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| Issue date | Title | Topic | |
|---|---|---|---|
| RBG-45077, Application for Amend to License NPF-47 to Change TS to Extend Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt.Encl Proprietary GE Rept NEDC-32778P Withheld | 30 July 1999 | Application for Amend to License NPF-47 to Change TS to Extend Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt.Encl Proprietary GE Rept NEDC-32778P Withheld | Hydrostatic Abnormal operational transient MELLLA |
| ML20206R927 | 12 January 1999 | Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 | |
| RBG-44721, Application for Amend to License NPF-47,proposing Change to TS Safety Limit 2.1.1.2.Amend Will Change Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13.Proprietary Encl Withheld | 16 December 1998 | Application for Amend to License NPF-47,proposing Change to TS Safety Limit 2.1.1.2.Amend Will Change Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13.Proprietary Encl Withheld | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence |
| RBG-44726, Application for Amend to License NPF-47,adding New Proposed TS 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned in Early Dec 1998 | 20 November 1998 | Application for Amend to License NPF-47,adding New Proposed TS 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned in Early Dec 1998 | Shutdown Margin Fuel cladding Power change |
| RBG-44593, Application for Amend to License NPF-47,implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution,Enhanced Option I-A | 8 October 1998 | Application for Amend to License NPF-47,implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution,Enhanced Option I-A | Anticipated operational occurrence |
| 05000458/LER-1997-004, LAR 98-08 to License NPF-47,changing Specific Gravity Acceptance Criteria for Div III Battery,Re TS 3.8.6, Battery Cell Parameters. Condition Leading to Change Was Described in LER 97-004 & Insp Rept 50-458/97-13 | 23 September 1998 | LAR 98-08 to License NPF-47,changing Specific Gravity Acceptance Criteria for Div III Battery,Re TS 3.8.6, Battery Cell Parameters. Condition Leading to Change Was Described in LER 97-004 & Insp Rept 50-458/97-13 | |
| RBG-44562, LAR 98-07 to License NPF-47,deleting License Conditions Associated with Transamerica Delaval,Inc EDGs | 22 September 1998 | LAR 98-07 to License NPF-47,deleting License Conditions Associated with Transamerica Delaval,Inc EDGs | Nondestructive Examination |
| RBG-44457, Application for Amend to License NPF-47,revising License Condition 2.C(13) Concerning Final Feedwater Temp Reduction Analysis, LAR 97-16.Affidavit Supporting LAR & Proprietary GE Rept NEDC-32549P,dtd May 1997,encl | 9 April 1998 | Application for Amend to License NPF-47,revising License Condition 2.C(13) Concerning Final Feedwater Temp Reduction Analysis, LAR 97-16.Affidavit Supporting LAR & Proprietary GE Rept NEDC-32549P,dtd May 1997,encl | Anticipated operational occurrence Abnormal operational transient Feedwater Controller Failure |
| RBG-44223, Application for Amend to License NPF-47,proposing Addl Change to Administrative Controls Associated W/Lar 97-18. Change Listed | 19 September 1997 | Application for Amend to License NPF-47,proposing Addl Change to Administrative Controls Associated W/Lar 97-18. Change Listed | |
| RBG-44153, Forwards Proposed Administrative Changes to LAR 96-42 & LAR 97-18,to Modify TS 2.1.1.2 W/Note Indicating Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents | 15 August 1997 | Forwards Proposed Administrative Changes to LAR 96-42 & LAR 97-18,to Modify TS 2.1.1.2 W/Note Indicating Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents | |
| RBG-44035, Application for Amend to License NPF-47,changing TS Safety Limit 2.1.1.2, Reactor Core (Safety Limits), to Increase Two Recirculation Loop MCPR Limit to 1.13.Proprietary Info Encl.Proprietary Encl Withheld | 5 August 1997 | Application for Amend to License NPF-47,changing TS Safety Limit 2.1.1.2, Reactor Core (Safety Limits), to Increase Two Recirculation Loop MCPR Limit to 1.13.Proprietary Info Encl.Proprietary Encl Withheld | Anticipated operational occurrence |
