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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20211G3041999-08-26026 August 1999 Suppl 981002 to LAR-98-006 to Licenses NPF-87 & NPF-89, Amending Tech Specs 4.0.6, SG Surveillance Requirements Which Provides Tube Insp Requirements & Acceptance Criteria to Determine Level of Degradation ML20210R6881999-08-13013 August 1999 Supplemental Application to License Amend Request LAR 98-010,for Licenses NPF-87 & NPF-89,correcting Existing Errors in Calculations of Original Lar.Revised Ts,Encl ML20209E1781999-07-0909 July 1999 Supplemental Application for LAR 99-002 for Licenses NPF-87 & NPF-89,proposing to Add Reactor Core Safety Limit Figures to Section 5.6.5 (COLR) of TSs TXX-9913, LAR 99-005 to Licenses NPF-87 & NPF-89,revising EDG Start to Emergency Start Instead of Normal Start Following Loss of Offsite Power1999-06-23023 June 1999 LAR 99-005 to Licenses NPF-87 & NPF-89,revising EDG Start to Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5311999-06-0404 June 1999 Supplemental Application for Amend to Licenses NPF-87 & NPF-89,proposing Addl Editorial Corrections.Corrections Are to Be Considered Administrative ML20195B6411999-05-27027 May 1999 LAR 99-004 to Licenses NPF-87 & NPF-89 by Incorporating Attached Change Re Plant Battery Surveillance Into TS ML20195B6571999-05-24024 May 1999 LAR 99-002 to Licenses NPF-87 & NPF-89,adding to COLR & Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206T5231999-05-14014 May 1999 Application for Amends to Licenses NPF-87 & NPF-89,changing Corporate Name of Licensee Texas Utilities Electric Co to Txu Electric Co. Marked-up OL Pages,Encl ML20206G7051999-05-0404 May 1999 LAR 99-001 for Amends to Licenses NPF-87 & NPF-89,revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections TXX-9826, Application for Amends to Licenses NPF-87 & NPF-89,proposing Increase in Licensed Power for Operation of Cpses,Unit 2 to 3445 Mwt (Approx 1%) & Changes Administratively for Unit 1.Supporting TSs & TR WCAP-10263,encl1998-12-21021 December 1998 Application for Amends to Licenses NPF-87 & NPF-89,proposing Increase in Licensed Power for Operation of Cpses,Unit 2 to 3445 Mwt (Approx 1%) & Changes Administratively for Unit 1.Supporting TSs & TR WCAP-10263,encl ML20195F1611998-11-13013 November 1998 LAR 98-08 to Licenses NPF-87 & NPF-89,changing Suppl to LAR 96-06,original Description & Assessment Provided in Ltr Dtd 960802,revised to Reflect Addition of Configuration Risk Mgt Program ML20195F5191998-11-11011 November 1998 LAR 98-007 to Licenses NPF-87 & NPF-89,revising Reactor Trip Setpoint for Cycle 5 ML20154C8971998-10-0202 October 1998 Application for Amends to Licenses NPF-87 & NPF-89,revising TS 4.0.6, SG Sr. Encls Contain Supporting Tss,Proprietary TR WCAP-15004,non-proprietary TR WCAP-15005 & W Proprietary Authorization Ltr.Proprietary Encl,Withheld TXX-9810, LAR 98-005 to Licenses NPF-87 & NPF-89,incorporating Encl Change Into Plant,Units 1 & 2 Ts.Change Is Applicable to Unit 2 & Administrative for Unit 1.Affidavit,encl1998-04-0909 April 1998 LAR 98-005 to Licenses NPF-87 & NPF-89,incorporating Encl Change Into Plant,Units 1 & 2 Ts.Change Is Applicable to Unit 2 & Administrative for Unit 1.Affidavit,encl ML20216B1321998-04-0606 April 1998 Application for Amend to License NPF-89,requesting Enforcement Discretion to Allow Plant to Continue to Operate W/O Having Performed Portions of Listed SRs ML20217A3841998-03-18018 March 1998 LAR 98-004 to Licenses NPF-87 & NPF-89,requesting Enforcement Discretion to Allow Units 1 & 2 to Perform Shutdown Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power ML20248L3161998-03-12012 March 1998 Application for Amends to Licenses NPF-87 & NPF-89,re Enforcement of Discretion & Compliance W/Ts 4.8.1.1.2f ML20216D5841998-03-0909 March 1998 Revised LAR 98-002 for Licenses NPF-87 & NPF-89,temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a), for Unit 2 Only TXX-9803, Application for Amends to Licenses NPF-87 & NPF-89, Increasing RWST low-low Level Setpoint1998-02-27027 February 1998 Application for Amends to Licenses NPF-87 & NPF-89, Increasing RWST low-low Level Setpoint ML20203J4921998-02-25025 February 1998 Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Attached Change Into TS to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements ML20212C3801997-10-24024 October 1997 Application for Amends to Licenses NPF-87 & NPF-89, Incorporating Encl Changes Re Reactor Trip Setpoint for Cycle 7 Into TS TXX-9711, Application for Amends to Licenses NPF-87 & NPF-89, Consisting of Change Request 97-002 Re Rev to Unit 2 Rt Setpoint1997-05-16016 May 1997 Application for Amends to Licenses NPF-87 & NPF-89, Consisting of Change Request 97-002 Re Rev to Unit 2 Rt Setpoint ML20141C9271997-05-15015 May 1997 Application