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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARULNRC-04103, Application for Amend to License NPF-30,reflecting USQ Associated with Increases to Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents1999-09-0808 September 1999 Application for Amend to License NPF-30,reflecting USQ Associated with Increases to Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ULNRC-04024, Suppl 1 to Application to License NPF-30,adding License Conditions to Address Surveillance Requirements as Described in Ltr1999-04-30030 April 1999 Suppl 1 to Application to License NPF-30,adding License Conditions to Address Surveillance Requirements as Described in Ltr ULNRC-03910, Application for Amend to License NPF-30,updating Request to Allow Use of Electrosleeves on Two Cycle Basis.Proprietary & non-proprietary Version of 51-5001925-01,encl.Proprietary Rev 3 to TR BAW-10219P Also Encl.Proprietary Info Withheld1998-10-27027 October 1998 Application for Amend to License NPF-30,updating Request to Allow Use of Electrosleeves on Two Cycle Basis.Proprietary & non-proprietary Version of 51-5001925-01,encl.Proprietary Rev 3 to TR BAW-10219P Also Encl.Proprietary Info Withheld ULNRC-03902, Application for Amend to License NPF-30,revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start Turbine Driven Pump in TS Tables 3.3-3,3.3-4 & 4.3.21998-09-29029 September 1998 Application for Amend to License NPF-30,revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start Turbine Driven Pump in TS Tables 3.3-3,3.3-4 & 4.3.2 ULNRC-03873, Application for Amend to License NPF-30,revising TS Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr1998-07-30030 July 1998 Application for Amend to License NPF-30,revising TS Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ULNRC-03854, Application for Amend to License NPF-30,revising TS 3.7.1.7 Re SG Atmospheric Steam Dump Lines1998-06-29029 June 1998 Application for Amend to License NPF-30,revising TS 3.7.1.7 Re SG Atmospheric Steam Dump Lines ML20216F3731998-03-0909 March 1998 Application for Amend to License NPF-30,revising TS SR 3/4.5.2b.1 by Adding Clarification in Regard to Venting & ECCS Pump Casings & Accessible Discharge Piping High Points ML20198P3321997-10-31031 October 1997 Application for Amend to License NPF-30,reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4081997-10-31031 October 1997 Application for Amend to License NPF-30,revising Tech Specs Tables 3.3-3,3.3-4 & 4.3-2 Re ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump ML20217K2281997-10-17017 October 1997 Application for Amend to License NPF-30,revising TS 3/4.4.9, Pressure/Temperature Limits. Westinghouse Repts WCAP-14894,WCAP-14896 & WCAP-14895 Encl W/Application.Review & Approval of Amend Application Requested by 970301 ULNRC-03627, Application for Amend to License NPF-30,revising TS Table 3.7-2 Specifying That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer1997-08-0808 August 1997 Application for Amend to License NPF-30,revising TS Table 3.7-2 Specifying That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer ULNRC-03628, Application for Amend to License NPF-30,revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 as Listed1997-08-0808 August 1997 Application for Amend to License NPF-30,revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 as Listed ULNRC-03626, Application for Amend to License NPF-30,revising Tech Spec 3/4.7.4, Essential Svc Water Sys, by Removing Requirement to Perform SRs 4.7.4.b.1,4.7.4.b.2 & 4.7.4.c During Shutdown1997-08-0808 August 1997 Application for Amend to License NPF-30,revising Tech Spec 3/4.7.4, Essential Svc Water Sys, by Removing Requirement to Perform SRs 4.7.4.b.1,4.7.4.b.2 & 4.7.4.c During Shutdown ULNRC-03625, Application for Amend to License NPF-30,revising Tech Spec 3/4.3 Re Instrumentation & Changing Slave Relay Quarterly Surveillance to Quarterly Actuation Logic Test for Ms & FW Isolation Sys Actuation & Relays1997-08-0808 August 1997 Application for Amend to License NPF-30,revising Tech Spec 3/4.3 Re Instrumentation & Changing Slave Relay Quarterly Surveillance to Quarterly Actuation Logic Test for Ms & FW Isolation Sys Actuation & Relays ML20148C4541997-05-15015 May 1997 Application