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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARRBG-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 Withheld1999-07-30030 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 ML20206R9271999-01-12012 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 Withheld1998-12-16016 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 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 19981998-11-20020 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 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-A1998-10-0808 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 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 50-458/97-131998-09-23023 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 EDGs1998-09-22022 September 1998 LAR 98-07 to License NPF-47,deleting License Conditions Associated with Transamerica Delaval,Inc EDGs 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,encl1998-04-0909 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 RBG-44223, Application for Amend to License NPF-47,proposing Addl Change to Administrative Controls Associated W/Lar 97-18. Change Listed1997-09-19019 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 Documents1997-08-15015 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 Withheld1997-08-0505 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 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 Withheld1997-01-20020 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 RBG-43560, Application for Amend to License NPF-47,requesting Rev to TS 3.4.11 Re RCS Pressure & Temp Limits1997-01-10010 January 1997 Application for Amend to License NPF-47,requesting Rev to TS 3.4.11 Re RCS Pressure & Temp Limits 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 21996-11-15015 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 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 1.121996-11-15015 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 ML20134H4051996-11-0606 November 1996 Application for Amend to License NPF-47,requesting Single Deviation from Approved Fire Protection Program IAW Change Process 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 Requirements1996-11-0606 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 RBG-43243, LAR 96-46 to License NPF-47,changing Tech Spec 3.8.1, A.C. Sources-Operating, Per GL 94-011996-10-24024 October 1996 LAR 96-46 to License NPF-47,changing Tech Spec 3.8.1, A.C. Sources-Operating, Per GL 94-01 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 Encl1996-08-29029 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 RBG-43161, Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power1996-08-29029 August 1996 Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power RBG-42913, Application for Amend to License NPF-47,revising Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves1996-08-0101 August 1996 Application for Amend to License NPF-47,revising Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20112E1741996-05-31031 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 3.8.31996-05-30030 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,Inc1996-05-20020 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 Cells1996-04-18018 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 RBG-42191, LAR 95-22,proposing Changes to Ts,By Eliminating Selected Response Time Testing Requirements1995-11-20020 November 1995 LAR 95-22,proposing Changes to Ts,By Eliminating Selected Response Time Testing Requirements 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 Leakage1995-11-20020 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 Corrections1995-10-26026 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 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 Program1995-10-24024 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 RBG-41728, LAR 95-04 to License NPF-47,revising TS Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions1995-08-17017 August 1995 LAR 95-04 to License NPF-47,revising TS Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions RBG-41632, Application for Amend to License NPF-47.Amend Will Implement TSs Based on NUREG-1434, Improved Tss,Rev 01995-06-30030 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 Structure1995-05-30030 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 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 Reactors1995-05-30030 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 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 Fire1995-01-20020 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 ML20077S4381995-01-18018 January 1995 Application for Amend to License NPF-47 Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20024J3321994-10-0404 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 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 94-021994-09-12012 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 ML20072U7861994-09-0808 September 1994 Application for Amend to License NPF-47,changing TS 3.10.2, Special Test Exceptions - Rod Pattern Control Sys RBG-40366, LAR 93-12 to License NPF-47,revising TS to Remove Turbine Overspeed Protection Sys Requirements1994-03-15015 March 1994 LAR 93-12 to License NPF-47,revising TS to Remove Turbine Overspeed Protection Sys Requirements RBG-40324, Application for Amend to License NPF-47,consisting of LAR 94-02,relocating Response Time Limits to Usar,Per GL 93-081994-03-0303 March 1994 Application for Amend to License NPF-47,consisting of LAR 94-02,relocating Response Time Limits to Usar,Per GL 93-08 ML20063K3691994-02-22022 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 & 91-081994-01-14014 January 1994 Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-08 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 Encl1994-01-14014 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 Testing1993-12-21021 December 1993 Application for Amend to License NPF-47,revising Applicable Tech Specs for one-time Extension Re Valve Leak Rate Testing ML20058H2221993-12-0808 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 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 01993-11-30030 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 ML20058C4121993-11-18018 November 1993 Application for Amends to License NPF-47,revising TS Re Valve Leak Rate Testing to Allow one-time Extension of Surveillance Intervals ML20045G2471993-07-0202 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 ML20045G8381993-07-0202 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 ML20044D5391993-05-13013 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 1999-07-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARRBG-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 Withheld1999-07-30030 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 ML20206R9271999-01-12012 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 Withheld1998-12-16016 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 