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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210P5931999-08-11011 August 1999 Amend Application Number 189 for License NPF-10 & Amend Application Number 174 for License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098 ML20195E5061999-06-0808 June 1999 Application for Amends to Licenses NPF-10 & NPF-15, Consisting of Proposed Change Number 495,which Revises TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20205T2841999-04-24024 April 1999 Amend Application 187 to License NPF-10,consisting of Proposed Change Number 504,requesting NRC Approval to Repair Degraded But Operable Shutdown Cooling Sys Check Valves at Unit 2 in Normal Operation (Mode 1) ML20204B9731999-03-12012 March 1999 Application for Amends to Licenses DPR-13,NPF-1 & NPF-15, Revising SONGS Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan for Defending Site Against Safeguards Emergencies.Details of Amend Withheld ML20199D0331999-01-13013 January 1999 Suppl 1 to Amend Applications 157 & 141 to Licenses NPF-10 & NPF-15,respectively,restricting Required Action Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2761999-01-11011 January 1999 Amends Applications 185 & 171 to Licenses NPF-10 & NPF-15, Consisting of Proposed TS Change Number 499,requesting Rev to TS 3.7.6 & Associated Bases to Increase Required Water Volume in CST T-120 from 280,000 to 360,000 Gallons ML20198L6131998-12-31031 December 1998 Amend Applications 184 & 170 to Licenses NPF-10 & NPF-15, Consisting of Proposed Change 501,requesting Rev of TS 3.3.5, ESFAS Instrumentation ML20198G3741998-12-22022 December 1998 Proposed TS Change Number 489 to Amend Applications 176 & 162 to Licenses NPF-10 & NPF-15,changing TS 5.5.2.11, SG Tube Surveillance Program ML20196J1681998-12-0808 December 1998 PCN-493 to Amends 183 & 169 to Licenses NPF-10 & NPF-15, Revising Units 2 & 3 Tech Specs 3.4.10, Pressurizer Safety Valves, Consistent with Certain UFSAR Chapter 15 Events Recently Reanalyzed ML20195J9461998-11-23023 November 1998 Amends 178 & 164 to Licenses NPF-10 & NPF-15,consisting of Proposed Tech Specs Change Number (PCN-494),revising UFSAR Pages Necessary to Identify Programs Which Govern Test Intervals for Turbine ML20195J8961998-11-23023 November 1998 Amends 182 & 168 to Licenses NPF-10 & NPF-15,consisting of Proposed Tech Spec Change Number 498,revising TS 3.3.1, RPS Instrumentation - Operating ML20155B8631998-10-20020 October 1998 Application for Amends to Licenses NPF-10 & NPF-15, Respectively.Proposed Change Number 485 Adds SR to TS 3.3.9, CR Isolation Signal ML20153G7471998-09-22022 September 1998 Amends 181 & 167 to Licenses NPF-10 & NPF-15,respectively, Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6751998-09-10010 September 1998 Application for Amends 180 & 166 to Licenses NPF-10 & NPF-15,eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Condition 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6521998-09-0404 September 1998 Application for Amends to Licenses NPF-10 & NPF-15,revising TS 3.4.10 by Increasing as-found Psv Setpoint Tolerances ML20236S6221998-07-22022 July 1998 Suppl 2 to Applications for Amend to Licenses NPF-10 & NPF-15,revising TS 3.8.1 by Extending Offsite Circuit Completion Time from 72 Hr & 6 Days from Discovery of Failure to Meet LCO ML20249B4271998-06-19019 June 1998 Application for Amends to Licenses NPF-10 & NPF-15,reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels & Eliminating Max RCS Flow Rate Limit ML20249A6511998-06-12012 June 1998 Application for Amends 178 & 164 to Licenses DPR-10 & DPR-15,revising Turbine Missile Protection Calculation Methodology,Per UFSAR Section,3.5, Missile Protection. Rev 1 to GEC-Alsthom Analysis Rept Encl.Subj Rept Withheld ML20216B6051998-05-11011 May 1998 Suppl 1 to Application for Amends 161 & 145 to Licenses NPF-10 & NPF-15,respectively,requesting Changes to Surveillance Requirements (Srs) 3.6.1.1,3.6.2.1 & 3.6.3.6 & Creating New TS 5.5.2.14 ML20216B4031998-05-0707 May 1998 Applications for Amend to Licenses NPF-10 & NPF-15,revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8391998-04-0606 April 1998 Application for Amends to Licenses NPF-10 & NPF-15,revising Containment Isolation Valves Completion Times ML20216B9991998-03-0606 March 1998 Application for Amends 175 & 161 to Licenses NPF-10 & Proposed Change 490,eliminating Ref to