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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
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,.s GUEF STATES UTELITIES COMPANY RIVER BEND ST ATION POST OFFICE BOX 220 ' 57. FRANCISVILLE. LOUIStANA 70775 AREA CODE $04 836 60945 346 8651 3 August 7, 1987 ,
RBG- 26408 )
File Nos. G9.5, G9.25.1.4 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 !
Gentlemen:
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I River Bend Station - Unit 1 Docket No. 50-458 Gulf . States Utilities (GSU) hereby files an amendment ~to the River Bend Station Unit 1 Technical Specifications, Appendix A to Facility Operating License NPF-47, pursuant to 10CFR50.90. This application is filed to revise Technical Specification 3.8.1.1, ?.C Sources-Operating.
Actions relating to demonstrating the diesel generators operability with I offsite circuits inoperable or onsite diesel. generators . inoperable.
Attachments- 1 and 2- address the offsite and onsite AC sources, respectively. The Enclosure contains the proposed revisions to the River Bend Station Technica1' Specifications.
River Bend Station Technical Specification 3.8.1.1, AC Sources-Operating currently requires that diesel generator operability be demonstrated as a result of conditions which may not have, and in most cases do not have, an impact on the reliability of the diesel generators. This requested change will revise these requirements to perform additional operability testing only when conditions warrant. This change would j therefore result in further reducing excessive test starts. River Bend' l Station has previously incorporated the recommendations of Generic Letter 85-16.
Pt osuant to 10CFR170.12, GSU has enclosed a check in the amount of one-hundred and fifty dollars ($150.00) for the- license amendment application fee. Your prompt attention to this application is apprecia'ed.
Sincerely, v 1 J. C. Deddens '
b Senior Vice President D ,
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.tAl River Bend Nuclear Group
/ ERG DAS/ch el 4040 Attachments 8708130228 870007 PDR ADOCK 05000458 p PDR w
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION l 1
l STATE OF LOUISIANA )
PARISH OF WEST FELICIANA )
In the Matter of ) Docket No. 50-458 50-459 .I GULF STATES UTILITIES COMPANY )
(River Bend St'ation, Unit 1)
AFFIDAVIT J. C. Deddens, being duly sworn, states that he is a Senior Vice President of 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.
, / ' W J.'b.Deddens Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this 7h1 day of k110)LAbf , 19 b.
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[Joan W. Middlebrooks Notary Public in and for West Feliciana Parish, Louisiana My Commission is for Life.
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cc: ' Mr. Robert D. Martin, Regional Administrator U.S. Nuclear Regulatory Commission I Region IV 611 Ryan Plaza Drive, Suite 1000
~11ngton, TX 76011 ARC Senior Resident Inspector P.O. Box 1051 St. Francisv111e, LA 70775 Mr. William H. Spell, Administrator Nuclear Energy Division Louisiana Department of Environmental Quality P.O. Box 14690 Baton Rouge, LA 70898
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ATTACHMENT 1 j GULF STATES UTILITIES COMPANY RIVER BEND STATION l DOCKET 50-458/ LICENSE NO. NPF-47 l
AC SOURCES - 0FFSITE LICENSING DOCUMENT INVOLVED: TECHNICAL SPECIFICATIONS ITEMS: 3.8.1.1 Action a ~
PAGE: 3/4 8-1 3.8.1.1 Action f 3/4 8-2 and 8-3 I
REASON FOR REQUEST A change is being requested in accordance with 10CFRf0.90 to remove the j requirements to start the diesel generators (DG) under degraded offsite l power conditions. River Bend Station Technical Specification 3.8.1.1, l
AC Sources-Operating, Actions a and f currently require that the diesel '
generators be demonstrated operable by performing surveillance requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 with offsite circuits inoperable. This proposed change would therefore result in further r'ducing the number of excessive test starts and reduce unnecessary hardship on the equipment. River Bend Station has previously incorporated the recommendations of Generic Letter 85-16.
