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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] |
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PECO ENERGY Nuclear Group Headquarters 965 Chesterbrook Boulevard Wayne, PA 190874691 September 16,1994 Docket Nos. 50-352 50-353 Ucense Nos. NPF-39 NPF-85 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Umerick Generating Station, Units 1 and 2 Technical Specifications Change Request No.94-504 Gentlemen:
PECO Energy Company is submitting Technical Specifications (TS) Change Request No.
94-50-0, in accordance with 10 CFR 50.90, requesting an amendment to the TS (Appendix A) of Operating Ucense Nos. NPF-39 and NPF-85 for Umerick Generating Station (LGS), Units 1 i and 2, respectively. This proposed TS change involves revising TS Surveillance Requirement (SR) 4.7.4.e, and tho associated Bases Section 3/43.4, to extend the snubber functional testing interval from 18-months (125%) to 24-months (*25%), and to increase the sample plan size as described in SR 4.7.4.e.1 from 10% to 13.3%.
By letter dated March 3,1992, we submitted TS Change Request No. 91-04-0 requesting changes to the snubber functional testing requirements defined in TS SR 4.7.4.a to incorporate the recommendations contained in the American Society of Mechanical Engineers (ASME)
Operations and Maintenance (OM) standard for snubber testing, i.e., 'ASME/ ANSI OM-1990 Addenda to ASME/ ANSI OM-1987, Part 4, " Examination and Performance Testing of Nuclear Power Plant Dynamic Restraints (Snubbers)" It'cluded as part of our March 3,1992 submitta!,
was a request to change the snubber functional testing interval from 18-months (*25%) to 24-months (*25%) to accommodate a 24-month fuel cycle at LGS, Units 1 and 2. Subsequently, by letter dated May 11,1992, the NRC approved a majority of the changes to TS SR 4.7.4.e requested in TS Change Request 91-044 (i.e., Amendment Nos. 54 and 19). However, the NRC did not approve the requested change to extend the snubber functional testing interval from 18 to 24 months (*25%), since adequate justification was not provided to support increasing the testing interval. The NRC indicated that the reasonable expected service life for snubbers, particularly those exposed to harsh environments, is 15 years and that increasing the testing l Interval from 18 to 24 months (*25%), without proportionally increasing the sample plan size, I would not ensure that the entire population of snubbers would be tested in a 15-year period.
I The NRC suggested that one way of maintaining the 15-year testing cycle, when increasing the testing interval period, would be to increase the sample plan size. The NRC indicated that if the testing interval is being increased from 18 to 24 months (i25%), an increase in the initial sample size by one-third (1/3) from 10% to 13.3% would rnalntain the 15-year cycle.
I nn n d V U V ,'_ d 9409260162 940916 1 PDR ADDCK 05000352 '
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", ,. September 16,1994 -l Page 2 1
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Therefore, we are submitting TS Change Request 94-504 to extend the snubber functional testing interval from 18-months (i25%) to 24-months (125%) in conjunction with increasmg the initial representative sample plan size described in Section 4.7.4.e.1 from 10% to 13; 1%, as recommended by the NRC, in order to accoiT,iriodate a 24-month fuel cycle.
Information supporting this TS Change Request is contained in Attachment 1 to this letter, and .,
the proposed replacement pages for the LGS, Units 1 and 2, TS are contained in Attachment 2. l This TS Change Request is being submitted under affirmation, and the required affidavit is enclosed.
We request that, if approved, the amendments to the LGS, Urdts 1 and 2, TS be issued -j November 4,1994, and become effective immediately upon issuance of the amendments.
l 1
if you have any questions or require additional information, please do not hesitate to contact us.
_]
l Very truly yours, i h a .
G. A. Hunger, J .
Director - Licensing Attachments ;
Enclosure ,
cc: T. T. Martin, Administrator, Region I, USNRC (w/ attachments, enclosure)
N. S. Perry, USNRC Senior Resident inspector, LGS (w/ attachments, enclosure)
R. R. Janati, Director, PA Bureau of Radiological Protection (w/ attachments, enclosure) '
l l
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)
1 COMMONWEALTH OF PENNSYLVANIA :
- ss.
