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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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+ g 1901 Grotiot Street St. Louis Donald F.Schnell February 12, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ULNRC- 1037
Dear Mr. Denton:
DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 REVISION TO TECHNICAL SPECIFICATION 4.6.1.6.1, SURVEILLANCE OF CONTAINMENT VESSEL TENDONS Union Electric Company herewith transmits three (e) original and forty (40) conformed copies of an application for amendment to Facility Operating License No. NPF-30 for Callaway Plant, Unit 1.
This application requests that the Callaway Technical Specifications, Appendix A to the Operating License, be revised to extend the period for completion of the containment vessel tendon surveillances required by Specification 4.6.1.6.1.
Deferral of the Callaway surveillance is required-to allow Union Electric's inspection contractor, INRYCO, Inc., to assist Alabama Power Company in evaluating anomalies recently found in the containment post tensioning system of the Parley-Unit 2 plant.
Without INRYCO's services, the outage at-Farley would be unnecessarily extended. The enclosures to this letter include a safety evaluation of the requested change,-. consideration of significant hazards, and a proposed revision to Page 3/4 6-8'of the Technical Specifications. These enclosures document Union Electric's position that the requested amendment does not present a significant hazard.
The requested change involves an additional 6 mo.nths in the'due date of the initial one year tendon surveillance and a resultant step change of 6 months in the subsequent surveillance dates. Our need date for approval of this amendment request is- -
April.5, 1985,-based on the current date. scheduled for completion of-the subject' surveillance. ' Enclosed is a check for the $150.00 application fee-required by 10CFR170.21.
Very truly yours, K ON 8 Donald F. Schnell DFS/DS/bjp
Enclosures:
1-Safety Evaluation \
2-Significant Hazard Consideration CP 3-Marked Specification Page 3/4 6-8 t% O' Moihng Addrest P.O Box 149, St. Louis MO 63166 g pM -
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s STATE OF MISSOURI )
)' SS CITY OF ST. LOUIS )
Donald F. Schnell, of lawful age, being first duly sworn
- upon oath says that-he is Vice President-Nuclear and an officer 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 /8 day of 198f BARBARA P
$f/w F NOTARY PUBLIC, STATE OF MISSOURI MY COMMISS1ON EXPIRES APRIL 22,1985 ST. LOUIS COUNTY n-
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cc: ' ' Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.
Washington, D.C. 20036
, LNicholas A. Petrick
, Executive Director ~
SNUPPS 5 Choke Cherry Road
[ Rockville,. Maryland 20850 John H. Neisler Callaway Resident Office
.U.S._ Nuclear Regulatory Commission RRil Steedman, Missouri 65077 2
- William Forney Division of Projects and 1 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 RRill '
Steedman, Missouri 65077 Jan'Stevens
. . Office of Nuclear Reactor Regulation
, :U.S.JNuclear Regulatory Commission Mail Stop P-316 e- 7920 Norfolk Avenue
-Bethesda, MD: 20014 Ron Kucera, Deputy Director Department of Natural Resources
- P.O. Box 1761
. Jefferson City, Missouri _ 65102 P'
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Enclosure 1 to ULNRC-1037 SAFETY EVALUATION This amendment request revises the timing associated with Technical Specification Surveillance 4.6.1.6.1, by extending each
>ofEthe three containment vessel tendon surveillances six (6) cmonths. . This. extension is requested because the-services of .
>INRYCO,'the inspection contractor for. Union Electric and Alabama
-Power.Co., are needed to evaluate anomalies recently found at the
'Farley -1 Unit.2-plant. We have released INRYCO to Alabama Power Company.so-that'the outage associated with the Farley problem is not-unnecessarily extended. In support of this request, the ti following sections address the Callaway post tensioning system design conservatism, inspections of installation activities,
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field. anchor head materials, recent field inspection results, and expected.results of the' initial tendon surveillance based on Bechtel' experience.
' Design Conservatism The containment vessel' post tensioning system is designed to
. provide a minimum level of prestress of 1.2 times the design accident pressure at the end of the 40-year design life of the
, plant.- The prestressing tendons are initially stressed to provide an.even-higher level of prestress to allow for-time-dependent stress-losses which occur during the life of the plant.
As such, there is a significantly higher level of prestress.
1provided at the beginning of the design'11fe overrthat remaining after 40 years.
The Callaway post tensioning system was designe5 for an internal containment pressure:of 72 psig,:which is_ .2 times the
- .designLaccident pressure'of 60.psig. The'containmentswas subjected.to a' test' pressure of-69 psig during the. Containment Structural 1 Integrity Test (SIT) in January,_1984. In the event-of a main steam line break (the accidentiwhich yields the-maximum containment 1 pressure), pressure.is--' calculated to peak..at'48.1; psig.. This~provides-a: margin of 1.50,.25% higherLthan the required value.of 1.2. 'Takingfprestressing(. levels predicted to occur in six months-into account, the margin?becomes approximately;1.65..