Inverters in TS 3.4.12.1 ML20198H6651998-01-0909 January 1998 Suppl 1 to Application to Amends 152 & 136 to Licenses NPF-10 & NPF-15,revising TS 3.5.1, Safety Injection Tanks, to Extend,In General,Completion Time for Single Inoperable Safety Injection Tank from 1 H to 24 H ML20199K6371998-01-0909 January 1998 Corrected Suppl 1 to Application for Amends 152 & 136 to Licenses NPF-10 & NPF-15,respectively ML20198H7441998-01-0909 January 1998 Suppl 1 to Application for Amends 150 & 134 to Licenses NPF-10 & NPF-15,revising TS 3.8.1, AC Sources - Operating, to Extend Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days ML20198H8381998-01-0909 January 1998 Suppl 1 to Application for Amends 151 & 135 to Licenses NPF-10 & NPF-15,revising TS 3.5.2, ECCS-Operating, to Extend Allowed Outage Time from 72 H to 7 Days for Single Low Pressure Safety Injection Train ML20198E5941998-01-0505 January 1998 Proposed Change Number 482 to Application for Amends 174 & 160 to Licenses NPF-10 & NPF-15.Amends Revise TS 3.7.5, AFW Sys & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Shutdowns & Testing ML20197C7001997-12-19019 December 1997 Application for Amends to Licenses NPF-10 & NPF-15,reducing Pressurizer Water Level Required for Operability to Be Consistent W/Certain Updated FSAR Chapter 15 Events Which Were Recently Reanalyzed ML20199H9441997-11-25025 November 1997 Supplemental Application for Amend to Licenses NPF-10 & NPF-15,respectively,revising License Condition 2G to Replace Region V W/Region IV ML20199C6191997-11-14014 November 1997 Suppl 1 to Application for Amends 138 & 122 to Licenses NPF-10 & NPF-15,revising Ufsar,Section 3.5 to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20217J9491997-10-17017 October 1997 Application for Amends to Licenses NPF-10 & NPF-15, Requesting Permission of Radiation Monitoring Sys Upgrade ML20148R3751997-06-30030 June 1997 Applications 165 & 149 to Licenses NPF-10 & NPF-15, Consisting of Proposed TS Change NPF-10/15-475 (PCN-475),to Delete SONGS Unit 2 License Condition 2.C.(19)b & Revise SONGS Units 2 & 3 TS ML20141B4421997-06-18018 June 1997 Applications 168 & 154 for Amends to Licenses NPF-10 & NPF-15,respectively,requesting Revision to TS 3.8.1, AC Sources - Operating & Applicable Bases ML20137V2251997-04-15015 April 1997 Application for Amends to Licenses NPF-10 & NPF-15, Requesting Rev of SR 3.8.1.8 & Applicable Bases to TS 3.8.1, AC Sources - Operating. Proposed Change Allows Credit Overlap Testing ML20134P9841997-02-21021 February 1997 Application for Amend to License NPF-15,which Would Clarify in Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation ML20138L1011997-02-18018 February 1997 Application for Amend to License NPF-15,to Defer Implementation of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation, for 30 Subgroup Relays Until Next Refueling Outage on Songs,Unit 3 ML20134J6921997-02-0707 February 1997 Application for Amend to License NPF-15,consisting of PCN-479,revising TS SR 3.1.5.4, CEA Alignment ML20134A9861997-01-24024 January 1997 Application for Amends to Licenses NPF-10 & NPF-15,to Revise SR 3.8.1.9 to TS 3.8.1, AC Sources - Operating, Which Will More Accurately Reflect Safety Analysis Conditions ML20133G9061997-01-14014 January 1997 Application for Amends to License NPF-15,requesting Rev to TSs 3.8.1.14 & 3.8.1.15, AC Sources - Operating, Surveillance Requirements ML20128P3441996-10-11011 October 1996 Application for Amends to Licenses NPF-10 & NPF-15, Requesting Change to Reinstate Provisions of SONGS Unit 2 & 3 TS Revised as Part of NRC Amendment 127 & 116 ML20117K9851996-08-30030 August 1996 Application for Amends 153 & 137 to Licenses NPF-10 & NPF-15,respectively,clarifying Figures 3.7.18-1 & 3.7.18-2 by Adding Line at 4.8 Weight % Initial U-235 Enrichment to Show Acceptable Zone of Operation Ends Maximum 4.8 W/O ML20116C6741996-07-29029 July 1996 Application for Amends 146 & 130 to Licenses NPF-10 & NPF-15 Consisting of Change Request 443,permitting Increase in Licensed Storage Capacity of Spent Fuel Pools,By Allowing Fuel to Be Consolidated After Required Time in SFP ML20113C2541996-06-25025 June 1996 Application for Amends 159 & 143 to Licenses NPF-10 & NPF-15 Revising TS 3.3.11, Pami, & TS 5.5.2.13, Diesel Fuel Oil Testing Program ML20112D4511996-06-0303 June 1996 Applications 159 & 143 for Amend to Licenses NPF-10 & NPF-15,consisting of Change