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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 filVI R lif ND $1 ATION PC$f Of FICE BOX 220 ' - ST FRANCISVlu.E. LOU 163ANA 707/6 -
. ARE A CODE SO4 C3$ 6094 346 Bfi61 September l8,.1987' RBG- 26571 1 File Nos.:G9.5, C9.25.'1.4'.
l U. S. Nuclear Regulatory Commission Document Control Desk, . J Washington, D.C. 20555 River Bend' Station.- Unit 1 Docket.No. 50-458 As requested' by ;your . staff, Gulf States Utilities Company (GSU) is providing'the' attached proposed revisions to the River -Bend Station:
(RBS) Operating ' License as . referenced .by your : letter to Mr. J.;C.
Deddens dated April 1, 1987. Attachment 3 to the. RBS Operating License NPF-47, Item 7, currently ' specifies. that operation beyond the first.
refueling outage is subject . to NRC Staff approval based 'on ' ' the s Staff's final review of the (TDI Diesel' Generator) Owners Group. generic findings .
and the overall design review and quality' revalidation program" at :RBS.
GSU- proposes to implement.the recommendations'of Revision 2 of' Appendix II of the.TDI Diesel Generator Owners Group Design' Review and :Qualityi Revalidation. (DR/QR) Report submitted : May 1, -1986- as reflected in'-
NUREG-1216. The Attachment contains..the' justifications;'and proposed ~
revisions to the RBS Operating : License. This. submittal: supplements- j GSU's previous'submittals dated' August,4, 1986,. August 15, .1986- and' September 26, 1986~ (reference REG-24147, RBC-24277 and RBG-24487, respectively). Revisions to GSU's previous submittals are indicated by, j double change bars. Your prompt attention to this application is' appreciated.
Sincerely
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J.'C. Deddens:
Senior Vice' President' 2 River ~ Bend Nuclear Group lh& Q'.
JCD/ EB/ ERG /RJK/DAS/ch
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Attachment '
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- l 8709140351 870908 O '
PDR ADDCK 05000458 P PDR .g k1.-
UNITED. STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
. STATE OF LOUISIANA
)
2ARISH OF WEST FELICIANA )
In the Matter of ) Docket No. 50-458 50-459 GULF' STATES UTILITIES COMPANY )
(River Bend Station,-
Unit 1)'
AFFIDAVIT J. C. Deddens, -being duly sworn, atates 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.
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J. C. I[eddens Subscribed and sworn to before me, a' Notary Public in-and for the State and Parish above named, this 2b day of enherbef , 19 M .
. }rtin s -
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goanW. Middlebbooks 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 l Region IV j 611 Ryan Plaza Drive, Suite 1000 {
Arlington, TX 76011 j l
NRC Senior Resident Inspector )
P.O. Box 1051 l St. Francisville. LA 70775 l Mr. William H. Spell, Administrator Nuclear Energy Division I Louisiana Department of I Environmental Quality P.O. Box 1469f' Baton Rouge,IA 70898
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ATTACHMENT i GULF STATES UTILITIES COMPANY RIVER BEND STATION DOCKET 50-458/ LICENSE NO. NPF-47 TDI DIESEL ENGINES REQUIREMENTS 1
LICENSING DOCUMENT INVOLVED: OPERATING LICENSE NPF-47 !
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ITEM: Attachment 3 l REASON FOR REQUEST Attachment 3 to the River Bend Station (RBS) Operating License NPF-47, Item 7 specifies that operation beyond the first refueling outage j (currently scheduled to begin September 15, 1987) is subject to NRC j Staff approval . based on the Staff's final review of the (TDI Diesel Generator) Owners Group generic findings and the overall design review and quality revalidation program at RBS. Gulf States Utilities Company proposes to implement the recommendations of revision 2 of Appendix II of the TDI Diesel Generator Owners Group Design Review and Quality Revalidation (DR/QR) Report submitted May 1, 1986 as reflected in NUREC-1216 " Safety Evaluation Report Related to the Operability and- 1 l Reliability of Emergency Diesel Generators Manufactured by Transamerica l Delaval Inc."
DESCRIPTION The change being requested herein concerns the requirements of Attachment 3 to NPF-47, "TDI Diesel Engines Requirements". GSU agreed to implement the Maintenance and Surveillance (M/S) program identified in Appendix II of the River Bend DR/QR Report, Revision 1 by letter
, dated May 17, 1985 (reference RBG-21026). Appendix II of the DR/QR I
Report presents a schedule of maintenance and surveillance procedures recommended by the owners groups for implementation at RBS. The NRC Staff's review of this program is documented in Supplement 3 to the RBS Safety Evaluation Report.