for Amends to Licenses NPF-87 & NPF-89,adding License Conditions to Address SRs Not Previously Performed by Existing Requirements or Tests.Attachments 1-20 Encl ML20116F0421996-08-0202 August 1996 LAR 96-006 to Licenses NPF-87 & NPF-89,increasing Allowed Outage Time for Charging Pump from 72 H to 7 Days ML20116F3561996-07-31031 July 1996 Application for Amends to Licenses NPF-87 & NPF-89,revising Unit 1 Rx Trip Setpoints & Incorporating TU Electric SBLOCA TR on COLR Ts,Applicable to Both Units ML20116E8471996-07-31031 July 1996 Application for Amends to Licenses NPF-87 & NPF-89,modifying Inverter/Battery Chargers by Incorporating Attached Changes Into CPSES Units 1 & 2 TSs ML20115E7991996-07-10010 July 1996 Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.7.11 to Revise Lco,Actions & SRs to Take Credit for Addition of Train Oriented Fan Coil Units for Each UPS & Distribution Room ML20115C9271996-07-0909 July 1996 LAR 96-003 to Licenses NPF-87 & NPF-89,increasing Allowable Value for Steam Line pressure-low for Cpses,Unit 1 ML20113B5831996-06-21021 June 1996 Application for Amends to Licenses NPF-87 & NPF-89,removing Request to Relocate MSIV Full Closure Time Requirement to Program Administratively Controlled by TS & Revising Associated Bases to Include Addl Info TXX-9600, Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B1996-03-12012 March 1996 Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B ML20100J0611996-02-22022 February 1996 Application for Amends to Licenses NPF-87 & NPF-89,revising TS LCO 3.9.4 to Allow Both Door of Pal to Remain Open If One Is Capable of Being Closed ML20096B3181996-01-0505 January 1996 Application for Amends to Licenses NPF-87 & NPF-89, Consisting of LAR 96-001 Revising TS Re Wide Range RCS Temp.-Th Remote Shutdown Indication.Changes Submitted on CPSES Unit 1 for Administrative Purposes Only TXX-9528, LAR 95-008 to License NPF-87 & NPF-89,incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints,Resulting from Reload Analyses for CPSES Unit 2,Cycle 31995-11-21021 November 1995 LAR 95-008 to License NPF-87 & NPF-89,incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints,Resulting from Reload Analyses for CPSES Unit 2,Cycle 3 ML20094N6161995-11-21021 November 1995 Application for Amends to Licenses NPF-87 & NPF-89,allowing Containment Personnel Airlock Doors to Remain Open During Movement of Irradiated Fuel & During Core Alterations for Plant ML20087K1721995-08-15015 August 1995 Requests Amend to Licenses NPF-87 & NPF-89,consisting of Change Request 95-05,moving Shutdown Margin Limits from TS to COLR & Providing Guidelines for Removal of cycle-specific Parameter Limits from TS ML20087J7921995-08-15015 August 1995 LAR 95-04 to Licenses NPF-87 & NPF-89,moving Overtemp N-16 Limits from TS to Colr,Per GL 88-16.Changes in LAR 95-04 Originally Submitted in LAR 95-03 on 950512.LAR 95-03 Being Divided Into Four Separate LARs for Ease in Processing ML20087E2521995-08-11011 August 1995 Suppl to Application for Amends to Licenses NPF-37,NPF-66, NPF-72 & NPF-77,revising TS 3.6.1.7, Containment Purge Ventilation Sys ML20083M8531995-05-12012 May 1995 Application for Amend to Licenses NPF-87 & NPF-89,consisting of LAR 95-03,removing cycle-specific Parameter Limits from Ts,Per GL 88-16 TXX-9509, Application for Amends to Licenses NPF-87 & NPF-89.Amends Would Reduce Min Fuel Oil Vol Requirement During Modes 5 & 6 for Operable EDGs1995-05-0101 May 1995 Application for Amends to Licenses NPF-87 & NPF-89.Amends Would Reduce Min Fuel Oil Vol Requirement During Modes 5 & 6 for Operable EDGs ML20082C6401995-04-0303 April 1995 Suppl to Application for Amends to Licenses NPF-87 & NPF-89 Re Quadrant Power Tilt Ratio TXX-9505, LAR 95-001 to Licenses NPF-87 & NPF-89,changing TS to Address Performance Requirements of Containment Spray Pumps1995-02-28028 February 1995 LAR 95-001 to Licenses NPF-87 & NPF-89,changing TS to Address Performance Requirements of Containment Spray Pumps ML20079B4721994-12-30030 December 1994 LAR 94-022 to Licenses NPF-87 & NPF-89,incorporating Changes to TS to Increase Spent Fuel Storage Capacity.Rev 0 of CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity Encl ML20078R8071994-12-19019 December 1994 Application for Amends to Licenses NPF-87 & NPF-89 to Allow Testing of RPS & ESFAS W/Channel Under Test in Bypass ML20078S0891994-12-19019 December 1994 Application for Amends to Licenses NPF-87 & NPF-89, Requesting Approval of Converted TSs to Format & Content of Improved STSs ML20077F0881994-12-0707 December 1994 License Amend Request 94-020 to Licenses NPF-87 & NPF-89, Revising TS LCO for MSIVs to Increase Allowed Outage Time in Mode 1 & Relocate MSIVs to Full Closure Time Requirement to Program Administratively Controlled ML20077F1951994-12-0606 December 1994 Application for Amends