|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F0941999-10-14014 October 1999 Application for Amends to Licenses DPR-39 & DPR-85,to Revise TS Sections 2.2 & 3.0/4.0 to Support Mod P000224 Which Will Install New Power Range Neutron Monitoring Sys & Incorporate long-term thermal-hydraulic Stability Solution Hardware ML20216J3341999-09-27027 September 1999 Supplements Application for Amends to Licenses NPF-39 & NPF-45,to Modify Appearance of TS Page 3/4 4-8 as Typo Was Identified in Section 3.4.3.1 of Ts.Corrected TS Page,Encl ML20212H5521999-09-27027 September 1999 Application for Amends to Licenses NPF-39 & NPF-85,revising TS to Clarify Several Administrative Requirements,Deleting Redundant Requirements & Correcting Typos ML20212F9521999-09-20020 September 1999 Application for Amend to License NFP-39,requesting Issuance of TS Change Request 98-08-0 Re Increase in Allowable as- Found Main Steam SRV Setpoint Tolerance.Util Had Originally Requested That Subject TS Change Be Deferred in ML20196F5471999-06-22022 June 1999 Application for Amends to Licenses NPF-39 & NPF-85,change Request 99-01-0,to Revise TS to Delete Surveillance Requirement 4.4.1.1.2 & Associated TS Administrative Controls Section 6.9.1.9.h ML20195G0421999-06-0707 June 1999 TS Change Request 98-09-0 for Licenses NPF-39 & NPF-85, Revising TS Section 3/4.4.3, RCS Leakage,Leakage Detection Systems, by Clarifying Action Statement Re Inoperative Reactor Coolant Leakage Detection Systems ML20195E7521999-06-0707 June 1999 TS Change Request 91-08-01 to License NPF-39,reflecting Permanently Deactivated Instrument Reference Leg Isolation Valve HV-61-102 in TS Table 3.6.3-1, Primary Containment Isolation Valves & Associated Notations ML20195B8361999-05-26026 May 1999 TS Change Request 99-02-0 for Licenses NPF-39 & NPF-85, Revising TS Section 4.1.3.5.b by Removing & Relocating Control Rod Scram Accumulators Alarm Instrumentation to UFSAR & Revising TS Section 3.1.3.5 ML20207L6561999-03-11011 March 1999 TS Change Request 98-07-2 for License NPF-85,revising MCPR Safety Limit Contained in TS Section 2.1, Safety Limits. Proprietary & non-proprietary Info Re Cycle Specific SLMCPR for Lgs,Unit 2 Cycle 6,encl.Proprietary Info Withheld ML20199G1651999-01-12012 January 1999 TS Change Request 98-08-0 to Licenses NPF-39 & NPF-85, Proposing Rev to TS Section 3/4.4.2 & TS Bases Sections B 3/4.4.2,B 3/4.5.1 & B 3/4.5.2.Supporting TSs & Proprietary & non-proprietary Trs,Encl.Proprietary Info Withheld ML20199A6861999-01-0404 January 1999 TS Change Request 97-01-01 to Licenses NPF-39 & NPF-85, Revising Administrative Section on Controlled Access to High Radiation Areas & Rept Dates for Listed Repts ML20155H6311998-10-30030 October 1998 Application for Amends to Licenses NPF-39 & NPF-85, Respectively,Revising TS Surveillance Requirements 4.8.4.3.b.1,4.8.4.3.b.2 & 4.8.4.3.b.3 in Order to Reflect Relay Setpoint Calculation Methodology ML20154Q8781998-10-15015 October 1998 TS Change Request 97-04-0 to Licenses NPF-39 to NPF-85, Adding New TS Section & TS Bases Section to Incorporate Special Test Exception to Allow Rc Temp Greater than 200 F During IST & Hydrostatic Testing ML20151Z4541998-09-14014 September 1998 TS Change Request 98-04-2 to License NPF-85,revising TS Table 4.4.6.1.3-1 Re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules.Ge Rept GE-NE-B1100786,encl ML20151V0731998-09-0404 September 1998 TS Change Request 96-23-0 to Licenses NPF-39 & NPF-85, Revising TS Pages to Ensure Fidelity Between TS Pages & 970324 Submittal ML20236L5151998-07-0202 July 1998 Supplemental Application for Amend to Licenses NPF-39 & NPF-85,consisting of TS Change Request 96-06-0,modifying Appearance of Unit 1,FOL Page 8 ML20202G7591998-02-0909 February 1998 Application for Amend to License NPF-39,revising TS Section 2.1, Safety Limits, to Revise Minimum Critical Power Ratio Safety Limit.Proprietary Supporting Info Withheld (Ref 10CFR2.790) ML20199G7701998-01-27027 January 1998 Application for Amends to Licenses NPF-39 & NPF-89,removing Maximum Isolation Time for HPCI Turbine Exhaust Containment Isolation Valve HV-055-1(2)F072 from Ts.Change Request 98-01-0 & marked-up TS Encl ML20198M7551998-01-12012 January 1998 TS Change Request 97-02-1 to License NPF-39,revising TS Table 4.4.6.1.3-1 to Change Withdrawal Schedule for First Capsule to Be Withdrawn from 10 Effective Full Power Yrs to 15 Efpy.Ge Rept GE-NE-B1100786-01,Rev 1 Encl ML20212D1761997-10-24024 October 1997 Application for Amend to License NPF-39,revising