for Amend to License NPF-30,adding License Condition to Address Surveillance Requirements Not Previously Performed by Existing Requirements or Tests ML20138B7301997-04-24024 April 1997 Application for Amend to License NPF-30,revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer, Due to Retirement on 970430 & Replacement by GL Randolph on 970501 ML20137N6031997-04-0101 April 1997 Application for Amend to License NPF-30,requesting Rev to TS Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ULNRC-03402, Application for Amend to License NPF-30,changing TS 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys1996-07-18018 July 1996 Application for Amend to License NPF-30,changing TS 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20112E8731996-05-29029 May 1996 Application for Amend to License NPF-30,modifying Pneumatic Valve Control Configuration for Main Feedwater Control & Bypass Valves & Reflecting Unreviewed Safety Question Associated W/Mod ML20107M4401996-04-24024 April 1996 Application for Amend to License NPF-30,transferring License to Reflect Licensee as wholly-owned Operating Subsidiary of Ameren ML20107H3551996-04-17017 April 1996 Application for Amend to License NPF-30,adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2.Revise Table 3.3-3 by Adding Action Statements 27a & 34a ML20107E3171996-04-12012 April 1996 Application for Amend to License NPF-30,revising TS 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases to Address Installation of Laser Welded Tube Sleeves in Plant Sgs.Supporting Proprietary TR Encl.Proprietary TR Withheld ML20107F0421996-04-12012 April 1996 Application for Amend to License NPF-30,changing TS 3/4.4, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant Sgs.Info Re Installation Process in TR BAW-10219P,Rev 1 Dtd Mar 1996 Withheld ULNRC-03349, Application for Amend to License NPF-30,implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled1996-03-22022 March 1996 Application for Amend to License NPF-30,implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4091996-02-23023 February 1996 Application for Amend to License NPF-30,reflecting Union Electric as Wholly Owned Subsidiary of Ameren Corp ML20097D5681996-02-0909 February 1996 Application for Amend to License NPF-30,proposing Change to TS 5.3.1,to Allow Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6021996-02-0909 February 1996 Application for Amend to License NPF-30,proposing Changes to TS 4.6.1.2.a & Bases Re Containment Systems ML20097F8891996-02-0909 February 1996 Application for Amend to License NPF-30,revising TS 4.6.1.2.a Re Containment Sys ML20096B1811996-01-0202 January 1996 Application for Amend to License NPF-30,revising TS 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ULNRC-03264, Application for Amend to License NPF-30,revising TS Sections 5.3.1 & 5.6.1.1 & Figure 3.9-1 Re Spent Fuel Pool Storage. Rev 0 of Rept LFNF-95-02, Callaway Plant Region 1 Spent Fuel Rack Criticality Analysis Encl1995-09-0606 September 1995 Application for Amend to License NPF-30,revising TS Sections 5.3.1 & 5.6.1.1 & Figure 3.9-1 Re Spent Fuel Pool Storage. Rev 0 of Rept LFNF-95-02, Callaway Plant Region 1 Spent Fuel Rack Criticality Analysis Encl ULNRC-03244, Application for Amend to License NPF-30,revising TS 3/4.8.1 & Associated Bases to Achieve Overall Improvement in EDG Reliability & Availability Based Upon,In Part,Guidance of GLs 94-01,93-05 & Reg Guide 1.9,Rev 31995-07-25025 July 1995 Application for Amend to License NPF-30,revising TS 3/4.8.1 & Associated Bases to Achieve Overall Improvement in EDG Reliability & Availability Based Upon,In Part,Guidance of GLs 94-01,93-05 & Reg Guide 1.9,Rev 3 ML20086B7411995-06-26026 June 1995 Application for Amend to License NPF-30 Removing List of Containment Isolation Valves,Revising Allowed Outage Time for Component Cw Motor Operated Containment Penetration Check Valves as Isolation Devices ULNRC-03230, Application for Amend to License NPF-30.Amend Would Revise TSs to Implement Recommendations of GL 93-05 Re Reduction of SRs for Testing During Power Operation1995-06-23023 June 1995 Application for Amend to License NPF-30.Amend Would Revise TSs to Implement Recommendations of GL 93-05 Re Reduction of SRs for Testing During Power Operation