to Licenses NPF-87 & NPF-89, Consisting of LAR 94-021,revising TS to Allow Appropriate Remedial Action for High Particulate Levels in DG Fuel Oil & Other out-of-limit Properties in New DG Fuel Oil ML20077A7071994-11-18018 November 1994 LAR 94-019 to Licenses NPF-87 & NPF-89,removing Accelarated Testing & Special Reporting Requirements for EDGs from TS, Based on GL 94-01 ML20078K7461994-11-18018 November 1994 LAR 94-018 to Licenses NPF-87 & NPF-89,revising TS Re Heat Flux Hot Channel Factor ML20078G7281994-11-11011 November 1994 Application for Amends to Licenses NPF-87 & NPF-89,revising TSs Re Exclusion of Failures from Total Number of Failures Used to Determine Diesel Generator Test Frequency ML20073B6491994-09-19019 September 1994 Application for Amends to Licenses NPF-87 & NPF-89, Incorporating Encl Change Into Licensee Units 1 & 2 TSs 1999-08-26
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211J4031999-08-27027 August 1999 Errata to Amends 66 & 66 to Licenses NPF-87 & NPF-89, Respectively.Footnote on TS Page 3.8-26 Was Incorrectly Deleted ML20211G3041999-08-26026 August 1999 Suppl 981002 to LAR-98-006 to Licenses NPF-87 & NPF-89, Amending Tech Specs 4.0.6, SG Surveillance Requirements Which Provides Tube Insp Requirements & Acceptance Criteria to Determine Level of Degradation ML20210R6881999-08-13013 August 1999 Supplemental Application to License Amend Request LAR 98-010,for Licenses NPF-87 & NPF-89,correcting Existing Errors in Calculations of Original Lar.Revised Ts,Encl ML20209E1781999-07-0909 July 1999 Supplemental Application for LAR 99-002 for Licenses NPF-87 & NPF-89,proposing to Add Reactor Core Safety Limit Figures to Section 5.6.5 (COLR) of TSs TXX-9913, LAR 99-005 to Licenses NPF-87 & NPF-89,revising EDG Start to Emergency Start Instead of Normal Start Following Loss of Offsite Power1999-06-23023 June 1999 LAR 99-005 to Licenses NPF-87 & NPF-89,revising EDG Start to Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5311999-06-0404 June 1999 Supplemental Application for Amend to Licenses NPF-87 & NPF-89,proposing Addl Editorial Corrections.Corrections Are to Be Considered Administrative ML20195B6411999-05-27027 May 1999 LAR 99-004 to Licenses NPF-87 & NPF-89 by Incorporating Attached Change Re Plant Battery Surveillance Into TS ML20195B6571999-05-24024 May 1999 LAR 99-002 to Licenses NPF-87 & NPF-89,adding to COLR & Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206T5231999-05-14014 May 1999 Application for Amends to Licenses NPF-87 & NPF-89,changing Corporate Name of Licensee Texas Utilities Electric Co to Txu Electric Co. Marked-up OL Pages,Encl ML20206G7051999-05-0404 May 1999 LAR 99-001 for Amends to Licenses NPF-87 & NPF-89,revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections TXX-9826, Application for Amends to Licenses NPF-87 & NPF-89,proposing Increase in Licensed Power for Operation of Cpses,Unit 2 to 3445 Mwt (Approx 1%) & Changes Administratively for Unit 1.Supporting TSs & TR WCAP-10263,encl1998-12-21021 December 1998 Application for Amends to Licenses NPF-87 & NPF-89,proposing Increase in Licensed Power for Operation of Cpses,Unit 2 to 3445 Mwt (Approx 1%) & Changes Administratively for Unit 1.Supporting TSs & TR WCAP-10263,encl ML20195F1611998-11-13013 November 1998 LAR 98-08 to Licenses NPF-87 & NPF-89,changing Suppl to LAR 96-06,original Description & Assessment Provided in Ltr Dtd 960802,revised to Reflect Addition of Configuration Risk Mgt Program ML20195F5191998-11-11011 November 1998 LAR 98-007 to Licenses NPF-87 & NPF-89,revising Reactor Trip Setpoint for Cycle 5 ML20154C8971998-10-0202 October 1998 Application for Amends to Licenses NPF-87 & NPF-89,revising TS 4.0.6, SG Sr. Encls Contain Supporting Tss,Proprietary TR WCAP-15004,non-proprietary TR WCAP-15005 & W Proprietary Authorization Ltr.Proprietary Encl,Withheld TXX-9810, LAR 98-005 to Licenses NPF-87 & NPF-89,incorporating Encl Change Into Plant,Units 1 & 2 Ts.Change Is Applicable to Unit 2 & Administrative for Unit 1.Affidavit,encl1998-04-0909 April 1998 LAR 98-005 to Licenses NPF-87 & NPF-89,incorporating Encl Change Into Plant,Units 1 & 2 Ts.Change Is Applicable to Unit 2 & Administrative for Unit 1.Affidavit,encl ML20216B1321998-04-0606 April 1998 Application for Amend to License NPF-89,requesting Enforcement Discretion to Allow Plant to Continue to Operate W/O Having Performed Portions of Listed SRs ML20217A3841998-03-18018 March 1998 LAR 98-004 to Licenses NPF-87 & NPF-89,requesting Enforcement Discretion to Allow Units 1 & 2 to Perform Shutdown Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power ML20248L3161998-03-12012 March 1998 Application for Amends to Licenses NPF-87 & NPF-89,re Enforcement of Discretion & Compliance W/Ts 4.8.1.1.2f ML20216D5841998-03-0909 March 1998 Revised LAR 98-002 for Licenses