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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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ddh July 18, 1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555 Gentlemen: ULNRC-0 34 02 l l
l DOCKET NUMBER 50-483 '
CALLAWAY PLANT CHARCOAL TEST METHODOLOGY - EMERGENCY EXHAUST SYSTEM Union Electric Company herewith transmits an application lor amendment to Facility Operating License No. NPF-30 for the Callaway Plant.
This ame.'dment application includes changes to the Surveillance 3equirements c of Technical Specifications 3/4.7.7, 3/4.9.13 and corresponding Bases. The changes implement an updated charcoal test methodology for the emergency exhaust system. The updated methodology, ASTM D-3803-1989, is consistent with that used for the control room ventilation system approved in Callaway License Amendments 96 and 106.
The Callaway Plant Onsite Review Committee and the Nuclear Safety Review Board have reviewed this amendment application. Attachments 1 through 4 provide the Safety Evaluation, Significant Hazards Evaluation, Environmental Consideration, and proposed Technical Specification revisions, respectively, in support of this request. It has been determined that this amendment application does not involve an unreviewed i safety question as determined per 10CFR50.59 nor a l
significant hazard consideration as determined per 10CFR50.92. Pursuant to 10CFR51.22 (b) , no environmental assessmant need be prepared in connection with the issuance of this amendment.
l 9607230411 960718 PDR ADOCK 05000483 N
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U.S. Nuclear Regulatory Commission l . Page 2 It is requested that when this amendment is i l issued, an additional 30 days be allowed for l implementation. If you have any questions on this request, please contact us.
1 Very truly yours, 5
Donald F. Schnell DES /plr l
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i l ._ STATE OF MISSOURI )
) SS CITY OF ST. LOUIS )
- Alan C.-Passwater, of lawful age, being first duly sworn i l upon' oath says that-he is Manager, Licensing and Fuels l (Nuclear) for Union Electric Company; that he has read the i' 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 j stated are true and correct co the best of his knowledge, i
t information and belief.
By L
Alan C. Passwater .
Manager, Licensing and Fuels j Nuclear l
SUB ED and sworn to before me this M NM day of -
, 1996. 8
/ e 0bM e av BARBARA J. PFAFY.
NOTARY PUBLIC-STATE OF MISSOURI MY COMMISSION EXPIRES APRIL 22,199Z SL LOUIS COUN1%
l g yw --'p+7 e -
. __ - _ _ . _ _ = . _ _ . . _ . _ _ . - - _
cc: T. A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington, D.C. 20037 M. H. Fletcher Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 L. Joe' Callan Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Kristine M. Thomas (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Don Woodlan TU Electric 1601 Bryan Street Dallas, TX 75201-3411 Pat Nugent Pacific Gas & Electric Regulatory Services P.O. Box 56
( Avila Beach, CA 93424 d
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ATTACHMENT 1 1
SAFETY EVALUATION i
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. Attachment 1
, , Page 1 of 4 Safety Evaluation Eronosed Chance This license amendment request proposes to revise surveillance requirements 4.7.7.b.2, 4.7.7.c, and 4.9.13.b.2 and 4.9.13.c to reflect a proposed change to the acceptance criteria for the testing of carbon samples from the auxiliary / fuel building emergency exhaust system charcoal adsorbers. This proposed change would adopt ASTM D-3803-1989 as the laboratory testing standard for charcoal samples from the charcoal adsorbers (FGG02 A,B) in the auxiliary / fuel building emergency exhaust system.
Laboratory testing of the carbon samples taken from the charcoal adsorbers will be performed at 30 degrees Centigrade ( C) and 70% relative humidity for a methyl iodide penetration of 2%, instead of a 1% limit at 80 C and 70% relative humidity.
EvaluatioD The fuel building heating ventilation and air conditioning (HVAC) system and the auxiliary building HVAC system are discussed in Callaway Final Safety Analysis Report (FSAR)
Sections 9.4.2 and 9.4.3. These sections describe the l interrelationship of the emergency exhaust system for these ;
two buildings. l f'
The emergency exhaust system collects and processes the fuel building atmosphere in the event of a fuel handling
, accident. During operation of the emergency exhaust system, .
' I the nonessential fuel building HVAC air paths are isolated i
and the building exhausted to assure that fission products l and particulate matter are collected and processed. The fuel building intake air system is provided with two motor-operated dampers in a series arrangement. Indication of high radiation levels in the fuel building will initiate automatic transfer to the emergency exhaust system. In this
! lineup, the emergency exhaust system will maintain the fuel l building at a negative pressure of 0.25 in. w.g. relative to the outside atmosphere.
