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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
.- - - . .
M Log # TXX 96007
== File # 916 (3/4.3) 0 4 10010 E 5 Ref. # 10CFR50.90 10CFR50.36 1UELECTRIC January 5, 1996 Gmup Mce President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SUBMITTAL OF LICENSE AMENDMENT REQUEST 96 001 WIDE RANGE RCS TEMP.-Tn REMOTE SHUTDOWN INDICATION REF: 1. TV Electric letter logged TXX 96009 from C. L. Terry to the NRC dated January 4, 1996
- 2. TV Electric letter logged TXX 96010 from C. L. Terry To the NRC dated January 5, 1996 Gentlemen:
Pursuant to 10CFR50.90. TV Electric hereby requests an amendment to the l
CPSES Unit 1 Operating License (NPF-87) and CPSES Unit 2 Operating License 1 (NPF 89) by incorporating the attached change into the CPSES Units 1 and 2 Technical Specifications. These changes are only applicable to CPSES Unit l 2 and are being submitted on the CPSES Unit 1 docket for administrative '
purposes only because the CPSES Units 1 and 2 Technical Specifications is a single document which applies to both units.
This license amendment requast (LAR) proposes a temporary change to the l Technical Specifications to revise the requirements for Minimum Channels l OPERABLE for Wide Range RCS (Reactor Coolant System) Temp.(Temperature)-T, remote shutdown indication for CPSES Unit 2. The minimum number of channels required is being revised from 1 per RCS Loop for each RCS Loop to 1 per RCS Loop for 3 of the 4 RCS Loops. This temporary change is requested as a result of the failure of one of the Tn channels in a manner which cannot be repaired without a unit shutdown and a possible cooldown.
Attachment 1 is the required affidavit. Attachment 2 provides a detailed description of the proposed changes, a safety analysis of the changes, and TV Electric's determination that the proposed changes do not involve a significant hazard consideration. Attachment 3 provides the affected Technical Specification page, marked up to reflect the proposed changes.
This LAR is being submitted as follow-up to a request for enforcement discretion (References 1 and 2). Approval of the Technical Specification change is requested in accordance with the time allowance of the enforcement discretion. The license amendment should be effective upon issuance to be implemented immediately.
9601160197 960105 >
PDR ADOCK 05000445 P PDR 110109 ""8'"- " "*"5"" " " " * = " * "
') '
'. l TXX 96007 Page 2 of 2 In accordance with 10CFR50.91(b), TV Electric is providing the State of.
Texas with a copy of this proposed amendment.
Should you have any questions, please contact Mr. Jose Rodriquez at (214) 812 8674.
Sincerely,
- 9. 4, V C. L.-Terry By: -
Roger 06. Walker Regulatory Affairs Manager JDR/dw Attachments:
- 1. Affidavit
- 2. Description and Assessment
- 3. Affected Technical Specification page as revised by all approved license amendments ,
cc - Mr. L. J. Callan, Region IV Mr. T. J. Polich, NRR Hs. W. D. Johnson, Region IV Resident Inspectors, CPSES Mr. Arthur C. Tate '
Bureau of Radiation Control Texas Department of Public Health 1100 West 49th Street ,
Austin, Texas 78704
, j Attachment 1 to TXX 96007 Page 1 of 1 UNITED STATES OF AMERICA l
NUCLEAR REGULATORY COMMISSION In the Matter of )
)
Texas Utilities Electric Company ) Docket Nos, 50 445
) 50 446 l (Comanche Peak Steam Electric ) License Nos. NPF 87 I Station, Units 1 & 2) ) NPF 89 AFFIDAVIT Roger D. Walker being duly sworn, hereby deposes and says that he is l Regulatory Affairs Manager for TU Electric, the licensee herein: that he is duly authorized to sign and file with the Nuclear Regulatory Commission this License Amendment Request 96 001: 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.
C*jf7 b' ~
Roger '6. Walker Regulatory Affairs Manager 1 STATE OF TEXAS ) .
)
COUNTY OF DALLAS )
Subscribed and sworn to before me, on this 5th day of Janupyy, 1996 . I h .