DESCRIPTION As addressed in IE Information Notice 84-69, and Supplement 1 " Operation of Emergency Diesel Generators," when a DG is operated connected to offsite sources and nonvital loads, disturbances in thes-e areas can adversely affect DC reliability. Further, this reliability is significantly reduced when the offsite circuits are degraded or not available. Additionally, a demand for emergency DG start is more probable while connected to the grid and nonvital loads for the required ,
surveillance. These surveillance require the diesel generatora be started and reach rated speed, voltage and frequency within 10 seconds, be synchronized to the grid, and be fully loaded in less than 60 seconds for at least one hour.
This proposed change would delete the requirements to start the diesel generators, synchronize and load them to the safety buses in Actions a and f during periods when offsite power is in a degraded condition. The required " demonstration" of DG operability was intended to add assurance l of availability of onsite AC sources in the event of degraded offsite sources. It is contended that adequate assurance of DG operability is maintained by the frequencies specified in the normal Technical Specification surveillance requirements. Additionally, as stated above, l assurance of DG availability is lessened by a demonstration requiring !
connecting the DGs to offsite sources when the offsite sources are !
abnormally degraded. !
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SIGNIFICANT HAZARDS CONSIDERATIONS As required by 10CFR50.92, the following is provided to the NRC Staff in support of'"no significant hazards considerations."
- 1. No significant increase in the probability or the consequences of an accident previously evaluated results from this change because:
The required " demonstration" of DG operability was intended to add assurance of availability of onsite AC sources in the event of l degraded offsite sources. It is contended that adequate assurance of DG operability is maintained by the testing frequencies specified
=in the normal Technical Specification surveillance requirements. j Assurance' of DG availability is lessened by a demonstration j requiring connecting the DGs to offsite sources when the offsite '
sources are abnormally degraded.
Additionally , as outlined in IE Information Notice 84-69 and Supplement 1, " Operation of Emergency Diesel Generators,"
potentially significant safety problems can arise when one or more DGs are operated in modes other-than the prescribed standby service mode (such as in parallel with offsite power sources as required by the subject Actions). Testing of DGs when offsite circuits are in jeopardy can lead to a complete loss of-AC power to safety buses.
Therefore, not testing DGs as currently required by Technical Specification 3.8.1.1 regarding inoperable offsite circuits will tend to decrease the probability or the consequences of an accident previously. evaluated.
- 2. This change would not create the possibility of a new or different kind of accident from any accident previously evaluated because:
By not testing DGs as currently required by Technical Specification l' Section 3.8.1.1, no possibility of a new or different accident than previously evaluated is created because no new modes of operation are introduced. 'All equipment functions remain as previously evaluated in the River Bend Station FSAR and SER. Conformance with applicable Regulatory Guides is maintained as indicated in FSAR Section 1.8.
- 3. This change would not involve a significant reduction in the margin of safety because:
The DCs are less vulnerable when in their normal standby alignment i and not parallel to the grid. As outlined in IE Information Notice I 84-69 and Supplement 1, " Operation of Emergency Diesel Generators,"
potentially significant safety problems can arice when one or more DGs are operated in modes other than the prescribed standb. service mode (such as in parallel with offsite power sources as requ; red by the subject actions). Testing of DGs when offsite circuits are in jeopardy can lead to a complete loss of AC power to safety buses. I Therefore, not testing DGs as currently outlined in Technical Specification 3.8.1.1 will tend to increase the margin of safety by
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not exposing DGs to the offsite transmission network when it is in a ,
degraded condition. Additionally, the Technical Specification bases {
do not define any margin or safety for this surveillance j requirement. j The proposed amendment as discussed above, has not changed the system i design, function or operation as discussed in the FSAR and therefore, will not increase the probability or the consequences- of a previously evaluated accident and will not create a new or different accident.
Adequate assurance of DG availability is maintained by the testing frequencies specified in the normal Technical Specification surveillance requirements. Also, the results of the change are clearly within acceptable criteria with respect to system components' and design requirements. As a result, the ability to perform as described in the FSAR is maintained and therefore, the proposed change does not result in a significant reduction in the margin of safety. Therefore, GSU proposes that no significant hazards are involved.