Number 466,reinstating Provisions of Current SONGS TS Revised as Part of NRC Amends 127 & 116 ML20117J8371996-05-30030 May 1996 Applications for Amends 161 & 145 to Licenses NPF-10 & NPF-15,consisting of Change Number 468,requesting Changes to SR 3.6.1.1,SR 3.6.2.1 & SR 3.6.3.6 Which Allows Implementation of Option B to 10CFR50,App J ML20117J4431996-05-29029 May 1996 Amends 162 & 146 to Licenses NPF-10 & NPF-15,respectively, Consisting of Proposed Change Number 465,changing Unit 2 Amend 127 & Unit 3 Amend 116 Approved TS 3.5.1, Safety Injection Tanks ML20112D0231996-05-29029 May 1996 Application for Amends to Licenses NPF-10 & NPF-15, Consisting of PCN-454,revising Acceptance Criteria for Agastat Time Delay Relays Used in ESF Load Sequencer in TS 3.8.1.18, A.C. Sources - Operating ML20117D7991996-05-0909 May 1996 Amend Applications 160 & 144 to Licenses NPF-10 & NPF-15, Consisting of Proposed TS Change Number 467,adding Section 5.5.2.14, Barrier Control Program ML20108E3251996-05-0808 May 1996 Application for Amends to Licenses NPF-10 & NPF-15, Consisting of Change Number 458,revising Unit 2 Amend 127 & Unit 3 Amend 116 Changing TS 3.9.4 & 3.9.5 ML20107B9781996-04-11011 April 1996 Application for Amends 158 & 142 to Licenses NPF-10 & NPF-15,respectively,revising TS 3.6.3, Containment Isolation Valves, to Resolve Inconsistency in TSs 1999-08-11
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210P5931999-08-11011 August 1999 Amend Application Number 189 for License NPF-10 & Amend Application Number 174 for License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098 ML20195E5061999-06-0808 June 1999 Application for Amends to Licenses NPF-10 & NPF-15, Consisting of Proposed Change Number 495,which Revises TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20205T2841999-04-24024 April 1999 Amend Application 187 to License NPF-10,consisting of Proposed Change Number 504,requesting NRC Approval to Repair Degraded But Operable Shutdown Cooling Sys Check Valves at Unit 2 in Normal Operation (Mode 1) ML20204B9731999-03-12012 March 1999 Application for Amends to Licenses DPR-13,NPF-1 & NPF-15, Revising SONGS Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan for Defending Site Against Safeguards Emergencies.Details of Amend Withheld ML20199D0331999-01-13013 January 1999 Suppl 1 to Amend Applications 157 & 141 to Licenses NPF-10 & NPF-15,respectively,restricting Required Action Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2761999-01-11011 January 1999 Amends Applications 185 & 171 to Licenses NPF-10 & NPF-15, Consisting of Proposed TS Change Number 499,requesting Rev to TS 3.7.6 & Associated Bases to Increase Required Water Volume in CST T-120 from 280,000 to 360,000 Gallons ML20198L6131998-12-31031 December 1998 Amend Applications 184 & 170 to Licenses NPF-10 & NPF-15, Consisting of Proposed Change 501,requesting Rev of TS 3.3.5, ESFAS Instrumentation ML20198G3741998-12-22022 December 1998 Proposed TS Change Number 489 to Amend Applications 176 & 162 to Licenses NPF-10 & NPF-15,changing TS 5.5.2.11, SG Tube Surveillance Program ML20196J1681998-12-0808 December 1998 PCN-493 to Amends 183 & 169 to Licenses NPF-10 & NPF-15, Revising Units 2 & 3 Tech Specs 3.4.10, Pressurizer Safety Valves, Consistent with Certain UFSAR Chapter 15 Events Recently Reanalyzed ML20195J8961998-11-23023 November 1998 Amends 182 & 168 to Licenses NPF-10 & NPF-15,consisting of Proposed Tech Spec Change Number 498,revising TS 3.3.1, RPS Instrumentation - Operating ML20195J9461998-11-23023 November 1998 Amends 178 & 164 to Licenses NPF-10 & NPF-15,consisting of Proposed Tech Specs Change Number (PCN-494),revising UFSAR Pages Necessary to Identify Programs Which Govern Test Intervals for Turbine ML20155B8631998-10-20020 October 1998 Application for Amends to Licenses NPF-10 & NPF-15, Respectively.Proposed Change Number 485 Adds SR to TS 3.3.9, CR Isolation Signal ML20153G7471998-09-22022 September 1998 Amends 181 & 167 to Licenses NPF-10 & NPF-15,respectively, Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6751998-09-10010 September 1998 Application for Amends 180 & 166 to Licenses NPF-10 & NPF-15,eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Condition 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6521998-09-0404 September 1998 Application for Amends to Licenses NPF-10 & NPF-15,revising TS 3.4.10 by Increasing as-found