The emergency exhaust system serves the auxiliary building l only following a loss of coolant accident (LOCA) to assure that all emergency core cooling system (ECCS) leakage to the auxiliary building atmosphere and the containment air purged
, via.the hydrogen purge system are processed. All ductwork
! which is not required for operation of the emergency exhaust
{ system and penetrates the auxiliary building boundary is automatically isolated. These nonessential systems are l
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i ULNRC-0 3 4 0 2
. Attachment 1 )
. Page 2 of 4 I
provided with two motor-operated dampers in a series j arrangement at the boundary penetrations. These will clos <3 l automatically following receipt of an SIS. In this lineup, I the emergency exhaust system will maintain a negative ]
pressure of 1/4 in. w.g. to assure that all leakage is into the auxiliary building. Charcoal samples are routinely l
tested to verify filter efficiency: every eighteen months; upon achieving total run time of 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />; and following a significant event or activity, such as painting, welding, or fire, which could potentially create fumes in an amount that could affect charcoal filter efficiency. Technical Specification Surveillance Requirements 4.7.7 and 4.9.13 specify that charcoal is to be tested per the guidance of Regulatory Guide 1.52, Rev. 2, March 1978, position C.6.a.3.
The Regulatory Guide, in turn, specifies the testing is to be performed in accordance with ANSI N509-1976. ANSI N509-1976 specifies that testing is to be performed in accordance with Military Specification RDT M-16-1T, with no year specified. An issue has been identified with regard to the te1 ting conditions specified by RDT M-16-1T and ANSI N509-l '. 7 6 . The RDT M-16-1T test consists of three stages, with the air flow in each stage at 25 C, whereas ANSI N509-1976 specifies that the air used in the second stage be at 80 C.
Technically, this test cannot be completed by injecting 80 C and 70% relative humidity air into a test specimen that has been stabilized at 25 C. Doing this causes condensation to form in the charcoal sample, which disqualifies the test.
Callaway charcoal samples are analyzed by an outside testing laboratory, which recognized the problem described above and changed their test method to the latest version of RDT M16-1T (the 1977 version), as allowed by ANSI N509-1976.
RDT M-16-1T-1977 specifies that 80 C air be used for all three stages of the test, which eliminates the condensation problem. In order to remove the confusion in the current Technical Specifications concerning the correct testing protocol required, the referenced testing protocol for these charcoal samples is being revised to ASTM D-3803-1989, which specifies the testing to be performed at 30*C and 70%
relative humidity with the exception that methyl iodide penetration shall not exceed 2%, instead of a 1% limit.
The 30*C at 70% relative humidity ASTM D-3803-1989 test to be performed on charcoal samples from FGG02A,B is representative of the postulated conditions for the auxiliary building or fuel building following a design basis
! accident. The current specification 3/4.7.7 and 3/4.9.13 penetration limit of 1% for testing at 80*C and 70% relative l humidity per test standard RDT M-16-1T is less conservative t than a 2% penetration limit for testing at 30'C and 70%
relative humidity, due to the more stringent tolerances
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ULNRC-03402 l
, Attachment 1 l l , Page 3 of 4 l
placed upon temperature and humidity in ASTM D-3803-1989, as ]
well as the test being performed at the lower temperature of ;
30'C. Thus, testing the charcoal using the new protocol I will provide greater assurance that the charcoal filters will perform at an efficiency of at least 90%.
This change in test protocol is consistent with that approved in callaway License Amendments 96 and 106.
Amendment 96 eliminated the containment spray additive system and replaced it with a passive Recirculation Fluid pH Control (RFPC) system. Amendment 96 as supplemented by Amendment 106 revised the control room dose charcoal filter assumption from 90% to 95% efficiency. The updating of the test protocol to ASTM D-3803-1989 at 30 C, 70% relative humidity and a methyl iodide penetration not to exceed 2%
supported this revised assumption. This amendment request does not involve a change in assumption of the efficiency for the emergency exhaust system units FGG02A,B. The current analysis for the fuel handling accident and the LOCA ,
assume a 90% efficiency. This change in test protocol and j the design residence time of 20.25 seconds would allow '
future changes to the charcoal filter efficiency of up to 95%. Any changes would be done under the criteria of 10CFR50.59. i Unreviewed Safety Ouestion Evaluation l
The changes to the technical specifications discussed above !
do not involve an unreviewed safety question because i operation of Callaway Plant with these changes would not: !
- 1. Increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.
The requested change to the charcoal sample j surveillance acceptance criteria for the fuel building and auxiliary building emergency exhaust system will not affect the method of operation of the system. The testing of the charcoal filter samples will continue to be performed in accordance with NRC-accepted methods and acceptance criteria, and the new test protocol will still ensure filter efficiency is maintained equal to or greater than 90%. There are no changes to the I emergency exhaust system and it will continue to l function in a manner consistent with the safety analysis assumptions and the plant design basis. There
, will be no degradation in the performance of or an increase in the number of challenges to equipment assumed to function during an accident. Therefore, the proposed changes will not increase the probability or
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ULNRC-03402 Attachment 1 Page 4 of 4 consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR.