NPF-87 & NPF-89,temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a), for Unit 2 Only TXX-9803, Application for Amends to Licenses NPF-87 & NPF-89, Increasing RWST low-low Level Setpoint1998-02-27027 February 1998 Application for Amends to Licenses NPF-87 & NPF-89, Increasing RWST low-low Level Setpoint ML20203J4921998-02-25025 February 1998 Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Attached Change Into TS to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements ML20212C3801997-10-24024 October 1997 Application for Amends to Licenses NPF-87 & NPF-89, Incorporating Encl Changes Re Reactor Trip Setpoint for Cycle 7 Into TS TXX-9711, Application for Amends to Licenses NPF-87 & NPF-89, Consisting of Change Request 97-002 Re Rev to Unit 2 Rt Setpoint1997-05-16016 May 1997 Application for Amends to Licenses NPF-87 & NPF-89, Consisting of Change Request 97-002 Re Rev to Unit 2 Rt Setpoint ML20141C9271997-05-15015 May 1997 Application for Amends to Licenses NPF-87 & NPF-89,adding License Conditions to Address SRs Not Previously Performed by Existing Requirements or Tests.Attachments 1-20 Encl ML20116F0421996-08-0202 August 1996 LAR 96-006 to Licenses NPF-87 & NPF-89,increasing Allowed Outage Time for Charging Pump from 72 H to 7 Days ML20116F3561996-07-31031 July 1996 Application for Amends to Licenses NPF-87 & NPF-89,revising Unit 1 Rx Trip Setpoints & Incorporating TU Electric SBLOCA TR on COLR Ts,Applicable to Both Units ML20116E8471996-07-31031 July 1996 Application for Amends to Licenses NPF-87 & NPF-89,modifying Inverter/Battery Chargers by Incorporating Attached Changes Into CPSES Units 1 & 2 TSs ML20115E7991996-07-10010 July 1996 Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.7.11 to Revise Lco,Actions & SRs to Take Credit for Addition of Train Oriented Fan Coil Units for Each UPS & Distribution Room ML20115C9271996-07-0909 July 1996 LAR 96-003 to Licenses NPF-87 & NPF-89,increasing Allowable Value for Steam Line pressure-low for Cpses,Unit 1 ML20113B5831996-06-21021 June 1996 Application for Amends to Licenses NPF-87 & NPF-89,removing Request to Relocate MSIV Full Closure Time Requirement to Program Administratively Controlled by TS & Revising Associated Bases to Include Addl Info TXX-9600, Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B1996-03-12012 March 1996 Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B ML20100J0611996-02-22022 February 1996 Application for Amends to Licenses NPF-87 & NPF-89,revising TS LCO 3.9.4 to Allow Both Door of Pal to Remain Open If One Is Capable of Being Closed ML20096B3181996-01-0505 January 1996 Application for Amends to Licenses NPF-87 & NPF-89, Consisting of LAR 96-001 Revising TS Re Wide Range RCS Temp.-Th Remote Shutdown Indication.Changes Submitted on CPSES Unit 1 for Administrative Purposes Only ML20094N6161995-11-21021 November 1995 Application for Amends to Licenses NPF-87 & NPF-89,allowing Containment Personnel Airlock Doors to Remain Open During Movement of Irradiated Fuel & During Core Alterations for Plant TXX-9528, LAR 95-008 to License NPF-87 & NPF-89,incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints,Resulting from Reload Analyses for CPSES Unit 2,Cycle 31995-11-21021 November 1995 LAR 95-008 to License NPF-87 & NPF-89,incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints,Resulting from Reload Analyses for CPSES Unit 2,Cycle 3 ML20087J7921995-08-15015 August 1995 LAR 95-04 to Licenses NPF-87 & NPF-89,moving Overtemp N-16 Limits from TS to Colr,Per GL 88-16.Changes in LAR 95-04 Originally Submitted in LAR 95-03 on 950512.LAR 95-03 Being Divided Into Four Separate LARs for Ease in Processing ML20087K1721995-08-15015 August 1995 Requests Amend to Licenses NPF-87 & NPF-89,consisting of Change Request 95-05,moving Shutdown Margin Limits from TS to COLR & Providing Guidelines for Removal of cycle-specific Parameter Limits from TS ML20087E2521995-08-11011 August 1995 Suppl to Application for Amends to Licenses NPF-37,NPF-66, NPF-72 & NPF-77,revising TS 3.6.1.7, Containment Purge Ventilation Sys ML20083M8531995-05-12012 May 1995 Application for Amend to Licenses NPF-87 & NPF-89,consisting of LAR 95-03,removing cycle-specific Parameter Limits from Ts,Per GL 88-16 TXX-9509, Application for Amends to Licenses NPF-87 & NPF-89.Amends Would Reduce Min Fuel Oil Vol Requirement During Modes 5 & 6 for Operable EDGs1995-05-0101 May 1995 Application for Amends to Licenses NPF-87 & NPF-89.Amends Would Reduce Min Fuel Oil Vol Requirement During Modes 5 & 6 for Operable EDGs ML20082C6401995-04-0303 April 1995 Suppl to Application for Amends to Licenses NPF-87 & NPF-89 Re Quadrant Power Tilt Ratio TXX-9505, LAR 95-001 to Licenses NPF-87 & NPF-89,changing TS to Address Performance Requirements of Containment Spray Pumps1995-02-28028 February 1995 