Nota PubTic
_._-t ,
1 >
Gayle R. Peck >
,
- l Notary Put&,, State d Texas ,
y My Cemm. Empires 01/06/98 ,
f_,,,__..-'
, 1 Attachment 2 to TXX 96007 Page 1 of 4 l 1
i DESCRIPTION AND ASSESSMENT l
I. BACKGROUND j On December 31, 1995, at 2:10 a.m. CST, the Wide Range RCS (Reactor Coolant System) Temp. (Temperature) Tn remote shutdown indication for one RCS Loop was discovered to be inoperable. Troubleshooting efforts indicated a ground.
The location of the ground has been isolated to an area inside containment that is normally only accessible during periods of a reactor shutdown.
Radiation levels, temperature and personnel safety considerations preclude further corrective actions without performing a plant shutdown and a possible cooldown. CPSES Unit 2 is scheduled to commence a refuelir.g outage on February 22, 1996. CPSES Unit 2 has no other outages planned during the 7 weeks prior to the scheduled start of the refueling outage. TV Electric is i requesting a revision to the Technical Specifications requirement that all I four remote shutdown monitoring channels for Wide Range RCS Temp. Tn be l operable. The requested revision is temporary and is meant to expire upon Unit l 2 entry into MODE 4 at the beginning of the second refueling outage for Unit 2.
II. DESCRIPTION OF TECHNICAL SPECIFICATIONS CHANGE REQUEST l
In Technical Specification Table 3.3 5 " REMOTE SHUTDOWN MONITORING INSTRUMENTATION" add the following:
add an asterisk "*" to the MINIMUM CHANNELS OPERABLE column for item 3
" Wide range RCS Temp.-Tn" to reference e footnote at the bottom of the page. 4 Add a footnote at the bottom of the page after the definitions of the acronyms to state
- - The requirements for Minimum Channels OPERABLE for Wide Range RCS Temp.-Tn remote shutdown indication for Unit 2 are revised to 1/ Loop for three (3) of the four (4) RCS Loops. This revision is to remain in effect until CPSES Unit 2 enters MODE 4 at the beginning of the second refueling outage for Unit 2.
In summary, this license amendment revises the requirements to allow operation with one of the four available instruments out of service until CPSES Unit 2 enters MODE 4 at the beginning of the second refueling outage for Unit 2.
III. ANALYSIS Limiting Condition for Operation (LCO) 3.3.3.2.1, " Remote Shutdown Instrumentation," requires, in part, that one Wide Range RCS Temp. Tn per RCS Loop be OPERABLE in MODES 1, 2, and 3. ACTION Statement "a" requires that an
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inoperable instrument be restored to OPERABLE status within 7 days or be in at least MODE 4 H0T SHUTD0WN, within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The subject instrument is part of the CPSES design for shutdown from outside l the control room (see CPSES Final Safety Analysis Report (FSAR) section l 7.4.1.3). The Wide Range RCS Temperature indication is used in a remote shutdown situation for verification of natural circulation, verification of adequate RCS sub-cooling, and for verifying that RCS temperature is adequate for initializing Residual Heat Removal (RHR) cooling. In the unlikely event that shutdown from outside the control room, the inoperability of Wide Range Temp. Tn for a single RCS Loop is expected to have no measurable impact on the ability of the operators to safely cooldown the RCS and establish RHR cooling.
The Tn indication is used for monitoring natural circulation cooldown. Steam Generator Pressure is the primary means of temperature control based on the saturated steam conditions in the Steam Generator. Under low steam flow conditions, the Steam Generator temperature is close to the RCS cold leg temperature. Knowledge of the saturation temperature corresponding to the observed steam pressure provides the best indicator of RCS conditions. Tc and especially Tn indication lags behind the steam pressure indication, particularly under natural circulation conditions due to the loop transit time. For this reason the Tnindication is a secondary indication of RCS conditions to the Steam Generator pressure. For the situation of a cooldown when there is forced RCS flow. there is a small differential temperature across the Steam Generator and Reactor Core and T is nearly the same as the c
T, and provides the same information as the inoperable Tn. For the situation of natural circulation, there is a larger differential temperature but the relationship of steam pressure as previously explained exists. Trending of the steam pressure and T in the loops will provide indication that the e
natural circulation is occurring in the active loops and therefore, the Tn of the loop without indication is approximately the same as that indicated in any other active loops with Tn indication. Abnormal operating procedures for shutdown from outside the Control Room address the use of Steam Pressure as the primary indicator of RCS temperature for comparison to the RCS Pressure
[also available on the Hot Shutdown Panel (HSP)] to confirm adequate subcooling margin exists during the cooldown. The procedure specifically calls for the use of steam generator pressure in the determination c' subcooling margin, cooldown rate and RCS temperature. The operator:, are trained on these procedures and also to use all available instrumentation.
