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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARSVP-99-182, Application for Amends to Licenses DPR-29 & DPR-30,to Remove Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A1999-10-12012 October 1999 Application for Amends to Licenses DPR-29 & DPR-30,to Remove Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A SVP-99-127, Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs1999-07-16016 July 1999 Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs SVP-99-128, Application for Amends to Licenses DPR-29 & DPR-30,changing TS Section 3/4.3.C, Reactivity Control - Control Rod Operability1999-06-29029 June 1999 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Section 3/4.3.C, Reactivity Control - Control Rod Operability SVP-99-032, Application for Amend to License DPR-29,changing SR 4.6.E.2 to Allow one-time Extension of 18-month Requirement to Pressure Set Test or Replace One Half of MSSVs to Interval of 24 Months1999-03-30030 March 1999 Application for Amend to License DPR-29,changing SR 4.6.E.2 to Allow one-time Extension of 18-month Requirement to Pressure Set Test or Replace One Half of MSSVs to Interval of 24 Months SVP-99-001, Application for Amends to Licenses DPR-29 & DPR-30,deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info1999-03-30030 March 1999 Application for Amends to Licenses DPR-29 & DPR-30,deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info SVP-99-038, Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable1999-03-30030 March 1999 Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable SVP-99-003, Application for Amends to Licenses DPR-29 & DPR-30, Relocating Chemistry TS Requirements of TS Section 3/4.6.I, Primary Sys Boundary - Chemistry, to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process1999-01-21021 January 1999 Application for Amends to Licenses DPR-29 & DPR-30, Relocating Chemistry TS Requirements of TS Section 3/4.6.I, Primary Sys Boundary - Chemistry, to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process SVP-98-355, Application for Amends to Licenses DPR-29 & DPR-30,revising TS 3/4.8.J, Safe Shutdown Makeup Pump, to Reduce Current AOT from 67 Days to 14 Days1998-11-30030 November 1998 Application for Amends to Licenses DPR-29 & DPR-30,revising TS 3/4.8.J, Safe Shutdown Makeup Pump, to Reduce Current AOT from 67 Days to 14 Days ML20151X2491998-09-0909 September 1998 Application for Amends to Licenses DPR-29 & DPR-30, Requesting Consent of NRC for Indirect Transfer of Control of Midamerican Energy Co SVP-98-291, Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.61998-08-31031 August 1998 Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.6 SVP-98-252, Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C1998-07-31031 July 1998 Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C ML20196G0161997-05-0101 May 1997 Application for Amends to Licenses DPR-29 & DPR-30,revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3231997-04-29029 April 1997 Application for Amends to Licenses DPR-29 & DPR-30, Permitting Loading of ATRIUM-9B Fuel in Plant Unit 2 Core for Operational Modes 3,4 & 5 ML20138B3161997-04-21021 April 1997 Application for Amends to Licenses DPR-29 & DPR-30, Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Cycle 15 Operation Scheduled to Begin 970519 ML20137G3801997-03-26026 March 1997 Application for Amends to Licenses DPR-29 & DPR-30, Requesting to Reconcile Discrepancy in Free Volume for Secondary Containment ML20135F7161997-03-0303 March 1997 Application for Amends to Licenses DPR-29 & DPR-30,revising Bases for TS 3/4.9.E to Clarify Purpose of SR 4.9.E ML20138L3641997-02-17017 February 1997 Application for Amends to Licenses DPR-29 & DPR-30, Requesting Correction of Error in Surveillance Requirement 4.9.A.8.h Re Diesel Generator Endurance Test ML17187A7971997-02-17017 February 1997 Application for Amend to Licenses DPR-19 & DPR-25,App A,Tss, Section 3/4.7.K, Suppression Chamber & Section 3/4.8, Ultimate Heat Sink, to Address Issues Re Efforts to Reconstitute Design Basis of Containment Heat Removal Sys ML20113A7761996-06-10010 June 1996 Application for Amends to Licenses DPR-29 & DPR-30,to Reflect Transition of Fuel