REVISED TECHNICAL SPECIFICATION The requested revisfon is provided in the Enclosure.
SCHEDULE FOR ATTAINING COMPLIANCE As indicated above, River Bend Station is currently in compliance with the applicable Technical Specification.
NOTIFICATION OF STATE PERSONNEL A copy of this amendment application has been provided to the State of Louisiana, Department of Environmental Quality - Nuclear Energy Division.
ENVIRONMENTAL IMPACT APPRAISAL Revision of this Technical Specification does not result in an environmental impact beyond that previously analyzed. Therefore, approval of this amendment does not result in a significant environmental impact nor does it change any previous environmental impact statements for River Bend Station.
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f ATTACHMENT 2 GULF STATES UTILITIES COMPANY RIVER BEND STATION DOCKET 50-458/ LICENSE NO. NPF-47 AC SOURCES - ONSITE LICENSING DOCUMENT INVOLVED: TEC3NICAL SPECIFICATIONS ITEMS: 3.8.1.1 Action b PAGE: 3/4 8-1 3.8.1.1 Action c 3/4 8-2 3.8.1.1 Action d 3/4 8-2 3.8.1.1 Action g 3/4 8-3 3/4.8.1 Bases B 3/4 8-1 i REASON FOR REQUEST i River Bend Station Technical Specification 3.8.1.1, AC Sources-Operating, Actions b, c, d, and g currently require that with a diesel i generator (DG) inoperable due to any cause other than preplanned preventive maintenance or testing, the remaining DGs be demonstrated operable by performing surveillance requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5. This proposed change would therefore result in further reducing the number of excessive test starts and reduce unnecessary hardship on the equipment. River Bend Station has previously incorporated the recommendations of Generic Letter 85-16.
DISCUSSION These Technical Specification surveillance require the DGs be started and reach rated speed, voltage and frequency within 10 seconds, be synchronized to the grid, and be fully loaded in 60 seconds for at least one hour. This proposed change would revise these Actions to require the operability of the remaining DGs be demonstrated only if the other DG became inoperable as a result of a " valid failure" as defined in US NRC Regulatory Guide 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants", Revision !
1, August 1977.
The requirements to demonstrate the operability of the remaining operable DGs during these events are, in part, to verify that no common mode / generic failures exist on the redundant DGs. There are countless circumstances which could render a DG inoperable and not bring into question the possibility of a similar " generic" problem with other onsite DGs (e.g., any number of auxiliary support system Iailures which are easily detected and are functional on redundant DGs). If the inoperability was a readily identified failure under non-operating circumstances and can be assured not to exist on the remainine operable i DGs, there should be no requirement to operate any o aer DG to i
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demonstrate its operability. If the inoperable DG was a result of a
. failure during operation and is related to its ability to perform its safety related function, it would then seem appropriate to subject the remaining operable DGs to an additional demonstration to show no common mode / generic problem exists. As outlined in Regulatory Guide 1.108 and the Technical Specifications, it is " valid failures" which should require increased scrutiny and increased testing to. assure DG availability. If a DG were discovered inoperable while in the standby service mode (i.e., no failure during a valid test) then the potential j common mode / generic failure can be investigated and operability of the remaining DGs verified without increased testing.
I There have been numerous instances where River Bend Station has l performed the required surveillance on redundant DGs when the type of event which initially rendered the DG inoperable did not require i performance of the DG's surveillance test to restore it to operable status. This appears to be an obvious case of excessive testing of redundant DGs. Specific instances of inoperable DGs which were not the result of a " valid failure" include:
- Blown fuse to lube oil pump with DG in standby.
- Breaker trip on DG room exhaust fan with DG in standby.
- Invalid " Loss of Generator Field" alarm during surveillance testing resulting in manual DG shutdown. l
- Service water valve to DG failed ISI surveillance.
- Division III battery declared' inoperable.