TS Section 3/4.1.3.6,to Exempt Control Rod 50-27 from Coupling Test for Remainder of Cycle 7,provided Certain Conditions Are Met ML20216H0931997-09-0808 September 1997 Application for Amends to Licenses NPF-39 & NPF-85, Supplementing Changes Request 96-06-0 by Adding Three Addl TS Pages Containing Typo Errors Discovered Since 970225 Submittal ML20210T9141997-09-0202 September 1997 TS Change Request 96-20-0 to Licenses NPF-39 & NPF-85, Revising TS Section 4.0.5 & Bases Sections B 4.0.5 & B 3/4.4.8,re SRs Associated W/Isi & Inservice Testing of ASME Code Class 1,2 & 3 Components ML20137X7931997-04-0909 April 1997 TS Change Request 96-24-0 to Licenses NPF-39 & NPF-85, Deleting Requirement to Correct Specific Gravity Values Based on Electrolyte Battery State of Charge ML20137G6611997-03-24024 March 1997 Application for Amends to Licenses NPF-39 & NPF-85,deleting Drywell & Suppression Chamber Purge Sys Operational Time Limit & Adding SR to Ensure Purge Sys Large Supply & Exhaust Valves Are Closed as Required ML20135D0861997-02-25025 February 1997 Application for Amends to Licenses NPF-39 & NPF-85, Reflecting Name Change from PA Electric Co to PECO Energy Co ML20135F0911996-12-0606 December 1996 Application for Amend to License NPF-85,revising TS 2.1 to Change Minimum Critical Power Ratio Safety Limit ML20135A3841996-11-25025 November 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS SR 4.8.1.1.2.e.2 & Supporting TS Bases Section 3/4.8,to Clarify Requirements Associated W/Single Load Rejection Testing of EDGs ML20128N7551996-09-27027 September 1996 Application for Amends to Licenses NPF-39 & NPF-85, Requesting Rev to Increase Reactor Enclosure Secondary Containment Maximum Inleakage Rate ML20116L2551996-08-0808 August 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS Sections 3/4.3.1,3/4.3.2,3/4.3.3 & Associated TS Bases Sections 3/4.3.1 & 3/4.3.2 to Eliminate Selected Response Time Testing Requirements ML20116H6161996-08-0505 August 1996 Application for Amend to License NPF-85,revising TS Section 2.1, Safety Limits, to Revise Min Critical Power Ratio Safety Limit ML20116E5981996-08-0101 August 1996 Application for Amend to License NPF-85,revising TS Section 3/4.4.4.6 to Reflect Addition of Two Hydroset Curves Effective for 6.5 & 8.5 Effective Full Power Years,To Existing Pressure-Temp Operating Limit for LGS Unit 2 ML20115A9071996-06-28028 June 1996 Application for Amend to Licenses NPF-39 & NPF-85 to Perform Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B ML20117H2441996-05-20020 May 1996 TS Change Request 96-12-0 to Licenses NPF-39 & NPF-85, Revising TS Sections 3/4.4.9.2,3/4.9.11.1,3/4.9.11.2 & Associated TS Bases 3/4.4.9 & 3/4.9.11 to More Clearly Describe,Rhr Sys Shutdown Cooling Mode of Operation ML20117D7451996-05-0303 May 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS SRs to Change Surveillance Test Frequency for Performing Flow Testing of SGTS & RERS from Monthly to Quarterly ML20107M5061996-04-25025 April 1996 TS Change Request 95-08-0 to Licenses NPF-39 & NPF-85, Relocating TS 3/4.7.7 Re Traversing in-core Probe LCO ML20101L9111996-03-29029 March 1996 Application for Amends to Licenses NPF-39 & NPF-85, Respectively,Revising TS SR 4.5.1.d.2.b to Delete Requirement to Perform Functional Testing of ADS Valves as Part of start-up Testing Activities ML20095K4801995-12-22022 December 1995 Application for Amend to Licenses NPF-39 & NPF-85,increasing Drywell & Suppression Chamber Purge Sys Operating Time Limit from 90 H Each 365 Days to 180 H Each 365 Days ML20092J3941995-09-18018 September 1995 TS Change Request 95-01-0 to Licenses NPF-39 & NPF-85, Revising TS Table 4.3.1.1-1, RPS Instrumentation SRs to Reflect Change in Calibr Frequency for LPRM Signal from Every 1,000 EFPH to Every 2,000 Megawatt Days Per Std Ton ML20092J3181995-09-14014 September 1995 Application for Amends to Licenses NPF-39 & NPF-85,revising TS to Remove Secondary Containment Isolation Valve Tables ML20087C9451995-08-0101 August 1995 TS Change Request 95-12-0 Revising TS Section 3/4.9.1, to Provide Alternate Actions to Allow Continuation of Core Alterations in Event Certain RMCS & Refueling Interlocks Are Inoperable ML20086S5981995-07-28028 July 1995 Application for Amends to Licenses NPF-39 & NPF-85,revising TS Table 4.3.1.1-1,to Reflect Changes to Surveillance Test Frequency Requirements for Various RPS Instrumentation ML20086U4821995-07-28028 July 1995 TS Change Request 94-28-0 to Licenses NPF-39 & NPF-85, Revising TS SR & Deleting