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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] |
Text
_ _ ~ _ . - . . _ . _ .. - . _ - _ _ _ _ _ _ _ _ . . _ - _ . . . . . _ . . _ . .
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.- ctruen rupport o.pretm. t 10 CFR 50.90 4 1 7
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i ' PECO NUCLEAR nco m,w c , ;
A Unit of PECO Energy p7$$**'d November 25,1996 Docket Nos. 50452 ,
50453 i
License Nos.' NPF-39 NPF-85
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U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Subject. Limerick Generating Station, Units 1 and 2 Tecnnical SpecNications Change Request No. 96-22-0 Gentlemen-L PECO Energy Company is submitting Technical Specifications (TS) Change Request No.96-224, in accordance wkh 10 CFR 50.90, requesting an amendment to the TS (Appendix A) of Operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively. This proposed TS change involves revising TS Surveulance Requirement (SR) 4.8.1.1.2.e.2, and supporting TS Bases Section 3/4.8, to clarNy the requirements associated with' single load rejection testing of the Emergency Diesel Generators (EDGs). SpecNically, this prW TS Change involves modWying the wording in TS SR 4.8.1.1.2.e.2 to remove the specific reference to the Residual Heat Removal (RHR) pump motor and ks corresponding kW rating value, and replace k with wording consistent with that specified in the improved TS (i.e.,
NUREG-1433, Revision 1, " Standard Technical Specifications General Electric Plants").
We request that, if approved, the amendments to the LGS, Units 1 and 2 TS be issued prior to January 24,1997, and become effective within 30 days following issuance.
If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours,
<4s .
G. A. Hunger, Jr.
Director - Licensing <f
'l c0 l Attachments f
! Enclosure
! cc: H. J. Muler, Administrator, Region I, USNRC (w/ attachments, enclosure)
- N. S. Perry, USNRC Senior Resident inspector, LGS (w/ attachments, enclosure) j R. R. Janati, Director, PA Bureau of Radiological Protection (w/ attachments, enclosure)
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' COMMONWEALTH OF PENNSYLVANIA :
- as. .
t COUNTY OF CHESTER :
D. B. Fetters, being first duly sworn, deposes and says:
l r
That he is Vice President of PECO Energy Company, the Applicant herein; that he has read the
- foregoing Technical Specifications Change Request No. 96-22-0 for Limerick Generating Station, Units 1 and 2, Facility Operating License Nos. NPF-39 and NPF-85, cor.ce,r.ing Emergency Diesel Generator single load l
rejection testing, and knows the contents thereof; and that the statements and matters set forth therein are l true and correct to the best of his knowledge, information, and belief.
I O f, i h JN Vice President ;
Subscribed and sworn to before me this Od day W
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t i ATTACHMENT 1 i
UMERICK GENERATING STATION UNITS 1 AND 2 l
l Docket Nos. 50-352 1 50-353 1
Ucense Nos. NPF-39 NPF-85 l
l r TECHNICAL SPECIFICATIONS CHANGE REQUEST 1
i No. 96-22-0 l l
1 " Clarification of Single Load Rejection Testing for !
l Emergency Diesel Generators" I l
Supporting information for Changes - 4 pages i
i 1
i l
Attachment 1 Page 1 of 4 PECO Energy Company, Licensee under Facilky Operating License Nos. NPF-39 and NPF-85 for :
Limerick Generating Station (LGS), Units 1 and 2, respectively, requests that the Technical Specifications 1 (TS) contained in Appendix A to the Operating Licenses be amended as proposed herein to revise TS !
Survellance Requirement (SR) 4.8.1.1.2.e.2, and associated TS Bases Section 3/4.8, to clarify the requirements pertaining to single load rejection testing of the Emergency Diesel Generators (EDGs). I SpecificaNy, this proposed TS Change involves revising the wording in TS SR 4.8.1.1.2.e.2 to remove the !
apecific reference to the Residual Heat Removal (RHR) pump motor and ks corresponding kW rating value, and replace it with wording consistent with that specified in the improved TS (i.e., NUREG-1433, Revision 1, " Standard Technical Specifications General Electric Plants"). The proposed changes to the TS are shown on the attached mark-up of TS Page 3/4 6-4 and Bases Page B 3/4 8-2 for Units 1 and 2, and are contained in Attachment 2.