| RBG-43608, Application for Amend to License NPF-47,to Enhance Operation of Plant,Thereby Yielding Economic Benefit to RBS Through Extended Power production.NEDC-32611P Encl.Rept Withheld | 20 January 1997 | Application for Amend to License NPF-47,to Enhance Operation of Plant,Thereby Yielding Economic Benefit to RBS Through Extended Power production.NEDC-32611P Encl.Rept Withheld | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Abnormal operational transient Feedwater Controller Failure Fuel cladding Flow Induced Vibration |
| RBG-43560, Application for Amend to License NPF-47,requesting Rev to TS 3.4.11 Re RCS Pressure & Temp Limits | 10 January 1997 | Application for Amend to License NPF-47,requesting Rev to TS 3.4.11 Re RCS Pressure & Temp Limits | Unanalyzed Condition Anticipated operational occurrence Hydrostatic Affidavit |
| RBG-43328, Application for Amend to License NPF-47,requesting Mod to Surveillance Requirement 3.8.1.14 to Allow 24-hour Diesel Generator Maint Run While Unit Is in Either Mode 1 or Mode 2 | 15 November 1996 | Application for Amend to License NPF-47,requesting Mod to Surveillance Requirement 3.8.1.14 to Allow 24-hour Diesel Generator Maint Run While Unit Is in Either Mode 1 or Mode 2 | Fuel cladding |
| RBG-43326, Application for Amend to License NPF-47,changing TS SL 2.1.1.2, Reactor Core (Safety Limits), Which Will Increase Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR Limit from 1.08 to 1.12 | 15 November 1996 | Application for Amend to License NPF-47,changing TS SL 2.1.1.2, Reactor Core (Safety Limits), Which Will Increase Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR Limit from 1.08 to 1.12 | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence |
| ML20134H405 | 6 November 1996 | Application for Amend to License NPF-47,requesting Single Deviation from Approved Fire Protection Program IAW Change Process | Safe Shutdown Fire Barrier Fire Protection Program Fire Watch |
| RBG-43358, Application for Amend to License NPF-47,permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Main steam-positive Leakage Control Sys Requirements | 6 November 1996 | Application for Amend to License NPF-47,permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Main steam-positive Leakage Control Sys Requirements | Local Leak Rate Testing Integrated leak rate test Exemption Request Fuel cladding Affidavit |
| RBG-43243, LAR 96-46 to License NPF-47,changing Tech Spec 3.8.1, A.C. Sources-Operating, Per GL 94-01 | 24 October 1996 | LAR 96-46 to License NPF-47,changing Tech Spec 3.8.1, A.C. Sources-Operating, Per GL 94-01 | Reactor Vessel Water Level |
| RBG-43042, License Amend Request 96-35 Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule. GE-NE-B1301807-02, Surveillance Specimen Program Evaluation for River Bend Station Encl | 29 August 1996 | License Amend Request 96-35 Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule. GE-NE-B1301807-02, Surveillance Specimen Program Evaluation for River Bend Station Encl | Unanalyzed Condition Anticipated operational occurrence Hydrostatic |
| RBG-43161, Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power | 29 August 1996 | Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power | Anticipated operational occurrence MELLLA |
| RBG-42913, Application for Amend to License NPF-47,revising Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves | 1 August 1996 | Application for Amend to License NPF-47,revising Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves | |
| ML20112E174 | 31 May 1996 | Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks | |
| RBG-42946, Application for Amend to License NPF-47,consisting of Licensing Amend Request 96-25 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG in TS 3.8.3 | 30 May 1996 | Application for Amend to License NPF-47,consisting of Licensing Amend Request 96-25 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG in TS 3.8.3 | |
| RBG-42920, License Amend Request (LAR) 96-29 to License NPF-29, Reflecting Change in Name from Gulf States Utils Co to Entergy Gulf States,Inc | 20 May 1996 | License Amend Request (LAR) 96-29 to License NPF-29, Reflecting Change in Name from Gulf States Utils Co to Entergy Gulf States,Inc | |
| RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells | 18 April 1996 | Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells | Shutdown Margin Spiral reload |
| RBG-42191, LAR 95-22,proposing Changes to Ts,By Eliminating Selected Response Time Testing Requirements | 20 November 1995 | LAR 95-22,proposing Changes to Ts,By Eliminating Selected Response Time Testing Requirements | Reactor Vessel Water Level |
| RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage | 20 November 1995 | Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage | |
| RBG-41968, Application for Amend to License NPF-47,consisting of Change Request 95-10,deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections | 26 October 1995 | Application for Amend to License NPF-47,consisting of Change Request 95-10,deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections | Loop seal High Radiation Area Post Accident Monitoring Biofouling |
| RBG-42084, Application for Amend to License NPF-47,consisting of LAR 95-21,changing TS 3.6.1.1 Through 3.6.1.3 Re Containment Sys & Notifies of Intent to Implement performance-based Containment Leak Rate Testing Program | 24 October 1995 | Application for Amend to License NPF-47,consisting of LAR 95-21,changing TS 3.6.1.1 Through 3.6.1.3 Re Containment Sys & Notifies of Intent to Implement performance-based Containment Leak Rate Testing Program | Integrated leak rate test Exemption Request |
| RBG-41728, LAR 95-04 to License NPF-47,revising TS Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions | 17 August 1995 | LAR 95-04 to License NPF-47,revising TS Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions | Fuel cladding Recently irradiated fuel Affidavit |
| RBG-41632, Application for Amend to License NPF-47.Amend Will Implement TSs Based on NUREG-1434, Improved Tss,Rev 0 | 30 June 1995 | Application for Amend to License NPF-47.Amend Will Implement TSs Based on NUREG-1434, Improved Tss,Rev 0 | |
| RBG-41525, Application for Amend to License NPF-47,allowing TS 3/4.6.2.2, Drywell Bypass Leakage, to Be Performed at Intervals as Long as Five Yrs Based Upon Demonstrated Performance of Drywell Structure | 30 May 1995 | Application for Amend to License NPF-47,allowing TS 3/4.6.2.2, Drywell Bypass Leakage, to Be Performed at Intervals as Long as Five Yrs Based Upon Demonstrated Performance of Drywell Structure | Integrated leak rate test Water hammer |
| RBG-41524, Application for Amend to License NPF-47,applying for Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors | 30 May 1995 | Application for Amend to License NPF-47,applying for Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors | Probabilistic Risk Assessment Integrated leak rate test |
| RBG-41159, LAR 95-01 to License NPF-47,requesting Deviation from 10CFR50,App R,Section III.G.3 W/Respect to Requirement for Fixed Fire Suppression Sys in Fire Area C-17 in Order to Credit Remote Shutdown Sys for Shutdown in Event of Fire | 20 January 1995 | LAR 95-01 to License NPF-47,requesting Deviation from 10CFR50,App R,Section III.G.3 W/Respect to Requirement for Fixed Fire Suppression Sys in Fire Area C-17 in Order to Credit Remote Shutdown Sys for Shutdown in Event of Fire | Safe Shutdown Fire Barrier Fire Protection Program Fire Watch Hourly Fire Watch |
| ML20077S438 | 18 January 1995 | Application for Amend to License NPF-47 Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 | |