Psv Setpoint Tolerances ML20236S6221998-07-22022 July 1998 Suppl 2 to Applications for Amend to Licenses NPF-10 & NPF-15,revising TS 3.8.1 by Extending Offsite Circuit Completion Time from 72 Hr & 6 Days from Discovery of Failure to Meet LCO ML20249B4271998-06-19019 June 1998 Application for Amends to Licenses NPF-10 & NPF-15,reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels & Eliminating Max RCS Flow Rate Limit ML20249A6511998-06-12012 June 1998 Application for Amends 178 & 164 to Licenses DPR-10 & DPR-15,revising Turbine Missile Protection Calculation Methodology,Per UFSAR Section,3.5, Missile Protection. Rev 1 to GEC-Alsthom Analysis Rept Encl.Subj Rept Withheld ML20216B6051998-05-11011 May 1998 Suppl 1 to Application for Amends 161 & 145 to Licenses NPF-10 & NPF-15,respectively,requesting Changes to Surveillance Requirements (Srs) 3.6.1.1,3.6.2.1 & 3.6.3.6 & Creating New TS 5.5.2.14 ML20216B4031998-05-0707 May 1998 Applications for Amend to Licenses NPF-10 & NPF-15,revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8391998-04-0606 April 1998 Application for Amends to Licenses NPF-10 & NPF-15,revising Containment Isolation Valves Completion Times ML20216B9991998-03-0606 March 1998 Application for Amends 175 & 161 to Licenses NPF-10 & Proposed Change 490,eliminating Ref to Inverters in TS 3.4.12.1 ML20199K6371998-01-0909 January 1998 Corrected Suppl 1 to Application for Amends 152 & 136 to Licenses NPF-10 & NPF-15,respectively ML20198H8381998-01-0909 January 1998 Suppl 1 to Application for Amends 151 & 135 to Licenses NPF-10 & NPF-15,revising TS 3.5.2, ECCS-Operating, to Extend Allowed Outage Time from 72 H to 7 Days for Single Low Pressure Safety Injection Train ML20198H6651998-01-0909 January 1998 Suppl 1 to Application to Amends 152 & 136 to Licenses NPF-10 & NPF-15,revising TS 3.5.1, Safety Injection Tanks, to Extend,In General,Completion Time for Single Inoperable Safety Injection Tank from 1 H to 24 H ML20198H7441998-01-0909 January 1998 Suppl 1 to Application for Amends 150 & 134 to Licenses NPF-10 & NPF-15,revising TS 3.8.1, AC Sources - Operating, to Extend Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days ML20198E5941998-01-0505 January 1998 Proposed Change Number 482 to Application for Amends 174 & 160 to Licenses NPF-10 & NPF-15.Amends Revise TS 3.7.5, AFW Sys & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Shutdowns & Testing ML20197C7001997-12-19019 December 1997 Application for Amends to Licenses NPF-10 & NPF-15,reducing Pressurizer Water Level Required for Operability to Be Consistent W/Certain Updated FSAR Chapter 15 Events Which Were Recently Reanalyzed ML20199H9441997-11-25025 November 1997 Supplemental Application for Amend to Licenses NPF-10 & NPF-15,respectively,revising License Condition 2G to Replace Region V W/Region IV ML20199C6191997-11-14014 November 1997 Suppl 1 to Application for Amends 138 & 122 to Licenses NPF-10 & NPF-15,revising Ufsar,Section 3.5 to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20217J9491997-10-17017 October 1997 Application for Amends to Licenses NPF-10 & NPF-15, Requesting Permission of Radiation Monitoring Sys Upgrade ML20148R3751997-06-30030 June 1997 Applications 165 & 149 to Licenses NPF-10 & NPF-15, Consisting of Proposed TS Change NPF-10/15-475 (PCN-475),to Delete SONGS Unit 2 License Condition 2.C.(19)b & Revise SONGS Units 2 & 3 TS ML20141B4421997-06-18018 June 1997 Applications 168 & 154 for Amends to Licenses NPF-10 & NPF-15,respectively,requesting Revision to TS 3.8.1, AC Sources - Operating & Applicable Bases ML20137V2251997-04-15015 April 1997 Application for Amends to Licenses NPF-10 & NPF-15, Requesting Rev of SR 3.8.1.8 & Applicable Bases to TS 3.8.1, AC Sources - Operating. Proposed Change Allows Credit Overlap Testing ML20134P9841997-02-21021 February 1997 Application for Amend to License NPF-15,which Would Clarify in Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation ML20138L1011997-02-18018 February 1997 Application for Amend to License NPF-15,to Defer Implementation of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation, for 30 Subgroup Relays Until Next Refueling Outage on Songs,Unit 3 ML20134J6921997-02-0707 February 1997 Application for Amend to License NPF-15,consisting of PCN-479,revising TS SR 3.1.5.4, CEA Alignment ML20134A9861997-01-24024 January 1997 Application for Amends to Licenses NPF-10 & NPF-15,to Revise SR 3.8.1.9 to TS 3.8.1, AC Sources - Operating, Which Will More Accurately Reflect Safety Analysis Conditions ML20133G9061997-01-14014 January 1997 Application for Amends to License NPF-15,requesting Rev to TSs 3.8.1.14 & 3.8.1.15, AC Sources - Operating, Surveillance Requirements ML20132B9051996-12-13013 December 1996 Revised TS Pages D6.1-1,D6.2-1 & D6.5-4 for Amend 158 to License DPR-13 ML20128P3441996-10-11011 October 1996 Application for Amends to Licenses NPF-10 & NPF-15, Requesting Change to Reinstate Provisions of SONGS Unit 2 & 3 TS Revised as Part of NRC Amendment 127 & 116 ML20128L7141996-10-0303 October 1996 Amend 158 to License DPR-13,revising Section 2.D of Plant, Unit 1 Operating License to Remove Reporting Requirement Redundant to Reporting Requirements in 10CFR50.72 & 50.73 ML20117K9851996-08-30030 August 1996 Application for Amends 153 & 137 to Licenses NPF-10 & NPF-15,respectively,clarifying Figures 3.7.18-1 & 3.7.18-2 by Adding Line at 4.8 Weight % Initial U-235 Enrichment to Show Acceptable Zone of Operation Ends Maximum 4.8 W/O ML20116C6741996-07-29029 July 1996 Application for Amends 146 & 130 to Licenses NPF-10 & NPF-15 Consisting of Change Request 443,permitting Increase in Licensed Storage Capacity of Spent Fuel Pools,By Allowing Fuel to Be Consolidated After Required Time in SFP ML20113C2541996-06-25025 June 1996 Application for Amends 159 & 143 to Licenses NPF-10 & NPF-15 Revising TS 3.3.11, Pami, & TS 5.5.2.13, Diesel Fuel Oil Testing Program ML20112D4511996-06-0303 June 1996 Applications 159 & 143 for Amend to Licenses NPF-10 & NPF-15,consisting of Change Number 466,reinstating Provisions of Current SONGS TS Revised as Part of NRC Amends 127 & 116 ML20117J8371996-05-30030 May 1996 Applications for Amends 161 & 145 to Licenses NPF-10 & NPF-15,consisting of Change Number 468,requesting Changes to SR 3.6.1.1,SR 3.6.2.1 & SR 3.6.3.6 Which Allows Implementation of Option B to 10CFR50,App J ML20117J4431996-05-29029 May 1996 Amends 162 & 146 to Licenses NPF-10 & NPF-15,respectively, Consisting of Proposed Change Number 465,changing Unit 2 Amend 127 & Unit 3 Amend 116 Approved TS 3.5.1, Safety Injection Tanks ML20112D0231996-05-29029 May 1996 Application for Amends to Licenses NPF-10 & NPF-15, Consisting of PCN-454,revising Acceptance Criteria for Agastat Time Delay Relays Used in ESF Load Sequencer in TS 3.8.1.18, A.C. Sources - Operating ML20117D7991996-05-0909 May 1996 Amend Applications 160 & 144 to Licenses NPF-10 & NPF-15, Consisting of Proposed TS Change Number 467,adding Section 5.5.2.14, Barrier Control Program 1999-08-11
[Table view] |
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! UNITED STATES OF AMERICA NUCLEAR REGULATORY COMISSION Application of SOUTHERN CALIFORNIA )
EDIS0N COMPANY, H R. for a Class 103) Docket No. 50-361 License to Acquire, Possess, and Use )
a Utilization Facility as Part of ) Amendment Application Unit No. 2 of the San Onofre Nuclear ) No. 179.
Generating Station )
SOUTHERN CALIFORNIA EDIS0N COMPANY, H R . pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 179. This ainendment application consists of Proposed Change No. PCN-491 to Facility Operating License NPF-10. PCN-491 is a request to revise the Unit 2 Technical Specification (TS) 3.4.1, "RCS DNB (Pressure, Temperature, and Flow) Limits." The proposed change includes:
- 1) A reduction in the minimum primary Reactor Coolant System (RCS) cold leg temperature (T,,u) from 544 F to 535 F between the 70% and 100% rated thermal power levels.
- 2) A conversion of the specified RCS minimum flow rate from a " Mass" (i.e., lbm/hr) to a " Volumetric" (gpm) flow basis.
- 3) Elimination of the maximum RCS flow rate limit.
9906230086 980619 PDR ADOCK 05000361 P PDR _
Subscribed on this /9 day of - , 1998.
O Respectfully submitted, SOUTHERN CALIFORNIA EDISON COMPANY i
By "
DwightE.% unn ~
Vice President State of California County of San Diego On 6-/'l-9E before me, tete M/dut/ f. personally 1
appeared DRHN E JunrL , perskallyknowntome(orprovedtome on the basis of satisfactory evidence) to be the person (s) whose name(s) is/aresubscribedtothewithininstrumentandacknowledgedtomethat he/she/theyexecutedthesameinhis/her/theirauthorizedcapacity(ies),and that by his/her/their signature (s) on the instrument the person (s), or the entity upon behalf of which the person (s) acted, executed the instrument.
