Amend Application 129 to License NPF-15,consisting of Proposed TS Change Number 442,revising TS 3/4.2.1, Linear Heat Rate (Lhr) & Associated Bases to Reduce Lhr Limit from 13.9 Kw Per Ft (Kw/Ft) to 13 Kw/FtML20073B452 |
Person / Time |
---|
Site: |
San Onofre  |
---|
Issue date: |
09/16/1994 |
---|
From: |
Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20073B444 |
List: |
---|
References |
---|
NUDOCS 9409220018 |
Download: ML20073B452 (8) |
|
|
---|
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 ML20199K6371998-01-0909 January 1998 Corrected Suppl 1 to Application for Amends 152 & 136 to Licenses NPF-10 & NPF-15,respectively 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 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 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 ML20217A8181997-09-16016 September 1997 Application for Amends to Licenses NPF-10 & NPF-15.Amends Consist of Proposed TS Changes to TS 3.4.13,5.5.2.11,5.7.2 & Affected Bases,Allowing SG Tube Repair Using Asea Brown/Boveri/Combusting Engineering Leak Tight Sleeving 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 1999-08-11
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217B4401999-10-0707 October 1999 Amends 159 & 150 to Licenses NPF-10 & NPF-15,revising License Condition 2.C(19) for Unit 2 & 2.C(17)d for Unit 3 & TS 3.3.11 Re Hydrogen Monitoring Requirements ML20211R0411999-09-0909 September 1999 Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively, Modifying TS Surveillance Requirements Re Diesel Generator Testing ML20212A2321999-09-0707 September 1999 Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively, Consisting of Changes to TS 3.3.5, ESFAS Instrumentation, in Response to 981231 Application & Suppl ML20211E9281999-08-19019 August 1999 Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively, Revising TS 3.4.10, Pressurizer Safety Valves, to Increase as-found Pressurizer Safety Valve Setpoint Tolerances ML20211F1921999-08-19019 August 1999 Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively, Changing TS in Response to Application ML20210P5931999-08-11011 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 ML20209G3331999-07-12012 July 1999 Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively, Authorizing Changes to UFSAR to Permit Installation of Digital Radiation Monitors for Both Containment Purge Isolation & Control Room Isolation Signals 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 ML20207A0151999-05-13013 May 1999 Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively, Modifying TSs to Allow Refueling Operation with 20 Ft of Water Level in Refueling Cavity for Many Operating Conditions & at 12 Ft of Water Level for Certain Conditions ML20206D1391999-04-26026 April 1999 Amend 152 to License NPF-10,allowing Facility to Be Outside Licensing Basis Re Remote Shutdown Capability of SDC Sys as Described in Updated Safety Analysis Rept,Section 5.4.7.1.2, During Period of Repair 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) ML20205N2601999-04-0909 April 1999 Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively, Revise SR 3.8.1.9 to TS 3.8.1, AC Sources-Operating, to More Accurately Reflect Test Conditions & Plant Design Requirements 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 ML20203J1771999-02-12012 February 1999 Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively, Modifying TS to Reduce Min RCS Cold Leg Temp,Convert Specified RCS Flow from Mass Units to Volumetric Units & Eliminate Max RCS Flow Rate Limit from TS 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 ML20198S5461998-12-22022 December 1998 Amends 147 & 139 to Licenses NPF-10 & NPF-15,respectively, Deleting License Condition 2.C.