Supplier from GE to Spc. Nonproprietary EMF-94-219(NP) & Proprietary EMF-94-219(P) encl.EMF-94-219(P) Withheld Per 10CFR2.790 ML20098A3451995-09-20020 September 1995 Application for Amends to Licenses DPR-29 & DPR-30,revising TS Upgrade Program & Improving Plant Submittals ML20082H7181995-04-10010 April 1995 Application for Amends to Licenses DPR-29 & DPR-30,revising SR for HPCI & RCIC Sys ML20080K8021995-02-23023 February 1995 Application for Amends to Licenses DPR-29 & DPR-30,changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc ML20080J0881995-02-21021 February 1995 Application for Amends to Licenses DPR-29 & DPR-30 Re Changes to Name of Iowa-Illinois Gas & Electric Co,25% co- Owner of Plant,To Reflect Results of Merger Between Electric Company,Midwest Power Sys Inc & Midwest Resources Inc ML20078Q6011994-12-12012 December 1994 Application for Amend to License DPR-29,incorporating Corrections to TS Section 3.4/4.4 Re Standby Liquid Control Sys ML20077A4081994-11-21021 November 1994 Application for Transfer & Amend to Licenses DPR-29 & DPR-30 ML20064J3041994-03-11011 March 1994 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Limiting Conditions of Operation & Surveillance Requirements 3.6.1 & 4.6.1,describing Snubber Visual Insp Intervals & Corrective Actions,Per GL 84-13 & GL 90-09 ML20059K7351994-01-14014 January 1994 Application for Emergency Amend to License DPR-30 for NRC Review & Approval of Two USQs Associated W/Interim Mod on Quad-Cities Station Unit 2,to Resolve Concerns Described in NRC Bulletin 93-003 ML20059A7241993-12-20020 December 1993 Application for Amends to Licenses DPR-29 & DPR-30, Increasing MCPR Safety Limit from 1.06 to 1.07 for Units 1 & 2 ML20059A8211993-10-21021 October 1993 Application for Amends to Licenses DPR-29 & DPR-30,proposing TS to Delete Requirements for Demonstrating Operability of Redundant Equipment When ECCS Equipment Is Found Inoperable or Made Inoperable for Maint ML20101R7871992-07-0606 July 1992 Application for Amend to License DPR-29,reflecting Mod to HPCI Turbine Steam Exhaust Line.Ge Proprietary Calculation, GE-NE-901-013-0491, Quad Cities HPCI Turbine Steam Supply Pressure Low Setpoint Calculation Encl.Rept Withheld ML20096F3941992-04-20020 April 1992 Application for Amends to Licenses DPR-29 & DPR-30, Requesting Deletion of Isolation Functions & Surveillance Requirements for CR Ventilation Sys Chlorine & Sulfur Dioxide Analyzers ML20091C4681992-03-31031 March 1992 Application for Amends to Licenses DPR-29,DPR-30,NPF-11 & NPF-18,changing TS to Include Commed Topical Rept NFSR-0085, & Suppls 1 & 2 to Section 6.6 to Describe Improved Analytical Methods Re Core Operating Limits Rept ML20091L7561992-01-21021 January 1992 Application for Amends to Licenses DPR-29 & DPR-30,changing Spec Ref in TS 3.5.C.2 from 4.5.C.3 to 4.5.C.3.a & in TS 3.5.E.2 from 4.5.E.3 to 4.5.E.3.a,in Regard to HPCI & RCIC Sys ML20086E2271991-11-20020 November 1991 Revised Application for Amends to Licenses DPR-29 & DPR-30, Restoring Various Channel Calibr Frequencies from STS Requirements to Current Requirements Re TS Section 3.1/4.1, Reactor Protection Sys, in Ref to ML20085E6071991-10-11011 October 1991 Application for Amends to Licenses DPR-29 & DPR-30,revising TSs Sections 6.1.G to Reflect Position Title Change, 6.1.G.1.b to Reflect Rev of Approval Authority & Adding Sections 6.11 & 6.12 Re Access to High Radiation Areas ML20085D4301991-10-0707 October 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Specs to Reflect Tech Spec Upgrade Program. Existing Tech Specs & Environ Protection Plan (Nonradiological) Encl ML20079H0551991-10-0202 October 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Spec Section 1.0, Definitions to Reflect Tech Spec Upgrade Program ML20079H2081991-10-0202 October 1991 Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing Tech Spec Section 6.0, Administrative Controls ML20085C7571991-10-0202 October 1991 Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing TS Sections 3.5/4.5, Core & Containment Cooling Sys & 3.6/4.6, Primary Sys Boundary, as Part of TS Upgrade Program ML20079G0411991-09-30030 September 1991 Application for Amends to Licenses NPF-29 & DPR-30,changing Current License Conditions Re Fire