Specific Requirements to Perform Surveillances Prior to Beginning or Resuming Core Alterations or CR Withdrawal Assoc W/Refueling Activities ML20086U4361995-07-28028 July 1995 TS Change Request 95-09-0 to Licenses NPF-39 & NPF-8, Revising Ts,By Deleting Operability & SR Involving Secondary Containment Diffrential Pressure Instrumentation ML20086T6061995-07-28028 July 1995 TS Change Request 95-13-0 of License NPF-39 & NPF-85, Requesting Change to Ts,To Eliminate TS Requirement to Perform 10CFR50,App J,Type C,Hydrostatic Testing on Certain Valves ML20086A1631995-06-23023 June 1995 Application for Amend to License NPF-85,consisting of Change Request 95-07-2,extending AOT to Allow Adequate Time to Install Isolation Valves & cross-ties on ESW & RHRSW Sys to Facilitate Future Insps or Maint ML20085M8811995-06-20020 June 1995 Application for Amend to Licenses NPF-39 & NPF-85,consisting of Change Request 95-06,requesting one-time Schedular Exemption from 10CFR50,App J, Primary Containment Leakage Testing for Water-Cooled Power Reactors ML20085M9171995-06-19019 June 1995 Application for Amend to License NPF-39,consisting of Change Request 95-03,revising TS Section 2.1, Safety Limits, to Change MCPR Safety Limit,Due to Use of GE13 Fuel Product Line ML20084Q9241995-06-0505 June 1995 Application for Amends to Licenses NPF-39 & NPF-85, Consisting of TS Change Request 94-49-0,revising TS Section 3/4.1.5, SLCS to Remove Min Flow Rate Requirement for SLCS Pumps ML20083R0031995-05-19019 May 1995 Application for Amends to Licenses NPF-39 & NPF-85, Consisting of Change Request 95-02,revising TS Table 3.3.3-3, ECCS Response Times to Reflect Value of 60 Seconds for HPCI Sys Response Time Instead of 30 Seconds ML20082J4001995-04-0606 April 1995 Application for Amends to Licenses NPF-39 & NPF-85, Consisting of TS Change Requests 94-51 Delete Independent Tech Review Section from TS, 94-52 Delete Nrb Review Section from TS, 94-53 Delete Nrb Audit Section from Ts 1999-09-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F0941999-10-14014 October 1999 Application for Amends to Licenses DPR-39 & DPR-85,to Revise TS Sections 2.2 & 3.0/4.0 to Support Mod P000224 Which Will Install New Power Range Neutron Monitoring Sys & Incorporate long-term thermal-hydraulic Stability Solution Hardware ML20216J3341999-09-27027 September 1999 Supplements Application for Amends to Licenses NPF-39 & NPF-45,to Modify Appearance of TS Page 3/4 4-8 as Typo Was Identified in Section 3.4.3.1 of Ts.Corrected TS Page,Encl ML20212H5521999-09-27027 September 1999 Application for Amends to Licenses NPF-39 & NPF-85,revising TS to Clarify Several Administrative Requirements,Deleting Redundant Requirements & Correcting Typos ML20212F9521999-09-20020 September 1999 Application for Amend to License NFP-39,requesting Issuance of TS Change Request 98-08-0 Re Increase in Allowable as- Found Main Steam SRV Setpoint Tolerance.Util Had Originally Requested That Subject TS Change Be Deferred in ML20196F5471999-06-22022 June 1999 Application for Amends to Licenses NPF-39 & NPF-85,change Request 99-01-0,to Revise TS to Delete Surveillance Requirement 4.4.1.1.2 & Associated TS Administrative Controls Section 6.9.1.9.h ML20195E7521999-06-0707 June 1999 TS Change Request 91-08-01 to License NPF-39,reflecting Permanently Deactivated Instrument Reference Leg Isolation Valve HV-61-102 in TS Table 3.6.3-1, Primary Containment Isolation Valves & Associated Notations ML20195G0421999-06-0707 June 1999 TS Change Request 98-09-0 for Licenses NPF-39 & NPF-85, Revising TS Section 3/4.4.3, RCS Leakage,Leakage Detection Systems, by Clarifying Action Statement Re Inoperative Reactor Coolant Leakage Detection Systems ML20195B8361999-05-26026 May 1999 TS Change Request 99-02-0 for Licenses NPF-39 & NPF-85, Revising TS Section 4.1.3.5.b by Removing & Relocating Control Rod Scram Accumulators Alarm Instrumentation to UFSAR & Revising TS Section 3.1.3.5 ML20207L6561999-03-11011 March 1999 TS Change Request 98-07-2 for License NPF-85,revising MCPR Safety Limit Contained in TS Section 2.1, Safety Limits. Proprietary & non-proprietary Info Re Cycle Specific SLMCPR for Lgs,Unit 2 Cycle 6,encl.Proprietary Info Withheld ML20199G1651999-01-12012 January 1999 TS Change Request 98-08-0 to Licenses NPF-39 & NPF-85, Proposing Rev to TS Section 3/4.4.2 & TS Bases Sections B 3/4.4.2,B 3/4.5.1 & B 3/4.5.2.Supporting TSs & Proprietary & non-proprietary Trs,Encl.Proprietary Info Withheld ML20199A6861999-01-0404 January 1999 TS Change Request 