COUNTY OF CHESTER : l W. H. Smith,111, being first duly swom, deposes and says: !
That he is Vice President of PECO Energy Company, the Applicant herein; that he has read the foregoing Technical Specifications Change Request No.94-504 for Umerick Generating Station, Units 1 and 2, Facility Operating License Nos. NPF-39 and NPF-85, to 1) exterd the snubber functional testing interval from 18 to 24 months (i25%), and 2) increase the initial representative sample size for snubber testing from 10% to 13.3%, 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.
j7 Vice President Subscribed and sworn o befor me this ! day of p q 1994.
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Ndtary Public NotanalSea!
Erica A Santon, tetary Public TrtetnnTS.Ches:er County My Conmission E2presJuly10.1995
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ATTACHMENT 1 UMERICK GENERATING STATION UNITS 1 AND 2 Docket Nos. 50-352 50-353 Ucense Nos. NPF-39 NPF-85 i
TECHNICAL SPECIFICATIONS CHANGE REQUEST ,
i No. 94-50-0
" Revise the Technical Specifications Surveillance Requirements to ;
increase Snubber Functional Testing interval from 18-Months to 24-Months j l
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Supporting Information for Changes - 4 pages 1
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, Attachment 1 l Page 1 PECO Energy Company, Licensee under Facility Operating Ucense Nos. NPF-39 and NPF-85 for !
Limerick Generating Station (LGS), Units 1 and 2, respectively, requests that the Technical Specifications (TS) contained in Appendix A to the Operating Licenses be amended as proposed herein to revise TS Surveillance Requirement (SR) 4.7.4.6, and associated Bases Section 3/4.7.4, to extend the snubber functional testing interval from 18-months (i25%) to 24-months (*25%), and to increase the initial representative sample plan size as described in Section 4.7.4.e.1 from 10% to 13.3%. The proposed change to the TS SR is indicated by a vertical bar in the margin of TS page 3/4 7-13 and Bases page B 3/4 7-3 for Units 1 and 2. The TS paDes showing the proposed changes are contained in Attachment 2.
We request that, if approved, the TS changes proposed herein be issued by November 4,1994, and becomo effective immediately effective upon issuance of the amendments.
I This TS Change Request provides a discussion and description of the proposed TS changes, a safety assessment of the proposed TS changes, information supporting a finding of No Significant Hazards Consideration, and infoimation supporting an Environmentai Assessment.
Discussion and Descriotion of the Procosed Chanaes Currently, Limerick Generating Station (LGS), Units 1 and 2, Technical Specifications (TS) Surveillance Requirement (SR) 4 7.4.e requires that at least every 18 months a representative sample of each type of snubber shall be tened using either sample plan described in Sections 4.7.4.e.1 (i.e.,10% Plan) or 4.7.4 e.2 (i.e.,37 Plan). These two (2) snubber sampling plans are used at LGS to determine the initial population of snubbers or compensating struts that will be functionally tested during a panicular interval. -
Previously, by letter dated March 3,1992, we submitted TS Change Request No. 91-04-0 requesting changes to the snubber functional testing requirements defined in TS SR 4.7.4.e to incorporate the recommendations delineated in the American Society of Mechanical Engineers (ASME) Operations and ,
Maintenance (OM) standard for snubber testing, i.e., *ASME/ ANSI OM-1990 Addenda to ASME/ ANSI OM 1987, Part 4, " Examination and Performance Testing of Nuclear Power Plant Dynamic Restraints (Snubbers)." included as part of our March 3,1992 submittal, was a request to extend the snubber functional testing interval fiom 18-months (i25%) to 24-months (*25%) to accommodate a 24-month fuel cycle at LGS, Units 1 and 2. Subsequently, by letter dated May 11,1992, the NRC approved a ,
majority of the changes to TS SR 4.7.4.e requested in TS Change Request 91-04-0 (i.e., Amendment Nos. 54 and 19) regarding the snubber functional testing requirements. However, the NRC did not approve the requested change to increase the snubber functional testing interval from 18 to 24 months
(*25%), since adequate justification was not provided to support this increasing the testing interval. The NRC indicated that the reasonable expected service life for snubbers, particularly those exposed to harsh environments, is 15 years and that increasing the testing interval from 18 to 24 months (*25%),
without proportionally increasing the sample plan size, would not ensure that the entire population of !
snubbers would be tested in a 15-year period. The NRC suggested that one way of maintaining the 15- j year testing cycle, when increasing the testing interval period, would be to increase the size of the '
sample population. The NRC indicated that if the testing interval is being increased from 18 to 24 :
months (125%), an increase in the initial sample size of one-third (1/3) from 10% to 13.3% would maintala the 15-year cycle.
