical Specification Bases Update
GNRO-2011/00096, Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme Grand Gulf Nuclear Station28 October 2011Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme Grand Gulf Nuclear Station
GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update21 December 2012Technical Requirements Manual and Technical Specification Bases Update
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-2014/00068, License Amendment Request to Revise Technical Specification 2.1.1.221 November 2014License Amendment Request to Revise Technical Specification 2.1.1.2
GNRO-2016/00024, Operating License Manual Update Submittal17 May 2016Operating License Manual Update Submittal
GNRO-2018/00007, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control.10 April 2018Application to Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control.
GNRO-2018/00039, Report of Technical Specification Bases Changes20 August 2018Report of Technical Specification Bases Changes
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