Protection W/New Tech Spec 3.12/4.12, Fire Protection Sys, Per Generic Ltrs 86-10 & 88-12 ML20079F9871991-09-30030 September 1991 Application for Amends to Licenses NPF-29 & DPR-30,changing TS to Reflect Util Efforts to Upgrade Existing TS 3.8/4.8, Radioactive Effluents & 3.10/4.10, Refueling ML20079G0921991-09-30030 September 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing TS to Reflect Effort to Upgrade Existing TS Sections: 3.2/4.2, Protective Instrumentation & 3.9/4.9, Auxiliary Electrical Sys ML20083D3541991-09-24024 September 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Spec 4.8.H.2.b(2) to Define Differential Temp Criteria for Control Room Emergency Filtration Sys Header ML20082V2021991-09-17017 September 1991 Application for Amends to Licenses DPR-29 & DPR-30,App a, Reflecting Efforts to Upgrade Existing Tech Specs 3.3/4.3, Reactivity Control ML20082M8551991-08-29029 August 1991 Application for Amends to Licenses DPR-29 & DPR-30,deleting Tech Spec 3.11/4.11, High Energy Piping Integrity (Outside Containment). Mods Completed in 1979 for High Energy Piping ML20082H5011991-08-15015 August 1991 Suppl to 910627 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Sections 1.1/2.1, Fuel Cladding Integrity & 1.2/2.2, RCS Changing 800 Psig to 800 Psia in Specs 1.1.A & 1.1.B ML20082H1881991-08-15015 August 1991 Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing TS Section 3.4/4.4, Standby Liquid Control Sys. Tech Spec Upgrade Program Encl ML20085B5851991-07-29029 July 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Specs to Reflect Tech Spec Upgrade Program & TS Section 5.0, Design Features. Quad Cities Nuclear Power Station Tech Spec Upgrade Program Encl ML20076D8771991-07-23023 July 1991 Application for Amends to Licenses DPR-29 & DPR-30, Upgrading Tech Specs Section 3.1/4.1, Reactor Protection Sys ML20077G9951991-06-28028 June 1991 Application for Amend to License DPR-30,reflecting Proposed Mod to HPCI Turbine Steam Exhaust Line.Ge Proprietary Rept GE-NE-901-013-0491,Rev 1, Quad Cities HPCI Turbine Steam Supply... Encl.Rept Withheld (Ref 10CFR2.790(b)(4)) 1999-07-16
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARSVP-99-182, Application for Amends to Licenses DPR-29 & DPR-30,to Remove Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A1999-10-12012 October 1999 Application for Amends to Licenses DPR-29 & DPR-30,to Remove Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A SVP-99-127, Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs1999-07-16016 July 1999 Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs SVP-99-128, Application for Amends to Licenses DPR-29 & DPR-30,changing TS Section 3/4.3.C, Reactivity Control - Control Rod Operability1999-06-29029 June 1999 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Section 3/4.3.C, Reactivity Control - Control Rod Operability SVP-99-032, Application for Amend to License DPR-29,changing SR 4.6.E.2 to Allow one-time Extension of 18-month Requirement to Pressure Set Test or Replace One Half of MSSVs to Interval of 24 Months1999-03-30030 March 1999 Application for Amend to License DPR-29,changing SR 4.6.E.2 to Allow one-time Extension of 18-month Requirement to Pressure Set Test or Replace One Half of MSSVs to Interval of 24 Months SVP-99-001, Application for Amends to Licenses DPR-29 & DPR-30,deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info1999-03-30030 March 1999 Application for Amends to Licenses DPR-29 & DPR-30,deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info SVP-99-038, Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable1999-03-30030 March 1999 Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable SVP-99-003, Application for Amends to Licenses DPR-29 & DPR-30, Relocating Chemistry TS Requirements of TS Section 3/4.6.I, Primary Sys Boundary - Chemistry, to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process1999-01-21021 January 1999 Application for Amends to Licenses DPR-29 & DPR-30, Relocating Chemistry TS Requirements of TS Section 3/4.6.I, Primary Sys Boundary - Chemistry, to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process SVP-98-355, Application for Amends to Licenses DPR-29 & DPR-30,revising TS 3/4.8.J, Safe Shutdown