WITNESS my hand and official seal. -w^^^'
1 FRN " r2!ER >
Comcr.:. ""0906 l l Notary RP -2foste ;
i senc' mty
) 1 My Ce ' - 23,EDI I Signature M.AAMLu (M . '
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMISSION Application of SOUTHERN CALIFORNIA )
EDISON COMPANY, El R. for a Class 103) Docket No. 50-362 License to Acquire, Possess, and Use )
i a Utilization Facility as Part of ) Amendment Application Unit No. 3 of the San Onofre Nuclear ) No. 165.
Generating Station )
SOUTHERN CALIFORNIA EDIS0N COMPANY, El E. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 165. This amendment application consists of Proposed Change No. (PCN)-491 to Facility Operating License NPF-15. PCN-491 is a request to revise the Unit 3 Technical Specification (TS) 3.4.1, "RCS DBN (Pressure, Temperature, and Flow) Limits." The proposed change includes:
- 1) A reduction in the minimum primary Reactor Coolant System (RCS) cold leg temperature (T,,u) from 544 F to 535 F between the 70% and 100% rated thermal power levels.
- 2) A conversion of the specified RCS minimum flow rate from a " Mass" (i.e., Ibm /hr) to a " Volumetric" (gpm) flow basis.
- 3) Elimination of the maximum RCS flow rate limit.
l l
i l
Subscribed on this I9 day of e6 , 1998.
U Respectfully submitted, SOUTHERN CALIFORNIA EDIS0N COMPANY
\
By: .$ -- _
Dwight E. Nun Vice President State of California County of San Otego On /o - / 9- 79 before me, ACLMCAAM bMYpersonally appeared 8g4 41 E ft - ,perbnallyknowntome(orprovedtome on the basis of satisfactory evidence) to be the person (s) whose name(s) is/aresubscribedtothewithininstrumentandacknowledgedtomethat he/she/theyexecutedthesameinhis/her/theirauthorizedcapacity(ies),and thatbyhis/her/theirsignature(s)ontheinstrumenttheperson(s),orthe entity upon behalf of which the person (s) acted, executed the instrument.
WITNESS my hand and official seal.
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8 ama c ar MrConm Estes hear 28,3m >
Signature AAW bi drot '''''''' '
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DESCRIPTION OF TECHNICAL SPECIFICATION CHANGE PCN-491 SAN ONOFRE Units 2 and 3 Change No. PCN-491 will revise Technical Specification 3.4.1, "RCS DNB (Pressure, Temperature, and Flow) Limits."
Existing Technical Specifications:
Unit 2: See Attachment A Unit 3: See Attachment B Proposed Technical Specifications:
Unit 2: See Attachment C (redline and strikeout)
Unit 3: See Attachment D (redline and strikeout)
Proposed Technical Specifications:
Unit 2: See Attachment E Unit 3: See Attachment F Proposed Technical Specification Bases:
Unit 2: SeeAttachmentG(ForInformationOnly/ Unit 3issameasUnit2)
UFSAR Chapter 15 Assessment:
Units 2 and 3: See Attachment H Proposed UFSAR Pages:
. Units 2 and 3: See Attachment I (For Information Only)
Description of Change:
The proposed change to Technical Specification 3.4.1 consists of:
- 1) A reduction in the minimum primary Reactor Coolant System (RCS) cold leg temperature (Tg,) from 544*F to 535 F between the 70% and 100%
rated thermal power levels.
- 2) A conversion of the specified RCS minimum flow rate from a " Mass" (i.e., lbm/hr) to a " Volumetric" (gpm) flow basis.
- 3) Elimination of the maximum RCS flow rate limit.
Background:
Technical Specification (TS) 3.4.1 addresses Mode 1 requirements for maintaining RCS pressure, temperature, and flow rate within limits assumed in the plant safety analyses. The safety ar.alyses in the Updated Final Safety Analysis Report (UFSAR) (Chapters 6 and 15) of anticipated operational occurrences and design basis accidents assume initial conditions within the normal steady state operating envelope defined by the TSs as a whole. The limits placed on Departure from Nucleate Boiling (DNB) related parameters (i.e., parameters having a primary influence on DNB) ensure that these parameters will not be less conservative than those assumed in the safety analyses and will, thereby, provide assurance that the minimum Departure from Nucleate Boiling Ratio (DNBR) will meet the required criteria for each of the transients analyzed.
Southern California Edison (SCE) is proposing these changes for the following reasons: !
i Reduction in RCS Minimum Temperature The San Onofre Nuclear Generating Station (SONGS) steam generators have seen the onset of corrosion-induced tube cracking similar to that experienced by other Combustion Engineering designed steam generators (all with Alloy-600 tubing). !