With the operator training, and the availability of the other remote shutdown indications, one Tn indication is adequate for the operator to perform a controlled shutdown of the Reactor.
The worst case scenario for shutdown from outside the control room is for those instances involving a fire in either the control room or the cable spreading room. The failed Tn indication is one of two which have been analyzed per the Fire Safe Shutdown Analysis to be available for operation at the HSP following a fire. Only two have been analyzed. as only those Steam Generators fed by the Train A Auxiliary Feedwater Pumo are used for plant cooldown following a fire in these locations. If this event were to occur during the duration of this temporary Technical Specification change, the operator would retain indication of RCS hot leg temperature from the remaining Tn indication and use the correlations to other parameters
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previously described . For shutdowns other than post fire shutdown, the ,
remaining Tn indicators (3) allow for plant cooldown. l The Standard Review Plan 7.4 " Safe Shutdown Systems" and Branch Technical l Position CHEB 9.51 " Guidelines for .' ire Protection for Nuclear Power Plants." l states that systems designed to ensure post fire shutdown capability, need not be designed to meet single failure criteria. For shutdowns other than post fire shutdown, the remaining Tn indicators (3) allow for plant cooldown.
Therefore loss of a single loop Tn indicator has minimal safety significance with no potential for negative consequences should uso of the HSP be required.
l IV. SIGNIFICANT HAZARDS CONSIDERATIONS ANALYSIS l
TV Electric has evaluated whether or not a significant hazards consideration is involved with the proposed changes by focusing on the three standards set forth in 10CFR50.92(c) as discussed below:
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- 1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
The unavailability of one RCS Loop Tn indication at the HSP cannot be an initiating event for nor affect the progression or mitigation of any licensing basis accident: therefore the probability of occurrence of an) licensing accident cannot be affected.
The request proposes to change the minimum channels operable for Wide Range Hot Leg RCS Temperature Tnindication at the HSP. Sufficient alternate instrumentation is available on the HSP to provide the information normally directly obtained from Tn. The current Technical Specifications acknowledge the need to and allow for operation with one Tn inoperable for the Allowed Outage Time (A0T) in the action statement.
The current Technical Specifications have an A0T of seven days.
Further, the improved Standard Technical Specifications allows an A0T of 30 days. The duration of this request is not significantly different than these time periods. Thus the consequences of a remote shutdown with the affected instrument inoperable have already been considered and this change will not increase the consequences of an accident previously evaluated.
- 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Operation for a period of time with the one RCS Loop T 3 unavailable will not create the possibility of a new or different kind of accident from any accident previously evaluated. No hardware modifications are being made and no plant procedures are being revised that would alter normal plant operations.
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- 3. Do the proposed changes involve a significant reduction in a margin of safety?
The Wide Range Hot Leg RCS Temperature indication at the HSP is only required in the event that a remote shutdown from outside the control room is needed. The availability of other remote shutdown indications (including T , Tn in other RCS Loops, and Steam Generator pressure) in combination with licensed operators who have been briefed on how to compensate for an inoperable Tn for one RCS Loop using these other indications, assures that the increased unavailability of the instrument will not have a significant effect in the margin of safety.
Based on the above evaluations. TV Electric concludes that the activities i associated with the proposed changes satisfy the no significant hazards consideration standards of 10CFR50.92(c) and accordingly, a no significant hazards consideration finding is justified.
V. ENVIRONMENTAL EVALUATION TU Electric'has determined that the proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in 10CFR20, or would change an .
inspection or surveillance requirement. TU Electric has evaluated the j proposed changes and has determined that the changes do not involve (1) a significant hazards consideration, (ii) a significant change in the types or i significant increase in the amounts'of any effluent that may be released i offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9).
Therefore, pursuant to 10CFR51.22(b), an environmental assessment of the proposed change is not required.
VI. REFERENCES l 1, NUREG 1431, Revision 1, Standard Technical Specifications Westinghouse Plants April 1995.
- 2. TU Electric letter logged TXX 96009 from C. L. Terry to the NRC, dated January 4, 1996.
- 3. TV Electric letter logged TXX 96010 from C. L. Terry to the NRC, dated January 5, 1996.
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