Makeup Pump, to Reduce Current AOT from 67 Days to 14 Days1998-11-30030 November 1998 Application for Amends to Licenses DPR-29 & DPR-30,revising TS 3/4.8.J, Safe Shutdown Makeup Pump, to Reduce Current AOT from 67 Days to 14 Days ML20151X2491998-09-0909 September 1998 Application for Amends to Licenses DPR-29 & DPR-30, Requesting Consent of NRC for Indirect Transfer of Control of Midamerican Energy Co SVP-98-291, Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.61998-08-31031 August 1998 Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.6 SVP-98-252, Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C1998-07-31031 July 1998 Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C ML20196G0161997-05-0101 May 1997 Application for Amends to Licenses DPR-29 & DPR-30,revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3231997-04-29029 April 1997 Application for Amends to Licenses DPR-29 & DPR-30, Permitting Loading of ATRIUM-9B Fuel in Plant Unit 2 Core for Operational Modes 3,4 & 5 ML20138B3161997-04-21021 April 1997 Application for Amends to Licenses DPR-29 & DPR-30, Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Cycle 15 Operation Scheduled to Begin 970519 ML20137G3801997-03-26026 March 1997 Application for Amends to Licenses DPR-29 & DPR-30, Requesting to Reconcile Discrepancy in Free Volume for Secondary Containment ML20135F7161997-03-0303 March 1997 Application for Amends to Licenses DPR-29 & DPR-30,revising Bases for TS 3/4.9.E to Clarify Purpose of SR 4.9.E ML20138L3641997-02-17017 February 1997 Application for Amends to Licenses DPR-29 & DPR-30, Requesting Correction of Error in Surveillance Requirement 4.9.A.8.h Re Diesel Generator Endurance Test ML17187A7971997-02-17017 February 1997 Application for Amend to Licenses DPR-19 & DPR-25,App A,Tss, Section 3/4.7.K, Suppression Chamber & Section 3/4.8, Ultimate Heat Sink, to Address Issues Re Efforts to Reconstitute Design Basis of Containment Heat Removal Sys ML20113A7761996-06-10010 June 1996 Application for Amends to Licenses DPR-29 & DPR-30,to Reflect Transition of Fuel Supplier from GE to Spc. Nonproprietary EMF-94-219(NP) & Proprietary EMF-94-219(P) encl.EMF-94-219(P) Withheld Per 10CFR2.790 ML20098A3451995-09-20020 September 1995 Application for Amends to Licenses DPR-29 & DPR-30,revising TS Upgrade Program & Improving Plant Submittals ML20082H7181995-04-10010 April 1995 Application for Amends to Licenses DPR-29 & DPR-30,revising SR for HPCI & RCIC Sys ML20080K8021995-02-23023 February 1995 Application for Amends to Licenses DPR-29 & DPR-30,changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc ML20080J0881995-02-21021 February 1995 Application for Amends to Licenses DPR-29 & DPR-30 Re Changes to Name of Iowa-Illinois Gas & Electric Co,25% co- Owner of Plant,To Reflect Results of Merger Between Electric Company,Midwest Power Sys Inc & Midwest Resources Inc ML20078Q6011994-12-12012 December 1994 Application for Amend to License DPR-29,incorporating Corrections to TS Section 3.4/4.4 Re Standby Liquid Control Sys ML20077A4081994-11-21021 November 1994 Application for Transfer & Amend to Licenses DPR-29 & DPR-30 ML20064J3041994-03-11011 March 1994 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Limiting Conditions of Operation & Surveillance Requirements 3.6.1 & 4.6.1,describing Snubber Visual Insp Intervals & Corrective Actions,Per GL 84-13 & GL 90-09 ML20059K7351994-01-14014 January 1994 Application for Emergency Amend to License DPR-30 for NRC Review & Approval of Two USQs Associated W/Interim Mod on Quad-Cities Station Unit 2,to Resolve Concerns Described in NRC Bulletin 93-003 ML20059A7241993-12-20020 December 1993 Application for Amends to Licenses DPR-29 & DPR-30, Increasing MCPR Safety Limit from 1.06 to 1.07 for Units 1 & 2 ML20059A8211993-10-21021 October 1993 Application for Amends to Licenses DPR-29 & DPR-30,proposing TS to Delete Requirements for Demonstrating Operability of Redundant Equipment When ECCS Equipment Is Found Inoperable or Made Inoperable for Maint ML20101R7871992-07-0606 July 1992 Application for Amend to License DPR-29,reflecting Mod to HPCI Turbine Steam Exhaust Line.Ge Proprietary Calculation, GE-NE-901-013-0491, Quad Cities HPCI Turbine Steam Supply Pressure