SCE has retained outside expert consultants for several years who have helped to '
project future degradation based on industry experience and specific inspection findings at SONGS. The result of these ongoing analyses is a forecast of new cracking at rates which will increase geometrically with time and which eventually would have unacceptable safety (and economic) considerations. These forecasts also predict that over the next several years, greater than 90% of future degradation (requiring repair or plugging) will be caused by thermally l activated corrosion mechanisms. Temperature reduction reduces: '
- The occurrence of corrosion-induced tube cracking, and
- The rate of growth of these cracks.
Based on the foregoing and the best advice of industry experts, SCE has concluded that reducing operating temperatures below the minimum currently l permitted by LC0 3.4.1 is important to reduce the rate of forecast degradation to a manageable condition and to maximize the remaining safety and operating margins. SONGS is engineering a planned reduction of operating temperatures l which is expected to significantly reduce the rate of corrosive attack and which requires approval of PCN 491. This reduction is planned for implementation at the Cycle 10 refueling outage since it is the earliest opportunity to make major j modifications to the turbine plant to operate at lower steam pressure. Timely l approval of PCN 491 is necessary to successfully complete this project and '
! reduce degradation of margins associated with steam generator tube corrosion.
RCS Flow Rate Unit Conversion Reactor Coolant System (RCS) Total mass flow rate is a function of temperature, pressure, and volumetric flow. A change to the engineering units for RCS flow from lbm/hr to gpm is being requested to distinguish the independent variable of volumetric flow from the temperature and pressure parameters specified in the LC0. This change is consistent with the primary safety analysis variable.
Elimination of Maximum RCS Flos Rate Elimination of the maximum RCS Total Flow Rate is being proposed because 1) it is not a limiting DNBR criterion, 2) the safety margin to departure from nucleate boiling increases as the flow rate increases, and 3) actual reactor coolant pump (RCP) flow output is physically limited to values well below the approximately 120% of RCS design basis. Consequently, a shiftly surveillance has no meaningful DNBR significance.
For accident analyses that can be adversely be affected by elevated flow rates, a flow rate which is conservatively large compared to baseline measured flow is used.
Discussion:
The primary parameters which influence DNB.are RCS pressure, temperature, and flow rate. Attachment H provides summary results of engineering assessments that have been performed which support the proposed technical specification changes. These assessments consist primarily of the evaluated changes in the thermal hydraulic response to postulated transient and accident events given in Chapters 6 and 15 of the UFSAR in consideration of the expanded range of allowable operating temperatures at full power.
The T coi, LC0 limits are applicable to plant operation in Mode 1 (i.e., Power Operation, K ,, 20.99, and Rated Thermal Power >5% Rated Thermal Power (RTP)).
With respect to RCS Two, at Power Levels <70% RTP, the LC0 limits remain unchanged. The proposed TS change expands the allowable range for Two at power j levels >70% of RTP commensurate with the intended future operation at temperatures less than the current minimum allowable Two. Likewise, the conversion of. the minimum RCS Flow Rate to a volumetric flow basis necessitated j a review of the safety analyses for consistency with values used therein. l Therefore, under these conditions affected safety analyses have been assessed to assure continued compliance with regulatory requirements.
The requirements of LC0 3.4.1 represent the initial conditions for DNB limited transients analyzed in the safety analyses presented in Chapter 15 of the UFSAR.
The safety analyses have shown that Moderate Frequency Events initiated from the limits of this LC0 will meet the criterion of DNBR > 1.31. This is the
. acceptance limit for the RCS DNB parameters. Changes to the facility that could impact these parameters must be assessed for their impact on the DNB criterion.
The transients analyzed include Excess Load, Loss of Coolant Flow, Dropped Control Element Assembly (CEA), and CEA Withdrawal events. A key assumption for ,
the analysis of these events is that the core is operated within the limits of ;
LC0 3.1.7, " Regulating CEA Insertion Limits"; LC0 3.1.8, "Part length CEA Insertion Limits"; LC0 3.2.3, " AZIMUTHAL POWER TILT (T,)"; and LC0 3.2.5, " AXIAL l POWER SHAPE INDEX (ASI)". The current safety analyses are performed for each fuel cycle over the following range of initial values (including uncertainty):
RCS pressure 2000 - 2300 560"F (for s 70% RTP_and > 30%and RTPpsia, Tg,) (for 520 - 560*F 542s-30%
560 RTP) F (forand power reactor > 70% RTP),
vessel inlet coolant flow rate > 95% of design volumetric flow. For fuel
- cycles subsequent to this TS change, safety analyses will be performed using the
! same parameters except that for power levels > 70% of RTP a Two of 533 - 560 F will replace the 542 - 560*F previously used.
Similarly, an assessment of the Loss-of-Coolant Accident (LOCA) analyses presented, in part, in both UFSAR Chapters 6 and 15, have shown that transients initiated from the limits of the proposed TS change continue to meet the
.. acceptance criteria of 10 CFR 50.46.