PECO Energy is requesting that, if approved, the amendments to the TS be issued by January 24,1997, and become effective within 30 days of issuance.
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 information supporting an Environmental Assessment Discussion and Description of the Procosed Changes The proposed Technical Specifications (TS) changes to the Limerick Generating Station (LGS), Units 1 and 2, TS involve revising TS Survelliance Requirement (SR) 4.8.1.1.2.e.2, and supporting TS Bases Section 3/4.8, to clarify the requirements associated with performing single load rejection testing of the Emergency Diesel Generators (EDGs). Currently, TS SR 4.8.1.1.2.e.2 stipulates that every 24-months each EDG be tested to verify ks capahalty to reject a load of greater than or equal to that of the Residual ,
Heat Removal (RHR) pump motor whle maintaining voltage and frequency within established parameters. The current TS wording reads as follows:
"Every 24 months verify the diesel generator capabuity to reject a load of greater than or equal to that of the RHR Pump Motor (902 Kw) for each diesel generator whNe maintaining voltage at 4285
- 420 volts and frequency at 60 i 1.2 hz and after steady state conditions are reached, voltage is maintained at 4280
The proposed TS changes revise TS SR 4.8.1.1.2.e.2 to remove the specific reference made to the RHR pump motor, and replaces it with wording consistent with that delineated in the improved TS (i.e.,
NUREG-1433, Revision 1, " Standard Technical Specifications General Electric Plants") while maintaining the existing voltage and frequency parameters. The proposed TS wording reads as follows:
"Every 24 months verify each diesel generator's capabNity to reject a load of greater than or equal to that of ks single largest post-accident load while maintaining voltage at 4285
- 420 volts and frequency at 60 i 1.2 hz and after steady state conditions are reached, voltage is maintained at 4280 i 120 volts.'
The proposed TS changes also involve revising TS Bases Section 3/4.8 to include a statement clarifying that the single largest post-accident load on each EDG is the RHR pump motor.
i Safety Assessment
{ The proposed TS changes involve revising TS SR 4.8.1.1.2.e.2, and the associated Bases Section 3/4.8, j to clarify the requirements associated with Emergency Diesel Generator (EDG) testing and the rejection
, of the single largest electrice! load. Specifically, the proposed changes wHl revise the TS wording to remove the specific reference to the RHR pump motor and ks associated 992 kW loading value, and replace it with wording consistent with that described in NUREG-1433, Revision 1, " Standard Technical Specifications General Electric Plants.* The proposed TS SR wording wHI require that the
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- Attachment 1 1 Page 2 of 4 i EDGs be capeble of rejecting the single largest post-accident load whue mairmaining the current voltage !
and frequency parameters, rather than making the specific reference to the RHR pump motor. The applicable TS Bases wIl be revised to provide the 5Fvpi' " darWication in support of the proposed changes The proposed TS changes wul provide greater flexibilty in performing future plant J maintenance actMties (i.e., replacement of a pump motor or addition of a new post-accident load on the 4W emergency buses) at Limerick Generating Station (LGS), Units 1 and 2.
TS SR 3 8.1.g in NUREG-1433, Revision 1, states the following
" Verify each DG rejects a load greater than or equal to ks associated single largest post accident load, and...."
The supporting Bases for this requirement in NUREG-1433, Revision 1, indicates that each EDG is provided with an overspeed trip to prevent damage to the engine Recovery from a transient caused by the loss of a large electrical load could cause the EDG engine to overspeed, which, if excessive, might result in the trip of the engine This SR demonstrates the EDG load response characteristics and capaNiky to reject the single largest post-accident electrical load Without exceeding predetermined voltage and frequency parameters and maintaining a specified margin to the overspeed trip.