97-01-01 to Licenses NPF-39 & NPF-85, Revising Administrative Section on Controlled Access to High Radiation Areas & Rept Dates for Listed Repts ML20155H6311998-10-30030 October 1998 Application for Amends to Licenses NPF-39 & NPF-85, Respectively,Revising TS Surveillance Requirements 4.8.4.3.b.1,4.8.4.3.b.2 & 4.8.4.3.b.3 in Order to Reflect Relay Setpoint Calculation Methodology ML20154Q8781998-10-15015 October 1998 TS Change Request 97-04-0 to Licenses NPF-39 to NPF-85, Adding New TS Section & TS Bases Section to Incorporate Special Test Exception to Allow Rc Temp Greater than 200 F During IST & Hydrostatic Testing ML20151Z4541998-09-14014 September 1998 TS Change Request 98-04-2 to License NPF-85,revising TS Table 4.4.6.1.3-1 Re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules.Ge Rept GE-NE-B1100786,encl ML20151V0731998-09-0404 September 1998 TS Change Request 96-23-0 to Licenses NPF-39 & NPF-85, Revising TS Pages to Ensure Fidelity Between TS Pages & 970324 Submittal ML20236L5151998-07-0202 July 1998 Supplemental Application for Amend to Licenses NPF-39 & NPF-85,consisting of TS Change Request 96-06-0,modifying Appearance of Unit 1,FOL Page 8 ML20247M6891998-05-14014 May 1998 Amend 128 to License NPF-39,documenting NRC Staff Approval of Implementation of Plant Mod to Support Installation of Replacement Suction Strainers for ECCS at Plant,Unit 1 ML20217Q5001998-05-0404 May 1998 Amend 127 to License NPF-39,revising Minimal Critical Power Ratio Safety Limits for Operation Cycle 8 ML20217M0731998-03-31031 March 1998 Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively, Revising LGS Units 1 & 2 TS Section 4.0.5 & Bases Sections B 3/4.4.8 Re Surveillance Requirements Associated W/Isi & IST ML20202G7591998-02-0909 February 1998 Application for Amend to License NPF-39,revising TS Section 2.1, Safety Limits, to Revise Minimum Critical Power Ratio Safety Limit.Proprietary Supporting Info Withheld (Ref 10CFR2.790) ML20199G7701998-01-27027 January 1998 Application for Amends to Licenses NPF-39 & NPF-89,removing Maximum Isolation Time for HPCI Turbine Exhaust Containment Isolation Valve HV-055-1(2)F072 from Ts.Change Request 98-01-0 & marked-up TS Encl ML20198M7551998-01-12012 January 1998 TS Change Request 97-02-1 to License NPF-39,revising TS Table 4.4.6.1.3-1 to Change Withdrawal Schedule for First Capsule to Be Withdrawn from 10 Effective Full Power Yrs to 15 Efpy.Ge Rept GE-NE-B1100786-01,Rev 1 Encl ML20212D1761997-10-24024 October 1997 Application for Amend to License NPF-39,revising TS Section 3/4.1.3.6,to Exempt Control Rod 50-27 from Coupling Test for Remainder of Cycle 7,provided Certain Conditions Are Met ML20216H0931997-09-0808 September 1997 Application for Amends to Licenses NPF-39 & NPF-85, Supplementing Changes Request 96-06-0 by Adding Three Addl TS Pages Containing Typo Errors Discovered Since 970225 Submittal ML20210T9141997-09-0202 September 1997 TS Change Request 96-20-0 to Licenses NPF-39 & NPF-85, Revising TS Section 4.0.5 & Bases Sections B 4.0.5 & B 3/4.4.8,re SRs Associated W/Isi & Inservice Testing of ASME Code Class 1,2 & 3 Components ML20137X7931997-04-0909 April 1997 TS Change Request 96-24-0 to Licenses NPF-39 & NPF-85, Deleting Requirement to Correct Specific Gravity Values Based on Electrolyte Battery State of Charge ML20137G6611997-03-24024 March 1997 Application for Amends to Licenses NPF-39 & NPF-85,deleting Drywell & Suppression Chamber Purge Sys Operational Time Limit & Adding SR to Ensure Purge Sys Large Supply & Exhaust Valves Are Closed as Required ML20135D0861997-02-25025 February 1997 Application for Amends to Licenses NPF-39 & NPF-85, Reflecting Name Change from PA Electric Co to PECO Energy Co ML20135F0911996-12-0606 December 1996 Application for Amend to License NPF-85,revising TS 2.1 to Change Minimum Critical Power Ratio Safety Limit ML20135A3841996-11-25025 November 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS SR 4.8.1.1.2.e.2 & Supporting TS Bases Section 3/4.8,to Clarify Requirements Associated W/Single Load Rejection Testing of EDGs ML20128N7551996-09-27027 September 1996 Application for Amends to Licenses NPF-39 & NPF-85, Requesting Rev to Increase Reactor Enclosure Secondary Containment Maximum Inleakage Rate ML20116L2551996-08-0808 August 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS Sections 3/4.3.1,3/4.3.2,3/4.3.3 & Associated TS Bases Sections 3/4.3.1 & 3/4.3.2 to Eliminate Selected Response Time Testing Requirements ML20116H6161996-08-0505 August 1996 