(19)b for SONGS Unit 2 & Revising Listed TSs for Both SONGS Units ML20198H5151998-12-21021 December 1998 Amends 146 & 138 to Licenses NPF-10 & NPF-15,respectively, Revising Licensing Basis to Incorporate New Turbine Missile Protection Calculation Methodology ML20206N6141998-12-16016 December 1998 Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively, Revising Reference for Obtaining Thyroid Dose Conversion Factors Used in Definition of Dose Equivalent I-131 in TS Section 1.1, Definitions, for Plant 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 ML20196A6051998-11-23023 November 1998 Amend 136 to License NPF-15,revising TS to Change Operative Parameter for Setting & Removing Operating Bypass Bistables for Logarithmic Power Level 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 ML20155H5891998-11-0606 November 1998 Amends 144 & 135 to Licenses NPF-10 & NPF-15,respectively, Revising TS to Implement 10CFR50,App J, Option B for performance-based Reactor Containment Leakage Testing ML20196A1611998-10-26026 October 1998 Errata to Amends 143 & 134 to Licenses NPF-10 & NPF-15, Respectively.Due to Administrative Oversight,Implementation Date for Each Amend Was Incorrect ML20155B9511998-10-26026 October 1998 Amends 143 & 134 to Licenses NPF-10 & NPF-15,respectively, Modifying TSs to Eliminate Ref to Shutdown Cooling Sys Isolation Bypass Valve Inverters 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 ML20154B9331998-09-25025 September 1998 Amend 142 to License NPF-10,revising TS to Change Operative Parameter for Setting & Removing Operating Bypass Bistables. Operative Parameter in TS Changed from Thermal Power to Logarithmic Power 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 ML20197D0091998-09-0909 September 1998 Amends 141 & 133 to Licenses NPF-10 & NPF-15,respectively, Revising TS to Extend AOT for off-site Circuits & for EDG 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 ML20239A1401998-08-26026 August 1998 Amends 140 & 132 to Licenses NPF-10 & NPF-15,respectively, Allowing Sleeving of SG Tubes W/Sleeves Designed by Vendor, ABB-CE 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 ML20249C7331998-06-19019 June 1998 Amends 139 & 131 to Licenses NPF-10 & NPF-15,respectively, Modifying TSs to Extend Allowed Outage Times for Single Inoperable SIT from 1 H to 24 H 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 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 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 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 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 ML20198A2351997-12-16016 December 1997 Amends 138 & 130 to Licenses NPF-10 & NPF-15,respectively, Deleting Physical Protection Program Reporting Requirement from License Condition 2.G & Clarifying License Condition 2.E 1999-09-09
[Table view] |
Text
.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )
EDISON COMPANY, ET AL. for a Class )
Docket No. 50-362 103 License to Acquire, Possess,
)
and Use a Utilization Facility as
)
Amendment Application Part of Unit No. 2 of the San
)
No. 129 Onofre Nuclear Generating Station
)
SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 129.
This amendment application consists of Proposed Change Number (PCN) NPF-15-442 to Facility Operating License No. NPF-15.
PCN NPF-15-442 is a request to revise the San Onofre Unit 3 Linear Heat Rate (LHR) limit in Technical Specification (TS) 3/4.2.1, " Linear Heat Rate," and the associated Bases.
This request will reduce the LHR limit from 13.9 kilowatts per foot (kw/ft) to 13.0 kw/ft.
9409220010 940916 PDR ADOCK 05000361 p
PDR
~ _
l bb#
Subscribed on this day of *
, 1994.
Respectfully submitted, SOUTHERN CALIFORNIA EDIS0N COMPANY
/
By:
/
A /AdA Richard M. Rosenblum Vice President Engineering and Technical Services State of California l@
_ befc re me, Iblf/ aft 10M4personaiiy n
appeared lU $hkVTl lYI.EoVAb1l)Yersonally known to me to be the person whose name is subscribed to the within instrument and acknowledged to me that he executed the same in his authorized capacity, and that by his signature on the instrument the person, or the entity upon behalf of which the person acted, executed the instrument.
WITNESS my hand and official seal.
0
/t.:
uShflM$hrz l
I e
c ay "wese Signatur l,
/
k L
9 i
i l
i
D e
ENCLOSURE 1 DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-10/15-442 d
l i
j
DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-10/15-442 This is a request to revise Technical Specification (TS) 3/4.2.1, " Linear Heat i
Rate," for San Onofre Units 2 and 3.
The Bases of TS 3/4.2.1, " Linear Heat Rate," will also be revised.