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 19981998-11-20020 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 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-A1998-10-0808 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 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 50-458/97-131998-09-23023 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 EDGs1998-09-22022 September 1998 LAR 98-07 to License NPF-47,deleting License Conditions Associated with Transamerica Delaval,Inc EDGs 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,encl1998-04-0909 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 RBG-44223, Application for Amend to License NPF-47,proposing Addl Change to Administrative Controls Associated W/Lar 97-18. Change Listed1997-09-19019 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 Documents1997-08-15015 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 Withheld1997-08-0505 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 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 Withheld1997-01-20020 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 RBG-43560, Application for Amend to License NPF-47,requesting Rev to TS 3.4.11 Re RCS Pressure & Temp Limits1997-01-10010 January 1997 Application for Amend to License NPF-47,requesting Rev to TS 3.4.11 Re RCS Pressure & Temp Limits 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 1.121996-11-15015 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 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 21996-11-15015 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 ML20134H4051996-11-0606 November 1996 Application for Amend to License NPF-47,requesting Single Deviation from Approved Fire Protection Program IAW Change Process 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 Requirements1996-11-0606 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 RBG-43243, LAR 96-46 to License NPF-47,changing Tech Spec 3.8.1, A.C. Sources-Operating, Per GL 94-011996-10-24024 October 1996 LAR 96-46 to License NPF-47,changing Tech Spec 3.8.1, A.C. Sources-Operating, Per GL 94-01 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 Encl1996-08-29029 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 RBG-43161, Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power1996-08-29029 August 1996 Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power RBG-42913, Application for Amend to License NPF-47,revising Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves1996-08-0101 August 1996 Application for Amend to License NPF-47,revising Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20112E1741996-05-31031 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 3.8.31996-05-30030 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,Inc1996-05-20020 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 Cells1996-04-18018 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 RBG-42191, LAR 95-22,proposing Changes to Ts,By Eliminating Selected Response Time Testing Requirements1995-11-20020 November 1995 LAR 95-22,proposing Changes to Ts,By Eliminating Selected Response Time Testing Requirements 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 Leakage1995-11-20020 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 Corrections1995-10-26026 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 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 Program1995-10-24024 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 RBG-41728, LAR 95-04 to License NPF-47,revising TS Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions1995-08-17017 August 1995 LAR 95-04 to License NPF-47,revising TS Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions RBG-41632, Application for Amend to License NPF-47.Amend Will Implement TSs Based on NUREG-1434, Improved Tss,Rev 01995-06-30030 June 1995 Application for Amend to License NPF-47.Amend Will Implement TSs Based on NUREG-1434, Improved Tss,Rev 0 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 Reactors1995-05-30030 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 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 Structure1995-05-30030 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 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 Fire1995-01-20020 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 ML20077S4381995-01-18018 January 1995 Application for Amend to License NPF-47 Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20024J3321994-10-0404 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 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 94-021994-09-12012 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 ML20072U7861994-09-0808 September 1994 Application for Amend to License NPF-47,changing TS 3.10.2, Special Test Exceptions - Rod Pattern Control Sys RBG-40366, LAR 93-12 to License NPF-47,revising TS to Remove Turbine Overspeed Protection Sys Requirements1994-03-15015 March 1994 LAR 93-12 to License NPF-47,revising TS to Remove Turbine Overspeed Protection Sys Requirements RBG-40324, Application for Amend to License NPF-47,consisting of LAR 94-02,relocating Response Time Limits to Usar,Per GL 93-081994-03-0303 March 1994 Application for Amend to License NPF-47,consisting of LAR 94-02,relocating Response Time Limits to Usar,Per GL 93-08 ML20063K3691994-02-22022 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-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 Encl1994-01-14014 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-39894, Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-081994-01-14014 January 1994 Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-08 RBG-39796, Application for Amend to License NPF-47,revising Applicable Tech Specs for one-time Extension Re Valve Leak Rate Testing1993-12-21021 December 1993 Application for Amend to License NPF-47,revising Applicable Tech Specs for one-time Extension Re Valve Leak Rate Testing ML20058H2221993-12-0808 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 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 01993-11-30030 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 ML20058C4121993-11-18018 November 1993 Application for Amends to License NPF-47,revising TS Re Valve Leak Rate Testing to Allow one-time Extension of Surveillance Intervals ML20045G8381993-07-0202 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 ML20045G2471993-07-0202 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 ML20044D5391993-05-13013 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 1999-07-30
[Table view] |
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GULF STATES UTILITIES COMPANY RNE818thD ST AtlON POST OFFnCE BOX 220 SI FRAhCtSylLLE. LOUl$1ANA 70??5 t ARE4 CODE 604 636 6094 346 8651 I
September 28, 1990 RBG- 33677 File Nos._G9.5, G9.42-
"W U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.- 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Gulf States Utilities Company (GSU) hereby files an application.