Low Setpoint Calculation Encl.Rept Withheld ML20096F3941992-04-20020 April 1992 Application for Amends to Licenses DPR-29 & DPR-30, Requesting Deletion of Isolation Functions & Surveillance Requirements for CR Ventilation Sys Chlorine & Sulfur Dioxide Analyzers ML20091C4681992-03-31031 March 1992 Application for Amends to Licenses DPR-29,DPR-30,NPF-11 & NPF-18,changing TS to Include Commed Topical Rept NFSR-0085, & Suppls 1 & 2 to Section 6.6 to Describe Improved Analytical Methods Re Core Operating Limits Rept ML20091L7561992-01-21021 January 1992 Application for Amends to Licenses DPR-29 & DPR-30,changing Spec Ref in TS 3.5.C.2 from 4.5.C.3 to 4.5.C.3.a & in TS 3.5.E.2 from 4.5.E.3 to 4.5.E.3.a,in Regard to HPCI & RCIC Sys ML20086E2271991-11-20020 November 1991 Revised Application for Amends to Licenses DPR-29 & DPR-30, Restoring Various Channel Calibr Frequencies from STS Requirements to Current Requirements Re TS Section 3.1/4.1, Reactor Protection Sys, in Ref to ML20085E6071991-10-11011 October 1991 Application for Amends to Licenses DPR-29 & DPR-30,revising TSs Sections 6.1.G to Reflect Position Title Change, 6.1.G.1.b to Reflect Rev of Approval Authority & Adding Sections 6.11 & 6.12 Re Access to High Radiation Areas ML20085D4301991-10-0707 October 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Specs to Reflect Tech Spec Upgrade Program. Existing Tech Specs & Environ Protection Plan (Nonradiological) Encl ML20079H0551991-10-0202 October 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Spec Section 1.0, Definitions to Reflect Tech Spec Upgrade Program ML20079H2081991-10-0202 October 1991 Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing Tech Spec Section 6.0, Administrative Controls ML20085C7571991-10-0202 October 1991 Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing TS Sections 3.5/4.5, Core & Containment Cooling Sys & 3.6/4.6, Primary Sys Boundary, as Part of TS Upgrade Program ML20079G0411991-09-30030 September 1991 Application for Amends to Licenses NPF-29 & DPR-30,changing Current License Conditions Re Fire Protection W/New Tech Spec 3.12/4.12, Fire Protection Sys, Per Generic Ltrs 86-10 & 88-12 ML20079F9871991-09-30030 September 1991 Application for Amends to Licenses NPF-29 & DPR-30,changing TS to Reflect Util Efforts to Upgrade Existing TS 3.8/4.8, Radioactive Effluents & 3.10/4.10, Refueling ML20079G0921991-09-30030 September 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing TS to Reflect Effort to Upgrade Existing TS Sections: 3.2/4.2, Protective Instrumentation & 3.9/4.9, Auxiliary Electrical Sys ML20083D3541991-09-24024 September 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Spec 4.8.H.2.b(2) to Define Differential Temp Criteria for Control Room Emergency Filtration Sys Header ML20082V2021991-09-17017 September 1991 Application for Amends to Licenses DPR-29 & DPR-30,App a, Reflecting Efforts to Upgrade Existing Tech Specs 3.3/4.3, Reactivity Control ML20082M8551991-08-29029 August 1991 Application for Amends to Licenses DPR-29 & DPR-30,deleting Tech Spec 3.11/4.11, High Energy Piping Integrity (Outside Containment). Mods Completed in 1979 for High Energy Piping ML20082H5011991-08-15015 August 1991 Suppl to 910627 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Sections 1.1/2.1, Fuel Cladding Integrity & 1.2/2.2, RCS Changing 800 Psig to 800 Psia in Specs 1.1.A & 1.1.B ML20082H1881991-08-15015 August 1991 Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing TS Section 3.4/4.4, Standby Liquid Control Sys. Tech Spec Upgrade Program Encl ML20085B5851991-07-29029 July 1991 Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Specs to Reflect Tech Spec Upgrade Program & TS Section 5.0, Design Features. Quad Cities Nuclear Power Station Tech Spec Upgrade Program Encl ML20076D8771991-07-23023 July 1991 Application for Amends to Licenses DPR-29 & DPR-30, Upgrading Tech Specs Section 3.1/4.1, Reactor Protection Sys ML20077G9951991-06-28028 June 1991 Application for Amend to License DPR-30,reflecting Proposed Mod to HPCI Turbine Steam Exhaust Line.Ge Proprietary Rept GE-NE-901-013-0491,Rev 1, Quad Cities HPCI Turbine Steam Supply... Encl.Rept Withheld (Ref 10CFR2.790(b)(4)) 1999-07-16
[Table view] |
Text
_ _ .
