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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] |
Text
_ ____________ ---
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN, CALIFORNIA )
EDISON COMPANY, ET AL. 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. 182 Generating Station )
SOUTHERN CALIFORNI A EDISON COMPANY, EI A.L. pursuant to 10CFR50.90, hereby submit Amendment Application No. 182. This amendment application consists of Proposed Change No. PCN-498 to Facility Operating License NPF-10. PCN-498 is a request to revise footnotes (a) and (d) to Table 3.3.1-1 in Technical Specification 3.3.1.
Subscribed on this day of kU6hv , 1998.
Respectfully Submitted, SOUTHERN CALIFORNIA EDIS0N COMPANY By 2M --
Dwight E. h t nn Vice Presic nt State of Californla County of San Diego On before me, b b.
personally appeared . I personally known to me rer gu u n d t ^ -- - t hn__ba s i s .nfat4sfano ry e v i uced. to be the pe rso n % who s e name% is/4.c.c subscribed to the within Instrument and acknowledged to me that helchnithny. executed the same in his/hc r ' ' ^!: authorfled capacity %), and that by his/hetMAc.it signature N on the instrument the person (q . or the entityuponbehalfofwhichtheperson(() acted, executed the Instrument.
W11NESSm3y andi official seal.
S1gnature [ ] No' cry Puerc. California f San Diego County i I
MyComet Egies Oct14,ZIn
.-- -.-.p 9811250105 981123'
, PDR ADOCK 05000361 P PDR
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN, CALIFORNI A )
EDIS0N COMPANY, ET AL. for a class 103 ) Docket No. 50-362 License to Acquire, Possess, and Use )
a Utilization Facility as Part of ) Amendment Application
!'elit No. 3 of the San Onofre Nuclear ) No. 168 benerating Station )
SOUTHERN CALIFORNIA EDISON COMPANY, EI AL. pursuant to 10CFR50.90, hereby submit Amendment Application No.168. This amendment application consists of Proposed Change No. PCN-498 to Facility Operating License NPF-15. PCN-498 is a request to e '. 4 n iootnotes (a) and (d) to Table 3.3.1-1 in Technical Specifi cation 3.3.1.
Subscribed on this day of f4 T ., 1998.
Respectfully Submitted, SOUTHERN CALIFORNIA EDISON COMPANY By: ( e( -
Dwight E. tunn ,
4 Vice Presi ent State of California County of San Diego On before me,/ Il b b pei; anally appeared
- M he/onally known to me h l'
' ^ ^
i_ b;;i- ^' ;; d ,' n iu,, e&4dex.e3 to be the person whose tiameBQ lh subscribed to the within instrument and acknowledged to me that he/' bry executed the same
- isH" 'rtr authorized capacity (k), and that by his A ,;W signature (y on the instrument the person \), or the entity upon behalf of which the person acted, executed the instrument.
WITNESS my hand and official seal. "-^^-------^-=
, 4 MAR'ANE SANCHE2 Commission # 1196482 Signature / i
[q
< /W { .
No*Gy PvDGc- Cofifomio l Son Jego county f I 4 ,
MyComm.E#es Oct14,2002)
DESCRIPTION OF TECHNICAL SPECIFICATION CHANGE PCN-498 SAN ONOFRE Units 2 and 3 Change Number PCN-498 will revise Technical Specification 3.3.1, " Reactor Protective System I (RPS) Instrumentation - Operating."
Existing Technical Specifications:
Unit 2: See Attachment A i
Unit 3: See Attachment B Proposed Technical Specifications:
1 Unit 2: See Attachment C (redline and strikeout)
Unit 3: See Attachment D (redline and strikeout) l Proposed Technical Specifications:
Unit 2: See Attachment E Unit 3: See Attachment F Proposed UFSAR: See Attachment G Description of Change:
The proposed change to Technical Specification (TS) 3.3.1 consists of revising Notes (a) and (d) to Table 3.3.1-1 to change the specified setpoints, to provide allowable values for the automatic 3 enable setpoints, and to clarify the nature of the measured parameter.