LAR 95-001 to Licenses NPF-87 & NPF-89,changing TS to Address Performance Requirements of Containment Spray Pumps ML20079B4721994-12-30030 December 1994 LAR 94-022 to Licenses NPF-87 & NPF-89,incorporating Changes to TS to Increase Spent Fuel Storage Capacity.Rev 0 of CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity Encl ML20078R8071994-12-19019 December 1994 Application for Amends to Licenses NPF-87 & NPF-89 to Allow Testing of RPS & ESFAS W/Channel Under Test in Bypass ML20078S0891994-12-19019 December 1994 Application for Amends to Licenses NPF-87 & NPF-89, Requesting Approval of Converted TSs to Format & Content of Improved STSs ML20077F0881994-12-0707 December 1994 License Amend Request 94-020 to Licenses NPF-87 & NPF-89, Revising TS LCO for MSIVs to Increase Allowed Outage Time in Mode 1 & Relocate MSIVs to Full Closure Time Requirement to Program Administratively Controlled ML20077F1951994-12-0606 December 1994 Application for Amends to Licenses NPF-87 & NPF-89, Consisting of LAR 94-021,revising TS to Allow Appropriate Remedial Action for High Particulate Levels in DG Fuel Oil & Other out-of-limit Properties in New DG Fuel Oil ML20078K7461994-11-18018 November 1994 LAR 94-018 to Licenses NPF-87 & NPF-89,revising TS Re Heat Flux Hot Channel Factor ML20077A7071994-11-18018 November 1994 LAR 94-019 to Licenses NPF-87 & NPF-89,removing Accelarated Testing & Special Reporting Requirements for EDGs from TS, Based on GL 94-01 ML20078G7281994-11-11011 November 1994 Application for Amends to Licenses NPF-87 & NPF-89,revising TSs Re Exclusion of Failures from Total Number of Failures Used to Determine Diesel Generator Test Frequency 1999-08-27
[Table view] |
Text
.. - _ _ _ _ _ - ___ _ _ . - _ _ _ . - _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ .
Log # 1xX-92323 lF""
~ -
. File # 916 (6)
Ref. # 10CFR50.90 1UELECTRIC September 3, 1992 wmlam J. Cohm Jr, amp he fresidner .
V. S Nuclear Regul6 tory Commission t Atta: Document Control Desk ,
Washington, DC 20555
$UBJECT: C0HANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 1 DOCKET NO. 50-445 LICENSE AHENDHENT REQUEST 92 003 REPLACEMENT OF THE.WFLASH C0HPUTER CODE WITH THE NOTRUMP COMPUTER CODE FOR THE SHALL BREAK LOSS OF COOLANT ACCIDENT (LOCA) EMERGENCY CORE COOLING SYSTEM (ECCS) EVALUATION H0 DEL Gentlemen:
Pursuant to 10CFR50.90, TV Electric hereby renuests an amendment to the CPSES Unit 1 Operating License (NPF 87) by incorporating the enclosed change into the CPSES Unit 1 Technical Specifications.
The proposed change involves replacement of the analysis of record for the CPSES Unit 1 Small Break LOCA. The change replaces the 1976 Small Break
-LOCA evaluation model using the WFLASH computer code with the 1985 Small Break LOCA evalurtion model using the NOTRUMP computer code.
This change is being requested because the Small Break LOCA Peak Cladding Temperature (PCT) i s greater than 2200 F when the PCT penalties (due to plant modifications and analysis changes) are added to the base PCT calculated by the 1975 evaluation model. To obtain a PCT of less than 2200*F, the event '
needed to be reanalyzed with the plant modifications and analysis changes incorporated, or a new analysis needed to be performed using a more current model. Since Westinghouse was already using the more advanced 1985 Small Break LOCA evaluation model with the NOTRUMP computer code to perform new analyses and update existing analyses for other plants, as well as CPSES Unit 2, TV Electric. decided that the analysis of record should be changed to the.1985 Westinghouse evaluation model.
Upon receiving written notification from Westinghouse on July 14, 1992, TV Electric orally reported th* PCT exceeding 2200*F in accordance with 10CFR50.46 and 10CFR50.72. 's ectric issued a written report describing the condition and corrective a,tions in accordance with 10CFR50.46 and 10CFR50.73 on August 13, 1992.
E . Attachment 2 provides a detailed description of the proposed change, the basis ~for the change, a safety analysis of the change, and TV Electric's determination that the proposed change does not involve a significant hazards consideration.
9209090249 920903 Af '
PDR ADOCK 05000445 Pt PDR moun sw La.st o.n u a n u m ot
- l(kf l
_e - - - . , .n
. nn-, r-, , , - - - . ~
l TXX 92323 Page 2 o'. 2 Attachment 3 provides the affected Technical Specification pages
( NUREG 1399), marked-up to reflect the proposed thange.
In accordance with 10CFR50.91(b). TV Electric is providing the State of Texas l with a copy of this proposed amendment.
TV Electric requests approval of the proposed amendment by August 31, 1993, with implementation to occur within thirty days af ter NRC approval.
Should you have any questions in this matter, please contact David Bize at (214) 812 8879.
Sincerely, William J. Cahill, Jr.