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By performing new safety analyses or confirming the bounding nature of the existing analyses for the proposed TS changes, it is demonstrated that the acceptance criteria for'LOCAs are satisfied and that plant responses to transients meet the limiting DNBR criterion.
The LC0 limits for minimum and maximum RCS pressure remain consistent with operation within the nominal operating envelope and continue to be bounded by
-those used as initial pressures in the safety analyses. Likewise, the LC0 limits for minimum RCS total flow rate remain consistent with operation within the nominal operating envelope and continue to be bounded by those used as initial flow rates in the safety analyses. The specified flow rate has, however, been-converted from a " Mass" (i.e.,148x10 6 lbm/hr) to a " Volumetric" (396,000 gpm) flow basis. This change represents a straight flow " unit" conversion at original design operating conditions and does not represent any change to the actual magnitude of flow.
The LC0 for maximum RCS Total Flow Rate does not have a relevant basis in TS 3.4.1. This TS is applicable to Mode 1 operation and assurance of protection of the DNBR_ criterion. Rather, specification of a maximum RCS Total Flow Rate
- was originally intended to afford protection against core uplift which is actually a Mode 3 operation concern.. Further, core uplift has been evaluated at flow rates of approximately 120% of the RCS design basis minimum total flow rate. The actual physical limitations of pump design in concert with the overall RCS flow' resistance limits RCP output to flow rates well below 120% of the RCS design basis minimum total flow rate in MODE 1. For accident analyses that can be adversely affected by elevated flow rates, a flow rate which is conservatively large compared to baseline measured flow is used.
Attachment I is.being provided for information only. This attachment contains the proposed revision to The Loss of Condenser Vacuum, and The Loss of Condenser Vacuum with a Concurrent Single Failure of an Active Component descriptions contained in Sections 15.2.1.3 and 15.2.2.3 of the UFSAR. Changes to Section 15.10 of the UFSAR will also be revised prior to implementation of the T,,,,
reduction amendment.
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No Significant Hazards Considerations:
The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92. A proposed amendment to an operating license for facility involves no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not:
( (1) involve a significant increase in the probability or consequences of an l accident previously evaluated; or (2) create the possibility of a new or l different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. A discussion of these standards as they relate to this amendment request follows:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
i No.
The proposed change to Technical Specification (TS) 3.4.1 does not adversely impact structure, system, or component design or operation in a manner which would result in a change in the frequency of occurrence of accident initiation. Nor are the affected parameters themselves accident initiators. As such, the proposed TS change will not significantly increase the probability of accidents previously evaluated. Likewise, the proposed TS change does not significantly increase the consequences of an accident previously evaluated. The safety analysis assessments (Attachment H) confirm that the existing Analyses of Record (AORs) for San Onofre Units 2 and 3' remain valid or have been re-analyzed to demonstrate continued compliance with applicable Acceptance Criteria.
The change in Reactor Coolant System (RCS) " Mass" flow to " Volumetric" flow is a change in measuring units to be consistent with the measure used in '
the performance of the safety analysis. Therefore, there is no impact on any evaluated accidents.
The elimination of the upper RCS flow limit has no effect on Departure from Nucleate Boiling which is a concern at lower flows, and the maximum flow that is physically possible is less than the current upper limit.
Therefore,.this amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
No.
T coi, is an input parameter used in event analysis, it is not an event initiator. No new or different accidents have been identified which could !
result from operating at the proposed Tc io. The safety analysis assessments performed confirm that the existing safety system settings for San Onofre Units 2 and 3 remain valid, thereby assuring continued conformance to the Acceptance Criteria for all events.
A change in RCS flow measuring units can not initiate an accident, nor can the elimination of an upper RCS flow limit which can not be attained.
l Therefore, this amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Involve a significant reduction in a margin of safety.
No.
Updated Final Safety Analysis Report (UFSAR) safety analyses have been assessed and remain valid or have been re-analyzed to demonstrate continued compliance with applicable Acceptance Criteria for operation at the reduced-T,g o . All other safety limits and safety system settings remain unchanged.
l A change in measuring units for RCS flow does not reduce the margin of safety.
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Elimination of an RCS flow limit that can not physically be reached does not reduce the margin of safety. The shiftly surveillance requirement for maximum flow has no practical basis or safety benefit. Additionally, the margin to departure from nuclear boiling increases as the flow rate increases.
Therefore, this amendment does not involve a significant reduction in a margin of safety.
Based on the responses to these three criterion, SCE has concluded that the proposed amendment involves no significant hazards consideration.
Environmental Consideration:
SCE has determined that the proposed amendment involves no changes in the amount or type of effluent that may be released offsite, and results in no increase in individual or cumulative occupational radiation exposure. As described above, the proposed TS amendment involves no significant hazards consideration and, as such, racets the eligibility criteria for categorical exclusion set forth in 10 CFR51.22(c)(9).
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