Amendment No.142 (submitted as PCN 500) was issued under emergency conditions for Unit 2 only on September 25,1998. This amendment corrected a long-standing incorrect use of terms
(' THERMAL POWER' for ' logarithmic power') in Notes (a) and (d), the subject of this ,
amendment request. Since the comparable emergency circumstances did not apply to Unit 3, the change proposed in PCN 500 will be issued separately at a later date. The subsequent discussion will describe this proposed change (ie: PCN 498) using current Unit 2 nomenclature (Note the Unit 3 ' Existing Technical Specifications' read differently). Also, the ' Proposed Technical Specifications' will show incorporation of both this proposed change, PCN 498, and the emergency proposed change, PCN 500, for both Units.
l l Note (a) to Table 3.3.1-1 currently permits bypassing the Logarithmic Power Level -- High (log L Power) trip when logarithmic power is > 1E-4% RATED THERMAL POWER (RTP) and I
i requires automatic enable of the Log Power trip to occur at a setpoint of $ IE-4% RTP when l reactor power is decreasing. Note (d) to Table 3.3.1-1 currently permits bypassing the Reactor l Coolant Flow -- Low, the Local Power Density -- High, and the Departure From Nucleate Boiling Ratio -- Low (RCS Flow /LPD/DNBR) trips when logarithmic power is < 1E-4% RTP and t requires automatic enable of the RCS Flow /LPD/DNBR trips to occur at a setpoint of 2 lE-4%
RTP when reactor power is increasing. Both enables (Log Power and RCS Flow /LPD/DNBR) are accomplished by the same bistable device for each channel. The RCS Flow /LPD/DNBR trips l enable occurs when the bistable trips; the Log Power trip enable occurs when the bistable resets.
The bistable reset occurs at a lower reactor power level than the trip. Consequently, with the i RCS Flow /LPD/DNBR enable correctly set at less than IE-4% RTP, the Log Power enable will occur at a reactor power level less than IE-4% RTP (typically around 8E-5% RTP), contrary to the requirement of Note (a). l l ' Thus, the current wording of the TS and the installed and approved RPS instrumentation are l incompatible. Revising Notes (a) and (d) to provide a setpoint compatible with the installed l instrumentation corrects this problem. The proposed revision also clarifies that the setpoints are l set relative to logarithmic power (not THERMAL POWER), and that manual enable of the trip is 1 l permissible (by deleting the word " automatically"). The proposed setpoints are " allowable l values," consistent with the other setpoints in Table 3.3.1-1.
l Discussion:
A. General SCE has evaluated the impact ofintroducing the allowable values irto Notes (a) and (d) on the UFSAR Chapter 15 design basis events. Figure 1 shows the allowable and safety analysis values ;
for the logarithmic power and RCS Flow /LPD/DNBR trip enable setpoints. As describcd in l Section B, SCE has concluded that an allowable value for the Log Power trip automatic enable of
, 2 4E-5% RTP provides adequate reactor protection. Therefore, the proposed wording of Note L
(a) to Table 3.1.1-1 requires the Log Power trip to be enabled at logarithmic power levels less than 4E-5% RTP. It should be noted that if the trip iz not manually enabled before logarithmic power decreases to 4E-5% RTP, then the trip will be automatical!y enabled by that allowable value.
As described in Section B, SCE has similarly determined that an allowable value for the RCS
, Flow /LPD/DNBR trips enable of51.5E-4% RTP provides adequate reactor protection.
l Therefore, the proposed wording of Note (d) to Table 3.1.1-1 requires the RCS Flow /LPD/DNBR trips to be enabled at logarithmic power levels greater than 1.5E-4% RTP.
Again it should be noted that if the trip is not manually enabled before logarithmic power l increases to 1.5E-4% RTP, then the trips will be automatically enabled by that allowable value.
l l
a
l l
l l
1 1
l l
- Figure 1
- Bistable Allowable & Safety Analysis Values.
s L Safety Analysis Value 1 x 10~3 % Power (DNBR/LPD/ Low Flow)
Allowable Value (Increasing 1.5 x 10-4 % Power Power)
Setpoint 1 x 10-4 % Power l
l Allowable Value !
(Decreasing 4 x 10_3 % Power i Power) l Safety Analysis Value 1 x 10*5 % Power (Log Power) l l
r
B. Analyses in order to determine the impact of the proposed change in the Notes (a) and (d), an assessment was performed of the UFSAR Chapter 15 events. Note (a) impacts the logarithmic power bypass and Note (d) applies to the CPC DNBR or LPD trip and the RCS flow trip. Based on the allowable values of 4E-5 % power for the decreasing setpoint (i.e. log power trip enable) and 1.5E-4 % power for the increasing setpoint (i.e. RCS Flow /LPD/DNBR trip enable),
conservative safety analysis limits of < l.0E-5 for the log power trip enable and > 1.0E-3 for the RCS Flow /LPD/DNBR trip enable were used in the safety analysis.