- Seiemic restraint found non-functional with DG in standby.
There art additional instances - some repetitious.
Other circumstances have the potential for generating unnecessary DG starts per their associated Action statements. Specifically, the River Bend Station Technical Specifications have a few Action statements which ,
require the administrative inoperability of a DG (i.e., Specifications:
3.3.3-1 Action 36 and 37, 3.5.1 Action c.1, 3.7.1.1 Action a, 3.8.2.1 Action b, and 3.8.3.1 Action a.2).
In conclusion, the required demonstration may be perceived to provide added assurance of the availability of onsite AC sources. However, as addressed in IE Information Notice 84-69 and Supplement 1, " Operation of Emergency Diesel Generators," when a DG is operated connected to offsite sources and nonvital loads, disturbances can adversely affect DG reliability. Assurance of availability is therefore lessened by a demonstration of operability requiring connection of the DGs to offsite and nonvital loads at a time when one other DG is already inoperable.
It is contended that adequate assurance of operability is maintained by the testing frequencies specified in the normal Technical Specification surveillance requirements.
SIGNIFICANT HAZARDS CONSIDERATIONS As required by 10CFR50.92, the following is provided to the NRC Staff in support of "no significant hazards considerations."
- 1. No significant increase in the probability or the consequences of an accident previously evaluated results from this change because:
This change does not affect the availability or function of equipment and/or systems. The reduction in DG testing would not subject the remaining redundant operable DGs to periods of inoperability and reduced reliability while connected to offsite and nonvital loads which occur during the required testing when one other DG is already inoperable. This would tend to decrease the probability or consequences of an accident previously evaluated.
- 2. This change would not create the possibility of a new or different kind of accident from any accident previously evaluated because: l By not testing the remaining operable DGs as currently required by Technical Specification 3.8.1.1, no possibility of a new or different accident previously evaluated is created because no new medes of operation are introduced. All equipment functions remain as previously evaluated in the River Bend Station FSAR and SER.
Conformance with applicable Regulatory Guides is maintained as indicated in FSAR Section 1.8.
- 3. This change would not involve a ciF nificant reduction in the margin of safety because:
The perceived gain in safety from demonstrating the operability of the remaining redundant DGs upon the loss of one DG is, in part, to identify potential common mode / generic failures. If a DG were discovered inoperable while in the standby service mode (i.e., no failure during a " valid test") then the potential common mode / generic failure can be investigated and operability of the remaining DGs verified without increased testing. Furthermore, the increased testing represents a reduction of the margin safety due to the vulnerability of the DG when connected to offsite and nonvital loads. Additionally, the Technical Specification bases do not define any margin of safety for this surveillance requirement.
The proposed amendment, as discussed above, has not changed the system design, function or operation as discussed in the FSAR and therefore, will not increase the probability or the consequences of a previously evaluated accident and will not create a new or different accident.
c.dequate assurance of DG availability is maintained by the testing frequencies specified in the normal Technical Specification surveillance l requirements. Also, the results of the change are clearly within acceptable criteria with respect to system components, design requirements and applicable Regulatory Guides. As a result, the ability )
to perform as described in the FSAR is maintained and therefore, the proposed change does not result in a significant reduction in the margin
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of safety. Therefore, GSU proposes that no significant hazards i considerations are involved.
. REVISED TECHNICAL SPECIFICATION The requested revision is provided in the Enclosure.
1 SCHEDULE FOR ATTAINING COMPLIANCE As indicated above, River Bend Station is currently in compliance with the applicable Technical Specification.
NOTIFICATION OF STATE PERSONNEL A copy of this amendn:ent application has been provided to the state of Louisiana, Department of Environmental Quality - Nuclear Energy Division.
ENVIRONMENTAL IMPACT APPRAISAL i
Revision of this Technical Specification does not result in an environmental impact beyond that previously analyzed. Therefore, approval of this amendn;ent does not result in a- significant environmental impact nor does it change any previous- environmental impact statements for River Bend Station.
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