- 2. Create a possibility for an accident or malfunction of a different type than previously evaluated in the safety analysis report.
The changes to the surveillance requirements are being made to adopt current NRC-accepted methods of testing charcoal samples. These changes will not affect the method of operation of the applienble systems and the laboratory testing will continue to demonstrate the required adsorber performance after a design-basis LOCA or fuel handling accident. Therefore, the changes will not create the possibility for an accident or malfunction of a different type than previously evaluated.
- 3. Reduce the margin of safety as defined in the bases for any Technical Specification.
The new charcoal adsorber sample laboratory testing protocol is more stringent than the current testing practice and meets current NRC-approved test methods.
The new testing criteria will continue to demonstrate the required adsorber performance after a design-basis LOCA or fuel handling accident and will not affect the filter system performance. Therefore, this change will not reduce the margin of safety of the emergency exha'at system filter operation.
Based on the above discussions and the no significant hazards consideration determination presented in Attachment 2, the proposed changes do not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously eduluated in the safety analysis report; or reduce the margin of safety as defined in the basis for any technical specification. Therefore, the proposed changes do not adversely affect or endanger the health or safety of the general public or involve an unreviewed safety question.
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l ATI'ACHMENT 2 SIGNIFICANT HAZARDS EVALUATION l i
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ULNRC-03402 Attachment 2
, Page 1 of 4 Sionificant Hazards Evaluation This license amendment request proposes to revise surveillance requirements 4.7.7.b.2, 4.7.7.c, and 4.9.13.b.2 and 4.9.13.c to reflect a proposed change to the acceptance criteria for the testing of carbon samples from the auxiliary / fuel building emergency exhaust system charcoal adsorbers. This proposed change would adopt ASTM D-3803-1989 as the laboratory testing standard for charcoal 1 samples from the charcoal adsorbers (FGG02 A,B) in the auxiliary / fuel building emergency exhaust system.
Laboratory testing of the carbon samples taken from the ;
charcoal adsorbers will be performed at 30 degrees Cent!, grade ( C) and 70% relative humidity for a methyl iodide penetration of 2%, instead of a 1% limit at 80 C and 70% relative humidity.
Evaluation The fuel building heating ver'c ilation and air conditioning (HVAC) system and the auxiliary building HVAC system are discussed in Final Safety Analysis Report (FSAR) Sections 9.4.2 and 9.4.3. These sectiens describe the interrelationship of the emergency exhaust system for these two buildings.
The emergency exhaust system collects and processes the fuel building atmosphere in the event of a fuel handling accident. During operation of the emergency exhaust system, the nonessential fuel building HVAC air paths are isolated and the building exhausted to assure that fission products '
and particulate matter are collected and processed. The fuel building intake air system is provided with two motor-operated dampers in a series arrangement. Indication of high radiation levels in the fuel building will initiate automatic transfer to the emergency exhaust system. In this lineup, the emergency exhaust system will maintain the fuel building at a negative pressure of 0.25 in. w.g. relative to the outside atmosphere.
The emergency exhaust system serves the auxiliary building I only following a loss of coolant accident (LOCA) to assure !
that all emergency core cooling system (ECCS) leakage to the l auxiliary building atmosphere and the containment air purged :
via the hydrogen purge system are processed. All ductwork l which is not required for operation of the emergency exhaust l system and penetrates the auxiliary building boundary is !
automatically isolated. these nonessential systems are j provided with two motor-operated dampers in a series j arrangement at the boundary penetrations. These will close automatically following receipt of an SIS. In this lineup
ULNRC-03402
, Attachment 2
. Page 2 of 4 the emergency exhaust system will maintain a negative pressure of 1/4 in, w.g. to assure that all leakage is into the auxiliary building.
Charcoal samples are routinely tested to verify filter efficiency: every eighteen months; upon achieving total run time of 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />; and following a significant event or activity, such as painting, welding, or fire, which could potentially create fumes in an amount that could affect charcoal filter efficiency. Technical Specification Surveillance Requirements 4.7.7 and 4.9.13 specify that charcoal is to be tested per the guidance of Regulatory Guide 1.52, Rev. 2, March 1978, position C.6.a.3. The Regulatory Guide, in turn, specifies the testing is to be performed in accordance with ANSI N509-1976. ANSI N509-1976 specifies that testing is to be performed in accordance with Military Specification RDT M-16-1T, with no year specified.
An issue has been identified with regard to the testing conditions specified by RDT M-16-1T and ANSI N509-1976. In order to remove the confusion in the current Technical Specifications concerning the correct testing protocol required, the referenced testing protocol for these charcoal camples is being revised to ASTM D-3803-1989, which specifies the testing to be performed at 30*C and 70%
relative humidity with the exception that methyl iodide penetration shall not exceed 2%, instead of a 1% limit.