All of the relevant UFSAR Chapter 15 safety analysis events were assessed for San Onofre Units 2 and 3 with regards to the impact of the above TS modification. The events adversely impacted by this change were the uncontrolled control element assembly (CEA) withdrawal from subcritical and low power. These events are discussed below:
UFSAR Section 15.4.1.1 Uncontrolled CEA withdrawal from Subcritical and Low Power (i) Uncontrolled CEA Withdrawal From Subtritical The event is analyzed to the fuel failure and peak RCS pressure criteria. The worst case initial condition for this event is from a core power of approximately 1E-8% power. The credited reactor trip is the logarithmic power trip at a setpoint of 4% rated thermal power. Reducing the enabling setpoint from lE-4% power to lE-5% power reduces the operating space requiring protection from the log power trip. Therefore since the worst case initial condition is still maintained and the log power trip setpoint remains unchanged, the change to Note (a) will have no adverse impact on the consequences of this event.
The change in the RCS Flow /LPD/DNBR trip enable setpoint from lE-4% power to IE-3%
power could potentially impact this event in several ways. If out-of-sequence regulating or shutdown bank withdrawals were eliminated from consideration by crediting the LPD/DNBR trips, the later enabling setpoint would have to be specifically considered in determining the worst case condition for this event. However, for SONGS 2 & 3, all regulating and shutdown banks were surveyed to determine the worst CEA bank withdrawn. Therefore, no LPD/DNBR trip credit was required to eliminate out-of-sequence regulating or shutdown banks.
The second potential impact applies if the event credited the RCS Flow trip or the Core Protection Calculator pump speed auxiliary trip. These trips are credited for this event with less than four Reactor Coolant pumps operating. The event was reanalyzed for part loop operation with the IE-3% CPC DNBR & LPD and RCS low flow trip enable analyticcl setpoint. The results show that the consequences of this event remain bounded by the analysis as presented in UFSAR Section 15.4.1.1. Therefore, the change to Note (d) will have no adverse impact on the cc,nsequences of this event.
(ii) Uncontrolled CEA witi.drawal from low power
This event is also analyzed to the fuel failure and peak RCS pressure criteria. The change in Notes (a) and (d) will extend the range ofinitial power conditions protected by this portion of the event from lE-4% power to IE-5% power. The worst case initial condition for this event is at the low power condition. This event was thus reanalyzed to accommodate the allowable range window of the enable setpoint. The results of this reanalysis show that the fuel centerline melt acceptance criterion of 4706 F, the DNBR acceptance criterion of 1.31, and the peak RCS pressure acceptance criterion of 110% design pressure are met for this event.
No Significant llazards 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 a facility operating license 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 accident previously evaluated; or (2) create the possibility of a new or 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) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
No.
The proposed change to TS 3.3.1 does not adversely impact structure, system, or component design or operation in a manner which would result in a change in the l frequency of occurrence of accident initiation. SCE has re-analyzed the relevant accidents and established that accident consequences are not significantly increased by the proposed changes to the bypass-permissive and enable setpoints. The reactor trip bypass and automatic enable functions are not accident initiators. Consequently, the proposed TS change will not significantly increase the probability of accidents previously evaluated.
Therefore, this amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated.
I
- 2) Does this amendment request create the possibility of a new or different kind of accident ,
from any accident previously evaluated? l No.
No new or different a:cidents result from changing the reactor trip bypass-permissive and automatic enable sete,oints. Introducing an uncenainty band for the enable setpoints delays the mitigation action of the reactor trip for the design basis analysis for the events that credit this trip. The enable setpoint itself does not cause any accident. Therefore, the amendment request does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) . Does this amendment request involve a significant reduction in a margin of safety?
No.
SCE has re-analyzed the accidents and determined that the consequences of the accidents are within their acceptance criteria under the proposed amendment so that the margin of safety that bounds the setpoint in both directions remains intact. The analyses are relatively insensitive to the reactor trip automatic enable setpoints, and no significant reduction in the margins of safety ensues from the relatively minor proposed changes to the bypass-permissive and enable setpoints, nor from establishing allowable values for the -
setpoints.
Based on the negative responses to these three Commission criteria, SCE concludes that the proposed amendment involves no significant hazards consideration.
Environmental Consideration:
Southern California Edison has determined that the proposed TS change involves no changes in the amount or type ofeffluent 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, meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9).
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