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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
- -- - _ - . _ - . -
,y v.
g so - cio.o. m EDISON ?"S"" !
'An unsonirtwnom came.n l T
l February 18, 1997
.l I
'i O. S. Nuclear Regulatory Commission i Attention: Document Control Desk l Washington, D.C.20555 j Gentlemen: l l
Subject:
Docket Nos. 50-362 'l Engineered Safety Features Response Time Testing Proposed- j Technical Spectfication Change Number 480 i' San Onofre Nuclear Generating Station, Unit 3
Reference:
.-February 16, 1997 letter from R. W. Krieger (Edison) to-William H. Bateman (NRC),
Subject:
. Request for Enforcement Discretion, Engineered Safety Features Response Time Testing, San Onofre Nuclear Generating Station, Unit 3 Enclosed is Amendment Application Number 152 to Facility Operating License
.NPF-15, for the_ San Onofre Nuclear Generating Station (SONGS), Unit 3. The l
Amendment Number 480_ PCN-480) Ap(plication
. This isconsists a requestoffor Proposed an exigentTechnical Technical Specification Change l Specification Change as a followup to the Request for Enforcement Discretion l referenced above. j The proposed change is requested to defer implementation of Surveillance i Requirement- (SR) 3.3.5.6 of Technical Specification (TS) 3.3.5, " Engineered l Safety Features Actuation System (ESFAS) Instrumentation" for 30 subgroup !
relays until the next refueling outage on San Onofre Unit 3. The need for {'
[ 'this recuest results from an error in implementation of this SR.This SR was
. believec to be satisfied by a surveillance which included a bounding allowance ;
a for the subgroup relays, in lieu of actually testing these relays. l This change is not being requested for Unit 2 because Unit 2 is currently i
- shutdown for a_ refueling outage. The ESFAS subgroup relays.in Unit 2 will be j tested:in accordance with SR 3.3.5.6 prior to return to Mode 4. l i- The-Southern California Edison Company requests this amendment be issued as an exigent TS change, effective as of its date of issuance. The exigent i
- ' . circumstances for this TS amendment request exist because it would avoid'an !
4 undesirable transient associated with an unnecessary plant shutdown and thus i minimize potential safety consequences and operational risks associated with l such' action. In the event of a planned or unplanned shutdown of Unit 3, prior :l to_the Cycle 9 refueling outage, testing in accordance with SR 3.3.5.6 will be j i I
- completed prior to increasing in Modes from that shutdown. j j P. O. Box 128 P k M !6 pg g a lh -
j San Clemente CA 92674 0128 !
714-368 148o !
. Fax 714 3681490 l y 3
e Document Control Disk If you would like additional information regarding this Amendment Application, please let me know.
5 Sincerely
\
l Enclosure cc: L. J. Callan, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 t
I
Document Control Desk UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )
EDIS0N COMPANY, ET 6L. for a Class 103 Docket No.
License to Acquire, Possess, and Use 50-362 a Utilization Facility as Part of Amendment Unit No. 3 of the San Onofre Nuclear Application Generating Station No 152.
SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No 152. This amendment application consists of Proposed Technical Specification Change No. 480 to Facility Operating License NPF-15. Proposed Technical Specification Change No. 480 is a request to revise TS 3.3.5, " Engineered Safety Features Actuation System (EFSAS) l Instrumentation." The proposed change defers implementation of Surveillance Requirement 3.3.5.6, " Verify ESF RESPONSE TIME is within limits" until the Unit 3, Cycle 9 refueling outage.
Subscribed on this 'b d ay of dI)f'll OL NA , 1997.
J Respectfully submitted, SOUTHERN CALIFORNIA EDIS0N COMPANY F
Dwight E. Nunn Vice President
Document Control Desk State of California County of an Diego tr On b lf 47 _
beforeme,[,'tTIl4 s_ N4Cb M rsonally <
appeared Olts i%htM Alluut, personally known to me to be the person whose i nameissubscribedtothewithininstrumentandacknowledgedtomethat he executed the same in his authorized capacity, and that by his signature on the instrument the person, or the entity upon behalf of which the person acted, executed the instrument.