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Attachment 1 ;
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This proposed TS change involves revising TS SR 4.7.4.e. and associated Bases Section 3/4.7.4, to extend the snubber functional testing interval from 18-months (i25%) to 24-months (*25%) in conjunction with increasing the initial representative sample plan size described in 4.7.4.e.1 from 10% to l 13.3%, as recommended by the NRC, in order to accommodate a 24-month fuel cycle. This proposed l TS change wHI not modify the requirements for the sample plan described in Section 4.7.4.e.2 (i.e.,37 Plan).
Safety Assessment l I
Snubbers are installed on piping systems and components at Limerick Generating Station (LGS), Units 1 l and 2, to mitigate the effects of earthquakes and other dynamic transients, but are not used to mitigate ;
the direct effects of a Loss of Coolant Accident (LOCA) or any pipe break accident. Snubbers permit the slow movement of piping and components during heat-up and cool-down and provide rigid restraint during seismic or other dynamic events. The following events (accidents) may be considered as producing loads that could affect snubbers.
o Seismic Events 1 o Operational Basis Earthquake i o Safe Shutdown Earthquake
- o Safety Rollef Valve Lift I o Main Turbine Trip (Stop Valve Closure) o Loss of Coolant induced Loads o Pool Swell '
o Chugging o Condensation O!, wu o Drag Loads o Annulus Pressurization The LGS, Units 1 and 2, TS require that at least every 18 months a representative sample of each type of snubber shall be tested using either sample plan described in Sections 4.7.4.e.1 (i.e.,10% Plan) or l 4.7.4.e.2 (i.e.,37 Plan). The current snubber functional testing requirements were established as a result of the NRC approving changes previously requested (i.e., TS Change Request No. 91-04-0), and as documented in an NRC letter dated May 11,1992, issulng Amendment Nos. 54 and 19 to Facility j Operating License Nos. NPF-39 and NPF-85 for LGS, Units 1 and 2, respectively. ;
The 10% sample plan is used for smaller sample populations (i.e., less than approximately 400 snubbers) and will be primarily used for Failure Mode Grouping (FMG) rather than testing of the general population.
At LGS, this plan is used for selecting the initial representative sample size of compensating struts that will be functionally tested during a particular interval.
l The 37 plan (i.e., TS SR 4.7.4.e.2) uses TS Figure 4.7.4-1 to determine the need to continue testing. This !
sample plan is the methcx1 used at LGS for selecting the sample population of snubbers that will be functionally tested during a particular interval. This proposed TS change will not modify the requirements specified in TS SR 4.7.4.e.2.
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Attachment 1 Page 3 This proposed TS change involves revising TS SR 4.7.4.e to extend the snubber functional testing interval from 18 to 24 months (t25%) along with increasing the sample size described in Section 4.7.4.e.1 from 10% to 13.3%. The proposed change in the representative sample size (i.e.,10% to 13.3%) is being implemented in accordance with the NRC's recommendation as documented in its letter dated May 11,1992, and supporting Safety Evaluation Report (SER), issuing Amendment Nos. 54 and 19 to FacDity Operating License Nos. NPF-39 and NPF-85 for LGS, Units 1 and 2, respectively. Increasing the sample size, as recommended by the NRC, would ensure that the entire population of snubbers would be tested within a 15-year period.
Extending the functional testing interval from 18 months to 24 months ($25%) in conjunction with increasing the number of snubbers tested in the initial 10% sample plan to 13.3%, as proposed, will continue to maintain the same test scope ratio that currently exists. This will ensure that all of the snubbers of a given type will be tested within a 15-year period.
