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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
[Table view] |
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53 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555 Gentlemen: ULNRC-3033 DOCKET NUMBER 50-483 CALLAWAY PLANT REVISION TO TECHNICAL SPECIFICATION 6.0 ADMINISTRATIVE CONTROLS Union Electric Company herewith transmits an application for amendment to Facility Operating License No. NPF-30 for Callaway Plant.
This amendment application deletes the sections describing the On-Site Review Committee (ORC) and the Nuclear Safety Review Board (NSRB) from the Technical Specifications. All of the information contained in these sections is also contained in Chapter 13 of the Callaway Plant Final Safety Analysis Report. This change was suggested in an NRC letter to the Technical Specification Committee Chairmen of the four owners groups dated October 25, 1993, " Content of Standard Technical Specifications, Section 5.0, Administrative Controls."
Attachments 1, 2, 3, and 4 contain the Safety Evaluation, the Significant Hazards Evaluation, the Environmental Evaluation, and the Proposed Technical Specification Changes in support of this amendment request.
This change request has been approved by the Callaway Onsite Review Committee and the Nuclear Safety Review Board.
Very truly yours,
.. p Donald F. Schnell RMD/kea Attachments 9406290163 DR 940621 ADOCK 03 coo 4gv . ) i PDR
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- Attachments ULNRC-3033 Attachment 1 - Safety Evaluation Attachment 2 - Significant Hazards Evaluation Attachment 3 - Environmental Consideration Attachment 4 - Proposed Technical Specification Changes
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STATE OF MISSOURI )
) SS CITY OF ST. LOUIS )
Alan C. Passwater, of lawful age, being first duly sworn upon oath says that he is Manager, Licensing and Fuels (Nuclear) for 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 ###
Alan C. Passwater Manager, Licensing and Fuels Nuclear SUBSCRIBED and sworn to before me this N/- day of slune -
, 1994.
/ NA UL '? ff BARBARA J. hkAF1' k k [/
NOTARY PUBLIC-STATE OF MISSOURI Mf COMMISSION EXPIRES APRIL 22, 1997.
SI. LOUls COUNIX l
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. I cc: T. A. Baxter, Esq. I Shaw, Pittman, Potts & Trowbridge i 2300 N. Street, N.W.
Washington, D.C. 20037 M. H. Fletcher CFA, Inc.
18225-A Flower Hill Way i Gaithersburg, MD 20879-5334 L. Robert Greger '
Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 50532-4351 Bruce Bartlett Callaway Resident Office U.S. Regulatory Commission RR#1 Steedman, MO 65077 L. R. Wharton (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 3 Jefferson City, MO 65102 l
Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 l
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Attachmant 1 Page 1 of 2 ULNRC-3033 SAFETY EVALUATION Backaround Effective July 1, 1994 the Manager, Nuclear Safety and Emergency Preparedness (a member of the Nuclear Safety Review l Board) will retire. That position will no longer exist, and the j responsibilities will be divided between the Manager, Quality Assurance and the Manager, Emergency Preparedness and l Organizational Support.
Rather than making a Technical Specification change of narrow scope now, and making subsequent changes upon each title or organizational change, we request a Technical Specification -
revision of the Administrative Controls section based on the latest proposed revision of the Standardized Technical Specifications.
Proposed Chances "
The proposed technical specification changes delete the sections describing the On-Site Review Committee (ORC) and the Nuclear Safety Review Board (NSRB). All of the information contained in these sections is also contained in Chapter 13 of the Callaway Plant Final Safety Analysis Report (FSAR). >
In addition, references to the Independent Safety Engineering Group (ISEG) will reflect that it now reports to the Manager, Quality Assurance, who is also a member of the NSRB, instead of the Manager, Nuclear Safety and Emergency Preparedness. All references to the Manager, Nuclear Safety and Emergency Preparedness will be removed as that position no longer exists.
The affected Technical Specification Sections are 6.2.3, ;
6.5.1, 6.5.2, 6.5.3, and the Index.
Evaluation i The sections being deleted describe the function, composition, alternate membership, meeting frequency, quorum, responsibilities, and records of the On-Site Review Committee (ORC) and the Nuclear ,
Safety Review Board (NSRB) . These topics- are covered in equivalent .
detail in the Callaway Plant Final Safety Analysis Report (FSAR) !
and plant administrative procedures as required by our commitment !
to ANSI N18.7-1976. Changes to the FSAR are controlled based on 10CFR50.59 and updated in accordance with the requirements of 10CFR50.71(e). No change is made to the ORC or the NSRB, except for the retirement of the Manager, Nuclear Safety and Emergency {
Preparedness, and no change is made to the manner in which they !
function.