| ML20024J332 | 4 October 1994 | LAR 94-11,revising TS 4.11.2.1.2 Table 4.11.2.1.2-1,by Removing one-hour Requirement for Completing Noble Gas & Tritium Sampling & Analysis | Grab sample Offsite Dose Calculation Manual Power change |
| RBG-40868, LAR 94-10 to License NPF-47,changing TS 3/4.2.2, APRM Setpoints in Order to Be Able to Operate Greater than 35% Rtp,Per Condition Identified During Review of GL 94-02 | 12 September 1994 | LAR 94-10 to License NPF-47,changing TS 3/4.2.2, APRM Setpoints in Order to Be Able to Operate Greater than 35% Rtp,Per Condition Identified During Review of GL 94-02 | Anticipated operational occurrence |
| ML20072U786 | 8 September 1994 | Application for Amend to License NPF-47,changing TS 3.10.2, Special Test Exceptions - Rod Pattern Control Sys | Anticipated operational occurrence |
| RBG-40366, LAR 93-12 to License NPF-47,revising TS to Remove Turbine Overspeed Protection Sys Requirements | 15 March 1994 | LAR 93-12 to License NPF-47,revising TS to Remove Turbine Overspeed Protection Sys Requirements | Turbine Missile |
| RBG-40324, Application for Amend to License NPF-47,consisting of LAR 94-02,relocating Response Time Limits to Usar,Per GL 93-08 | 3 March 1994 | Application for Amend to License NPF-47,consisting of LAR 94-02,relocating Response Time Limits to Usar,Per GL 93-08 | |
| ML20063K369 | 22 February 1994 | Application for Amend to License NPF-47,requesting Line Item Improvement Consistent W/Tech Specs 3.6.1.8 & 3.6.1.9 of NUREG-1434, Std TS GE Plants,BWR/6 | |
| RBG-39894, Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-08 | 14 January 1994 | Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-08 | Reactor Vessel Water Level |
| RBG-39895, Application for Amend to License NPF-47,extending Allowable Outage Times of Instruments Involved & Increase Channel Functional Surveillance Test Interval from Monthly to Quarterly Requirement.Proprietary Rept Encl | 14 January 1994 | Application for Amend to License NPF-47,extending Allowable Outage Times of Instruments Involved & Increase Channel Functional Surveillance Test Interval from Monthly to Quarterly Requirement.Proprietary Rept Encl | |
| RBG-39796, Application for Amend to License NPF-47,revising Applicable Tech Specs for one-time Extension Re Valve Leak Rate Testing | 21 December 1993 | Application for Amend to License NPF-47,revising Applicable Tech Specs for one-time Extension Re Valve Leak Rate Testing | |
| ML20058H222 | 8 December 1993 | Application for Amend to License NPF-47,revising TS Re Sys Testing & Instrumentation Calibration,Response Time Testing & Lfst to Allow one-time Extension of Surveillance Intervals | Reactor Vessel Water Level Scram Discharge Volume Affidavit |
| RBG-39478, Application for Amend to License NPF-47,proposing Changes to Improve TS Through Implementation of Guidance in NUREG-1434, Sts,Ge Plants BWR/6, Rev 0 | 30 November 1993 | Application for Amend to License NPF-47,proposing Changes to Improve TS Through Implementation of Guidance in NUREG-1434, Sts,Ge Plants BWR/6, Rev 0 | |
| ML20058C412 | 18 November 1993 | Application for Amends to License NPF-47,revising TS Re Valve Leak Rate Testing to Allow one-time Extension of Surveillance Intervals | |
| ML20045G247 | 2 July 1993 | Application for Amend to License NPF-47,revising TS 6.9.3.2,part of Colr.Revision Indicates Cycle 5 Impact on Operating Limit Not Due to Core Verifications | Anticipated operational occurrence Fuel cladding |
| ML20045G838 | 2 July 1993 | Application for Amend to License NPF-47,revising TS to Change Frequency for Submittal of Radioactive Effluent Release Repts from Semiannual to Annual & to Extend Preparation Period from 60 Days to 90 Days | Offsite Dose Calculation Manual Process Control Program Affidavit |
| ML20044D539 | 13 May 1993 | Application for Amend to License NPF-47,changing Attachment 3 to License NPF-47,Amend 15, Tdi Diesel Engines Requirements. Group Cross Ref Table Between NUREG-1216 & Current River Bend Status Encl | Nondestructive Examination Liquid penetrant Affidavit |