Application for Amend to License NPF-85,revising TS Section 2.1, Safety Limits, to Revise Min Critical Power Ratio Safety Limit ML20116E5981996-08-0101 August 1996 Application for Amend to License NPF-85,revising TS Section 3/4.4.4.6 to Reflect Addition of Two Hydroset Curves Effective for 6.5 & 8.5 Effective Full Power Years,To Existing Pressure-Temp Operating Limit for LGS Unit 2 ML20115A9071996-06-28028 June 1996 Application for Amend to Licenses NPF-39 & NPF-85 to Perform Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B ML20117H2441996-05-20020 May 1996 TS Change Request 96-12-0 to Licenses NPF-39 & NPF-85, Revising TS Sections 3/4.4.9.2,3/4.9.11.1,3/4.9.11.2 & Associated TS Bases 3/4.4.9 & 3/4.9.11 to More Clearly Describe,Rhr Sys Shutdown Cooling Mode of Operation ML20117D7451996-05-0303 May 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS SRs to Change Surveillance Test Frequency for Performing Flow Testing of SGTS & RERS from Monthly to Quarterly ML20107M5061996-04-25025 April 1996 TS Change Request 95-08-0 to Licenses NPF-39 & NPF-85, Relocating TS 3/4.7.7 Re Traversing in-core Probe LCO ML20101L9111996-03-29029 March 1996 Application for Amends to Licenses NPF-39 & NPF-85, Respectively,Revising TS SR 4.5.1.d.2.b to Delete Requirement to Perform Functional Testing of ADS Valves as Part of start-up Testing Activities ML20095K4801995-12-22022 December 1995 Application for Amend to Licenses NPF-39 & NPF-85,increasing Drywell & Suppression Chamber Purge Sys Operating Time Limit from 90 H Each 365 Days to 180 H Each 365 Days ML20092J3941995-09-18018 September 1995 TS Change Request 95-01-0 to Licenses NPF-39 & NPF-85, Revising TS Table 4.3.1.1-1, RPS Instrumentation SRs to Reflect Change in Calibr Frequency for LPRM Signal from Every 1,000 EFPH to Every 2,000 Megawatt Days Per Std Ton ML20092J3181995-09-14014 September 1995 Application for Amends to Licenses NPF-39 & NPF-85,revising TS to Remove Secondary Containment Isolation Valve Tables ML20087C9451995-08-0101 August 1995 TS Change Request 95-12-0 Revising TS Section 3/4.9.1, to Provide Alternate Actions to Allow Continuation of Core Alterations in Event Certain RMCS & Refueling Interlocks Are Inoperable ML20086S5981995-07-28028 July 1995 Application for Amends to Licenses NPF-39 & NPF-85,revising TS Table 4.3.1.1-1,to Reflect Changes to Surveillance Test Frequency Requirements for Various RPS Instrumentation ML20086U4821995-07-28028 July 1995 TS Change Request 94-28-0 to Licenses NPF-39 & NPF-85, Revising TS SR & Deleting Specific Requirements to Perform Surveillances Prior to Beginning or Resuming Core Alterations or CR Withdrawal Assoc W/Refueling Activities ML20086U4361995-07-28028 July 1995 TS Change Request 95-09-0 to Licenses NPF-39 & NPF-8, Revising Ts,By Deleting Operability & SR Involving Secondary Containment Diffrential Pressure Instrumentation ML20086T6061995-07-28028 July 1995 TS Change Request 95-13-0 of License NPF-39 & NPF-85, Requesting Change to Ts,To Eliminate TS Requirement to Perform 10CFR50,App J,Type C,Hydrostatic Testing on Certain Valves ML20086A1631995-06-23023 June 1995 Application for Amend to License NPF-85,consisting of Change Request 95-07-2,extending AOT to Allow Adequate Time to Install Isolation Valves & cross-ties on ESW & RHRSW Sys to Facilitate Future Insps or Maint ML20085M8811995-06-20020 June 1995 Application for Amend to Licenses NPF-39 & NPF-85,consisting of Change Request 95-06,requesting one-time Schedular Exemption from 10CFR50,App J, Primary Containment Leakage Testing for Water-Cooled Power Reactors ML20085M9171995-06-19019 June 1995 Application for Amend to License NPF-39,consisting of Change Request 95-03,revising TS Section 2.1, Safety Limits, to Change MCPR Safety Limit,Due to Use of GE13 Fuel Product Line 1999-09-27
[Table view] |
Text
l Station Support Department A 10 CFR 50.90 v --
PECO NUCLEAR nw -u c-A Unit of PECO Energy NvNItNsYe January 27, 1998 Docket Nes. 50-352 50-353 License Nos. NPF-39 i NPF-85 U.S. Nuclear Regulatory Comission ATTN: Document Control Desk Washington, DC 20555
Subject:
Limerick Generating Station, Units 1 and 2 Technical Specifications Change Request No. 98-01-0 Deletion of HPCI Turbine Exhaust Valve Isolation Time from Technical Specifications
Dear NRC Officials:
PECO Energy Company is submitting Technical Specifications (TS) Change Request No. 98-0.-0, in accordance with 10 CFR 50.90, requesting a change to TS (i.e., Appendix A) of operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2.