ML20082S7701995-04-26026 April 1995 Application for Amend to License NPF-30.Amend Would Change Surveillance Requirements of TS 3/4.7.6,reducing Upper Limit on Flow Rate Through CR Filtration Subsystem ULNRC-03198, Application for Amend to License NPF-30,changing Table 2.2-1 of TS 2.2.1 to Reduce Repeated Alarms & Partial Reactor Trips Associated w/C-4 Control Sys Interlock & Overpower Delta-T,which Occurred in Past Cycles1995-04-17017 April 1995 Application for Amend to License NPF-30,changing Table 2.2-1 of TS 2.2.1 to Reduce Repeated Alarms & Partial Reactor Trips Associated w/C-4 Control Sys Interlock & Overpower Delta-T,which Occurred in Past Cycles ULNRC-03184, Application for Amend to License NPF-30,responding to Concerns Raised by NRC Staff During Review of Final Policy Statement on TS Improvements1995-03-29029 March 1995 Application for Amend to License NPF-30,responding to Concerns Raised by NRC Staff During Review of Final Policy Statement on TS Improvements ULNRC-03151, Application for Amend to License NPF-30,revising TS 4.6.1.7.4 & Associated Bases Re Containment Ventilation Sys1995-02-24024 February 1995 Application for Amend to License NPF-30,revising TS 4.6.1.7.4 & Associated Bases Re Containment Ventilation Sys ML20078A4731995-01-13013 January 1995 Application for Amend to License NPF-30 for Callaway Plant. Amend Would Relocate TS 3.3-2, Reactor Trip Sys Instrumentation Response Times ML20080C7531994-12-0909 December 1994 Application for Amend to License NPF-30,revising TS 4.3.2.2, 4.7.1.2.1 & Bases for Spec 3/4.7.1.2 for Afs ML20078P7001994-12-0909 December 1994 Application for Amend to License NPF-30,revising TS Surveillance Requirement 4.8.1.1.2f.7 to Remove Requirement to Perform Hot Restart within 5 Min of Completing 24 H Test & Place Requirement in Separate TS ML20077F2311994-12-0909 December 1994 Application for Amend to License NPF-30,requesting Exemption to 10CFR50,App J,Section III.D.1(a) & Rev to TS SR 4.6.1.2.a & Associated Bases to Defer Next Scheduled Containment ILRT for One Outage,From Refuel 7 to Refuel 8 ML20073A6091994-09-12012 September 1994 Application for Amend to License NPF-30,revising Tech Specs Table 3.7.1 Re Limit Max Allowable Power Levels W/Inoperable Main Steam Line Safety Valves ML20072T3421994-09-0909 September 1994 Application for Amend to License NPF-30,revising TS 3/4.8.1 & Associated Bases to Achieve Overall Improvement in Emergency Diesel Generator Reliability & Availability ML20073A6841994-09-0909 September 1994 Application for Amend to License NPF-30,revising Tech Specs 3/4.8.2.1,3/4.8.2.2,3/4.8.3.1 & 3/4.8.3.2 Re Electrical Power Sys Dc Sources & Onsite Power Distribution ML20072U4381994-09-0808 September 1994 Application for Amend to License NPF-30,revising TS 4.2.2.2, 4.2.2.4 & 6.9.19 to Incorporate Penalty in COLR to Account for Fq Increases Greater That 2% Between Measurements ML20072U7551994-09-0808 September 1994 Application for Amend to License NPF-30,reflecting Unreviewed Safety Question Associated W/Use of Reactor Makeup Water to Rinse Items Removed from Refueling Pool & Spray Down Refueling Pool ML20072A9671994-08-0404 August 1994 Application for Amend to License NPF-30,replacing TS 3/4.6.2.2, Spray Additive Sys W/Spec 3/4.6.2.2 Entitled, Recirculation Fluid Ph Control (Rfpc) Sys, Supporting Passive Rfpc Sys Consisting of Stainless Steel Baskets ML20072A0761994-08-0404 August 1994 Application for Amend to License NPF-30,revising TS to Reflect Changes in Boron Dilution Accident Analysis to Address Boron Dilution Mitigation Sys (Bdms) Time Delays & Bdms Actuation Setpoint Uncertainty ML20070A7931994-06-21021 June 1994 Application for Amend to License NPF-30,deleting TS Sections Describing On-Site Review Committee & Nuclear Safety Review Board ML20069D7321994-05-20020 May 1994 Application for Amend to License NPF-30,modifying TSs to Incorporate Improvements in Scope & Content Endorsed by NRC in Final Policy Statement on TS Improvements for Nuclear Power reactors,58FR39132 1999-09-08