to amend the River Bend Station- -
Unit 1 Technical Specifications, Appendix A to Facility Operating License. NPF-47, 4 pursuant to 10CFR50.90. This application is filed-to change the approval requirements for procedures and programs important to
-nuclear safety, as discussed in Technical Specification' Section 6 '. 5. 2.1. 'The Attachment to this letter and the Enclosure provide the- justifications and proposed revisions to the Technical Specifications.
Should you have any questions, please contact Mr. L. L..Dietrich of my staff at (504)-381-4866.
. Sincerely, 1
. . Odell >
Manager-0versight River Bend Nuclear Group Attachment I
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA ) ,
'PARISii OF WEST PELICIANA ) '
Docket No. 50-458 In-the Matter of )
GULF STATES UTILITIES COMPANY )
L (River Bend Station - Unit 1) '
APPIDAVIT W. H. Odell, being duly sworn, states that he is a Manager
- Oversight for Gulf' States Utilities Company; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to' the best of his knowledge, information and belief f
N~ H". ~Odell '
Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this cR P E day.of MAoXhddA , 19 h , My Commission expires with Life.
0AllLA L n l ur T Claudia F. Hurst Notary Public in and for West Feliciana Parish, Louisiana
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ATTACWENT F ' PROPOSED ,
GULF STATES UTILITIES COMPANY-RIVER BEND STATION DOCKET 50-458/ LICENSE NO. NPF-47 TECHNICAL REVIEW AND CONTROL (90-14)
LICENSING DOCUMENT INVOLVED: TECHNICAL SPECIFICATIONS ITEM: 6.5.2.1
-REASON FOR REQUEST:
In accordance with 10CFR50.90, a change is being requested to modify the approval-requirements for procedures and programs important to nuclear safety, as discussed in Technical Specification (TS) 6.5.2.1. In general terms, this specification currently requires procedures important to safety to be approved by the Plant Manager or one of the Assistant Plant Managers. Gulf States Utilities Company (GSU) believes that this requirement is overly restrictive and may not result in the most effective implementation of the procedure review program.
DISCUSSION:
The content required in the administrative controls section of the TS is specified in 10CFR50.36(c)(5). The regulation requires that the TS contain the controls and provisions that are necessary to assure operation of the facility in a safe manner and does specifically require inclusion of procedures and approvals.
TS 6.5.2.1 requires "Each procedure and program required by Specification 6.8 and other procedures that affect nuclear safety, and changes thereto, . . .
shall be approved, prior to implementation, by the Plant Manager or one of the Assistant Plant Managers or the Director - Radiological Programs , with the u exception of the Emergency Plan and implementing procedures which shall be h approved by the Manager - Administration, Plant Manager and Senior Vice President - RBNG."
Reviews of the River Bend Station (RBS) Safety Analysis Report, NUREG-0800, "USNRC Standard.-Review Plan", and NUREG-0989, " Safety Evaluation Report
'Related to the Operation of River Bend Station," revealed no specific requirements for Plant Manager approval of procedures related to safety.