DNB/dnb Attachments: 1. Affidavit
- 2. Description and Assessment
- 3. Marked-up Technical Specification Page (NUREG-1399)
Enclosures:
- 1. Westinghouse letter, WPT-14670, 'TU Electric Company, Comanche Peak Steam Electric Station Unit Number 1, Small Break LOCA Using W-FLASH Peak Clad Temperature (PCT),'
July 13, 1992
- 2. Westinghouse letter, WPT-14387, 'TU Electric Company, Comanche Peak Steam Electric Station, Unit Number 2. Small Break LOCA ECCS Reanalysis (PCT)," February 26, 1992
- 3. Westinghouse Letter, WPT 14479 'TU Electric Company, Comanche Peak Steam Electric Station. Unit Number 1, NOTRUMP Small Break LOCA Analysis - Engineering Assessment in Support of Continued Operation,' July 13, 1992 c - Mr. J. L. Milhoan, Region IV Resident inspecter, CPSES (2)
Mr. T. A. Bergman, NRR Hr. D. K. Lacker Bureau of Radiation Control Texas Department of Public Health 1100 West 49th Street Austin, Texas 78704
i i
Attachment I to TXX 92323 Page 1 of I l
UNITED STATES OF AMER]CA tiUCLEAR REGULATORY COMMISSION in the Matter of )
)
Texas Utilities Electric Company ) Docket No. 50 445 l
) I (Comanche Peak Steam Electric ) l Station, Unit 1) ) i i
AFFIDAVIT W. J. Cahill, Jr. being duly sworn, hereby deposes and says that he is Executive Vice President, Nuclear of TV Electric, the lead Applicant herein; that he is duly authorized to sign and file with the Nuclear Regulatory Commission License Amendment Request 92+003 ' Replacement of the WFLASH Computer Code with the NOTRUMP Computer Code for the Small Break Loss of Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) Evaluation Model,'
for the captioned facility; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.
W. J. Cahill . _V Executive Vi President. Nuclear STATE OF TEXA5 )
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COUNTY OF DAMAS)
Subscribed and swore to before me, on this day of G 6[ ._u 1992.
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n 1 A SHARION HAMDRICK
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- Notary Puolic, S.ste of Toass Notary Public
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DESCRIPTION AND ASSESSMENT t
i,TTACHMENT 2 TO TXX 92323 f PAGE-1 0F 10 i
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< e Attachment 2 to TXX 92323 Page 2 of 10 REPLACEMENT OF THE WFLASH COMPUTER CODE WITH THE NOTRUMP COMPUTER CODE FOR THE SMALL BREAK LOSS OF COOLANT ACCIDENT (LOCA)
EMERGENCY CORE COOLING SYSTEM (CCCS) EVALUATION MODEL
- 1. BACKGROUND The CPSES Unit 1 Small Break LOCA analysis described in the CPSES Final Safety Analysis Report (FSAR) Chapter 15.6.5 (Ref. [1]) was licensed using Westinghouse's 1975 Small Break LOCA evaluation model incorporating the WFLASH computer code. Currently. Westinghouse is using the 1985 Small Break LOCA evaluation model with the NOTRUMP computer code to perf orm new analyses and update existing analyses. The 1985 Small Break LOCA evaluation model with the NOTRUMP computer code was developed following Three Mile Island (THI) *n response to NUREG 0737 TMI Action Item !!.K.3.30 (Ref. [2]). This
- model, which incorporates a number of advanced features over-its -
predecessor, was developed to provide a more realistic Small Break LOCA simulation as required by the NRC. TV Electric participated as a member of-Westinghouse Owners Group inLthe development of the modified Small Break
' LOCA code NOTRUMP. NOTRUMP demonstrated compliance with Appendix K to 10CFR50 and the NRC issued a Safety Evaluation Report (SER) on May 21.-1985.
As: required by NUREG 0737 TMl Action item !!.K.3.31 (Ref. -[2]). plant-specific calculations with the models described in-TM1 Action Item II.K.3.30 must be' submitted to the NRC demonstrating compliance with 10CFR50.46. The NRC staff further indicated that this may be accomplished by generic
- analyses to demonstrate that the previously--NRC approved WFLASH Small Break LOCA results were-conservative when compared with the new NOTRUMP Small Dreak LOCA results.
The generic _results, documented in WCAP-11145 (Ref. [3]), demonstrated'that a plant . specific reenalysis of CPSES with the NOTRUMP Small Break LOCA should result in the calculation of a limiting Peak Cladding Temperature (PCT) which would be significantly-lower than that calculated by WFLASH r
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Attachment 2 to TXX 92323 Page 3 of 10 j i
Small Break LOCA. It was therefore concluded that a plant specific ;
I reanalysis using the 1985 Small Break LOCA evaluation model with the NOTRVHP '
computer was not needed to comply with TH! Action Item II.K.3.31 because the l WFLASH Small Break LOCA analyses results conservatively had shown compliance ;
with 10CFR50,46. #
On July 13, 1992 -Westinghouse transmitted the results of a 10CFR50.59 safety' evaluation to TV Electric (Ref. [4) Enclosure 1). The safety evaluation was for an error in the portion of the CPSES Small Break LOCA 7
analysis which addresses fuel cladding burst and the resultant coolant channel blockage. -Correction of the error increased the Small Break LOCA I PCT over the 10CFR50.46 criteria of c200*F. TV Electric received the
. Westinghouse letter on July 14, 1992, and notified the NRC Operations Center via the-Emergency Notification System in accordance with 10CFR50.72.