The proposed TS changes are consistent with the guidance stipulated in NUREG-1433, Revision 1, as described above. There are.no changes to the existing voltage and frequency parameters specified in TS SR 4.8.1.1.2.e.2 as a resuk of the proposed TS changes. The current requirement to maintain voltage at 4286 420 volts and frequency at 60
- 1.2 hz and steady state condklons at 4280
- 120 volts will be maintained The proposed TS changes do not modify any existing EDG testing methods or testing frequencies The largest post accident electrical load on each 4kV emergency bus is the RHR pump motor. The RHR pump motors are currently used to perform the single load rejection test for the EDGs in order to satisfy the TS requirements The RHR pump motors wBl continue to be used in poiferireng TS SR 4.8.1.1.2.e.2.
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The largest electrical loads connected to the 4kV emergency buses are the dryweN chillers. However, the dryweN chtlers are non-safety related loads and are shed from the 4kV emergency buses upon receipt of a Loss-of-Coolant-Accident (LOCA) or Loss-of-Offsite-Power (LOOP) signal Also, ll the EDGs are the only source of AC power (i.e., under LOOP conditions), then the dryweN chillers cannot be started due to drywell chtied water process conditions. The drywell chilled water circulation pumps, which provide cooling water to the dryweN chluers, cannot operate during LOOP conditions since their electrical supply is provided from a non-safety related power source. With the drywell chNied water pumps not operating, pressure differential and low-flow switches prevent the starting of the dryweN chillers Although the dryweN chulers are the single largest electrical loads connected to the 4kV emergency buses, they are not considered the single largest post-accident load under LOOP conditions when the EDGs are supplying the 4kV emergency buses. The RHR pump motors are the single largest post-ecident loads on the 4kV emergency buses if non-safety related power is restored whRe the diesel generators are supplying the 4kV emergency buses, esisting administrative controls prevent the drywell chillers from being started unti the normal offdte p.mer is restored to the 4kV emergency buses and the EDGs are disconnected from the emergrex:y buses. The existing administrative controls are contained in procedure E 10/20, " Loss of Offske Power," which requires that offsite power be restored and the EDGs shutdown prior to starting the dryweN chRied water system.
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Attachment 1
.- Page 3 of 4 I
l Infonnation Supporting a Finding of No Significant Hazards Conalderation l We have concluded that the proposed changes to Limerick Generating Station (LGS), Unks 1 and 2, Technical Specifications (TS), and associated TS Bases, to clarify the requirements for perforrning i Emergency Diesel Generator (EDG) single load rejection testing de not involve a Significant Hazards !
l Consideration. In support of this C^: ,,,;,=^': i, an evaluation of ea':h of the three (3) standards set forth in 10 CFR 50.92 is provided below. I
- 1. The propomad Technical Soecifications (TS) chances do not im alve a sionificant increase in the orobablity or conssouances of an accident oreviously evaluated.
l The proposed TS changes do not make any physical alterations or modifications to the plant l l systems or equipment. The proposed changes do not adversely impact the operation of any )
l plant equipment. The EDGs wNl continue to function as designed to ensure that the necessary ,
i electrical power is provided to essential plant equipment to mitigate the consequences of an .)
l accident, e.g., Loss-of-Offsite-Power (LOOP) and Loss-of-Coolant Accident LOCA) coincident ;
l with a LOOP (LOCA/ LOOP). The proposed TS changes do not impact the performance testing ;
l requirements anaelated with the EDGs. The acciderA mitigating capablittles of the diesel !
l generators and emergency loads wul remain the same. ;
The pr@nand TS changes are consistent with the guidance stipulated in NUREG-1433, Revision, l
" Standard Technical Specification General Electric Plants," regarding single load rejection testing j of the EDGs. Specifically, the proposed changes involve revising the wording in TS Surveulance :
Requirement (SR) 4.8.1.1.2.e.2 to remove the specific reference to the Residual Heat Removal l (RHR) pump motor and anaelated kW loading value (902 kW), and replace it with wording indicating that the EDGs must be cap-ble d rejecting the single largest post-accident load, which is consistent with NUREG-1433, Revision 1, guidance. The proposed changes wil also provide addhional flexibuty for future plant maintenance activities.