Communu cahh 1:dison Coinp.uty e e' ~*
QUJd G:ic% GCHCf,Hing Aldtjon 22'lO 206th Asenue North
( .ordon a. !!. 612 e2 *)740 Tri w>v,u2 ii SVP-99-038 March 30,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D C 20555 Quad Citics Nuclear Power Station, Unit I and Unit 2 FacEity Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Technical Specification Change Request Technical Specification Section 3/4.6.G, Leakage Detection Systems
Reference:
Letter from L. Olshan (USNRC) to T. Kovach (Comed), dated August 21,1990," Review of Response to Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" Pursuant to 10 CFR 50.90, Commonwealth Edison (Comed) Company proposes to change Appendix A, Technical Specifications (TS) Section 3/4.6.0," Leakage Detection Systems,"
of Facility Operating License., DPR-29 and DPR-30. The purpose of this proposed change is to allow an alternate methodology for quantifying Reactor Coolant System (RCS) leakage when the normal RCS leakage detection system is inoperable. This change is consistent with the NRC guidance provided in the referenced letter.
The proposed amendment request is subdivided as follows:
O
- 1. Attachment A gives a description and safety analysis of the proposed changes,
- 2. Attachment B includes the marked-up Technical Specifications pages with the ;
requested change, indicated,
/
- 3. Attachment C provides information supporting a finding of no significant hazards in accordance with 10 CFR 50.92(c) and, t
- 4. Attachment D provides information supporting an environmental assessment.
9904120284 990330 }
PDR ADOCK 05000254 ,
P PDR }
g' gG N
A l'nicom Osmpany .
7
'USNRC 2 March 30,1999 SVP-90 438 Comed requests NRC approval of this request by October 28,1999, to be effective no later than 60 days following approval.
1 This proposed Technical Specification amendment has been reviewed and approved by j l
the On-Site Plant Operations Review Committee and Off-Site Nuclear Safety Review Board in accordance with Comed procedures.
Comed is notifying the State of Illinois of this application for amendment by transmitting a copy of this letter and its attachments to the designated State Official.
l l If there are any questions or comments concerning this letter, please refer them to Mr. Wally Beck, Acting Regulatory Assurance Manager, at (309) 654-2241, extension 3100.
Sine ely,
- O
/utavn '
l Joel P. Dimmette, Jr.
l Site Vice President :
Quad Cities Nuclear Power Station
- Attachments
- A. Description and Safety Analysis for Proposed Changes l B. Marked-Up Technical Specifications Pages C. Information Supporting a Finding of No Significant Hazards D. Information Supporting an Environmental Assessment i
l cc: Regional Administrator-NRC Region III NRC Senior Resident Inspector- Quad Cities Nuclear Power S;ation l
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STATE OF ILLINOIS l Docket Nos. 50-254 50-265 IN TIIE MATTER OF COMMONWEALTII EDISON COMPANY 1
QUAD CITIES NUCLEAR POWER STATION - UNITS 1 AND 2 CII ANGE TO TECIINICAL SPECIFICATIONS SECTION 3/4.6 G, LEAKAGE DETECTION SYSTEMS AFFIDAVIT I affirm that the content of this tr smittal is true and correct to the best of my knowledge, information and belief. ,
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Site ice President Subscribed and sworn to before me, a Notary Public in and for the State above named, this 30 day of ihnacH ,19 Pi .
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Notary Public F WFICLAl N pL.EESTOERMER NatsyPdtc.M fnW2000 mem i
ATTACHMENT A l Description and Safety Analysis for Proposed Changes SVP-99-038 (Page 1 of 5) l HACKGROUND INFORMATION !
l General Design Criteria (GDC) 30 of Appendix A to 10 CFR 50 requires a mear.s for detecting and identifying the source of any potential Reactor Coolant System (RCS)leabge. Leakage detection systems must have the capability to detect RCS boundary degradation as soon as practical to minimize the potential for propagation into a gross failure condition.