TU~ Electric provided a written report, Licensee Event Report LER 92 018 00 *
(transmitted via TU Electric letter TXX 92371), which satisfied the reporting requirements of 10CFR50.46(a)(3) and 10CFR50.73, to the NRC on August 13. 1992.-
i TU Electric decided that the analysis of record should be changed to the more advanced 1985 Wentinghouse evaluation model with the NOTRUMP computer ,
- code because Westinghouse was already using the 1985 evaluation model to periWrm new analyses or update existing analyses for other plants, the 1985 evaluation model code had previously received NRC approval for use at other plants, and the 1985 evaluation model had been- used in the .Small Break' LOCA analysis for CPSES Unit 2 (submitted.to the NRC for review in Ref. [5),
Enclosure 2).-
In-anticipation of changingfthe analysis of record and to' demonstrate continued compliance with 10CFR50.46. TV Electric had Westinghouse perform an analysis of CPSES Unit 1 for the limiting break size using the 1985 Small Break.LOCA evaluation model with the NOTRUMP_ computer code. A single break
-size was analyzed rather_than a break spectrum because a comparison between b
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-Attachment 2 to TXX 92323 Page 4 of 10 CPSES Unit 1 and CPSES Unit 2 demonstrated that the results of the break spectrum study for CPSES Unit 2 could be applied to CPSES Unit 1, The results of the analysis confirmed that CPSES Unit 1 continued to comply with -!
10CFR50.46.
- 11. DESCRIPTION Of TECHNICAL SPECIFICATION CHANGE RE0 VEST TV Electric is proposing to replace the 1975 Westinghouse Small Break LOCA
. evaluation model of record for CPSES Unit I with the 1985 Westinghouse Small Break LOCA evaluation model for the reasons discussed above. The proposed change revises the Small Break LOCA analytical method referenced in the ;
Administrative Controls Section of.the Technical Specifications (Ref. (63).
Specifically, in section 6.9.1.6 of the Technical Specifications the changes o deletes '
WCAP 8200, "WFLASH, A FORTRAN IV COMPUTER PROGRAM FOR SIMULATION Of i
TRANSIENTS IN A MULTI LOOP PWR,* Revision 2. June 1974 (H Proprietary). :(Methodology for Specification 3.2.2 - Heat -Flux Hot Channel Factor.), and ,
o adds WCAP 10079-P A, *HOTRUMP.- A N0DAL TRANS!ENT-SHALL BREAK AND GENERAL NETWORK CODE," August' 1985, (H Proprietary!. . ( Hethodology'for -
Specification 3.'2.2 Heat flux Hot Channel f actor. )
WCAP-10054 P A, ' WESTINGHOUSE SHALL ECCS F JALVATION MODEL USING THE
.N0 TRUMP CODE,' August 1985, (W Proprietark). (Hethodology for Specification 3.2.2 - Heat Flux Hot Channel factce.) _ !
WCAP 11145-P A,_' WESTINGHOUSE SHALL BREAK LOCA-ECCS EVALVATION MODEL GENERIC STUDY WITH THE NOTRUMP CODE, October 1986, (H Proprietary).
(Methodology. f or -Specification 3.2.2 Heat Flux Hot Channel Factor. )
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Attachment 2 to TXX 92323 -l Page 5 of 10 The affected Technical Specification page. 6-25 has been marked to reflect these changes and has been provided as Attachment 3.
!!!. ANALYSIS l
The CPSES Unit 2 Small Break.LOCA analysis (Ref. [5]) has been perfomed
-with the NRC approved 1985 Small Break LOCA evaluation model and submitted to the NRC for review. The CPSES Unit 2 analysis included a break spectrum consisting of 2 . 3+ and 4 inch breaks. In Small Break LOCA, the thermal- {
hydraulic response is governed mainly by system parameters; the effect on the thermal-hydraulic response due to minor core dif ferences is less significant. The system parameters of the two units are very similar.
Table 1 is-a comparison'of the pertinent plant' system and design parameters of CPSES Unit 1 and Unit 2. As shown, the plant specific data for the two q plants are-almost identical. This similarity can also be applied to the break spectrum studies because the system response to the different break sizes would be similar. 'Due-to the similarity of the two units, the I
-limiting break size for Unit 2 would also be the limiting break size for Unit 1.
~ Based on the NOTRUMP Small Break LOCA analyses performed for CPSES Unit 2, 6-
, single Small Break LOCA analysis (Ref. [7], Enclosure 3) wLs performed for -
-. - r CPSES-Unit 1 using the NOTRUMP evaluation model. That is, the most limiting break identified in the CPSES Unit 2 analyses, the 3-inch cold leg break, '
was analyzed for CPSES Unit 1 with the changes necessary to model the CPSES Unit 1 core (17x17 standard fuel anj the D4 steam generator instead-of 17x17 optimized fuel and the model 05 steam generator). The PCT results for both e units are-shown in Table 2. Comparison of the CPSE! Jnit 1 and Unit 2
- results for the~ 3-inch break show the dif ference in PCT is small as expected. - The results are well below the 2200'F limit set forth-in 100FR50.46.