The proposed changes will remove the maximum isolation time for the High Pressure Coolant Injection (HPCI) Turbine Exhaust Containment Isolation Valve "HV-055-1(2)F072" from TS.
Information supporting this TS Change Request is contained in Attachment I to this letter, and copies of the " marked-up" Technical Specifica- I tions pages are contained.in Attachment 2. This information is being ii submitted under affirmation, and the required affidavit is enclosed.
We request that, if approved, the changes be issued as soon as possible, , i}
and become effective within 30 days of issuance.
a 0 C'7 IllIllI$l}l\ \\l)\ll)l[
9902040342 990127 PDR ADOCK 05000352
-P PDR g
. January .27,- 1997.-
.Page 2 k
If you have any questions, please do not hesitate to contact us.
Very truly-yours,
- b. AA,f ,
G. A. Hunger, r.
Director - Licensing Attachments
- Enclosure cc: H. J. Miller,' Administrator, Region I, USNRC (w/ Attachments, Enclosure).
A. L. Burritt, USNRC Senior Resident Inspector, LGS R. R. Janati, PA Bureau of Radiation Protection " "
n:
. s:.
,;.n- -- ...n ., , ,, , ,. - . - , -,
COMMONWEALTH OF PENNSYLVANIA :
- -ss COUNTY OF PHILADELPHIA : i J.- B. . Cotton, being first duly sworn, deposes and says: That he is Vice President of PECO Energy Company, the Applicant-herein; that he has read the enclosed Technical Specifications Change Request No. 98-01-0 " Deletion of HPCI Turbine Exhaust Valve Isolation Time from Technical Specifications," for Limerick Generating Station, Ur.!', I and Unit 2, Facility Operating License Nos. NPF-39 and NPF-85, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
r/w ,
/ Afice President Subscribed and sworn to before me this JM ' day o 1998.
d.kmu Notary public-wrARIAL stAL CAMOL A.WALTON NM M uvY urIeNy b ,
1
l;N i of' ..--- .
J
. ' 4- 'i
- ATTACHMENT LIMERICK GENERATING STATION m,
UNITS 1 AND 2 DOCKET.NOS.
50-352
- 50-353 LICENSE NOS.
NPF-39 NPF-85
" Deletion of HPCI Turbine Exhaust Valve Isolation Time from Technical Specifications" Information Supporting Changes.- 5 Pages c-W
- f. t ,
DISCUSSION AND DESCRIPTION OF THE PROPOSED CHANGES
-PECO Energy Company (PECO Energy) is requesting-Limerick Generating Station (LGS) Technical Specifications (TS) changes which will revise TS Table 3.6.3-1
'Part A - Primary Containment Isolation valves,' by removing the numerical maximum stroke time for penetration 210 "HPCI Turbine Exhaust" and adding a notation that the isolation time is not required.
SAFETY ASSESSMENT The maximum isolation time for the HPCI Turbine Exhaust Valve is not a criteria for safety limits delineated in 10 CFR 50.36 ( c )(1) nor does it mect the criteria for Limiting Conditions for Operation delineated in 10CFR50.36 ( c )(2)(ii)(A thru D). In addition, NRC Generic Letter 91-08
" Removal of Component Lists From Technical Specificatior.s," states that "The removal of valve stroke times that are included in some plant TS would not-alter the TS requirement to verify that the valve stroke times are within their limits. Therefore, removal of these closure times is acceptable."
Removal of- specific maximum isolation times and closure stroke verification for remote manual isolation valves from TS is consistent with Improved Standard Technical Specifications (NUREG -1433, Rev.1). Improved Standard TS generic Primary Containment _ Isolation Valve (PCIV) surveillance requirements are-limited to verifying isolation stroke times only for PCIVs receiving automatic isolation signals.
The subject valve: will continue to be included in the Inservice Test (IST)
Program (ML-008) and the Limerick Generic Letter 96-05 Motor Operated Valve (MOV)-Program and be subject to periodic verification testing involving-diagnostic testing. This testing will confirm the actuator and valve performance nargins established under the Generic Letter 89-10 MOV Program.