. . .m ,
WITNESS my hand and official seal. j mewan COMM.# 1033763
[
l Notory Pub 8c - Cotfornia p ( ORANGE COUNTY My Comm. Expires OCT 14.19 Signaturk O (Ibf e- -
l l
1 1
1 l
I
l DESCRIPTION AND SAFETY ANALYSIS )
0F PROPOSED CHANGE 480 ;
l l
This is a request for an exigent Technical Specification (TS) change to revise l Surveillance Requirement (SR) 3.3.5.6 of TS 3.3.5, " Engineered Safety Features Actuation System (ESFAS) Instrumentation" for San Onofre Nuclear Generating I Station (SONGS), Unit 3.
Existing SONGS Specification:
Unit 3: See Attachment "A" Proposed SONGS Specification:
- Unit 3: See Attachment "B"
- The following Note will be added to SR 3.3.5.6:
Verification of the RESPONSE TIME of the subgroup relays is not applicable until return to Mode 4 from the Unit 3 Cycle 9 refueling outage with the l additional commitments made in the February 18, 1997 Edison letter. The .
safety justification for not performing this. testing is also included in the February 18, 1997 letter. ,
Description of Chances SUMARY The proposed change is requested to defer implementation of Surveillance Requirement (SR) 3.3.5.6 of TS 3.3.5, " Engineered Safety Features Actuation System (ESFAS) Instrumentation" until the Unit 3, Cycle 9 refueling outage for i the 30 subgroup relays in the Engineered Safety Features Actuation System (ESFAS) listed in Attachment C. In the event of a planned or unplanned shutdown of Unit 3, prior to the Cycle 9 refueling outage, testing of these 30 relays in accordance with SR 3.3.5.6 will be completed prior to increasing in Modes from i that shutdown.
DISCUSSION i
On February 14, 197 Southern California Edison (Edison) recognized that the 3
existing Unit 3 surveillances of record did not fully satisfy SR 3.3.5.6. The SR requires verification that the ESF Response Time is within limits, which requires that the response time of the subgroup relays be measured. Although it ,
may be possible to perform this test with the Unit in Mode 1 for the 30 subgroup relays listed in Attachment C, it would involve testing these relrys inside the ESF cabinets using temporary jumpers and power supplies for safety significant ,
components (main steam isolation valves, feedwater valves, reactor coolant pump
- bleedoff, instrument air, and component cooling water), as well as defeating the safety function of these. relays during testing. Performance of this testing in Mode 1 would involve more risk of inadvertent actuation of ESF equipment and ;
trip of the Unit. .
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- After reviewing existing documentation, however Edison believes that the subgroup relays are fully functional and capable of performing their intended safety functions,-.as demonstrated by satisfactory performance during'other surveillance testing, the margin available fortrelay operation, and the .recent l
maintenance history of the relays, j
-System Description j The subgroup relays are part of the Enginecred Safety Features (ESF) systems.- l The safety-related instrumentation and controls of the ESF systems' include the i
. ESFAS, which consists of. the electrical and mechanical: devices and circuitry L(fromsensorstoactuationdeviceinputterminals)involvedingeneratingthose signals,that actuate the required ESF systems, and the arrangement of components ,
that perform protective actions after receiving a signal from either the ESFAS
- or the operator. ,
The-ESFAS includes sensors'to monitor selected safety significant parameters; The following actuation signals are generated.by the ESFAS when the monitored variables reach the levels that.are indicative of conditions which require protective. action: ;
t The signals from the ESFAS actuate the ESF equipment. .For the above actuation ,
systems, two-out-of-four coincidence of like initiating trip signals from four ;
independent measurement channels is required to actuate the ESF system. !
The response time of the ESF systems may be measured by means of any series of ,
sequential, overlapping, or total steps so that the entire response time is !
measured. At San Onofre the total response time has been determined by i sequentially adding the response times determined for separate segments of the
~ESF. systems. Response times have been measured during each surveillance from the sensor / transmitter to the subgroup relay and from the subgroup relay until '
the ESF equipment is capable of performing its safety function. However, instead of being measured during each surveillance, a bounding time response allowance was used for the subgroup relays based on measurements and an ,
engineering evaluation performed in 1983. The bounding time was based on testing '
completed from a large sample of relays tabulated by relay type.
Three st'andard deviations were applied to the average of the relay times and the ;
result was conservatively rounded up to 0.300 seconds.
- Subgroup Relays
! The subgroup relays are Potter & Brumfield Motor Driven Relays. These relays :
' utilize a coil-to. rotate a shaft which causes the contacts to open and close.