The Technical Specifications (TS) provide limits on leakage from the RCS coolant boundary so that appropriate actions can be taken before the integrity of the RCS boundary is seriously impaired. As described in Updated Final Safety Analysis Report (UFSAR) Sections 9.3.3.1 and 9.3.3.2, Quad Cities Nuclear Power Station, Unit I and Unit 2, have both a Drywell Equipment Drain Sump (DWEDS) and a Drywell Floor Drain Sump (DWFDS) which collect RCS leakage inside primary containment. The associated indication and controls for these pumps, including a ;
flow totalizer, are located in the main control room. Using the totalizer, flow from the DWEDS i is measured every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per TS Surveillance Requirement (SR) 4.6.H to determine IDENTIFIED system leakage. Total flow from the DWFDS is measured in a similar manner to determine UNIDENTIFIED leakage from the RCS boundary.
TS Scaion 3.6.G, Action 2, requires that with the DWFDS system inoperable in operational 1 mod 2 and 3, the system must be restored to an operable condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise the !
unit m. be shutdown. Historically, Quad Cities Nuclear Power Station, Unit I and Unit 2, has declazed the DWFDS system inoperable when the associated flow itotalizer (monitoring system) is not available. This is unnecessarily restrictive because alternative means are available for quantifying RCS leakage when the DWFDS monitoring system is inoperable.
A.
SUMMARY
OF PROPOSED CHANGES Pursuant to 10 CFR 50.90, Commonwealth Eo. on (Comed) Company proposes to change Appendix A, TS Section 3/4.6.G, " Leakage Detection Systems," for Facility Operating Licenses DPR-29 and DPR-30. The purpose of this proposed change is to allow an alternate methodology for quantifying RCS leakage when the DWFDS monitoring system is inoperable.
The purpose of this amendment request is to provide additional flexibility for monitoring RCS leakage and provide certain administrative changes to be consistent with the Improved Standard
- Technical Specifications, NUREG-1433, Rev.1. This enhancement would allow the use of other viable means of quantifying RCS leakage. The alternative method for quantifying RCS leakage will be administratively controlled and will have a measurement sensitivity consistent with the j sump flow totalizers.
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ATTACIIMENT A Description and Safety Analysis for Proposed Changes 1
- SVP-99-038
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(Page 2 of 5) l l
B. DESCRIPTION OF TIIE CURRENT REQUIREMENTS i 1
TS Section 3.6.G, Action 2, states:
With the drywellfloor drain sump system inoperable, restore the drywellfloor drain sump system to OPERABLE status within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within thefollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.G, Action 2,is required to be entered whenever Limiting Condition for Operation (LCO) 3.6.G.2 is not met. LCO 3.6.G.2 requires the drywell floor drain sump system to be OPERABLE in MODE (s) 1,2, and 3.
C. BASES FOR TIIE CURRENT REQUIREMENTS The RCS leakage detection system is provided to monitor and detect leakage from the RCS pressure boundary. Limits on leakage from the RCS boundary are required so that appropriate action can be taken before the integrity of the reactor coolant pressure boundary is impaired. '
Leakage detection systems for the RCS are provided to alert the operators when leakage rates above the normal background levels are detected and also to supply quantitative measurement of leakage rates. Leakage from the RCS boundary inside the drywell is detected by two independently monitored variables: (1) sump level changes and, (2) drywell atmosphere radioactivity levels. The means of detection are required to be OPERABLE in MODE (s) 1,2, and 3. The means of quantifying leakage in the drywell is the measurement of flow from the DWFDS and DWEDS pumps.
D. NEED FOR REVISION OF TIIE REQUIREMENT j The proposed.TS amendment for Quad Cities Station, Units 1 and 2, would allow the use of other means of quantifying RCS leakage (for up to 30 days) should the DWFDS monitoring system become inoperable. Requiring the DWFDS monitoring system to be returned to an operable condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is unnecessarily restrictive because an alternate method of l quantifying RCS leakage is available (as described in Section F below).
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ATTACHMENT A Description and Safe.,5 Analysis for Proposed Chang <rc
- a VP-99-038 i
(Page 3 of 5)
E. DESCRIPTION OF THE PROPOSED CIIANGES Current Requirement TS Section 3.6.G, Action 2, states:
\Vith the drywellpoor drain sump system inoperable, restore the drywellpoor drain sump system to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, be in at least HOT
' SHUTDO\YN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDO1VN within thefollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Proposed Requirement TS Section 3.6.G, Action 2, states:
\Yith the drywellpoor drain sump monitoring system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> establish an alternate method ofdetermining drywellfloor drain sumpjlow rates, AND withi.s 30 days restore the drywellfloor drain sump monitoring system to an OPERABLE status; otherwise, be in at least HOTSHUTDO1VN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within thefollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
In order to maintain consistency with the nomenclature in the Improved Standard Technical Specifications, NUREG 1433, Rev.1, the following additional administrative changes are proposed:
l l Current LCO 3.6.G.2:
The drywellpoor drain sump system.