Complete failure of the valve to isolate has been evaluated to be of negligible safety significance. This conclusion is based on the established long term water seal associated with the penetration and the Seismic Category I design of the HPCI system. In addition, installed outboard check valve 055-
'1(2)f021-will function to prevent gross suppression pool leakage through the HPCI turbine exhaust line.
The following discussions describe the functions of valve HV-055-1(2)F072.
The -' design considerations and specific discussions were derived from the current Limerick Safety Analysis-Report (SAR) and the Limerick TS.
The High Pressure Coolant Injection (HPCI) Valve "HV-055-1(2)F072" is a -
12 inch, normally open valve- that provides remote manual isolation to containment penetration 210. The subject valve is a remote manual primary containmut isolation valve (PCIV) which is not required to respond to any analyzed accidents or transients.
Maximum isolatirn time for this valve is not a safety analysis limit associated with any DBA accident (LOCA/ LOOP), station blackout or-fire safe shutdown analysis. The maximum time established for this valve is based on standard valve design practices and is used to establish Inservice Test (IST) 1
Lx
.. W _,,
.: w l-
. Program _ performance' criteria.- The LGS IST program will still-maintain an=IST
. .. basis maximum time for HV-055-1(2)F072 to establish action and= alert levels-
- for
- valve performance monitoring.1These performance-based values, in -
l conjunction with diagnostic: test criteria, are used for motor operated valve (MOV)L eaterialicondition monitoring and trending. - Therefore, eliminating' the subject maximum isolation time requirement from TS will not increase--the-iprobability of-malfunction of the valve since the principal means of; monitoring valve _ performance remains unchanged.
Tliis: v^alv'e'is capable of- performing the remote manual function described-in
'the SAR. The remote manual isolation design is used where the penetration is water sealed long tere following an. accident and the system that the valve is isolating is a closed ioop safety system which is in service following an accident.1This' general design-is ' described in the LGS Updated Final Safety -
Analysis Report-(UFSAR)'Section 6.2.4.3.1.3.1. - Section 6.2.4.3.1.3.1.4 of_the UFSAR describes the isolation features of this-specific penetration. This-section also describes a checi valve 055-1(2)F021,- upstream of HV-055-
-1(2)F072 which functions to prevent gross suppression pool water leakage to the HPCI turbine eyhaust line. Given the assured 30' day water seal and design
' features of the HPCI system, containment leakage through this valve and:
1 associated penetration _is not associated with any accident or radiol.ogical_
' release' analysis. Since the exhaust lines are submerged beneath the minimum--
-Suppres , ton Pool water level and the HPCI system is a closed system outside Primary *ontainment, containment bypass-leakage is not a concern.
HV-055-1(2)f072 provides a' system design feature to isolate a potential containment leak path. As' described in LGS UFSAR Section 6.2.4.3.1.3.1, any leakage through this path will be monitored and contained in the HPCI pump room. This turbine exhaust line is classified as a moderate energy fluid-system per the criteria of UFSAR_ Section 3.6.1.2. Per LGS UFSAR Section 3.6.1.1, a crack in this. line-is the only- postulated event. Pipe breaks of the applicable piping are beyond design. bases. Leakage of this line can be remotely isolated from the control room if a pipe crack occurred during normal-plant operation. Manual isolation of HV-055-1(2)F072 occurs procedurally when HPCI is no longer._needed and when plant parameters indicate there-is leakage into the HPCI room. This valve would only be manually closed under events where there was a need to' isolate HPCI from suppression pool water inventory.
based on plant indications'which are entry conditions for LGS Special Event procedure SE 4-1 " Reactor Enclosure Flooding", LGS Transient Response
-Implementation Plan procedures T-250 ' Remote manual Primary Containment Isolations," or.T-260 " Reactor Vessel Venting." Each of these procedures may ultimately require isolation of the-HPCI turbine exhaust line by manually closing:HV-055-1(2)F072. - Given that these procedurally mandated valve
- isolations are all via remote manual .means, valve isolation time is not-a -
Tcritical parameter requiring: specific acceptance criteria.
.Thit activiti ~doesLnot- affect'the ability'of the valve to isolate the leak or
( :to containia leak- M LGS UFSAR . Sections -6.2.4;3.1.3.1. and 6.2.4.3.1.3.1.C provide water seal penetration-general: design- and specific design details, respectively...These-sections;' describe that there are-multiple-barriers to the irelease of- suppression-pool water, and this valve provides_ one method to '
cisolate? potential leakage. 'As a result, the valve wil_1 function to isolate lany potential 1eak, - but=the failure of the valve is already analyzed by s-x< '
~
2 b
. k
ik- , . . . - .- .m -
i general plant design criteria. HV-055-1(2)F072 has no specific seat leakage
. integrity requirements as referenced in: TS Table 3.6.3-1 notation number 35 for Unit I and notation number 36 for Unit 2; IST Specification ML-008; and LGS UFSAR Table 6.2-17.