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARULNRC-04103, Application for Amend to License NPF-30,reflecting USQ Associated with Increases to Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents1999-09-0808 September 1999 Application for Amend to License NPF-30,reflecting USQ Associated with Increases to Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ULNRC-04024, Suppl 1 to Application to License NPF-30,adding License Conditions to Address Surveillance Requirements as Described in Ltr1999-04-30030 April 1999 Suppl 1 to Application to License NPF-30,adding License Conditions to Address Surveillance Requirements as Described in Ltr ULNRC-03910, Application for Amend to License NPF-30,updating Request to Allow Use of Electrosleeves on Two Cycle Basis.Proprietary & non-proprietary Version of 51-5001925-01,encl.Proprietary Rev 3 to TR BAW-10219P Also Encl.Proprietary Info Withheld1998-10-27027 October 1998 Application for Amend to License NPF-30,updating Request to Allow Use of Electrosleeves on Two Cycle Basis.Proprietary & non-proprietary Version of 51-5001925-01,encl.Proprietary Rev 3 to TR BAW-10219P Also Encl.Proprietary Info Withheld ULNRC-03902, Application for Amend to License NPF-30,revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start Turbine Driven Pump in TS Tables 3.3-3,3.3-4 & 4.3.21998-09-29029 September 1998 Application for Amend to License NPF-30,revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start Turbine Driven Pump in TS Tables 3.3-3,3.3-4 & 4.3.2 ULNRC-03873, Application for Amend to License NPF-30,revising TS Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr1998-07-30030 July 1998 Application for Amend to License NPF-30,revising TS Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ULNRC-03854, Application for Amend to License NPF-30,revising TS 3.7.1.7 Re SG Atmospheric Steam Dump Lines1998-06-29029 June 1998 Application for Amend to License NPF-30,revising TS 3.7.1.7 Re SG Atmospheric Steam Dump Lines ML20216F3731998-03-0909 March 1998 Application for Amend to License NPF-30,revising TS SR 3/4.5.2b.1 by Adding Clarification in Regard to Venting & ECCS Pump Casings & Accessible Discharge Piping High Points ML20198P3321997-10-31031 October 1997 Application for Amend to License NPF-30,reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4081997-10-31031 October 1997 Application for Amend to License NPF-30,revising Tech Specs Tables 3.3-3,3.3-4 & 4.3-2 Re ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump ML20217K2281997-10-17017 October 1997 Application for Amend to License NPF-30,revising TS 3/4.4.9, Pressure/Temperature Limits. Westinghouse Repts WCAP-14894,WCAP-14896 & WCAP-14895 Encl W/Application.Review & Approval of Amend Application Requested by 970301 ULNRC-03627, Application for Amend to License NPF-30,revising TS Table 3.7-2 Specifying That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer1997-08-0808 August 1997 Application for Amend to License NPF-30,revising TS Table 3.7-2 Specifying That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer ULNRC-03628, Application for Amend to License NPF-30,revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 as Listed1997-08-0808 August 1997 Application for Amend to License NPF-30,revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 as Listed ULNRC-03626, Application for Amend to License NPF-30,revising Tech Spec 3/4.7.4, Essential Svc Water Sys, by Removing Requirement to Perform SRs 4.7.4.b.1,4.7.4.b.2 & 4.7.4.c During Shutdown1997-08-0808 August 1997 Application for Amend to License NPF-30,revising Tech Spec 3/4.7.4, Essential Svc Water Sys, by Removing Requirement to Perform SRs 4.7.4.b.1,4.7.4.b.2 & 4.7.4.c During Shutdown ULNRC-03625, Application for Amend to License NPF-30,revising Tech Spec 3/4.3 Re Instrumentation & Changing Slave Relay Quarterly Surveillance to Quarterly Actuation Logic Test for Ms & FW Isolation Sys Actuation & Relays1997-08-0808 August 1997 Application for Amend to License NPF-30,revising Tech Spec 3/4.3 Re Instrumentation & Changing Slave Relay Quarterly Surveillance to Quarterly Actuation Logic Test for Ms & FW Isolation Sys Actuation & Relays ML20148C4541997-05-15015 May 1997 Application for Amend to License NPF-30,adding License Condition to Address Surveillance Requirements Not Previously Performed by Existing Requirements or Tests ML20138B7301997-04-24024 April 1997 Application for Amend to License NPF-30,revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer, Due to Retirement on 970430 & Replacement by GL Randolph on 970501 ML20137N6031997-04-0101 April 1997 Application for Amend to License NPF-30,requesting Rev to TS Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ULNRC-03402, Application for Amend to License NPF-30,changing TS 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys1996-07-18018 July 1996 Application for Amend to License NPF-30,changing TS 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20112E8731996-05-29029 May 1996 Application for Amend to License NPF-30,modifying Pneumatic Valve Control Configuration for Main Feedwater Control & Bypass Valves & Reflecting Unreviewed Safety Question Associated W/Mod ML20107M4401996-04-24024 April 1996 Application for Amend to License NPF-30,transferring License to Reflect Licensee as wholly-owned Operating Subsidiary of Ameren ML20107H3551996-04-17017 April 1996 Application for Amend to License NPF-30,adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2.Revise Table 3.3-3 by Adding Action Statements 27a & 34a ML20107E3171996-04-12012 April 1996 Application for Amend to License NPF-30,revising TS 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases to Address Installation of Laser Welded Tube Sleeves in Plant Sgs.Supporting Proprietary TR Encl.Proprietary TR Withheld ML20107F0421996-04-12012 April 1996 Application for Amend to License NPF-30,changing TS 3/4.4, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant Sgs.Info Re Installation Process in TR BAW-10219P,Rev 1 Dtd Mar 1996 Withheld ULNRC-03349, Application for Amend to License NPF-30,implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled1996-03-22022 March 1996 Application for Amend to License NPF-30,implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4091996-02-23023 February 1996 Application for Amend to License NPF-30,reflecting Union Electric as Wholly Owned Subsidiary of Ameren Corp ML20097D5681996-02-0909 February 1996 Application for Amend to License NPF-30,proposing Change to TS 5.3.1,to Allow Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6021996-02-0909 February 1996 Application for Amend to License NPF-30,proposing Changes to TS 4.6.1.2.a & Bases Re Containment Systems ML20097F8891996-02-0909 February 1996 Application for Amend to License NPF-30,revising TS 4.6.1.2.a Re Containment Sys ML20096B1811996-01-0202 January 1996 Application for Amend to License NPF-30,revising TS 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ULNRC-03264, Application for Amend to License NPF-30,revising TS Sections 5.3.1 & 5.6.1.1 & Figure 3.9-1 Re Spent Fuel Pool Storage. Rev 0 of Rept LFNF-95-02, Callaway Plant Region 1 Spent Fuel Rack Criticality Analysis Encl1995-09-0606 September 1995 Application for Amend to License NPF-30,revising TS Sections 5.3.1 & 5.6.1.1 & Figure 3.9-1 Re Spent Fuel Pool Storage. Rev 0 of Rept LFNF-95-02, Callaway Plant Region 1 Spent Fuel Rack Criticality Analysis Encl ULNRC-03244, Application for Amend to License NPF-30,revising TS 3/4.8.1 & Associated Bases to Achieve Overall Improvement in EDG Reliability & Availability Based Upon,In Part,Guidance of GLs 94-01,93-05 & Reg Guide 1.9,Rev 31995-07-25025 July 1995 Application for Amend to License NPF-30,revising TS 3/4.8.1 & Associated Bases to Achieve Overall Improvement in EDG Reliability & Availability Based Upon,In Part,Guidance of GLs 94-01,93-05 & Reg Guide 1.9,Rev 3 ML20086B7411995-06-26026 June 1995 Application for Amend to License NPF-30 Removing List of Containment Isolation Valves,Revising Allowed Outage Time for Component Cw Motor Operated Containment Penetration Check Valves as Isolation Devices ULNRC-03230, Application for Amend to License NPF-30.Amend Would Revise TSs to Implement Recommendations of GL 93-05 Re Reduction of SRs for Testing During Power Operation1995-06-23023 June 1995 Application for Amend to License NPF-30.Amend Would Revise TSs to Implement Recommendations of GL 93-05 Re Reduction of SRs for Testing During Power Operation ML20082S7701995-04-26026 April 1995 Application for Amend to License NPF-30.Amend Would Change Surveillance Requirements of TS 3/4.7.6,reducing Upper Limit on Flow Rate Through CR Filtration Subsystem ULNRC-03198, Application for Amend to License NPF-30,changing Table 2.2-1 of TS 2.2.1 to Reduce Repeated Alarms & Partial