Units 2 and 3 Technical Specifications Existing Specifications:
Unit 2: See Attachment "A" Unit 3: See Attachment "B" t
Proposed Specifications:
Unit 2: See Attachment "C" Unit 3: See Attachment "D"
1.0 DESCRIPTION
OF CHANGES:
This amendment request is to change the Technical Specification (TS) 3/4.2.1, " Linear Heat Rate," Linear Heat Rate (LHR) limit. TS 3/4.2.1 requires maintaining the linear heat rate at or below 13.9 kilowatts per i
linear foot (kw/ft) for steady state operation. This amendment request is to revise this value from 13.9 kw/ft to 13.0 kw/ft.
The Bases of TS 3/4.2.1, " Linear Heat Rate," are also being revised to reflect the new value.
2.0 BACKGROUND
2.1 Technical Specification TS 3/4.2.1 requires the LHR to be limited to 13.9 kw/ft or less during steady state operations to insure that, in the event of a large Break Loss of Coolant Accident (LBLOCA), the' peak temperature of the fuel cladding will not exceed 2200 F.
The LHR limit specified in TS 3/4.2.1 is monitored by the Core Operating Limit Supervisory System (COLSS) and the Core Protection Calculators (CPCs) when COLSS.is out of service during plant operation.
The CPCs ensure the overall safety of the reactor is maintained by using reactor trip functions to limit the maximum reactor power and the local power density.
COLSS is.a non-safety related monitoring system which alerts operators when certain reactor parameters, including LHR, exceed limiting conditions for operation values.
2.2 Linear Heat Rate TS 3/4.2.1 provides assurance that the LBLOCA event will be bounded for energy transfer from the reactor core by placing a..m
~
limit on the steady state LHR.
This energy transfer between the individual fuel pins in the core and the reactor coolant is measured in kilowatts per linear foot of fuel pin (kw/ft) and is called the Linear Heat Rate.
3.0 DISCUSSION
3.1 Basis for the Proposed Reduction of the Linear Heat Rate (LHR)
Limit The LHR limit of TS 3/4.2.1 is to be changed from 13.9 kw/ft to 13.0 kw/ft.
This change is conservative and supports a new LBLOCA reanalysis.
The LBLOCA reanalysis was performed to restore and provide additional analysis margin for recent changes in analysis input parameters.
The input parameter changes include 1) changes in physics parameters and assumptions used in support of an optimized fuel loading pattern, and 2) changes to accommodate future plant design and operational changes.
These changes and the LBLOCA reanalysis are described below.
l.
Optimized Fuel Loading Pattern By reducing the core neutron leakage a longer fuel cycle length can be achieved.
The improved fuel cycle length, however, affects the analysis for the LBLOCA due to more adverse radial power peaking factors at beginning of core life (BOL).
The more adverse BOL radial peaking factors result in an increase in the evaluated Peak Cladding Temperature (PCT). The evaluated PCT margin is increased by lowering the LHR limit as proposed in this amendment request.
2.
Future Plant Design and Operational Changes Various parameters in the LBLOCA reanalysis have been revised to accommodate anticipated changes in plant design and operation.
Examples of these changes include: 1) expected increases in steam generator tube plugging level and 2) anticipated reductions in reactor vessel inlet temperature.
The proposed reduction in LHR limit provides additional analysis margin to accommodate these and other anticipated plant changes.
3.
LBLOCA Reanalysis A reduction in the LHR limit provides an increase in PCT margin for the LBLOCA Analysis of Record (A0R).
Reducing the allowable LHR limit results in a reduction in the maximum allowable steady-state energy transfer from the reactor core to the reactor coolant.
By reducing the limit on local energy transfer to the coolant the maximum heat rate assumed in the analysis will be reduced. This, in
turn, reduces the heat-Sp of the fuel should the fuel be uncovered by coolant and reduces the PCT.
The reanalysis of the LBLOCA was performed using the Asea Brown Boveri - Combustion Engineering 1985 LBLOCA Evaluation Model (EM). This EM was used for San Onofre without change to the standard methodology as previously reported to the NRC.