The suppression pool inventory is also important to safety. The integrity of the suppression pool water supply is ensured by the general plant design of water sealed penetrations both with and without successful isolation of this single remote manual isolation valve. The penetration is water sealed from the containment atmosphere and there is no driving force for a water leak without containment being pressurized. This is the expected condition under which LGS Special Event procedure SE 4-1 " Reactor Enclosure flooding" is entered.
Following an accident when HPCI is no longer needed, containment may be slightly pressurized to 10 psig or less (reference UFSAR Figure 6.2.-7),
causing suppression pool water to pre:s into the HPCI exhaust line. Check valve 055-1(2)f021 provides the normal and immediate leakage barrier as described in UFSAR Section 6.2.4.3.1.3.1.4. A gross release of suppression pool water is prevented by HV-055-1(2)F072, 055- 1(2)F021 check valve, an intact HPCI exhaust line, or ultimately by the containment of water within the HPCI room.
The LGS UFSAR Table 6.2-17 describes that the stroke time of this valve is nominal and not critical for High Energy Line Break (HELB), accident release, or Emergency Core Cooling System (ECCS) performance concerns. LGS UFSAR Section 6.2.4.2 indicates that valves having critical stroke times to limit accident releases, to ensure proper operation of ECCS systems or to mitigate a HELB event are annotated on this table. HV-055-1(2)F072 has no special annotatior.s, only reference to a standard stroke time.
Information Suonortina a Findina of No Sionificant Hazards Consideratios We have concluded that the proposed changes to the Limerick Generating Station, Unit 1 and Unit 2, Technical Specifications (TS) which will revise TS Table 3.6.3-1 and its natations, do not involve a Significant Hazards Consideration. In support of this determination, an avaluation of each of the three (3) standards set forth in 10 CFR 50.92 is provided below.
- 1. The orocosed Technical Sorcifications chanaes do not involve a sianificant increase in the probability or conseouences of an accident previously evaluated.
Changes to Technical Specifications regarding the removal of the High Pressure Coolant Injection (HPCI) Turbine Exhaust Valve maximum stroke times do not change the frequency or consequences of any accident previously evaluated.
The proposed changes do not change the function of the HPCI system nor any cafety. function of the valve as described in the SAR. The isolation stroke times are not limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. The stroke times do not detect or indicate an abnormal degradation of the reactor coolant pressure boundary. The stroke times i
3
are not a process variable, design feature, or operating restriction
.. . that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The stroke times are not part of a component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that "ither assumes the failure of or presents a challenge to the integrity of a fission product barrier. The stroke times are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be signtficant to public 1ealth and safety.
Therefore, the changes will not increase the probability or consequences of an accident previously evaluated.
- 2. The oronosed Technical Soecifications chanaes do not create the gossibility of a new or different kind of accident from any accident Dreviously evaluated.
The proposed Technical Specifications changes regarding the removal of the High Pressure Coolant Injection (HPCI) Turbine Exhaust Valve maximum stroke times do not affect the probability of a malfunction of equipment important to safety. Safety related HPCI system operation occurs with the subject valve passively open. This valve would only be manually closed under events where there was a need to isolate the HPCI system from the suppression pool. The manual closing of the valve may occur under these events and is controlled by station procedures. Given that these procedurally mandated valve isolations are all via remote manual means, valve isolation time is not a critical parameter requiring specific acceptance criteria.
The Inservice Testing (IST) Program will still maintain an IST program basis maximum stroke time for HV-055-1(2)f072 to establish action and alert levels for valve performance monitoring. These performance based values, in conjunction with diagnostic test criteria, are used for motor operated valve material condition monitoring and trending. Therefore, eliminating the subject maximum isolation time requirement from TS will not increase the probability of malfunction of the valve since the d
principal means of monitoring valve performance remains unchanged.
Therefore, these changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The oroposed Technical Soecifications chanaes do not involve a sianificant reduction in a maroin of safety.
There is no defined margin of safety for remote manual valve isolation times discussed in Technical Specification Bases. In addition, the valve maximum stroke time will be retained in the IST program.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
)
4
,.l- ,
INFORMATION SUPPORTING AN ENVIRONMENTAL-ASSESSMENT ,
' An Environmental-Assessment is not required for the Technical Specifications changes proposed by this TS Change Request because the requested changes to the Limerick Generating Station, Unit 1.and Unit 2, TS e m form to the criteria for " actions eligible for categorical exclusion," as speo;fied in 10 CFR 51.22 (c) (9). The requested changes will have no impact on the environment. The proposed TS changes do not involve a Significant Hazards Consideration as discussed in the preceding safety assessment section. The-proposed changes do not involve a significant-change in the types or significant increase in the amounts of any effluent that may be released offsite, in addition, the proposed TS changes do not involve a significant increase in individual or cumulative occupational radiation exposure.
CONCLUSION The Plant Operations Review Committee ano the Nuclear Review 3 card have reviewed these proposed changes to the Limerick Generating Station, Unit I and
. Unit 2, Technical Specifications, and have concluded that they do not involve an unreviewed safety question, they do not involve a Significant Hazards ,
Consideration, and they will not endanger the health and safety of the public.
5