The audit and review function requirements of 10 CFR
- 50. 3 6 (c) (5) continue to be described in Technical Specification t section 6.5.3 and is controlled by the Operating Quality Assurance Manual (OQAM).
Attachment 1 Page 2 of 2 ULNRC-3033 ,
l The proposed changes are administrative in nature. No change l is required to plant facilities, components, or systems. The i changes do not significantly reduce the overall base of experience at the Callaway Plant nor the commitment to minimum qualifications. ,
Callaway Plant personnel will continue to have the training, !
experience, and expertise necessary to recognize, analyze, assess, evaluate, and effectively respond to plant transients or other )
abnormal events. l l
The proposed changes to the Technical Specifications do not 1 involve an unreviewed safety question because operation of the !
Callaway Plant with these changes would not:
- 1. Increase the probability of occurrence or the consequences i of an accident or malfunction of equipment important to !
safety previously evaluated in the safety analysis report. l The proposed changes do not affect accident initiators or assumptions. The radiological consequences of any accident j previously evaluated remain unchanged. The changes are i administrative and equivalent descriptions and requirements for these oversight committees are contained in FSAR Section 13.4.
- 2. Create the possibility for an accident or malfunction of a different type than any previously evaluated in the safety analysis report.
The proposed changes do not create any new accident initiators nor involve any modifications or changes in the plant. The changes are administrative and equivalent descriptions and requirements for these oversight committees are contained in FSAR Section 13.4.
- 3. Reduce the margin of safety as defined in the basis for any .
technical specifications. I The proposed changes do not affect any safety limits or boundary or system performance. The changes are administrative and equivalent descriptions and requirements I for these oversight committees are contained in FSAR Section 13.4.
On the basis of the above discussions and the considerations presented in the Significant Hazards Evaluation, the proposed changes do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard.
Attachment 2 Page 1 of 2 ULNRC-3033 SIGNIFICANT HAZARDS EVALUATION The proposed technical specification changes delete the sections defining the composition and responsibilities of the on-Site Review Committee (ORC) and the Nuclear Safety Review Board (NSRB). All of the information contained in these sections is also contained in Chapter 13 of the Callaway Plant Final Safety Analysis Report (FSAR).
In addition, references to the Independent Safety Engineering Group (ISEG) will reflect that it now reports to the Manager, Quality Assurance instead of the Manager, Nuclear Safety and Emergency Preparedness. The Manager, Quality Assurance is also a member of the NSRB. All references to the Manager, Nuclear Safety and Emergency Preparedness will be removed as that position no longer exists.
The affected Technical Specification Sections are 6.2.3, 6.5.1, 6.5.2, 6.5.3, and the Index.
The proposed changes do not involve a significant hazards consideration because operation of Callaway Plant with these changes would not: l
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
The changes are administrative and equivalent descriptions ,
and requirements for these oversight committees are !
contained in FSAR Section 13.4. i
- 2. Create the possibility of a new or different kind of accident from any previously evaluated.
These changes do not involve any physical alterations to the plant. There is no new type of accident or malfunction created and the method and manner of plant operation will not change. The changes are administrative and equivalent descriptions and requirements for these oversight committees are contained in FSAR Section 13.4.
- 3. Involve a significant reduction in a margin of : safety.
The margin of safety remains unaffected since no design l change is made and plant operation remains the same. The changes are administrative and equivalent descriptions and requirements for these oversight committees are contained in FSAR Section 13.4.
Attachmsnt 2
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Page 2 of 2 i ULNRC-3033 As discussed above, the proposed changes are strictly administrative in nature and have no effect on plant operations.
They do not involve a significant increase in the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any i previously evaluated. These changes do not result in a i significant reduction in a margin of safety. Therefore, it has !
been determined that the proposed changes do not involve a :
significant hazards consideration.
l Attachment 3 l Page 1 of 1 '
ULNRC-3033 ENVIRONMENTAL CONSIDERATION l l
l This amendment application requests revisions to Technical i Specification Sections 6.2.3., 6.5.1, 6.5.2, 6.5.3, and the Index.
The proposed changes delete the sections describing the On site ;
Review Committee (ORC) and the Nuclear Safety Review Board (NSRB).
All of the information contained in these sections is also contained in Chapter 13 of the Callaway Plant Final Safety Analysis Report (FSAR).
In addition, references to the Independent Safety I Engineering Group (ISEG) will reflect that it now reports to the ,
Manager, Quality Assurance instead of the Manager, Nuclear Safety !
and Emergency Preparedness.
Union Electric has determined that the proposed amendment involves changes in record keeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22 (c) (10) . Pursuant to 10 CFR 51.22(b) no l environmental assessment need be prepared in connection with the issuance of this amendment. j l
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