1 Following industry, Pacific Northwest Laboratories (PNL) and the NRC Staff review, revision 2 of Appendix II of the TDI Owners Group DR/QR Report was developed. This revision was submitted for NRC Staff review on May 1, 1986. The results of the NRC Staff's review of Revision 2 is documented in NUREG-1216. This requested Operating License Amendment merely incorporates the requirements of revision 2 as reflected in the NRC Staffs generic SER NUREG-1216.
NO SIGNIFICANT RAZARDS CONSIDERATION As discussed in 10CFR50.92, the following determinations are provided to :
the NRC Staff in support of "no significant hazards considerations". '
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- 1. No significant increase in the probability or the consequences of an l accident.previously evaluated results from this change because: ;;
I l' The Transamerica Delaval Inc. (TDI) Owners Group DR/QR Report requires inspections that are more thorough than the inspections currently being performed in accordance with the manufacturers recommendations. GSU's commitment to the DR/QR Report .is designed to increase the reliability of the Division I 'and II diesel l
generators. Implementing revision 2 of' Appendix II of the TDI DR/QR l report will increase the reliability of the diesel generators at RBS. Furthermore, this change is within the existing safety
. analysis provided in the RBS Final Safety Analysis Report (FSAR).
Thus, there is no increase in the probability or consequences of any l accident previously evaluated. .
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- 2. This change would not create the possibility of a new or different i kind of accident from any accident previously evaluated because: l The change clarifies the existing commitments presently being l adhered to. The River Bend Station Unit 1 Facility Operating License (NPF-47) currently contains a condition that GSU shall implement the TDI requirements as incorporated within the license.
by implementing the recommendations of Revision 2 of Appendix II of the TDI DR/QR. Report, GSU will be implementing a program that has ,
undergone extensive industry and regulatory review (reference '
NUREC-1216 dated July, 1986). Implementing revision 2 of Appendix II of the TDI DR/QR report will increase the reliability of the diesel generators at RBS.
Thus no new or different kind of accident scenardo is introduced for .,
any accident previously evaluated. I
- 3. This change would not involve a significant reduction in the margin of safety because:
The change makes the Technical Specifications consistent with the NRC Staff approved program (reference NUREG-1216) which ensures that the design adequacy and manufacturing of the TDI diesel generators for nuclear standby service is within the range normally assumed for diesel engines designed and manufactured in accordance with General Design Criterion (GDC) 17 and 10CFR50, Appendix B. Therefore, this change does not reduce any margin of safety as defined in the Technical Specification Bases.
GSU therefore requests that the requirements of Attachment 3 to NPF-47 be revised to reflect the recommendations of Revision 2 of the River Bend DR/QR Report maintenance and surveillance program as reflected _in NUREG-1216.
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l REVISED OPERATING LICENSE ATTACHMENT i The requested revision is provided in the Enclosure. !
I SCHEDULE FOR ATTAINING COMPLIANCE j River Bend Station is currently in compliance with the applicable
-Operating License Condition. l l
NOTIFICATION OF STATE PERSONNEL l
A copy of the amendment application and this submittal has been provided to the State of Louisiana, Department of Environmental Quality - Nuclear Energy Division.
ENVIRONMENTAL IMPACT APPRAISAL Revision of this Operating License Attachment does not result in an environmental impact beyond that previously analyzed. Therefore, i approval of this amendment does not result in a significant environment j l impact nor does it change any previous environmental impact statements for River Bend Station.
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ATTACHMENT 3 TO-NPF 47 TDI DIESEL ENGINES REQUIREMENTS GSU shall comply with the following requirements related to the TDI diesel engines.
- 1. Changes to the maintenance and surveillance program for the TDI diesel engines, as identified and approved by the NRC staff' in Supplement 3 to the SER, shall be subject to the provisions of 10 CFR 50.59. ;
1 The frequency of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.1. 1
" Overhaul Frequency" in revision 2 of Appendix II of the Design Review / Quality Revalidation report which was transmitted by letter dated May 1, 1986, from J. George, Owners Group, to H. Denton, NRC.
- 2. Crankshafts shall be inspected as follows:
l SD IB: During the first refueling outage, inspect the fillets and oil holes of the three most heavily loaded crankpin journals (Nos.
5, 6, and 7) with florescent liquid penetrant and ET as appropriate.
SD 1A and IB: During the 'second and third refueling outages, l inspect the fillets and oil holes of two of the three most heavily l
loaded crankpin journals in the manner just mentioned.
SD 1A and IB: At approximate 5 year intervals subsequent to the l third refueling outage, inspect the fillets and oil holes using florescent liquid penetrant and ET as appropriate, of the: a) three I most heavily loaded crankpin journals (Nos. 5, 6, and 7), and b) main journals located between crankpin journals 5, 6, and 7. One j i engine may be inspected at the refueling outage closest to 5 years, '
L and the other engine at the next refueling outage.
l If cracks are found during inspections of crankshafts, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable status" until the proposed disposition and/or corrective actions have been approved by the NRC staff.
l 3. Cylinder blocks shall be inspected for " ligament" cracks,
" stud-to-stud" cracks and " stud-to-end" cracks as defined in a report
- by Failure Analysis Associates. Inc. (FaAA) entitled,
" Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report no. FaAA-84-9-11.1) and dated December 1984. (Noted that the FaAA report specifies additional inspections
- This report was transmitted to H. Denton, NRC, from C. L. Ray, Jr.,
TDI Owners Group, by letter dated December 11, 1984.