l Each EDG wNl continue to be tested by rejecting a load of grower than or equal to that of ks ;
single largest post-accident load while maintaining voltage and frequency within the current specified parameters. The RHR pump motors are currently used in performing the EDG single load rejection testing The RHR pump motors wiu continued to be used in performing the survelNance testing since they are the single largest post-accident electrical load.The i
, consequences of a malfunction of equipment are not affected. Falure of a EDG or its safety- !
! related loads is bounded by the loss of a Class 1E electrical power division which has been f previously evaluated as diatamad in LGS Updated Final Safety Analysis Report (UFSAR)
Sections 8.1.5.2.e and 8.3.1.1.3.
l Therefore, the proposed TS changes do not involve an increase in the probablity or ,
l consequences of an accident previously evaluated.
- 2. The oronosed TS chances do not create the nossibility of a new or different kind of accident '
from any accident previously evaluated.
The proposed TS changes do not make any physical alterations or modifications to the plant systems or equipment The proposed changes do not adversely impact the operation of any i plant equipment. The EDGs wul continue to function as designed to provide essential electrical L power to mitigate the consequences of an accident The proposed TS changes are consistent i with the guidance stipulated in NUREG-1433, Revision 1, regarding single load rejection testing i of the EDGs. The proposed changes do not introduce any new accidents or transients The j proposed TS changes will provide additional flexibilty for future maintenance activities. The
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- Attachment 1 Page 4 of 4 prnpanar8 changes do not alter any EDG testing requirements or frequencies. The RHR pump motors are currendy used in performing the EDG single load rejection testing. _ The RHR pump motors wW continue to be used in performing the survellance testing since they are the single largest posteccident electrical load. The operation of the EDGs and their corresponding safety-related electrical loads remain unchanged as a result of the proposed TS changes-Therefore, the proposed TS changes do not create the possibilty of a now or different kind of accident from any arv4riant previously evaluated.
- 3. The nrannaari TS charw== do not involve a alanificant rartw*ian in a ,T,.ou;,i of anfatv The proposed TS changes do not involve any physical changes to plant systems or equipment The proposed TS changes are consistent with the guidance stipulated in NUREG-1433, Revision 1, " Standard Technical Specification General Electric Plants," regarding single load rejection testing of the EDGs. The proposed TS changes wlN provide addklonel flexibuty for future plant maintenance activities. The EDGs wHl continue to function as designed to provide essential electrical power to mitigate the consequences of an accident. The operation of the EDGs and their corresponding safety-related electricalloads remain unchanged as a result of the proposed TS changes Therefore, the prnpanart TS changes do not involve a signdicant reduction in a margin of safety, information Supporting an Environmental Assessment An Environmental Assessment is ry]t required for the changes proposed by thie TS Change Request wa= the requested changes to the LGS, Units 1 and 2 TS conform to the crkeria for " actions eligible for categorical exclusion," as specified in 10 CFR 51.22(c)(9).' The requested changes wBl have no impact on the environment. The proposed changes do not involve a significant hazards consideration as discussed in the preceding section The proposed changes do not involve a significant change in the j types or significant increase in the amounts of any ofnuent that may be released offsite. In addition, the l proposed changes do not Irwolve a significant increase in individual or cumulative occupational radiation awpamme Conclusion l The Plant Operations Review Committee and the Nuclear Review Board have reviewed the proposed changes to the LGS, Unks 1 and 2, TS and have concluded that they do not involve an unreviewed safety question, and wRI not endanger the health and safety of the public.
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I ATTACHMENT 2 l l l UMERICK GENERATING STATION l UNITS 1 AND 2 Docket Nos. 50-352 l 50 353 License Nos. NPF-39 NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST No. 96-22-0 l
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