The 30*C at 70% relative humidity ASTM D-3803-1989 test to i be performed on charcoal samples from FGG02A,B is representative of the postulated conditions for the i auxiliary building or fuel building following a design basis i accident. The current specification 3/4.7.7 and 3/4.9.13 penetration limit of 1% for testing at 80*C and 70% relative humidity per test standard RDT M-16-1T is less conservative than a 2% penetration limit for testing at 30*C and 70%
relative humidity, due to the more stringent tolerances placed upon temperature and humidity in ASTM D-3803-1989, as well as the test being performed at the lower temperature of 30*C. Thus, testing the charcoal using the new protocol will provide greater assurance that the charcoal filters will perform at an efficiency of at least 90%.
This change in test protocol is consistent with that approved in Callaway License Amendments 96 and 106.
Amendment 96 eliminated the containment spray additive system and replaced it with a passive Recirculation Fluid pH Control (RFPC) system. Amendment 96 as supplemented by Amendment 106 revised the control room dose charcoal filter assumption from 90% to 95% efficiency. The updating of the test protocol to ASTM D-3803-1989 at 30 C, 70% relative humidity and a methyl iodide penetration not to exceed 2%
supported this revised assumption. This amendment request does not involve a change in assumption of the efficiency
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ULNRC- 03 4 0 2
' Attachment 2 >
, Page 3 of 4 for the emergency exhaust system units FGG02A,B. The current analysis for the fuel handling accident and the LOCA assume a 90% efficiency.
Evaluation The proposed changes do not involve a significant hazards consideration because operation of Callaway Plant in ,
accordance with these changes would not. '
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
I The requested change to the charcoal sample surveillance acceptance criteria for the fuel building and auxiliary building emergency exhaust system will not affect the method of operation of the system. The testing of the charcoal filter samples will continue to be performed in accordance with NRC-accepted methods and acceptance criteria, and the new test protocol will still ensure filter efficiency is maintained equal to or greater than 90%. There are no changes to the emergency exhaust system and it will continue to function in a manner consistent with the safety analysis assumptions and the plant design basis. There will be no degradation in the perfernance of or an increase in the nuniber of challenges to equipment assumed to function during an accident. Therefore, the proposed changes will not increase the probability or consequences of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated.
The changes to the surveillance requirements are being made to adopt current NRC-accepted methods of testing charcoal samples. These changes will not affect the method of operation of the applicable systems and the laboratory testing will continue to demonstrate the required adsorber performance after a design-basis LOCA or fuel handling accident. No new or different kind of accident from any previously evaluated will be created.
- 3. Involve a significanc reduction in a margin of safety.
The new charcoal adsorber sample laboratory testing protocol is more stringent than the current testing practice and meets current NRC-approved test methods.
The new testing criteria will continue to demonstrate the required adsorber performance after a design-basis LOCA or fuel handling accident and will not affect the filter system performance. Therefore, this change will
UUTRC-0 34 0 2
, Attachment 2 l
Page 4 of 4 not reduce the margin of safety of the emergency exhaust system filter operation.
Conclusion Based upon the preceding information, it has been determined that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Therefore it is concluded that the proposed changes meet the requirements of 10CFR50.92 (c) and do not involve a significant hazards consideration.
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- ATTACHMENT 3
! ENVIRONMENTAL CONSIDERATION !
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ULNRC- 0 340 2 Attachment 3 Page 1 of 1 Environmental Consideration )
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'Dhis license amendment request proposes to revise surveillance j requirements 4.7.7.b.2, 4.7.7.c, and 4.9.13.b.2 and 4.9.13.c to !
reflect a proposed change to the acceptance criteria for the !
testing of carbon samples from the auxiliary / fuel building !
emergency exhaust system charcoal adsorbers. This proposed i change would adopt ASTM D-3803-1989 as the laboratory testing :
standard for charcoal samples from the charcoal adsorbers (FGG02 l A,B) in the auxiliary / fuel building emergency exhaust system.
l Laboratory testing of the carbon samples taken from the charcoal j adsorbers will be performed at 30 degrees Centigrade ( C) and 70% i relative humidity for a methyl iodide penetration of 2%, instead !
of a 1% limit at 80'C and 70% relative humidity.
{
r The proposed amendment involves changes with respect to the use ;
of facility components located within the restricted area, as l defined in 10 CFR 20. Union Electric has determined that the proposed amendment does not involve:
(1) A significant hazard consideration, as discussed in !
Attachment 2 of this. amendment application. l (2) A significant change in the types or significant increase in j the amounts of any effluents that may be related offsite; f
-(3) A significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility l criteria for categorical exclusion set forth in 10 CFR 51.22 (c)
( 9 ) '. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in .
connection with the issuance of this amendment.
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