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h lj 'to be performed 'for blocks with "known" .or " assumed" ligament cracks). The inspection intervals. (i.e., frequency) shall not' exceed the intervals calculated using the cumulative damage. index model in the subject FaAA report. In addition, inspection method
'shall be consistent with or. equivalent to those identified in the subject FaAA report.
! In addition to inspections .specified in the aforementioned FaAA l report, blocks with "known" or " assumed ligament cracks" (as defined in the FaAA report) should be inspected at each refueling outage to
-determine whether or not cracks have initiated on the top surface i exposed by the removal of two or more cylinder heads. This process l .should be repeated over several refueling outages until the. entire block top has been inspected. Liquid-penetrant testing or a
- similarly sensitive nondestructive testing technique should be used to detect cracking, and eddy current should be used as appropriate to determine the depth of any cracks discovered.
If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or " stud-to-end"-
cracks, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not'be restored to " operable status" until the proposed disposition and/or corrective actions have been approved by the NRC staff.
- 4. The following air roll test shall be performed as specified below, except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources":
The engines shall be rolled over with the airstart system and with the cylinder stopcocks open prior to each planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l after each shutdown. (In the event an engine is removed from l
i service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted abcve, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service.) The origin of any water detected in the cylinder must be determined and any cylinder head-which leaks due to a crack shall be replaced. The above air roll test may' be discontinued following the first refueling outage subject to the following conditions:
All cylinder heads are Group III heads (i.e., cast after September 1980).
Quality revalidation inspections, as identified in the Design ;
Review / Quality ' Revalidation report, have been completed for all cylinder heads.
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Group III heads continue to demonstrate leak free performance. ,
This should be confirmed with TDI before air roll tests are I discontinued. I ll I
- 5. Thefollowingactgsare required if SD 1A or SD 1B is operated in j excess of 3130 W : 1 a) For indicated. engine loads in g range of 3130 W to 3200 W j for a period less than twc hours , no additional action shall I be required. ;
1 b) For indicated engine loads in the range of g30 W to 3200 W j for a period equal to or exceeding two hours , a crankshaft j inspection pursuant to Item d below shall be performed at the j next refueling outage. l 1
c) For indicated engine loads in the r g e of 3200 W to 3500 KW l for a period less than I hour , a crankshaft inspection pursuant to item d below shall be performed for the affected J engine at the next refueling outage, d) For indicated engine loads in the range g 3200 KW to 3500 KW for periods equal to or exceeding one hour and for engine l loads exceeding 3500 KW for any period of time, (1) the engine {
shall be removed from service as soon as safely possible, (2) ;
the engine shall be declared inoperable, and (3) the crankshaft i shall be inspected. The crankshaft inspection shall include i erankpin journal numbers 5, 6, and 7 (the most heavily loaded) '
and the two main journals in between using . florescent liquid penetrant and eddy current as appropriate.
- 6. Periodic inspections of the turbocharger shall include the ]
following: l l
The turbocharger thrust bearings should be visually inspected for excessive wear after 40 non-prelubed starts since the previous {
i visual inspection. '
i Turbocharger rotor axial clearance should be measured at- each j refueling outage to verify compliance with TDI/Elliott I specifications. In addition, thrust bearing measurements should j be compared with measurements taken previously to determine a ;
need for further inspection or. corrective action. !
(1) Momentary transients (not exceeding 5 seconds) due to changing of '!
bus loads need not be considered as an overload. '
(2) If there are multiple overload events within a given load range since the previous crankshaft inspection, then the time period criterion applies to the total accumulated time in that load range.
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. Spectrographic and ferrographic engine . oil analysis shall be i performed quarterly to provide early evidence of bearing i degradation. Particular attention should be paid to copper level and particulate size, which could signify thrust bearing 'i degradation. (.
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l The nozzle ring components and inlet guide- vanes should be ' .- ,
visually inspected at each refueling outage for missing parts or : > L' parts showing distress on a one-turbocharger-per-refueling-outage ,\
basis. In addition, these inspections should be performed for .
'l all ' turbocharger at each turbocharger overhaul (i.e., at approximately 5-year intervals). If any missing parts or '
distress is noted, the entire ring assembly should be replaced ;
and the subject turbocharger should be reinspected at the next : d refueling outage.
- 7. Operation beyond the first refueling outage is subject to NRC- staff )
approval based on the staff's final review of the Owners Group !
generic findings and of the overall design review and quality l revalidation program at River Bend.
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