Regulatory Guide 1.33, " Quality Assurance Program Requirements (0pera tion) ,"
which invokes ANSI N18.7-1976/ANS 3.2, provides only a guideline of the types of procedures that should be in place at nuclear facilities. Section 5.2.15 of. ANSI N18.7-1976/ANS 3.2 states that 1) Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure, 2)
Procedures shall be approved as designated by the owner organization before initial use. Rules shall be established which clearly delineate the review of procedures by knowledgeable personnel other than the originator and the approval of procedure and procedure changes by authorized individuals, and 3) g Page 1 of 3 J ,
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Changes. to d6cuments shall be reviewed and approved by the same organizations that perform the original review and approval unless the owner organization L designates another qualified organization.
_ River Bend Station procedures are divided into several groups. The highest tier procedures are the River Bend Nuclear Procedures (RBNP) that govern general. practices for all persons working at RBS. The Station Operating F Manual (SOM) contains procedures which dictate how the plant is operated and i maintained. . The Station Support Manual (SSM) provides the procedures used to support operation and maintenance of RBS for personnel other than Plant Staff and- Quality Assurance (e.g. Engineering, Licensing, Purchasing, etc.). The F majority of safety-related procedures are contained in the SOM and currently receive review by the Plant Manager or one of the assistant plant managers.
However, GSU believes that it will be appropriate to have the ability to have the safety-related procedures located in the SSM reviewed by the appropriate manager / department head. This will allow the person most familiar with the ,
t procedure the ability to approve it, thus providing a more comprehensive i review of the procedure.
To accomplish this, GSU believes that an additional statement should be added '
to TS 6.5.2.1 to allow the manager / department head responsible for the program or activity described in the procedure the ability to approve the procedure. j SIGNIFICANT HAZARDS CONSIDERATION:
f In accordance with the requirements of 10CFR50.92, the following discussions are provided in support of the determination that no significant hazards are created or increased by the change proposed by this submittal. !
- 1. The proposed change would not increase the probability or consequences cf a previously evaluated accident because: "
i The proposed changes are administrative in nature and do not affect assumptions contained in'any safety analyses nor do they affect Technical l Specifications that. preserve safety analysis assumptions. Additionally, f these changes do not modify the physical design or operation of the plant.
- 2. The proposed change would not create the possibility of a new or different l kind of accident from any previously evaluated because: ;
These proposed ' changes affect administrative controls on the River Bend l Station Technical Specifications and do not affect plant equipment or physical features. Specific operational requirements are required j elsewhere in the Technical Specifications that bear more directly on-operational safety than procedure approvals.
- 3. The proposed change would not involve a significant reduction in the margin of safety because: ;
The changes being proposed are administrative in nature and do not relate ,
to or modify the safety margin defined in or required and maintained by Technical Specifications. The provision to allow managers / department heads to approve procedures within their own area of responsibility will ,'
not decrease the effectiveness of these procedure reviews.
Page 2 of 3 l
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h Based'on the'above, it'is determined that the proposed change does not (1).
involve _ significant increase in the probability or consequences of an accident'
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a previously evaluated,'(2) create the probability of-a new or different kind of accident from.any accident previously evaluated, or (3) involve a significant reduction'in a margin of safety and therefore, does'not involve a "significant hazard consideration.
REVIS_ED_ TECHNICAL _ SPECIFICATION: f The requested revision is provided in the Enclosure.
SCHEDULE FOR ATTAINING COMPLIANCE:
GSU is. currently in full compliance' with the applicable Technical <
Specification requirements. I i
N0_TIFICATION OF STATE PERSONNEL:-
A' copy of this amendment request has been provided to the State of Louisiana, Department of Environmental Quality - Radiation Protection Division'.
ENVIRONMENTAL IMPACT APPRAISAL:
GSU has reviewed the proposed -license amendment against' the criteria of i 10CFR51.22 for environmental considerations. The proposed changes 'do not !
involve a significant hazards consideration, nor increase the types and ,
amounts of effluents that may be released offsite, nor significantly _ increase i individual or cumulative occupational radiation exposures. Based on the foregoing, GSU concludes that the proposed change meets the criteria given in 100FR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.
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