Reactor Trips Associated w/C-4 Control Sys Interlock & Overpower Delta-T,which Occurred in Past Cycles1995-04-17017 April 1995 Application for Amend to License NPF-30,changing Table 2.2-1 of TS 2.2.1 to Reduce Repeated Alarms & Partial Reactor Trips Associated w/C-4 Control Sys Interlock & Overpower Delta-T,which Occurred in Past Cycles ULNRC-03184, Application for Amend to License NPF-30,responding to Concerns Raised by NRC Staff During Review of Final Policy Statement on TS Improvements1995-03-29029 March 1995 Application for Amend to License NPF-30,responding to Concerns Raised by NRC Staff During Review of Final Policy Statement on TS Improvements ULNRC-03151, Application for Amend to License NPF-30,revising TS 4.6.1.7.4 & Associated Bases Re Containment Ventilation Sys1995-02-24024 February 1995 Application for Amend to License NPF-30,revising TS 4.6.1.7.4 & Associated Bases Re Containment Ventilation Sys ML20078A4731995-01-13013 January 1995 Application for Amend to License NPF-30 for Callaway Plant. Amend Would Relocate TS 3.3-2, Reactor Trip Sys Instrumentation Response Times ML20080C7531994-12-0909 December 1994 Application for Amend to License NPF-30,revising TS 4.3.2.2, 4.7.1.2.1 & Bases for Spec 3/4.7.1.2 for Afs ML20078P7001994-12-0909 December 1994 Application for Amend to License NPF-30,revising TS Surveillance Requirement 4.8.1.1.2f.7 to Remove Requirement to Perform Hot Restart within 5 Min of Completing 24 H Test & Place Requirement in Separate TS ML20077F2311994-12-0909 December 1994 Application for Amend to License NPF-30,requesting Exemption to 10CFR50,App J,Section III.D.1(a) & Rev to TS SR 4.6.1.2.a & Associated Bases to Defer Next Scheduled Containment ILRT for One Outage,From Refuel 7 to Refuel 8 ML20073A6091994-09-12012 September 1994 Application for Amend to License NPF-30,revising Tech Specs Table 3.7.1 Re Limit Max Allowable Power Levels W/Inoperable Main Steam Line Safety Valves ML20072T3421994-09-0909 September 1994 Application for Amend to License NPF-30,revising TS 3/4.8.1 & Associated Bases to Achieve Overall Improvement in Emergency Diesel Generator Reliability & Availability ML20073A6841994-09-0909 September 1994 Application for Amend to License NPF-30,revising Tech Specs 3/4.8.2.1,3/4.8.2.2,3/4.8.3.1 & 3/4.8.3.2 Re Electrical Power Sys Dc Sources & Onsite Power Distribution ML20072U4381994-09-0808 September 1994 Application for Amend to License NPF-30,revising TS 4.2.2.2, 4.2.2.4 & 6.9.19 to Incorporate Penalty in COLR to Account for Fq Increases Greater That 2% Between Measurements ML20072U7551994-09-0808 September 1994 Application for Amend to License NPF-30,reflecting Unreviewed Safety Question Associated W/Use of Reactor Makeup Water to Rinse Items Removed from Refueling Pool & Spray Down Refueling Pool ML20072A9671994-08-0404 August 1994 Application for Amend to License NPF-30,replacing TS 3/4.6.2.2, Spray Additive Sys W/Spec 3/4.6.2.2 Entitled, Recirculation Fluid Ph Control (Rfpc) Sys, Supporting Passive Rfpc Sys Consisting of Stainless Steel Baskets ML20072A0761994-08-0404 August 1994 Application for Amend to License NPF-30,revising TS to Reflect Changes in Boron Dilution Accident Analysis to Address Boron Dilution Mitigation Sys (Bdms) Time Delays & Bdms Actuation Setpoint Uncertainty ML20070A7931994-06-21021 June 1994 Application for Amend to License NPF-30,deleting TS Sections Describing On-Site Review Committee & Nuclear Safety Review Board ML20069D7321994-05-20020 May 1994 Application for Amend to License NPF-30,modifying TSs to Incorporate Improvements in Scope & Content Endorsed by NRC in Final Policy Statement on TS Improvements for Nuclear Power reactors,58FR39132 1999-09-08
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e UNION ELECTRIC COM PANY 1908 GRATIOT STREET ST. Louis, MISSOURI
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Mr. Harold R. Denton Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
ULNRC-875 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 REVISIONS TO TECHNICAL SPECIFICATIONS 3. 4.9. 3, 4.6.1.2, AND 3/4.6.1.2 BASES Union Electric Company is transmitting three (3) original and forty (40) conformed copies of an application for knendment to Facility Operating License No. NPF-25 for the Callaway Plant, Unit 1.