Results of the LBLOCA reanalysis show that all acceptance criteria were met with the LHR limit reduced from the present limit of 13.9 kw/ft to 13.0 kw/ft.
The PCT calculated by the reanalysis was 2160 *F, which is within the required limit of 2200 *F.
3.2 Acceptability of the Proposed Reduction of the LHR Limit The LHR limit is being reduced to provide margin in the LBLOCA reanalysis performed in support of an optimized fuel loading pattern.
This reduction is possible because recent investigations performed by Southern California Edison (Edison) found that the normal maximum LHR value, including all applicable uncertainties, is approximately 12.0 kw/ft. On this basis, Edison determined that Units 2 and 3 may be operated at a lower LHR limit of 13.0 kw/ft without af fecting unit performance.
Normal operation of the plant is monitored by the COLSS and CPCs.
If the LHR limit is exceeded, the COLSS operating alarm sounds to warn the operator of the need to return the LHR to within the Limiting Condition for Operation limit.
To ensure minimal operational impact, sufficient analysis margin between the normal maximum LHR and the proposed TS LHR limit should be maintained.
The difference between the proposed TS LHR limit of 13.0 kw/ft and the normal maximum LHR of 12.0 kw/ft is sufficient to ensure that this proposed TS change has minimal operational impact.
Unit operation with COLSS out of service requires operator action to implement TS 3/4.2.4, " Power Distribution Limits - DNBR Margin," Figure 3.2-2, "DNBR Operating Limit Based on Core Protection Calculator - COLSS Out of Service - Both CEACS [ Control Element Assembly Calculators] Inoperable." Operator ability to operate when COLSS is out of service within the " Region of Acceptable Operation" shown on Figure 3.2-2 will not be impacted by the proposed reduction in LHR limit.
4.0 DISCUSSION OF CHANGES TO PCN-299:
PCN-299 implements the Technical Specification Improvement Project which incorporates the recommendations of NUREG-1432, " Standard Technical Specifications Combustion Engineering Plants."
PCN-299 was submitted to the NRC for review on December 30, 1993. This proposed change does not require any changes to PCN-299 because the LHR limit is being transferred to the Core Operating Limit Report.
5.0 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 any accident previously evaluated?
Response: No The only event impacted by this Technical Specification (TS) change is the large Break Loss of Coolant Accident (LBLOCA) which has been reanalyzed.
There is a direct correlation between the magnitude of the TS 3/4.2.1 Linear Heat Rate (LHR) limit and the calculated peak cladding temperature (PCT).
Since the LHR is being reduced in value, which is a conservative change, there will be no increase in the consequences of the event. The LBLOCA reanalysis, performed using the new LHR limit in support of an optimized fuel loading pattern, resulted in a reduction of the calculated LBLOCA PCT.
Therefore, this change will not involve an increase in the probability or consequences of any 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 previously evaluated?
Response: No This amendment request does not involve any change to plant equipment or operation.
The linear heat rate limit provided in T/S 3.2.1 is used only in the LBLOCA analysis. No change to the LBLOCA methodology was made. Therefore, this change does not create the possibility of a new or different kind of accident from any 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 This amendment does not change the manner in which safety limits, limiting safety settings, or limiting conditions for operation are determined. There is no change in the~ PCT acceptance criterion i
for this event as a result of the proposed reduction in the LHR limit. Therefore, there is no reduction in the margin of safety from the acceptance limit to the mechanical failure point of the fuel. Additionally, the analysis value for the LBLOCA PCT is reduced to 2160 *F.
This results in an increase in the analysis l
margin between the acceptance criterion and the analysis value.
Therefore, this proposed change does not involve a reduction in a margin of safety.
6.0 SAFETY AND SIGNIFICANT HAZARDS DETERMINATION:
Based on the above Safety Analysis, it is concluded that: (1) tha 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 action does not involve a significant hazards consideration, it will also not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement. 4
--