It:should be noted_that,the 1.2 prestress factor is.provided only to maintain compression inlthe concrete shell during the
- SIT. This level of prestress is-not required,1however, to maintain structural integrity. The containment'isfdesigned to'
/ remain elastic'atLinternal pressures of:approximately190 psig and
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"" it'can-be'shown-that the ultimate capacity is atlleastL120 psig.
' Inspections of Installation Activities ,
p During'the: period of'Februaryc1981 through October 1981, the-following audits, surveillances and inspections were completed
.' twhile; overseeing, installation ~of'the callaway containment. post tensioningssystem: e v
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_2-One Bechtel/UEQA Audit, Six UEQA Surveillances, One DIC/UEQA Audit, Three DIC/QA Surveillances, and Seven NRC Inspection Reports These reports document the performance of tendon button heading, tendon stressing, greasing, material storage, equipment calibration / qualification, QC inspection, and personnel qualification. All reports indicate satisfactory performance by INRYCO during installation of the Callaway post tensioning system.
Field Anchor Head Plate Materials Some of the problems encountered with containment post tensioning systems at other plants appear to be related to anchor head material manufactured and heat treated in the early 1970's.
A review of records provided for Callaway anchor heads by the material suppliers and heat treatment vendors showed the following:
Material Supplier Dates Copperweld 1980, 81 Tech. Steel & Alloy 1979, 80 Timken 1979, 80 Heat Treatment Vendors Specification Varco Heat Division MIL-H-6875-F Accurate Steel Treating PT 5.2.1 INRYCO FPM Heating Division PT 5.2.1 INRYCO It was determined that a different INRYCO heat treatment procedure was used for Callaway anchor heads (HT-101 had been used previously).* The material suppliers and heat treatment vendors employed for Callaway anchor heads are different than those involved with anchor heads which failed at other sites.
This reinforces our conclusion that tendons installed at Callaway continue to satisfy design requirements.
Recent Field Inspection Results On February 5, 1985 a visual inspection of the Callaway containment post tensioning system was conducted by personnel from Union Electric engineering and operations departments and Bechtel site engineering. The inspection involved looking for tendon grease cap deformation or abnormal grease leakage and excessive cracking around the tendon bearing plates. Further visual inspection cannot be performed without removing the grease cap, which requires the services of INRYCO.
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A close inspection was made of all 172 (86 tendons) inverted U and~100 (.0 5 tendons) reasonably accessible hoop anchorages. No
- deformation, abnormal grease leakage or cracking was found.
An inspection of the remaining 170 (85 tendons) hoop and 60'-(30 tendons) horizontal dome anchorages was made with the aid of~ field' glasses. Tha deformation or abnormal grease leakage Was
-found.
Based on this inspection of all Callaway tendon anchorages, nct evidence was found to indicate a tendon failure or excessive stress in the' concrete.
Bechtel Initial Tendon Surveillance Experience
~Bechtel-has designed 14 containment buildings which employ post' tensioning systems-and for which the first year inspections
- have been completed. Four of these units involved INRYCO, the
'same supplier-as was used at Callaway. All surveillances in the
.first year were acceptable.
Conclusion.
Based on the information above, the-proposed revision to Technical Specification 4.6.1.6;1 does not affect or endanger the thealth'and safety'of the general public and does not-involve an unreviewed' safety question.
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- Enclosure 2 to ULNRC-1037 SIGNIFICANT HAZARDS CONSIDERATIONS
-This amendment request revises the timing associated with Technical Specification Surveillance 4.6.1.6.1, by extending each of the three containment vessel tendon surveillances six (6) months. The Safety Evaluation, included as Enclosure 1 to this letter, provides Union. Electric's' bases for concluding that the Callaway Plantican be safely operated consistent with the revised surveillance schedule.
-The. Safety Evaluation addressed the design conservatism,
-inspections of installation activities, field anchor head materials, recent field' inspection results, and expected results
.from the initial inservice tendon surveillance for the Callaway post tensioning system. Based on this, a six month extension in the time for the detailed tendon surveillance will not
'significantly increase the probability of-tendon failure and will',.therefore, not increase the probability or consequences of any.previously analyzed accident.
- Because'the proposed extension of the time for detailed l tendon surveillance will not impact tendon integrity, will not affect'the method and manner of plant operation and will not Laffect. components and: equipment important to-safe operation, the proposed amendment does .not create the possibility of a new and -
-different accident-from any previously evaluated.
.Because recentEfield. inspections _showed no evidence of
. tendon failure and'because containment prestress levels are not E< : expected to decrease (by anyEsignificant degree in the proposed six month period of surveillance extension, this revision to the
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Technical Specifications will not significantly.' reduce,any' 3 margins'of safety.
Based on the foregoing analysis, the requested license amendment does not present a significant hazard.
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