This application requests that Callaway Technical Specifications 3.4.9.3, 4.6.1.2, and 3/4.6.1.2 bases be revised to reflect the following changes. The Technical Specification 4.6.1.2, containment leakage surveillance requirement, and its associated bases 3/4.6.1.2 have been revised to provide clarifications on the leak rate testing of valves pressurized with fluid from a seal system. The clarifications are provided by the incorporation of Standard Technical Specifications 4.6.1.2.d.3 and 4.6.1.2.g (NUREG-0452, Revision 4) into Callaway Specifications 4.6.1.2.d.3 and 4.6.1.2.h and by an addition to bases 3/4.6.1.2 to include callaway Plant specific requirements that are consistent with 10CFR50, Appendix J, Paragraph III.C. 3.
In addition the Callaway FSAR Section 6.2.6.3, Containment Isolation Valve Leakage Rate Tests (Type C tests), will be revised as attached and will be incorporated into the next revision of the FSAR.
The overpressure protection systems Technical Specification, limiting condition for operation (LCO), 3.4.9.3.a is being changed to set the allowable tolerance on the RHR suction relief valves at + 3% rather than + 1%. This change makes the SpecificatTon consistent with the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Article NB 7513.1, as long as the maximum pressure allowed is less than the lowest pressure setting of the power operated relief valves (PORVs). In addition, Action item (a) for this Specification is being changed as indicated in the enclosure to make the Action item consistent {g (3 with the LCO. \
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Mr. Harold R. Danton July 17, 1984 Page 2:
The proposed changes would become effective for Union Electric implementation upon NRC approval. Attachment 1 to this letter describes all enclosures transmitted herewith.
Enclosed is a check for the $150.00 application fee as requested by 10CFR170.21.
Very truly yours, D. F. Schnell DJW/lw Attachments l
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5 STATE OF MISSOURI )
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Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an of ficer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By Donald F. Schnell Vice President Nuclear SUBSCRIBED and sworn to before me this / day of , 198d BARDARA a w, PFAFF NOTARY PUBLIC, STATE OF MISSOURI MY C0tlMISSION EXPIRES APRIL 22,1985 ST. LOUIS COUNTY
cc: Gerald Charnoft, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.
Washington, D.C. 20036 Nicholas A. Petrick Executive Director SNUPPS
'S Choke Cherry Road Rockville, Maryland 20850 John H. Neisler Callaway Resident Office U.S. Nuclear Regulatory Commission RRil-Steedman, Missouri- 65077 William Forney Division of Projects and Resident Programs, Chief, Section LA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 Joseph J. Holonich, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop P-316 Washington, D.C. 20555 Ron Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65012
ULMRC-875 7/17/84 Attachment 1 Enclosure A Safety Evaluation Enclosure B Significant Hazards Consideration Enclosure C Marked Technical Specifications and Bases Enclosure D Marked FSAR Section 6.2.6.3
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ENCLOSURE A ULNRC-875 7/17/84 SAFETY EVALUATION This amendment request revises Technical Specification !