- Proposed LCO 3.6.G.2:
The drywellpoor drain sump monitoring system. !
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ATTACHMENT A )
Description and Safety Analysis for Proposed Changes i l SVP 99-038 (Page 4 of 5) l l
Current Surveillance Requirements (SR) 4.6.G.2: l l
Perfonning a CHANNEL CALIBRATION of the drywellfloor '
drain sump pump dischargeflow totali er at least once per 18 months.
Proposed SR 4.6.G.2 Performing a CHANNEL CALIBRATION ofrequired leakage detection instrumentation at least once per 18 months. l t
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The bases for TS Section 3/4.6.G will be changed to read as follows:
The RCS leakage detection systems required by this specification are provided to monitor and detect leakagefrom the reactor coolant pressure boundary. Limits on leakagefrom the reactor coolant pressure boundary are required so that appropriate action can be taken before the integrity of the reactor coolant pressure boundary is impaired. Leakage detection systemsfor the reactor coolant system are provided to alert the operators when leakage rates above the nonnal background levels are detected and also to i supply quantitative measurement ofleakage rates. Leakagefrom l the reactor coolant pressure boundary inside the drywell is detected by at least one or two independently monitored variables, such as sump level changes and drywell atmosphere radioactivity levels. The means ofquantifying leakage in the drywell is the drywellfloor drain sump pumps. With the drywellJloor drain l sump monitoring system inoperable an alternative method, such i as measuring sump run-timesfor quantifying leakage may be employedfor up to 30 days under administrative controls.
Primary containment atmosphere samplingfor radioactivity can provide indication ofchanges in leakage rates.
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l ATTACHMENT A Description and Safety Analysis for Proposed Changes l SVP-99-038 l
(Page 5 of 5)
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F. SAFETY ANALYSIS OF THE PROPOSED CHANGES The normal method for determining RCS leakage rates is to use the DWEDS and DWFDS flow totalizers. These measurements are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in accordance with TS SR 4.6.H.
The TS implies that if the flow totalizer fails, there is no alternative method for determining flow from the DWEDS and DWFDS. However, calculating flow rates using sump pump run times is an altemative method for quantifying RSC leakage. Both the DWEDS and DWFDS trip on low sump level; thus, pump run time multiplied by the rated pump flow can be used to determine the total volume of water collected in the sump between surveillances. The rated pump flow will be determined on a periodic frequency (approximately once per week) when the flow totalizer l is operable by dividing the totalizer flow by the pump run time during a routine RCS leakage surveillance. Since the totalizer will be used to determine rated pump flow, the alternate method has a measurement sensitivity consistent with the totalizer (i.e., normal method). This alternate methodology will be allowed for 30 days while effons are being made to restore the normal RCS leakage monitoring system to an operable condition. A thirty 30-day allowance is acceptable because significant degradation in rated pump flow is not expected to occur during this time frame.
In order to demonstrate the acceptability of the proposed alternate method for determining RCS l leakage, both DWEDS and DWFDS run-times have been collected (approximately once per week) since October of 1998. Using this information, Quad Cities Nuclear Power Station, Unit I and Unit 2, has been able to compare calculated rated pump flow to totalizer volume for both the DWEDS and DWFDS. An examination of this information has indicated no significant degradation in pump performance and comparison of calculated to measured mies are consistent.
For this reason, the alternate method of calculating RCS leakage is acceptable during the proposed 30-day allowed outage time for the normal floor drain sump monitoring system..
The alternate methodology will be controlled by station procedures and mflected in the UFSAR.
In addition, the altemate method is consistent with NRC guidance provided in letter L. Olshan (USNRC) to T. Kovach (Comed) dated August 21,1990, concerning Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping."
G. IMPACT ON PREVIOUS SUBMITTALS Comed has reviewed previous sthnittals and has concluded the proposed change has no impact on previous submittals currently under NRC review.
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! IL SCHEDULE REQUIREMENTS Comed requests NRC approval of this request by October 28,1999, to be effective no later than 60 days following approval.
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