Although earlier versions of these relays have had a history of petformance problems, theseLissues have been addressed and resolved as discussed below.
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During a Unit 2 integrated ESF test in November, 1987, one subgroup relay did not function properly. Examination of the relay revealed the presence of contamination and corrosion products in the motor housing. These materials were present on and around the bearing surfaces and in bushing to shaft spaces where the buildup of material caused the relay to mechanically jam.
The failure mode was found to be predominately one of relay binding due to "out-gassing" of corrosive material in the insulating varnish of the relay coil.
The out-gassed material would condense on the internal surfaces of the relay, such as the shaft and shaft bearing surface, causing corrosion and binding. The (temperature) primary driving force for the problem was excess heatgenerated b voltage.
Edison and other utilities worked with Potter & Brumfield to correct all the problems experienced. The changes included using an epoxy coil coating instead of varnish to eliminate chlorine, replacement of the brass spacers with stainless steel for enhanced corrosion resistance, tolerance changes to alleviate shaft binding, and replacement of the coil PVC insulating sleeves and neoprene grommets in the motor base with inert materials to eliminate these sources of corrosive out-gassing materials.
Revision controlled drawings were instituted with the vendor guaranteeing no changes to subgroup relays purchased by San Onofre without Edison approval.
Unique part numbers were assigned to further track changes and subsequent replacement of existing subgroup relays. On-site Quality Control inspection and testing was used to " qualify" the vendor for the new design subgroup relays.
The subgroup relays in ESF systems with varnish coils were replaced in the 1989 to 1993 time frame.
Justification of Operability Edison has completed a number of activities including 1) an assessment of the total time sequence for the individual ESF subgroup relays, 2) initial Unit 2 relay testing, 3) a maintenance history search for relay reliability, and
- 4) an evaluation of recent channel test results.
The tables in Attachment D provide the individual relay and component timing data for both Units 2 and 3 Trains A and B ESF equipment. The information in the tables was pulled from plant records on February 14 - 17, 1997 and is the best available information. The tables list the individual relays, the associated valve or pump that is actuated, timing data for the trains, the technical specification limit for the component, and allowable " margin" to the limit. Note that the table shows a "zero" time for the subgroup relays. This "zero" time is shown so that the allowable margin column effectively shows the time available to accomodate the actual response time for these relays.
As shown in the attached tables, there are 118 subgroup relays in the ESF relay cabinets. Edison has further evaluated each relay and actuated component. Of these 118 relays, 99 are required to be response time tested to comply with SR 3.3.5.6. As a result of the integrated ESF testing, response time data is credited for 10 of these relays. Of the remaining 89 relays, 59 can be response time tested on line. The remaining 30 relays cannot be response time tested 3
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on-line without rendering their associated equipment inoperable and incapable of .
performing their safety functions. These 30 relays close valves that are !
required to be open while the plant is operating in systems such as main steam '
isolation, main feedwater, reactor coolant pump bleedoff, component cooling water noncritical loop, and instrument air. ;
-In response to this missed surveillance, Edison placed a Mode 4 restraint on the i Unit 2 refueling outage, and a complete retest was immediately initiated and has ,
-been completed of all the ESFAS subgroup relays addressed by SR 3.3.5.6.
Additionally, response time testing was initiated on the Unit 3 ESFAS subgroup relays that can be tested on line. Response time data collected on' subgroup.
relays tested on Unit 2 shows time responses-in the range of 0.032 seconds to 0.119 seconds. This' testing includes a. sample of over 100 relays. Response time data collected on_ Unit 3 subgroup relays (currently, response time. testing on 52 of 59 relays has been completed on line) shows time response in the range of 0.029 seconds to 0.115 seconds. These results are an improvement over data obtained in 1983 for the previous version subgroup relays and support the 1 bounding time response allowance of 0.300 seconds used for the subgroup relays. l
-A' maintenance history search for ESF subgroup relay failures was completed.
This search found no failure on either San Onofre unit since the 1989-1993 time ,
period after the relays were replaced. ;
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In addition,'all ESF trains have successfully passed the following surveillance tests: ,
- 1. Channel Functional Test (SR 3.3.5.2, SR 3.3.5.3, SR 3.3.5.7, SR3.3.6.1,andSR3.3.6.3) i
- 2. Channel Calibration Test (SR 3.3.5.4 and SR 3.3.5.5) -l
- 3. Subgroup Relay Test (SR 3.3.6.2)
The ESF trains have satisfied the above surveillance test acceptance criteria, which provides assurance that the ESF trains are operable. .