4.6.1.2, and its associated bases, and FSAR Section 6.2.6.3 to provide claritications on the leak rate testing of valves pressurized with fluid from a seal system. These clarifications i
are consistent with 10CFR50, Appendix J, Paragraph III.C.3 and
-Standard Technical Specifications 4.6.1.2.d.3 and 4.6.1.2.g (NUREG-0452, Revision 4) . In addition, a specific example of the applicability of these clarifications is cited regarding containment penetrations P-28, P-29, P-71, and P-73 (essential 1 service water to/from containment coolers as depicted on FSAR Fig. 6.2.4-1). For these penetrations the water volume contained in the piping inside containment (from the cooler to the inboard
' isolation valve) provides a passive water seal on the affected valves (EF-HV-33,34,45, and 46 as shown on FSAR Fig. 9.2-2, sheet
- 2) . The water inventory insido containment is sufficient to assure the sealing function for at least 30-days at a pressure of 1.10 Pa (53 psig) when the leakage for each of these penetrations is less than or equal to 7500 cc/hr as stated in the revised bases for Technical Specification 3/4.6.1.2. This leakage acceptance criterion is being added to the. bases per 10CFR50,
' Appendix J, Paragraph II.C.3. (a) and Standard Review Plan 6.2.6 and is based upon the as-built piping configuration. The water volume from the air. cooler to the nearest containment isolation valve would be depleted in 30 days if the leakage rate were greater than 7641 cc/hr.
In addition this amendment request revises Technical Specification 3.4.9.3 limit ing condition for operation LCO (a) and Action' item (a). For LCO (a) the allowable tolerance on the RHR suction relief valves is being changed to + 3% rather than
+ 14. The + 1% tolerance was selected based on the tolerances t Tor the pressurizer code safety valves. To be consistent with the requirements of ASME Boiler and Pressure Vessel Code,Section III, Article NB 7513.1, a tolerance of + 3% is acceptable, as long as the maximum pressure allowed is less than the lowest pressure setting of the power operated relief valves (PORVs).
Also, Action item (a) as written is not consistent with the LCO as specified. The intent of the Specification is to give credit for the availability of the RHR suction relief valves for cold overpressure protection. In the Standard Technical Specifications (NUREG-0452) , Revision 4) , when relying on PORVs for cold overpressure protection, if one PORV becomes inoperable, seven days are allowed for restoring it or an action would be
- required forJCallaway to open a two square inch vent. Regardless of the status of the PORVs, this same action should be applicable
~if Callaway loses one RHR suction relief valve while relying on RHR suction relief for cold overpressure protection.
Pursuant to the above information, this amendment request
- 'does not adversely affect or endanger the health of the general public and does not involve an unreviewed safety question.
ENCLOSURE B ULNRC-875 7/17/84 SIGNIFICANT HAZARDS CONSIDERATION This amendment request. revises Technical Specification 4.6.1.2,Iand its associated bases, and FSAR Section 6.2.6.3 to provide clarifications on the leak rate testing of valves pressurized with fluid from a seal system. These clarifications are. consistent with 10CFR50,' Appendix J, Paragraph III.C.3 and
, Standard Techrtical Specifications 4.6.1.2.d.3 and 4.6.1.2.g i ~(NUREG-0452, Revision 4) . Containment penetrations for essential service water supply to and return from the containment coolers satisty the sealed system exclusion allowed by 10CFR50, Appendix J,. Paragraph III.C 3..
In addition this amendment request revises Technical Specification 3.4.9.3 limiting condition for operation, LCO (a) and Action item (a) . The LCO is revised to make the allowable
-tolerance on'the RER suction relief valves consistent with ASME Boiler and Pressure Vessel Code,Section III, Article NB 7513.1.
DFurther,-Action item (a) is being modified slightly to make it consistent with the LCO as specified and consistent with the
' intent as given in the Standard Technical Specifications (NUREG-0452, Revision 4) .
'The Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain
' examples (48FR14870). This amendment request is similar to the example of an action involving no significant hazards consideration which relates to a change to make the license
. conform to regulations, where the license amendment results in
~
1 changes to facility operations clearly in keeping with the regulations.
This amendment request does not involve a significant increase-in.the probability or consequences of an accident or other adverse condition over previous evaluations; nor create the possibility of a new or different kind of accident or condition over previous _ evaluations; nor involve a significant reduction in a margin of safety.. Based on the foregoing, the requested amendment does not present a significant hazard.
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