Lnformation Suncortina a Findina of No Stanificant Hazards Consideration We have concluded that the proposed changes to Limerick Generating Station (LGS), Units 1 and 2 Technical Specifications (TS) Surveillance Requirement (SR) 4.7.4.e to extend the snubber functional testing interval from 18 to 24 months (125%), and to increase the representative sample size as described in Section 4.7.4.e.1 from 10% to 13.3%, does not involve a Significant Hazards Consideration.
In support of this determination, an evaluation of each of the three (3) standards set forth in 10 CFR 50.92 is provided below.
- 1. The crocosed Technical Soecifications (TS) chances do not involve a slanificant increase in the orobability or consecuences of an accident oreviously evaluated.
The proposed TS changes do not require any modifications to plant systems, snubbers, or other plant equipment. The snubbers will continue to function as designed to mitigate the effects of earthquakes and other dynamic transients (e.g., main turbine trip).
Extending the snubber functional testing interval from 18 months to 24 months (i25%)
and increasing the initial sample size from 10% to 13.3%, as proposed, will continue to maintain the same test scope ratio as that which currently exists (i.e.1.5 yr./ interval @
10% snubbers / interval and 2 yr./ interval @ 13.3% snubbers / interval results in approximately 100% of all snubbers of a given type being tested within 15 years). The proposed TS change will only affect the interval between functional tests and the initial sample size population. As previously stated, LGS currently uses the 10% plan for compensating struts only, and since there are less than 10 struts per Unit, this proposed change will have a negligible impact on the number of struts in the initial sample size to be tested during a particular interval (i.e., each refueling outage). All systems and equipment important to safety that rely on snubbers will continue to function as l designed. l l
Therefore, the proposed TS changes do not involve an increase in the probability or i consequences of an accident previously evaluated. I l
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- 2. The crocosed TS chances do not create the oossiblitty of a new or different kind gf accident from any accident orevioustv evaluated.
The proposed TS changes do not invoive any physical changes to plant systems or equipment. The snubbers wul continue to function as designed to mitigate the effects of earthquakes and other dynamic transients (e.g., main turbine trip). Snubbers are not accident initiators, and function to mitigate the effects of an accident. The snubbers will continue to protect piping and equipment during dynamic events. Extending the snubber functional testing interval from 18 months to 24 months (125%) and increasing the initial sample size from 10% to 13.3%, as proposed, will continue to maintain the same test scope ratio as that which currently exists in the TS. The proposed TS changes will continue to ensure that approximately 100% of the snubbers of a given type are tested within a 15-year period.
Therefore, the proposed TS changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The orocosed TS chanaes do not involve a sianificant reduction in a marain of safety.
The bases for the TS require that all snubbers whose failure could have an adverse effect on any safety-related systems, be operable. This ensures that the structural integrity of the reactor coolant system and other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. The bases also discuss clarification and grouping of the general snubber population, snubber listing requirements, visual inspection frequency, and visual acceptance criteria. The proposed TS changes will provide for the same confidence level as that which currently exists in TS for determining snubber operability. The proposed TS changes will continue to maintain the same test scope ratio as that currently provided in the TS. . The 10% plan is used at LGS for compensating struts only, and increasing initial sample size to 13.3%, as proposed, will have a negligible effect on the number of struts functionally tested during each interval. No other aspects of the bases associated with snubber surveillance will be affected by these proposed TS changes.
Therefore, the proposed TS changes do not involve a reduction in a margin of safety.
Information Suotsina an Environmental Assessment An Environmental Assessment is not required for the changes proposed by this Change Request because the requested changes to the LGS, Units I and 2 TS conform to the criteria for " actions eligible for categorical exclusion," as specified in 10 CFR 51.22(c)(9). The requested changes will have no impact on the environment. The proposed changes do not involve a significant hazards consideration as discussed in the preceding s9ction. 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 changes do not involve a significant increase in individual or cumulative occupational radiation exposure.
ConcluslQD The Plant Operatione Review Committee and the Nuclear Review Board have reviewed the proposed changes to the LGS, Units 1 and 2, TS and have concluded that they do not involve an unreviewed safety question, and will not endanger the health and safety of the public.