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Attachment 2 to TXX 92323 Page 6 of 10 lable 1 CPSES Unit 1 and Unit 2 Comparison Unit 1 Unit 2 ;
ilSSS Thermal Power (HWt) 3411+14 (RCPs) 3411+14 (RCPs)
Total Peaking Factor, F,. 2.32 2.32 Limiting Power Shape = Same (F5AR_ Fig. 15.6 48, Ref..(1])
Accumulator. Water Volume (f t') 850 850 Accumulator Gas Pressure (psia) 600 600 Safety injection Pumped Flow Same (FSAR Fig. 15.6 47, Ref. [1])
_ Initial Con _ditions-(loop flow. Same vessel inlet & outlet temps, reactor coolant pressure, steam generator pressure and tube p1'ugging levels)
Steam Generator Tube OD (in) _0.75 0.75 ;
Tube Thickness (in) 0.043 0.043 tio, of U tubes 4578 4570 lieat Transfer Area (f t') _ 48,'300 .48,165 Core Desion Fuel Array 17x17 17x17 Clad OD-(in) 0.374 0.360 Gap Gas' Pressure-(psig) 450 275 Clad Thickness (in) 0.0225 0.0225 l: ~ ~
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Table 2 N01 RUMP Analysis Peak Cladding Temperature ('F) Comparisons Break Eltg Unit 1 Uni.t 2 :
2' 1005
Although the NOTRUHP analysis was run for only one break size, a spectrum of breaks (2 inch and 4 inch) is not required for CPSES Unit 1. as previously discussed, because of the similarities of the two units. The break spectrum results for CPSES Unit 2 exhibit large differences in the calculated PCTs ,
between the 2 inch and 4 inch breaks when compared to the limiting 3 inch break. Due to plant similarities and the similar analysis results, the i trend of the break spectrum results for CPSES Unit 2 can be ,
applied to.the. analysis for CPSES Unit 1. The CPSES Unit 1 current licensed I analysis' of record Lsing the-less refined WFLASH computer code shows that
-the 4-inch cold leg break is limiting. The 3 inch cold-leg break reported in Ref. [7] using the more advanced NOTRUHP code has been shown to be limiting.for CPSES Unit 2 and traditionally _ analyses performed using the Westinghouse N01 RUMP code have shown smaller breaks to be more limiting when ,
compared to' analyses performed using the WFLASH code for the same-plant. ;
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The'CPSES' Unit 1 specific analysis using NOTRUMP results in a significantly lower PCT compared to the current PCT using the WFLASH code in the 1975 Small Break LOCA evaluation model. The revised analysis results meet the regulatory requirements set forth in 10CFR50,46.
'The plant conditions. prior to and after this amendment will remain :
unaffected.
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Attachment 2 to TXX-92323 Page 8lof 10 IV. BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION TV Electric has evaluated the no significant hazards consideration involved with the' proposed change in accordance with the three standards set forth in 10CFR50,92(c) as discussed:
Does the proposed change; (1) Involve a significant-_ increase in the probability or consequences of an accident previously evaluated?
The proposed change pertains to replacing the CPSES Unit 1 1975 Small Break LOCA evaluation model using WFLASH with Westinghouse's current 1985-Small Break LOCA evaluation model using the NOTRUMP code. There are no potential failure modes identified or hardware and process parameters affected by the proposed change. Selection of an updated evaluation model does not increase the probability or consequences of an event.
Thus, implementation-of this change does not increase the probability-or the consequences of-an accident previously analyzed.
(2) _ Create the possibility of a new or different kind of accident from any accident previously evaluated?
The evaluation model that is being changed determines the effectsoof a licensing basis accident._ Because this change ~only affects analysis methods, there are no new-failure modes or new types of accidents introduced as a result of this proposed change. There sre no previously deemed -incredible events being made credible.
Therefore, this change does not create'the possibility of an accident
-different from any_ accident evaluated in the licensing basis documents.
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Attachment 2 to TXX-92323 Page 9 of 10 (3) Involve a significant reduction in the margin of safety?
The proposed change will not have any ef f ect on equipment perf ormance and availability. The analysis results must meet the regulatory requirements set forth in 10CFR50.46(b). The principle Small Breat LOCA result is the calculated PCT. Since the PCT remains under the 2200 F acceptance criteria, there is no increase in LOCA consequences. _
Therefore, the proposed change does not involve a significant reduction in the margin of safety.
Based on the above evaluations, TV Electric concludes that the above described change satisfy the no significant hazards consideration standards of 10CFR50.92(c) and, accordingly, a no significant hazards finding is justified.
V. ENVIRONMENTAL EVALUATION o p
As stated in Section IV(3), results satisfying he requirements of ;
10CFR50.46 will pose no increase in LOCA consequences or a reduction in the I
margin of safety. Therefore, the environmental evaluation is excluded, j VI. REFERENCES
[1] CPSES Final Safety Analysis Report, Section 15.6.5, ' LOSS OF COOLANT ACCIDENTS RESULTING FROM A SPECTRUM OF POSTULATED P!P!NG BREAKS WITHIN THE REACTOR C00LAftT PRESSURE BOUNDARY.*
[2] CPSES Final Safety Analysis Report , Response to NUSEG 0737 THI Action items ll.K.3.30 and ll.K.3.31, pp. II.L-15 through ll.K-18.
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- Attachment 2 to TXX-92323 l
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[3] WCAP-11145 P A, '
WESTINGHOUSE SHALL BREAK LOCA ECCS EVALVATION H0 DEL GENERIC STUDY WITH THE NOTRUMP CODE." October 1986.
[4] Westinghouse letter, WPT 14670. 'CPSES UNIT-1 SHALL BREAK LOCA ECCS REANALYSIS USING NOTRUMP
- July 13. 1992. (Enclosure 1)
[5] Westinghouse Letter, WPT*14387,
- CPSES UNIT-2 SMALL DREAK LOCA ECCS REANALYSIS," February 26, 1992. (Enclosure 2)
[6] CPSCS Unit 1. Technical Specifications, Administrative Controls, Section 6.9.1.6. ,
[7] Westinghouse Letter, WPT 14479, 'CPSES UNIT +1 NOTRUMP SMALL BREAK l LOCA ANALYSIS ' ENGINEERING ASSESSMENT IN SUPPORT OF CONTINUED OPERATION," April 15. 1992. (Enclosure 3) 1 1
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