In summary, Edison is confident that the Unit 3 ESF trains remain operable and l that the time response of the subgroup relays is within the assumed allowance of 0.300 seconds because: ,
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- 1. There is sufficient available margin for subgroup relays that are '
not currently timed (see Attachment D tables),
- 2. Results of Unit 2 subgroup relay testing conducted on I February 14 - 17, 1997 demonstrated that the timing of the subgroup ,
relays was consistent with and bounded by the 1983 assessment, ,
- 3. There~is no history of ESF subgroup relay failure since the
'1989-1993 time period. !
4.- Surveillance requirements for ESF Channel Functional Tests, ESF Channel Calibration Tests, and ESF Subgroup Relay Tests have been satisfied.
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In-addition, based on the current tests of record for the Unit 3 integrated ESF '
test per.SR 3.8.1.19, 10 subgrou ) relays plus actuated components were demonstrated to be well within t1eir overall response time requirement.
Probabilistic Risk Assessment
.The core damage and significant radioactive release risk impact of continued Unit 3 operation without performing the subject ESF surveillance testing has been determined negligible. -Since the engineering assessment concludes that the overal1 ESF 79sponse time remains within allowable design margins, no events modeled in the San Onofre Units 2 and 3 living probabilistic risk assessment are impacted. The impact on core damage risk from a forced unit shutdown to perform.
the subject surveillance test is estimated to be IE-6, which is non-negligible.
Therefore, the safest course of action is to remain at power and conduct the surveillance testing during the next outage.
This proposed change is requested to defer implementation of SR 3.3.5.6 until the next refueling outage on Unit 3 for 30 ESFAS subgroup relays. This proposed ,
change will preclude the need to shut down Unit 3 before the refueling outage for the sole purpose of performing this SR. The start of the Unit 3 Cycle 9 refueling outage is currently anticipated for April 12, 1997.
SAFETY ANALYSIS' The proposed change described above shall be deemed to involve a significant hazards consideration if there is a positive finding in any one of the following areas:
- 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change would defer completion of Surveillance Requirement (SR) 3.3.5.6 of Technical Specification (TS) 3.3.5 for 30 Emergency Safety .
Feature Actuation System (ESFAS) subgroup relays until the Unit 3, Cycle 9 refueling outage.
l Operation of the facility would remain unchanged as a result of the proposed change and no assumptions or results of any accident analyses are affected. Based on other surveillance testing, the response time margin available for these subgroup relays, results of response time testing on Unit 2 relays, and the history of no failures since the 1989 to 1993 time period, the capability of these ESFAS subgroup relays to perform their specified safety function has been demonstrated and they are operable.
Therefore, the proposed change will not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previoucif evaluated?
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i Response:No ;
The proposed change would defer completion of SR 3.3.5.6 of TS 3.3.5 for
.30.ESFAS subgroup relays _until the Unit 3, Cycle 9 refueling outage. l Operation of the facility would remain unchanged as a result of the ;
proposed change. No equipment change or operating procedure change is :
being made. Therefore, the proposed change will not create the ;
i possibility of a new or different kind of accident from any accident i previously evaluated. ;
- 3. Will operation of the facility in accordance with this proposed -
change involve a significant reduction in a margin of safety? ;
Response:No The proposed change'would defer completion of SR 3.3.5.6 of TS 3.3.5 for !
4 30 ESFAS subgroup relays until the Unit 3, Cycle 9 refueling outage. i 7
Based on other surveillance testing, the response time margin available
- for these subgroup relays, and results of testing on Unit 2 relays,-the
- capability _ of these ESFAS subgroup relays to perform their specified ,
safety. function has been-demonstrated and they are operable. Therefore, i this proposed change does not involve a significant reduction in a margin :
of safety. j Safety and Significant Hazards Determination ;
. dased on the above Safety Analysis, it is concluded that: (1) the proposed ;
change does not constitute a significant hazards consideration as defined by ,
. 10 CFR 50.92 and (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change. Moreover, because !
this proposed change does not involve a significant hazards consideration, it ;
will also not result in a condition which significantly alters the impact of the i
station on the environment as described in the NRC Final Environmental !
q Statement.
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